INFO 0554-2 CA9600089
VOL ' ) • ' V
Atomic Energy Commission de contrôle Control Board de l'énergie atomique Canad'â 1NFO-0554-2
Annual Report to the Atomic Energy Control Board on the Regulatory Research and Support Program April 1, 1993 - March 31, 1994
Appendices
by
the Regulatory Research and Support Program staff
Research and Support Division Directorate of Research and Safeguards Atomic Energy Control Board *-v-ï Ottawa, Canada
f-;-. I 1 May 1995 I Atomic Energy Commission de contrôle I Control b.ard de l'énergie atomique Canadaî TABLE OF CONTENTS
APPENDIX A : Review Panels: Membership and Activities 31
APPENDIX B : Project Summaries 39
APPENDIX C : Inactive Projects: Categories 2 and 3, Cancelled or Postponed 209
APPENDIX D : Projects Undergoing Review of Final Report or
Post-Project Evaluation Only 215
APPENDIX E : Fiscal Year 1993/94 Project List 219
APPENDIX F : Specific Objectives for Fiscal Year 1993/94 and How Each Was Met 231 -31-
APPENDIX A Review Panels: Membership and Activities -33-
APPENDIX A
Review Panels: Membership and Activities
1 RADIATION-INDUCED DEVELOPMENTAL DEFECTS Program Officer: V. Elaguppillai Panel Members - L.E. Becker University of Toronto, Toronto, Ontario - WJ. Schull University of Texas Health Sciences Center, Houston, Texas - J. Muller Willowdale, Ontario - P. Rakic Yale University, New Haven, Connecticut - T.V.N. Persaud University of Manitoba, Winnipeg, Manitoba - D.K. Myers Pembroke, Ontario L. Mclntyre IWK Children's Hospital, Halifax, Nova Scotia - C. Brisson Hospital Saint Sacrement, Québec, Québec - G. Howe University of Toronto, Toronto, Ontario - J.M. Yamazaki UCLA Medical Center, Los Angeles, California - R.L. Brent Jefferson Medical College, Phildelphia, Pennsylvania - G.B. H ill Health and Welfare Canada, Ottawa, Ontario
In Progress: Effects of In Utero Exposure on Central Nervous System (7.106.2) and Mechanism of Radiation-Induced Mental Retardation (7.135.1) Review Panel Activities: Review panel reviewed the work statement and suggested a number of changes. Review panel comments were incorporated into the final work statement in Project 7.106.2. -34-
2 EPIDEMIOLOGY Program Officer: V. Elaguppillai Panel Members - G.B. Hill McGill University, Montreal, Quebec - G. Howe National Cancer Institute of Canada, Toronto, Ontario - A. Arsenault Institut de Cardiologie de Montréal, Montreal, Quebec - D. Meyerhof Health and Welfare Canada, Ottawa, Ontario - D.K. Myers Pembroke, Ontario - L. Mclntyre IWK Children's Hospital, Halifax, Nova Scotia L. Smith Ontario Ministry of Health, Toronto In Progress: A Case - Control Study of Beaverlodge Uranium Miners from 1950-1980 (4.118.2) and Radon Progeny Exposures of Beaverlodge Uranium Miners - Phase 2 (4.118.4)
3 INHALATION STUDIES Program Officer: R. Avadhanula Panel Members - D.H. Bowden University of Manitoba, Winnipeg, Manitoba - P. Bredon COGEMA, Razes, France - L.D. Brown Saskatchewan Department of Labour, Regina, Saskatchewan - J. Chameaud COGEMA, Razes, France - V. Elaguppillai Atomic Energy Control Board, Ottawa, Ontario - F. Horvath Atomic Energy Control Board, Ottawa, Ontario - J. Lafuma Commissariat à L'Energie Nucléaire, Fontenay-aux-Roses, France - Y. Mao Health and Welfare Canada, Ottawa, Ontario - R. Masse, Commissariat à L'Énergie Nucléaire, Fontenay-aux-Roses, France - J. Muller Toronto, Ontario - C. Pomroy Atomic Energy Control Board, Ottawa, Ontario -35-
- B.L. Tracy Health and Welfare Canada, Ottawa, Ontario - M.E. Wrenn University of Utah, Salt Lake City, Utah In Progress: Study of the Health Effects of Inhaled Uranium Ore Dust (4.101.3)
4 DOSIMETRIC MODELS No panel activities were required in FY 1993/94.
5 LUNG SOLUBILITY STUDIES Program Officer: K.P. Ho Panel Members - J. Tai-Pow Ontario Ministry of Labour, Toronto, Ontario - M.L. Zamora Health and Welfare Canada, Ottawa, Ontario - R.G.C. McElroy AECL Research, Chalk River, Ontario - F. Horvath Atomic Energy Control Board, Ottawa, Ontario In Progress: Physical Characteristics and Solubility of Airborne Long-Lived Dust in Uranium Producing and Manufacturing Facilities (4.103.2)
6 RELATIVE BIOLOGICAL EFFECTIVENESS (RBE) Program Officer: E. Rabin Panel Memers - D. Whillans Ontario Hydro, Pickering, Ontario - S. Raman University of Ottawa, Ottawa, Ontario - G.F. Whitmore Ontario Cancer Institute, Toronto, Ontario In Progress: Response of Mice to Gamma Rays Delivered at Low Dose Rates (7.141.1)
7 BRONCHIAL EPITHELIUM No panel activities were required in FY 1993/94. -36-
8 RADIOSENSITIVITY OF BIOLOGICAL SYSTEMS No panel activities were required in FY 1993/94.
9 URANIUM TOXICITY No panel activities were required in FY 1993/94.
10 HYDROGEOLOGY No panel activities were required in FY 1993/94.
11 ENVIRONMENTAL PATHWAYS No panel activities were required in FY 1993/94.
12 SOFTWARE RELIABILITY No panel activities were required in FY 1993/94.
13 GEOCHEMISTRY No panel activities were required in FY 1993/94.
14 SEVERE ACCIDENTS No panel activities were required in FY 1993/94.
15NPP AGING Program Officers: J.K. Pereira (2.184.3) and W.A. Grant (2.184.4) Panel Members - D. J. Burns University of Waterloo, Waterloo, Ontario - R. Eadie University of Alberta, Edmonton, Alberta - C. M. Hansson Queens University, Kingston, Ontario - L. A. Simpson AECL Research, Pinawa, Manitoba In Progress: Ballooning of Pressure Tubes (2.184.3 and 2.184.4) -37-
Review Panel Activities: The panel reviewed a test facility design report and results from commissioning tests carried out in Project 2.184.3. They advised on data requirements and a test matrix for degraded specimen tests to be carried out using the facility in Project No 2.184.4.
16 DEEP GEOLOGICAL DISPOSAL No panel activities were required in FY 1993/94.
17 EXPOSURE EVALUATION No panel activities were required in FY 1993/94.
18 EXPOSURES OF NON-MONITORED PERSONNEL No panel activities were required in FY 1993/94.
19 FOETAL DOSIMETRY No panel activities were required in FY 1993/94.
20 CONTACT DOSIMETRY No panel activities were required in F Y 1993/94.
21 NPP EQUIPMENT QUALIFICATION (Environmental and Dynamic) No panel activities were required in FY 1993/94.
2 2 SEISMIC HAZARD No panel activities were required in FY 1993/94.
23 ETHICAL USE OF RESEARCH RESULTS No panel activities were required in FY 1993/94. -38-
24 FETAL DOSIMETRY Program Officer: E. Rabin Panel Members - Dr. D.W.Whillans Ontario Hydro, Whitby, Ontario - Dr. D. Benn Guelph, Ontario - Dr. A.L. Carsten Brookhaven National Laboratories, Upton, NY, U.S.A. - Ms. E. Lamothe AECL, Chalk River, Ontario In Progress: Metabolism and Fetal Dosimetry of Tritium (7.160.1 )
Review Panel Activities: Members of the Review Panel attended the project start-up meeting during which the technical details of the project were discussed with the contractor.
25 GENETIC COMPONENT IN RADIATION RISK Program Officer: V. Elaguppillai Panel Members - Dr. N. Yasuda National Institute of Radiological Sciences, Chiba, Japan - Dr. R. Chakraborty University of Texas, Houston, Texas - Dr. A. Czeizel WHO Collaborating Center for the Community Control of Hereditary Diseases, Budapest, Hungary - Dr. G. Tusnady
In Progress: Risk Estimates for Radiation-Induced Genetic Disorders (7.167.1) Review Panel Activities: The review panel reviewed the models and suggested a number of changes. The review panel comments were incorporated, and revised models are expected within the next several months. -39-
APPENDIX B Project Summaries
fNEXTrPAG E(5) left. BLANK -41- 2.111.2 International Piping Integrity Research Group - 2 Program Officer J.K. Pereira Contractor USNRC/Battelle Status Work in progress Comments Original Project Description In the IPIRG-2 project, data will be obtained for both quasi-static and dynamic (seismic) loadings, and experiments will be conducted on piping configurations representative of actual piping systems. The program will also include selected special-effect experiments in support of the pipe system experiments. The USNRC will be the lead organization, with multi-national contributions to the program. The cost of Canadian participation is expected to be shared equally between the AECB and Ontario Hydro (each contributing S300K over 3 years). The IPIRG-1 program was completed in July 1991. The work which will be conducted in the IPIRG-2 program will build on the solid base of information that has been established in IPIRG-1. The new program will include testing of piping systems, including cracks in straight pipes, elbows and tees. Such information is crucial to assessing licensees' designs. The information generated from this project will be used in assessing the merit of 'leak-before-break' integrity cases, defining in-service inspection frequency, and evaluating licensing criteria for protection against pipe rupture.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S220k SI 10k SOk SOk $330k Current Estimates S 194k $102k S104k SOk S400k Actual Spent to Date S 194k $102k S296k Progress to Date Two Technical Advisory Group meetings were held during the year. Fracture tests have been performed to investigate the behaviour of cracks in straight pipe and in circumferential welds at pipe elbows. The tests have involved cyclic and dynamic loading on four-point bend specimens and on test sections installed in a piping loop which is maintained at conditions which represent those in a reactor heat transport system. In parallel with the tests, there have been predictions of fracture behaviour expected and analysis of test results. -42- 2.128.5 Review of a Fire Drill at DNGS Program Officer M. Santini Contractor Fire Cross Consultants Inc. Status PPE initiated Comments
Original Project Description A contract is proposed for an external expert to assess the Darlington Nuclear Generating Station overall fire-fighting program/exercise which will involve response to a mayor fire as the only initiating event. AECB staff are concerned about the capability of Ontario Hydro's site fire crews at the Nuclear Generating Stations to cope with mayor fires. In response to this, OH has developed an improved program for its fire-fighting forces. The AECB requires the assistance of an expert to assess a station overall program and to evaluate the DNGS full-scale fire-fighting program. We anticipate further major demonstrations at Bruce and Pickering in succeeding years.
The conclusions of this work will help to establish a standard for a fire-fighting program applicable in general to any Nuclear Generating Station.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $35k SOk SOk S35k Actual Spent to .Date SOk S35k S35k
Final Results The Final Report submitted by the contractor presented a complete evaluation of Darlington NGS's fire plans, procedures, and fire fighting and rescue operations. It was evident that the framework for the provision of fire fighting and rescue services was in place, which constituted a significant improvement over what was observed at earlier evaluations. -43-
2.152.5 CATHENA Support Service Program Officer Q.s. Truong Contractor AECL - CANDU Status Complete Comments
Original Project Description The services of AECL staff are required to assist in the modification and running of the input for the CATHENA computer program and possible changes to the code itself. The capability of the CATHENA code to be used as an independent computing capability to perform check runs of licence submissions is known. In order to enhance the accuracy of the information of the results, the present input deck should be modified. The new version of CATHENA will be used by AECB staff to analyze various accident scenarios and to compare with the results produced by the licensee's computer codes.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S29k S4k SOk SOk S33k Actual Spent to Date $29k S4k S33k
Final Results A report documenting the tasks carried out for this project was submitted to AECB staff. The tasks included simulations of two standard problems (coolant discharge from a tank and U-tube flow oscillations), CATHENA simulations of reactor loss-of-coolant accidents (LOCAs) using one-channel-per-pass and five-channel-per-pass models, and providing the training to an AECB staff member which involved preparation of data and interpretation of results of several LOC A simulations. Final Evaluation CATHENA along with several input files were installed and successfully run by AECB staff. One staff member made extensive use of this facility to run several reactor cases. This presented an opportunity to compare the CATHENA results with those produced by two-fluid codes such as TUF, a two-fluid code developed and currently used by Ontario Hydro for LOCA analysis. Another staff member has performed a sensitivity analysis on the ways in which the five channels were grouped. This work was included in an AECB internal report (Technical Report TR-CR-701-2), which will be issued shortly. The standard problem results produced by this work were used in assessing CATHENA validation for a large LOCA application. This AECB assessment report has been sent to the code developer and users for their consideration and comments. -44-
2.162.4 Gardner Seminar on Childhood Leukemia Program Officer V. Elaguppillai Contractor Gardner, M.J. Status Complete Comments The seminar was attended by 120 participants from different p^rts of Caiudd.
Original Project Description It is proposed to have Dr. Gardner, the principal investigator of the study, conduct a one-day seminar on the methodology and results of the study of childhood cancer around the Sellafield, U.K., nuclear facility.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S4k SOk SOk SOk $4k Actual Spent to Date S4k SOk S4k
Final Results Dr. Gardner's seminar explained the design, conduct and the results of his study of radiation exposure of male workers at the Sellafield nuclear facility, and an apparent correlation between paternal doses received prior to conception of their offspring and development of leukemia in a small number of the children. Final Evaluation The one-day seminar was well received by the attendees from scientific, special interest groups, and media representatives. -45-
2.179.1 Performance of Steam Generator Emergency Water Injection Program Officer W.A. Grant Contractor Mu-Sigma Engineering Consultants Limited Status PPE initiated Comments Original Project Description It is intended to continue an experimental study in a section of the secondary side of a steam generator built to investigate phenomena associated with the emergency injection of water into the steam generator secondary side under accident conditions. The test section is similar in design to the actual geometry of the steam generators used in the Darlington NGS. Licensing submissions addressing the effectiveness of the steam generator emergency cooling injection system have treated some of the crucial parameters as uncoupled. AECB staff believes that combined effects such as spray-header water distribution, hot wall, and steam flow behaviour would dictate the overall performance of the steam generator emergency cooling system. Additional spray nozzle configurations, for various fluid droplet sizes and flow paths, are necessary to rationalize the effects observed in the first group of Phase I tests. The results of these extra experiments should provide additional insight into particular aspects of cold water injection into the steam generator secondary side. Those results would be used to assess the validity of licensee submissions on this topic.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $96k $25k $0k SOk S121k Actual Spent to Date $96k S25k S121k
Final Results This project was extended into fiscal year 1993/94 to include tests with fine spray patterns (500 micron droplet size). Those tests were successfully completed. The final report provides evidence that emergency injection of cold water into a hot dry-walled steam generator is possible under a range of dry-out conditions.
Publications A copy of the final report is available from the AECB's proprietary library collection. It will not be publicly available because it contains proprietary information for the Darlington Steam generators. -46- 2.184.3 Ballooning of CANDU Pressure Tubes - Construction of a Test Facility Program Officer J.K. Perdra Contractor Stern Laboratories Inc. Status Complete Comments
Original Project Description It is intended to conduct small-scale separate effects tests on as-received, irradiated, and hydrided pressure tube specimens to verify the hypotheses formed from previous phases of this project: a) that uniform hydriding has no effect on ballooning; and b) that irradiation and hydride blisters will affect ballooning. The influence of the ambient environment on pressure tube ballooning will also be assessed in these tests. The experiments will be designed and conducted in accordance with the results of a previous project (2.184.2). Safety analyses predicted that certain failures in reactor cooling systems could lead to coolant stagnation in fuel channels and to the ballooning and eventual rupture of pressure tubes. Current models of pressure tube ballooning behavour arc based on tests conducted with new pressure tube material in an inert environment, and may overestimate the ductility and creep behaviour of end-of-service-life pressure tubes under actual conditions.
The results of this project will enable improved predictions of the strain at failure of rapidly straining pressure tubes. This would permit improved assessments by AECB staff of predictions of pressure tube behaviour in accident conditions.
• Past 93/94 94/95 Future Total
93/94 Program Document Estimates S258k S49k SOk SOk S307k Current Estimates S260k S75k SOk SOk S335k Actual Spent to Date $260k S75k S335k
Review Panel 15 Comment The panel reviewed a test facility design report and results from commissioning tests carried out. Final Results An experimental facility has been built to enable creep testing of reactor pressure tube specimens. The facility is capable of tests at specimen temperature ramp rates up to 30°C per second, temperatures up to 1200°C and internal pressurization up to 6 MPa using either argon or steam. Instrumentation has been provided for measurement of temperature, strain and pressure. Data can be obtained to permit numerical analysis of the creep behaviour observed. Two tube ballooning tests were performed as part of the the facility commissioning work. Final Evaluation This facility has the capability to enable studies on the effect of in-service degradation on the ballooning behaviour of pressure tubes. Results from the first two ballooning tests suggest that material variability may be large enough to invalidate the licensee's safety analyses for Darlington NGS. Further tests are to be performed in Project No. 2.184.4 to investigate ballooning behaviour in degraded pressure tubes. AECB research effort in this area is being complemented by parallel work being done in a COG test program. The COG study has examined the effect of hydrogen content on the creep behaviour of the material. -47-
2.184.4 Ballooning of CANDU Pressure Tubes - Experiments with Degraded Tube Material Program Officer W.A. Grant Contractor Stem Laboratories Inc. Status Work in progress Comments
Original Project Description In this phase of the project, a series of tests are to be completed using the experimental facility that was built and commissioned in Project No 2.184.3. The tests will examine the effects of deuterium content, the presence of hydride blisters, flaws and channel environment on the creep behavior of pressurized tube specimens which are subjected to rapid rises in temperature. Safety analyses have predicted that certain failures in reactor cooling systems could lead to coolant stagnation in fuel channels and, as a consequence, to rapid temperature rise and creep deformation (ballooning) of the pressure tubes. Current models of pressure tube ballooning behavior are based on tests conducted with new pressure tube material in an inert environment. The effects of the service environment and life time degradation on creep behavior have not been addressed. A proposal (BMD 9]-175) for funding of experimental work on this topic was approved at a Board meeting held in September 1991. Results from this project will enable characterization of the effect of in-service degradation on the creep behavior and the integrity of pressure tubes which are subject to rapid straining at elevated temperatures. This would permit improved assessments by AECB staff of predictions of pressure tube behavior under accident conditions.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S 100k S 150k SOk S25Ok Current Estimates SOk S23k $129k SOk $152k Actual Spent to Date SOk S23k S23k Progress to Date This project was started in February 1994. A slightly flawed reactor-grade pressure tube has been purchased. Test rig refurbishment and modifications have commenced. The aim of this work is to improve control of pressure and electric ramp heating rate during ballooning. Six ballooning tests are planned for this phase of the study, using three "as-received" and three "artificially-flawed" specimens. Review Panel 15 Comment The review panel has recommended a test matrix that is intended to demonstrate that the test rig is capable of reproducible results. -48- 2.187.3 Behaviour of EFADS Filters Under Harsh Conditions - Phase 3 Program Officer M. Santini Contractor Science Applications International Corporation Status Work in progress Comments Original Project Description It is intended to review the current testing status of the filters used in the Emergency Filtered Air Discharge Systems (EFADS) and their behaviour under harsh conditions. This review should also serve to identify gaps in knowledge and data, defining the tests needed to evaluate the filters capability to deal with extreme conditions.
Technical and procedural problems involving the use of charcoal filters in the Emergency Filtered Air Discharge Systems have been studied in previous research projects (2.187.1 and 2.187.2). However, these studies did not include the review of filters' behaviour under extreme conditions, namely high temperature, high contamination, potential self-irradiation and self-heating. AECB staff are concerned about the performance of the filters in the long term after large LOCA events. In view of the importance of this system in post-accident recovery, it is crucial to know adequately the conditions which could lead to significant degradation of the fillers efficiency.
The results of this work will provide AECB staff with the basis for assessment of the EFADS under harsh conditions necessary to make informed licensing decisions. In addition, the results may contribute to emergency planning when containment venting must suddenly be interrupted.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk S 19k $14k SOk S33k Actual Spent to Date SOk $19k S 19k Progress to Date The first phase of the project, which included data gathering on laboratory and in-situ tests on EFADS filters was completed. A number of issues with respect to the completeness of the experimental support of EFADS behaviour under harsh conditions and in-situ testing procedures have been identified. The draft final report was being prepared by the contractor. -49- 2.196.1 Statistical Review of Pressure Tube Inspection Data Program Officer J.K. Perdra Contractor J.H. Parker & Associates Inc. Status Complete Comments Original Project Description This project is intended to study possible correlations between pressure tube deuterium measurements from In-Service Inspection (ISI) and tube-metallurgical, manufacturing or operational factors. The contractor would obtain available data from pressure tube history dockets and other industry sources. Deuterium pick-up is a potential life-limiting degradation of pressure tubes. A previous analysis by AECB staff of pressure tube deuterium contents indicates that some tubes are picking up deuterium at rates significantly faster than others; however, no correlation was evident with iron content, channel power, effective full power hours, core location or mass flow rate. It is therefore believed that the cause of the observed variation lies with other manufacturing or operational factors. A valid predictive relationship between pressure tube manufacturing or operational variables and deuterium contents would enable ISI sampling to be focussed on "high risk" populations of tubes, giving a greater degree of conservatism over the existing, random sampling program.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $95k $10k SOk SOk $105k Actual Spent to Date S95k SlOk $105k
Final Results A database of operational, manufacturing and metallurgical data was assembled for reactor pressure tubes for which there are measurements of deuterium content. Statistical analyses were then performed, to identify possible predictive relationships between deuterium ingress in service and other parameters in the database. The analyses identified only one variable as showing a significant functional relationship with deuterium ingress. It is a variable called "tube time", which is defined as the duration of a preheat treatment process applied during the manufacture of pressure tubes. Final Evaluation The project was subject to considerable delays because of difficulties encountered with getting access to data. Part of the effort required involved collection of some manufacturing process data which had not been previously assembled and reviewed by the industry. The study provided some valuable insights on relationships between various pressure tube parameters and, in particular, it has served to examine closely associations between deuterium ingress and certain other parameters. -50- 2.211.1 Tritium Surface Contact Dosimetry Program Officer E. Rabin Contractor Ontario Hydro, Research Division Status Work in progress Comments
Original Project Description It is intended to measure the uptake of tritium by mammals (rats, pigs, and humans) following contact of skin with surfaces which are contaminated with elemental tritium (HT), and to study quantitatively the subsequent distribution of organically-bound tritium (OBT) and oxidized HT (HTO) in body tissues and fluids. An unknown fraction of the total dose from tritium arises from contact with surfaces, contaminated with tritium. The only human data on tritium uptake from contact with surfaces, contaminated with elemental tritium, have been acquired from a few experiments that followed four volunteers in 1965. More recently, work at CRNL has been done with rats, using HT-contaminated planchettes. The present study is proposed because the earlier work on exposures of humans and rats, via contact with tritium-contaminated surfaces, has produced as-yet unexplained and sometimes dissimilar findings. These findings call into question the accuracy of currently-used calculational techniques for evaluating the dose to nuclear power reactor workers, and others, who are occupationally exposed to tritium via contact with surfaces contaminated with tritium (e.g., among workers at tritium removal facilities and tritium lighting manufacturers, and among university researchers). It is anticipated that the findings of this project will enable AECB staff and licensees to evaluate more accurately the dose and its distribution within the bodies of workers who are subject to exposure to tritium-contaminated surfaces. (It is expected that different aspects of the work will be carried out in Canada, in the United States, and in France. The AECB will be a member of a management group responsible for directing the work. Two external review groups, one of technical experts and the other concerned with ethical aspects, have been constituted to advise the management team. The work is cost-shared among Ontario Hydro, Atomic Energy of Canada Ltd., and AECB. Ontario Hydro is funding more than 50% of the cost of the total project, the upper estimate of which is likely to be approximately $800k.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SlOOk $50k SOk $0k $150k Current Estimates $113k S50k $0k SOk $163k Actual Spent to Date S113k $50k $163k Progress to Date Investigations were carried out by Ontario Hydro Research Division (OHRD) on the metabolism of tritium in hairless rats following skin-contact exposure to tritium contaminated stainless steel coupons. OHRD also provided the results of investigations of the nature of the tritiated compounds found on stainless-steel coupons exposed to elemental tritium, and the desorption of the tritiated compounds from the surfaces at low and high temperatures. The research reports are currently undergoing critical review by external experts. -51- 2.213.1 Review of Human Factors Guidelines Program Officer Y. Akl Contractor Rhodes & Associates Inc. Status Complete Comments Final report accepted Original Project Description It is proposed to fund a contract which would provide, through examination of the relevant literature, an annotated bibliography of current human factors standards, criteria and methodology applicable to the design, operation and maintenance of nuclear power plants. The bibliography should be prepared as annotated lists divided according to specific application areas within the plant (e.g. main control room displays, maintenance activities).
The AECB should provide guidance on the application of human factors to the design, operation and maintenance of nuclear power plants. Current information and references will be incorporated into the standards to be established in regulatory guides.
The contract would provide information which would aid development of AECB standards that should be met by licensees in the application of human factors knowledge to design, operation and maintenance of nuclear power plants.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $40k SOk $0k SOk S40k Actual Spent to Date $40k $0k S40k
Final Results The final report presented a review of the use of human factors guidelines and methods in high technology applications with emphasis on application to the nuclear industry. The review identified the major documents useful to the development of a foundation of human factors sources that could be applied to the nuclear industry in Canada. The selected documents and methods were critiqued and rated for their validity, applicability, completeness and practicality. The documents and methods identified in this project have been used to develop specifications for three human factors guides in project 2.280.1. The report is being processed for publication as an AECB INFO document. Final Evaluation The contractor produced a complete and substantial report which formed the basis for project 2.280.2. -52- 2.214.1 Review of Supervisory Functions in Nuclear Power Plants Program Officer Y. Akl Contractor Hickling Corporation Status Complete Comments Final report accepted for publication
Original Project Description It is proposed to fund a contract which would perform an assessment of the supervisory function in NPPs. Specific reference would be made to training for supervision, the practice of supervisory roles, and the criteria for supervisor performance assessment. The scope of the work would cover first-line supervisors in operations and in maintenance. One of the critical components in a program to ensure consistent high quality performance in the workplace is good supervision of the correct type. Consistent occurrence of problems associated with human error may have a source in the style or quality of supervision.
The development of regulatory stances on matters related to human performance in NPPs can only progress adequately when an improved insight into workplace dynamics is achieved. The results of the contract would provide information on the dynamics of the supervisory function.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S61k SOk SOk SOk S61k Actual Spent to Date $61k $0k S61k
Final Results The final report included a review of the nature of the tasks performed by the first line maintenance supervisors in three nuclear power plants (Pickering A, Bruce B and Point Lepreau). The contractor compared these tasks to core supervisory training curriculum, supervisory job descriptions, the process related to performance appraisals, and to the criteria applied in carrying out these performance evaluations. The results will be merged with the results of assessment of operations supervisors to generate for the first time an understanding of this function in OH NPPs . This information will be used for event analysis and review. Final Evaluation The contractor produced a final report that will help the AECB to understand the nature of the supervisory function in NPPs and to develop an appropriate regulatory stance. Several revisions were required to improve the report's technical quality prior to approval for publication as an INFO-report. -53-
2.214.2 Review of Supervisory Functions in Nuclear Power Plants - Phase II Program Officer Y. Akl Contractor Hickling Corporation Status PPE initiated Comments
Original Project Description The purpose of this project is to continue the work of Project 2.214.1, Review of Supervisor}' Functions in Nuclear Power Plants (NPPs), which covered supervisors in maintenance. This phase 2 work would address first-line supervisors in operations with specific reference made to training for supervision, the practice of supervisory roles, and the criteria for supervisor performance assessment. One of the critical components in a program to ensure consistent high quality performance in the workplace is good supervision of the correct type. Consistent occurrence of problems associated with human error may have a source in the style or quality of supervision. The development of regulatory stances on matters related to human performance in NPPs can only progress adequately when an improved insight into workplace dynamics is achieved. The results of the contract would provide information on the dynamics of the supervisory function.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $30k S30k SOk SOk S60k Current Estimates Slk S62k SOk SOk S63k Actual Spent to Date Slk $62k S63k
Final Results The final report provided an overview of first line supervisory activities at Ontario Hydro nuclear generating stations (Pickering "A" and Bruce "B"). The consultants developed activity profiles describing first line supervisory roles and responsibilities for nuclear operators. These profiles suggested that considerable overlap existed between first line union and management supervisory roles. In comparison to technical training, supervisory training was of secondary importance in terms of the training provided to nuclear operators in supervisory positions. The finding of this study with respect to supervisory functioning were not generally consistent with current trends in supervisory practices. The supervisory trends noted in the literature emphasize quality management, leadership, delegation and empowerment of staff, the middle management role in shrinking organizations, establishing a new corporate culture, cross training, performance coaching and process innovation. In general, there is a movement away from the more autocratic management styles. -54- 2.216.2 Validation of Positive Void - Phase II
Program Officer J. Kavanagh Contractor Diamond International Consulting Ltd. Status PPE initiated Comments Draft final report under review. Original Project Description In the first part of this study (Project No 2.216.1), a review was completed of the positive void reactivity effect in CANDU reactors. In this phase, a detailed review will be completed of submissions received from licensees in response to the report on findings from the first phase. The study will also address issues that arise owing to movement of fuel in channels as a consequence of a loss-of-coolant accident. Simulations of reactor power pulses under distorted flux conditions have indicated a proximity to prompt criticality. Also, certain designs, that have been considered for new CANDU reactors, feature acceptance of significant void reactivity effects. The AECB has, therefore, initiated work to examine the degree of conservatism in present industry estimates of the positive void coefficient and to obtain upper-bound estimates of the void reactivity likely to occur during a complete blowdown in a CANDU reactor. A critical review of the issues in question was completed in the first phase of this project. There is a" need for follow-up assessment on issues raised in that study and in particular for an evaluation of comments received from the industry. Results from the. study will be used in assessing related safety analyses and specifying any licensing actions that may be required.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S45k SOk SOk $45k Current Estimates SOk S46k S4k SOk S50k Actual Spent to Date SOk S46k S46k
Final Results The report contains an assessment of industry responses to INFO-0423, a document which addressed the treatment of positive void reactivity in CANDU safety analysis. The industry responses are reviewed and the proposed resolution to each issue, taking into account new developments in industry since the original recommendations had been made in INFO-0423, is presented. -55- 2.211 A Seismic Monitoring East and North of Toronto Program Officer J.L. Wallach Contractor Seismican Geophysical Ltd. Status Work in progress Comments Original Project Description It is intended to continue this project which commenced in 1990 with a background noise survey and a selection of five sites for instrumentation and deployment of both analogue and digital seismographs. This year's work would comprise data collection and analysis. This study was proposed in order to undertake seismic monitoring in the western Lake Ontario-Lake Simcoe-Georgian Bay area. This area was chosen because of the existence, there, of the Pickering and Darlington Nuclear Generating Stations. The objective of the study is to locate, as precisely as possible, microseismic events and ultimately to determine whether or not there is a spatial relationship between earthquakes, irrespective of size, and variously expressed lineaments in the aforementioned area.
It is anticipated that the results of this study will bear directly on improving seismic hazard estimates because reliable locations of microseismic events will aid geoscientists in determining whether or not there are active faults in the vicinity of the generating stations at Darlington and Pickering. If it is shown that there are active faults, then seismologists will be able to effect calculations of seismic wave attenuations from particular locations rather than assuming random sources.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $336k S35k $35k $50k S456k Current Estimates $450k S55k $39k SOk $544k Actual Spent to .Date S450k $55k $505k Progress to Date Forty earthquakes have been detected, several of which occurred on a straight line coincident with the Wilson-Pt. Hope magnetic lineament. Depths were poorly constrained because of a lack of adequate data. -56-
2.228.2 Steam Generator Fitness-For-Service Guidelines Program Officer W.A. Grant Contractor Dominion Engineering Inc. Status Work in progress Comments
Original Project Description It is intended to investigate the degradation mechanisms that do or may affect CANDU steam generator tubes and to review the design and safety criteria that apply in Canadian jurisdictions. It is further intended to identify procedures, for defect assessment and remaining life assessment, to the industry and regulatory authorities on the formulation of guidelines for dispositioning defects in steam generator tubes. After a period of exemplary performance, steam generator tubes at several CANDU plants are showing signs of serious degradation. Tube leaks have occurred at Pickering A, Bruce A, and Point Lepreau, as a result of corrosion or cracking. As existing codes and standards offer little detailed guidance, licensees have so far responded with ad hoc assessments of steam generator tube fitness for service. The industry is now proposing to standardize its approach in a set of guidelines. AECB staff are seeking advice on the state-of-the art in steam generator tube integrity assessment and the potential content of such guidelines. A report by independent experts on guidelines for assessing steam generator tube integrity would assist AECB staff in reviewing the expected proposals from industry. Timely completion would allow the project to make a constructive contribution.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k S47k S54k $0k SlOlk Actual Spent tu Date SOk $47k S47k Progress to Date This new project began in mid-December 1993 and has progressed rapidly because the responses from international regulatory agencies were received sooner than expected. -57- 2.231.1 Functional Graphical Languages for Process Control Program Officer Y. Aki Contractor Proctor & Redfem Limited Status PPE initiated Comments Original Project Description This project is to investigate functional graphical languages and techniques for use in safety related systems, especially in distributed control systems. It is proposed to carry out a survey to identify available functional graphical languages, followed by a detailed investigation of selected case studies. The preliminary design of the CANDU 3 nuclear generating station has proposed the use of a distributed control system which would be programmed using a functional graphical language. This is a significant departure from a central control system programmed more traditionally in languages such as FORTRAN or Assembler. Functional graphical languages are supposed to be easier for control engineers to understand and use. The AECB needs assurance that these gains are not offset by any decrease in safety.
This project will provide AECB staff with better understanding of functional graphical languages, how they are used in distributed control systems and what safety issues arise in their use. It will also prepare the AECB staff to competently deal with the analysis of systems using functional graphical languages, such as the one proposed in the preliminary desienofCANDU3.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S7k S 16k SOk SOk $23k Actual Spent to .Date $7k S16k S23k
Final Results The final report included an investigation of the use of functional graphical languages for controls in the process industry. A literature review was carried out and different vendor proprietary software and languages were investigated. The report discussed the advantages and disadvantages of procedural languages and functional graphical languages. An outline of an evaluation criterion for assessing functional graphical languages was identified. Recommendations for the appropriateness of functional graphical languages for a safety shutdown system were presented. -58- 2.234.1 Review of "Sub-Tier" Software Standards Program Officer Q.S. Truong Contractor McMaster University - Research Status PPE initiated Comments
Original Project Description It is proposed to have an independent review of Ontario Hydro's sub-tier software development standards. This independent review will provide input to a decision as to whether to accept these standards for the development of a prototype system and the redesign of the Darlington Safety Shutdown Systems. Ontario Hydro has proposed to define and submit to the AECB detailed standards for the development of safety critical software. This should fulfil part of the requirements placed on Ontario Hydro by AECB's licensing decision for Darlington No. 13/90. Considering the importance of these standards in the redesign of the Darlington Shutdown Systems, and all future software-based safety systems, it is important to thoroughly review Ontario Hydro's submissions in the light of accepted high-level standards (see 2.127.10), other national and international standards and best current software development practices. This project will provide AECB staff with independent and expert advice on the acceptability of Ontario Hydro's detailed software standards.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S24k SOk SOk SOk S24k Actual Spent to Date S24k SOk S24k
Final Results Pre-publication copies of the final report have been distributed to various interested parties including the licensees' staff. -59- 2.234.3 Review of Prototype Application of Software Standards Program Officer Y. Akl Contractor ADGA Systems International Limited Status PPE initiated Comments Original Project Description It is intended to have an independent review of Ontario Hydro's submissions regarding the prototype application of their software standards. This review will evaluate the complexity and relevance of the selected prototype application, suggest procedures and techniques of reviewing software design and documentation against accepted standards, demonstrate these procedures and techniques on the prototype application, and evaluate Ontario Hydro's interpretation and application of the standards. Ontario Hydro has proposed that a prototype application be developed as a test of the standards before applying them to a real safety shutdown system. The AECB should make use of this opportunity to develop and practice review and evaluation techniques. This project will provide AECB staff with valuable insight and examples of how to evaluate Ontario Hydro submissions for software developed according to their new standards.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S30k S20k SOk SOk S50k Current Estimates S9k $4 Ik SOk SOk S50k Actual Spent to Date S9k S41k S50k
Final Results The consultants conducted a critical review of the use by Ontario Hydro of a recently developed Software Engineering Standard for Safety Critical Software as a framework to develop software for the Heat Transport High Temperature Trip Meter at Pickering Nuclear Generating Station. The findings were grouped into four areas: 1) Finding re applicability of the prototype application; 2) Recommendations for Assessment Techniques; 3) Findings re Ontario Hydro's use of the Standard and 4) Comments on the Ontario Hydro Standard and Procedures. -60- 2.243.1 Marine Geophysics in Western Lake Ontario Program Officer j.L.Wallach Contractor Geological Survey of Canada Status Work in progress Comments Draft report received, evaluated and returned to contractor. Original Project Description It is proposed to undertake a marine geophysical investigation in Lakes Ontario, Simcoe and Scugog. The survey is to include seismic penetration deep into the bedrock,echo-sounding, shallow seismic penetration into the lake-bottom sediments and into the underlying Paleozoic bedrock surface, side-scan sonar and magnetics. Staff of the Atlantic Geosciences Center and the Terrain Sciences Division of the GSC have expressed an interest in participating in this project, though no commitments have been made. This work is proposed to determine if major geophysically expressed lineaments in the immediate vicinity of the Darlington and Pickering NGS are potentially seismically active. Information on their characteristics of these lineaments appear in AECBINFO-0342 and in a paper presented to the Canadian Geotechnical Conference. A single echo sounding traverse, conducted in June 1990 across one of the lineaments (NPLZ) in Frenchman's Bay (on which is situated the Pickering NGS), showed a change in elevation of the lake bottom. It is anticipated that this study will indicate whether the lineaments have, or do not have, topographic expression in the unconsolidated sediments on the bottoms of the aforementioned lakes. If there is abrupt topographic expression, this will imply that the potential for seismic activity is high. If such is the case, an analysis will be needed of the length of, and the vertical elevations across, the topographically expressed segments to estimate the magnitudes of previous earthquakes. This project has the potential for identifying crustally-derived, neotectonic movements. Depending on the results of this first phase, further similar investigations in subsequent years might be called for.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S50k S25k SOk SOk S75k Actual Spent to Date S50k S25k S75k Progress to Date Field work completed. Two draft reports have been submitted, reviewed and returned with comments. A final report is anticipated, but not yet received. -61- 2.243.3 Marine Geophysics in Western Lake Ontario, Lake Simcoe and the Kawartha Lakes Program Officer J.L. Wallach Contractor McQuest Marine Research & Development Company Ltd. Status Work in progress Comments
Original Project Description It is intended to continue the marine geophysical investigation in Lakes Ontario, Simcoe and Scugog. The survey is to include seismic penetration deep enough into the bedrock to penetrate the Precambrian-Paleozoic boundary, echo-sounding, shallow seismic penetration into the lake-bottom sediments and into the underlying Paleozoic bedrock surface, side-scan sonar and magnetics. This work is intended to determine if major geophysically expressed lineaments in the immediate vicinity of the Darlington and Pickering NGS are potentially seismically active. Information on the characteristics of these lineaments appears in AECB INFO-0342 and in a paper presented to the Canadian Geotechnical Conference. A single echo sounding traverse, conducted in June, 1990 across one of the lineaments (Niagara-Pickering Linear Zone, or NPLZ) in Frenchman's Bay (on which is situated the Pickering NGS), showed a change in elevation of the lake bottom. Seismic penetration of both young sediments and the underlying bedrock in Lake Simcoe show the presence of at least two faults. These faults are geologically young and if they are oriented parallel to the Georgian Bay Linear Zone (GBLZ) that would indicate that the GBLZ, which intersects the NPLZ within about 30-35 km of the Darlington and Pickering Nuclear Generating Stations, is a geologically active fault.
It is anticipated that this study will indicate whether the lineaments have, or do not have, topographic expression in the unconsolidated sediments on the bottoms of the aforementioned lakes. If there is abrupt topographic expression, this will imply that the potential for seismic activity is high. If such is the case, an analysis will be needed of the length of, and the vertical elevations across, the topographically expressed segments to estimate the magnitudes of previous earthquakes.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S80k S205k S205k $490k Current Estimates SOk $8 Ik SOk SOk S81k Actual Spent to Date SOk S81k S81k Progress to Date The field work has been completed. A final report is being prepared. -62- 2.244.1 Elevation Determinations of Stratigraphie Contacts in the CMBBZ Program Officer J.L. Wallach Contractor William R. Coe Limited Status Complete Comments
Original Project Description It is proposed to measure the elevations of the contacts of different stratigraphie units along the NPLZ/CMBBZ, most notably the contact between the Gull River Limestone and the overlying Bobcaygeon Formation which is exposed at several different outcrops.
This work is proposed because there is the strong suggestion of vertical displacements of stratigraphie markers due to faulting. However,the contour interval on the existing topographic maps in the area of interest is 50 ft (15m) which is too large to determine the amount of stratigraphie offset, if any, across major lineaments.
It is anticipated that this work will, in conjunction with project 2.242.2, show that there is evidence of bedrock faulting cutting the youngest rocks exposed along the projection of the NPLZ/CMBBZ and will reveal the precise amount of vertical displacement. As indicated for project 2.242.2, the results of this study will have direct implications for the assessment of seismic hazard in the vicinity of the Darlington and Pickering Nuclear Power Plants.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $8k $0k SOk SOk $8k Actual Spent to Date S8k SOk $8k
Final Results Elevations of contacts between upper Middle Ordovician rock units were determined. The report does identify vertical displacement of some stratigraphie contacts, in the area under study. Final Evaluation Results from the study were used in a study (Project No. 2.242.2) on stratigraphy in paleozoic rocks in the CMBBZ. -63- 2.247.1 Load Factors for the Design of CANDU Concrete Structures Program Officer J.K. Perdra Contractor Centre for Frontier - Engineering Research Status Complete Comments
Original Project Description It is proposed to review the current load factors and load combinations used in the design of concrete containment structures and safety related structures in CANDU nuclear power plants. Further, the margin of safety inherent through the use of these factors is to be assessed using a probabilistic approach. Recommendations are sought for revision of load factors if needed because of the variability of loads, to provide an acceptable and relatively uniform degree of safety in the design of structural members under different load combinations. The same approach is to be used to derive appropriate load factors for application to existing structures. The current load factors used in the design of containment and safety related structures were taken from the National Building Code of Canada. These factors were derived to be used in the design of building structures subjected to "normal" dead and live loads. CANDU nuclear power plants cannot be classified as "regular" buildings and arc subjected to very unusual loads. This should be reflected in the use of appropriate load factors and load combinations that reflect the more serious consequences of failure.
The study will enable a clear distinction between ultimate limit state design which is related to safety and serviceability limit state design which is related to vibration and/or cracking of concrete. The "updated" load factors will be considered for inclusion in revisions of the CSA-N287.3 (containments) and CSA-N291 (safety related structures) standards.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S20k S15k SOk SOk S35k Current Estimates S21k $15k $0k SOk S36k Actual Spent to Date S21k S15k S36k
Final Results The study shows that the approach taken in the CAN/CS A-N287.3-M93 standard is sound. The report notes that the present standard accounts for the infrequency of abnormal/environmental loads by using a load factor of 1.0 for all loads in the corresponding combinations. It suggests that more consistent safety levels could be achieved by basing the design loads for all rare events (including accident pressure and temperature) on a specified return period. Load factors could then be treated as being independent of the load combination, and defined as a function of the limit state. The report concludes that in relation to the current approach, load factors for dead load could be increased, and longer return periods could be used to define site design earthquakes. Load factors associated with the test pressure and operating pressure could be reduced because the uncertainty associated with these loads is small. These changes would even out the margins available for the various design load combinations considered. The approach developed in this study forms a basis for further verification and calibration of design requirements given in the CAN/CSA-N287.3-M93. Final Evaluation This study enabled an independent review of an approach being developed for application in the nuclear industry but which has been used in the petrochemical industry for some time. The contractor has experience with development of similar approaches for other industries. There was active participation by industry experts in the assembly of data for the project and considerable benefit was gained by all, via discussions with the contractor on the basis and strengths of the approach. -64- 2.247.2 Reliability of CANDU Concrete Containment Structures Under Seismic Loads Program Officer J. Kavanagh Contractor Centre for Frontier Engineering Research Status PPE initiated Comments Draft final report under review.
Original Project Description Concrete containment structures for CANDU nuclear power plants are designed according to the CAN/CS A-N287.3 standard. The seismic loads used in the design process are estimated using the knowledge available at the time of design. New seismological information acquired later may require a reassessment of the seismic design basis and seismic withstand capacity of an "existing concrete containment structure. The seismic design methodology presented in the CAN/CS A-N287.3 standard is intended for the design of new structures and may not be appropriate for the reassessment of existing structures. The uncertainties associated with the design of new structures are different from those associated with existing structures; e.g., material properties, floor loads and as-built conditions are available. Also, the characteristics of the seismic event to be used in the reassessment may be different from what is implied in the CAN/CSA-N287.3 standard.
This is a continuation of work begun under Phase 1 of this project. In Phase 2 we want to develop a methodology for seismic reassessment of existing concrete containment structures. Accurate estimates require proper modelling of the statistical characteristics of the resistance and seismic loads on as-built structures.
It is anticipated that this work will be used to assess the margins of safety inherent in concrete containment structures.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $50k SOk SOk S50k Current Estimates SOk S4Ok S6k SOk S46k Actual Spent to Date SOk $40k $40k
Final Results The report describes a reliability-based methodology for assessing existing CANDU concrete containment structures under seismic load and defines the parameters necessary to implement the methodology. Reliability analyses were performed for a number of test cases and the parameters required in the assessment methodology were defined. Key issues were the selection of design earthquake spectra that yield consistent safety levels and the use of structure-specific data in the evaluation of structural resistance. -65- 2.248.2 Seismic Analysis or a Mechanical System at Pickering NGS Program Officer WA. Grant Contractor Dr. A. Ghobarah Status Complete Comments
Original Project Description It is intended to assess the seismic withstand capacity of a safety related mechanical system at Pickering Nuclear Generating Station. Equipment associated with the pressure relief duct (PRD), such as the Emergency Coolant Injection System (ECIS) piping system and the vacuum ducts, will be analyzed using as input the imposed displacements and forces obtained from the PRD seismic analysis (project 2.248.1).
The Pickering A station was designed to seismic standards different from what is currently specified by codes for modern plant design. This study will comprise analytical simulations to obtain a measure of the likely "level of damage" as a function of "ground motion intensity". Such information is needed to afford benchmark data for use in assessment of submissions from Ontario Hydro on the proposed Pickering seismic safety margin review (project 2.209.1).
It is anticipated that this work will, with projects 2.248.1 and 2.248.3, be used to assess the seismic withstand capacity of safety related systems at Pickering A NGS.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $0k $45k $0k $0k $45k Current Estimates $0k $44k $0k $0k $44k Actual Spent to Date $0k $44k $44k
Final Results The study indicated that certain mechanical systems, including the emergency coolant injection system piping attached to the pressure relief duct at Pickering, would fail at peak ground acceleration levels similar to those that would cause the duct to fail. This study used an artificial seismic template, developed in the project 2.248.1, that may be representative of an Eastern North American earthquake. Computer simulations were used to determine the likely failure limit of the duct and its mechanical components and to deduce the safety margins in the existing structure. The final report has been submitted for internal approval and publication. Final Evaluation This is a good example of the value for money obtained from some of our best contractors, within the RSP. -66- 2.248.4 Seismic Response of the Pickering Pressure Relief Duct to the 1985 Nahanni Earthquake Program Officer WA Grant Contractor Dr. Ahmed Ghobarah Status Complete Comments The report has been approved for issue as a public information document and is awaiting publication.
Original Project Description In this phase of the Pickering Pressure Relief Duct (PRD) seismic studies, a series of computer analyses will model the duct's response to the 1985 Nahanni earthquake. The analytical simulations will be carried out using the nonlinear dynamic models devised during Phase 1. The actual ground motions, as recorded during the 1985 event, will be used in the simulation. This large magnitude earthquake (Richtcr 6.9) that occurred in 1985 near Nahanni, Northwest Territories, was unprecedented for that region. The vertical acceleration characteristics are the most severe in the Canadian records. While quantitatively similar to the large magnitude, shallow thrust earthquakes expected in many parts of eastern North America, the Nahanni event should provide an upper bound on the structural damage expected for the Pickering PRD. It is anticipated that this work will, with projects 2.248.1 and 2.248.2, be used to assess this special safety system (the PRD's) seismic withstand capacity. The information generated from this three phase project will be used in support of the Seismic Margin Review for Pickering (project 2.209.1).
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k $12k $0k $0k S 12k Actual Spent to Date $0k $12k S 12k
Final Results This study was initiated to study the load tolerance of the Pickering pressure relief duct under what was, until the recent North Ridge-1994 (Los Angeles) earthquake, the most severe vertical acceleration seismic event recorded in North America. Computer simulations of the Pickering pressure relief duct, from project 2.248.1 and from the seismic template from the Nahanni earthquake, were used for the analysis. Collapse of the duct was predicted. Final Evaluation The study was relevant to the Board's mandate with respect to the need to address hazards which could effect the integrity of Candu reactor containment structures. This particular project was undertaken as an extension of work done in Project No. 2.248.1. It was proposed as part of the preparation for the Nuclear Liability Litigation (1993) of a year ago. The work done by the contractor was of excellent quality. The study was a thorough one and the report provided fully addressed our requirements. -67- 2.248.5 Laboratory Testing of Reinforced Concrete Column Specimens Program Officer j. Kavanagh Contractor McMaster University Status Work in progress Comments
Original Project Description It is intended to carry out reverse cycle load tests on reinforced concrete beam-column specimens which are representative of members of the Pickering pressure relief duct (PRD) support frames. The tests are to simulate the likely behaviour of Pickering PRD support frame members during a seismic event. The required specimens will be designed and detailed under project 2.248.6. In projects 2.248.1 and 2.248.4, a series of analytical simulations were conducted to examine the likely performance of the Pickering PRD during seismic events. The results show that the structural integrity of the PRD relies heavily on the ability of its supporting frames to deform in the plastic range. The results also show that some beam-column connections may be the weak link in the lateral load resisting frame. Laboratory testing of representative portions of the frames will enable a more complete assessment of the seismic load tolerance of the PRD structure.
The results of this research project will be analyzed under Project No. 2.248.6, and together with those from projects 2.248.1 and 2.248.4, will be used to assess the seismic margin study currently being undertaken by Ontario Hydro for Pickering NGS.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k SOk S27k SOk S27k Actual Spent to Date SOk SOk SOk -68- 2.248.6 Assessment of Reinforced Concrete Column Specimens Program Officer J. Kavanagh Contractor A. Ghobarah Status Work in progress Comments
Original Project Description It is intended to design and detail two large-scale reinforced concrete beam-column specimens which are representative of members of the Pickering pressure relief duct (PRD) support frames. The likely behaviour of Pickering PRD support frame members during a seismic event will be assessed from reverse cycle load tests which are to be earned out on such specimens (Project 2.248.5). In projects 2.248.1 and 2.248.4, a series of analytical simulations were conducted to examine the likely performance of the Pickering PRD during seismic events. The results show that the structural integrity of the PRD relies heavily on the ability of its supporting frames to deform in the plastic range. The results also show that some beam-column connections may be the weak link in the lateral load resisting frame. Analysis of the laboratory test results of representative portions of the frames will enable a more complete assessment of the seismic load tolerance of the PRD structure. This research project will provide analysis of the test data obtained in project 2.248.5. Together with the results from projects 2.248.1, and 2.248.4, this project will enable an assessment of the seismic margin study currently being undertaken by Ontario Hydro for Pickering NGS.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk SOk $26k SOk S26k Actual Spent to Date SOk SOk SOk -69- 2.249.1 Compliance with Bundle Power and Channel Power Limits Program Officer W.A. Grant Contractor Diamond International Consulting Ltd. Status Work in progress Comments
Original Project Description It is intended to conduct a review of the computer codes which are used to demonstrate compliance with bundle power and channel power limits in various CANDU reactors. The study will include a review of models and input data used in these codes. It will also determine if comparisons with measurements are supported by an adequate data base and whether they remain valid for reactor operation with distorted flux shapes. Compliance with bundle and channel power limits specified in Operating Phase & Procedures documents is demonstrated through computer simulations, especially in reactors where boiling occurs in channels. Therefore, it is important to establish the accuracy of these simulations. Furthermore, the reactor models and input data used in these simulations have varying degrees of detail at various sites. The impact of these differences on accuracy of the calculations is not clear. The results of the study will be used in assessing licensee compliance with Operating Phase & Procedures bundle power and channel power limits.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $4 3k S35k SOk SOk S78k Current Estimates S39k $26k S19k SOk S84k Actual Spent to Date S39k S26k S65k Progress to Date This study was delayed while the contractor provided assistance to AECB staff on an extension to project 2.216.2. Briefings by Ontario Hydro, Hydro-Québec and New Brunswick Power fuel management groups have been completed. The draft final report is being prepared and is expected to be available in June 1994. -70- 2.250.1 Pressure Tube Inspection Capability Program Officer W.A. Grant Contractor C.M.E.L. Enterprises Ltd. Status Work in progress Comments
Original Project Description The aim of this project is-to study defects caused by the degradation of pressure tubes. In the project, data are to be assembled from pressure tube history dockets for 'in-service inspection' and 'periodic inspection' programs for evaluation and comparison with the accuracy needed to predict rates of degradation. The information is to be compiled to produce a document which can serve as an 'atlas' to complement the Fitness-for-Service Guidelines for operating pressure tubes. Currently, all reactors in service have some flaws in their pressure tubes. Justification for continuing operation with degraded pressure tubes requires that a database be maintained of flaws accepted after detection by in-reactor non-destructive examination techniques.
The database produced will assist in establishing a practical program of inspection, help quantify risks associated with the dispositioning of tubes with defects and possibly permit identification of the extent and rate of degradation.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $50k $40k SOk S90k Current Estimates $0k $21k S27k SOk $4Sk Actual Spent to Date $0k S21k $21k Progress to Date The contractor has reviewed Ontario Hydro's nondestructive examination records and is beginning to review the destructive examination records from AECL-CRL. The study is approximately 50% complete. -71-
2.252.1 Training for Troubleshooting Skills Program Officer Y. Akl Contractor Rhodes & Associates Inc. Status Complete Comments
Original Project Description It is proposed to do a review of literature to determine the state-of-the-art training for troubleshooting skills. In addition, a survey of industry and the defence sector for current practice in training for troubleshooting skills is required. Finally, a survey of current troubleshooting training in the nuclear industry should be completed and a comparison made with industry/defence practices. Part of the work performed by operations personnel and maintenance personnel at NPPs involves occasional troubleshooting of equipment/system failure. It is known that there are several different ways in which troubleshooting may be attempted, some of which are more applicable to certain situations than are others. Little is known about the type of training for troubleshooting skills given to personnel who must perform troubleshooting functions in NPPs.
The results of this project will be used to establish acceptable training practice for troubleshooting skills, and to assess training programs in the nuclear industry in terms of such training practice.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S24k Sl6k SOk SOk $40k Current Estimates S 14k S25k SOk SOk S39k Actual Spent to Date $14k $25k $39k
Final Results The final report described in detail the study carried out on training of troubleshooting skills for Canadian nuclear power plants operators and maintainers. The study was conducted in three distinct stages: 1) literature review and production of annotated bibliographies; 2) survey of experts in training for troubleshooting skills in North America; and 3) survey of Canadian nuclear power plant training centres. The review of the literature and the survey of training experts identified the "state of the art" in troubleshooting training with respect to training approaches and training tools. The survey of the Canadian industry found that, generally, the nuclear training centres in Canada offered very similar troubleshooting skills training for personnel. The training seemed to be based on a considerable amount of system theory, with diagnostics theory training often integrated with training of other skills and knowledge. The report included recommendations for methods to improve the troubleshooting task in Canadian NPPs. -72- 2.260.1 Review of Reactor Regulating System Software Program Officer M. Mortimer Contractor Prior Data Sciences Ltd. Status PPE initiated Comments Original Project Description It is proposed to carry out a review of the reactor regulating system software at the Bruce-A NGS, including a summary of the roles and designs of the various programs making up the computerized system. In addition, design changes, Significant Event Reports, and follow-up reports related to incidents or problems contributed to or caused by the reactor regulating system software would be reviewed. Recommendations on the impacts of previously implemented and proposed changes on the reliability and safety of the reactor regulating system would be given. A review of significant events has identified several events in which software design errors or inadequate software changes were either the cause or a contributing factor. Although the regulating system has traditionally received less AECB scrutiny than special safety systems, the events have indicated the potential importance to safety of the reactor regulating system software. The results of this review will assist AECB staff in establishing appropriate recommendations for the planned rehabilitation of these systems. They would also provide a basis for deciding whether more detailed reviews of these systems at Bruce NGS and at other CANDU stations are warranted.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $33k $lk S34k Actual Spent to Date S33k Slk S34k
Final Results The contractor has completed the following items: (a) a review of the Bruce-A Reactor Regulating System (RRS) software design documentation, (b) an analysis of certain Significant Event Reports, and (c) an examination of selected software changes. The contractor has submitted a Final Report which identifies short-comings such as lack of documentation of the RRS software requirements, incomplete and inaccurate design documents, poor documentation of follow-up investigations, and improvement required for the software change control procedures. The contractor made several recommendations, including the development of needed procedures, documentation, and tests for RRS software to be carried out by an independent organization working closely with Ontario Hydro staff. The Final Report has been approved for publication as an INFO-report. -73-
2.263.2 Faulting in Unconsolidated Sediments and Bedrock in Metro Toronto - Phase 2 Program Officer J.L. Wallach Contractor Seismican Geophysical Ltd. Status Work in progress Comments
Original Project Description It is intended to continue the search for and to document the presence of faults in glacial, interglacial and post-glacial sediments in the Toronto area. Interpretation of all such faults will also be an integral part of the study. This work is intended because evidence has already been uncovered in the Rouge River Valley, in eastern Metro Toronto, of faults which cut both the unconsolidated sediments and the underlying bedrock. From a seismic hazard and risk perspective, relevant to the nearby Pickering and Darlington Nuclear Generating Stations, it is necessary to characterize all such faults.
The results of this study will be used to determine the periodicity of brittle fault activity in the region of the nuclear plants, which is relevant io understanding the probability of occurrence of major earthquakes there.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $15k $15k SOk $30k Current Estimates SOk $16k $0k SOk $16k Actual Spent to Date SOk $16k $16k Progress to Date The field work has been completed and a final report is being prepared. -74- 2.267.1 Fire Hazards and Fire Protection Systems Design for CANDU 3 Reactor Facilities Program Officer J. Kavanagh Contractor Fire Cross Consultants Inc. Status Complete Comments Final report has been received. Original Project Description The purpose of this project is to obtain independent expert advice on the merit of the fire protection design proposed by AECL for CANDU 3 reactor facilities. The study will include a review of the fire hazard assessment, the fire protection system design and the specific designs of the building firewater and fire detection and alarm systems. Assessment of the adequacy of fire protection design requires expertise and experience in diverse fields. To ensure rigorous assessment of new designs, AECB staff effort needs to be supported by advice from independent fire protection specialists. This support will enable effective review of design submissions received from AECL and will help to develop the expertise of AECB staff. Results from this project will assist AECB staff in the assessment of the adequacy of the fire protection system proposed for CANDU 3 reactor facilities.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $25k $5k SOk SOk $30k Actual Spent to Date $25k $5k $30k
Final Results A two day seminar was given to AECB staff on fire hazards assessment and fire protection system designs for CANDU reactor facilities. The final report presented an assessment of the merits of the fire protection system design proposed by AECL for CANDU-3 reactor facilities. It included a critical review of documents which addressed the fire hazards assessment, the fire protection system design and the specific designs of the building firewater, fire detection and alarm systems that have been completed for CANDU-3 reactor facilities. The report was not issued as an AECB INFO document because the study involved a review of proprietary information. Final Evaluation This project provided useful training for AECB staff, plus a document review which was used by AECB staff in the assessment of the CANDU-3 design. -75- 2.269.1 Brittle Faulting Along the St. Lawrence Valley Fault System - Phase 1 Program Officer J.L.Wallach Contractor Martha Grier Status Complete Comments Report in preparation.
Original Project Description It is intended to compile existing information from articles, reports, theses, etc. in order to compile a lithological map of the Precambrian (Canadian Shield) and Paleozoic rocks along the St. Lawrence River from Cornwall, Ontario and Massena, New York through the 1000 Islands region to Prince Edward County, Ontario. The area of coverage shall extend at least 30 km north and south of the St. Lawrence River. Should there be sufficient information, a geological base map at a scale of 1:250,000 will be prepared and will cover the area designated above.
This work is intended as a preliminary step to carrying out Phase 2 and to determine whether or not lithological units are truncated by possible faults.
The results of this study will be used to provide a base map and to guide in identifying potential areas for detailed work in Phase 2.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S8k SlOk SOk SOk S18k Actual Spent to Date S8k SlOk S18k
Final Results The study found evidence of brittle faulting along both sides of the St. Lawrence River, at least as far up as Kingston. This supports a change from the position that the St. Lawrence fault system stops at Brockville. Evaluation The pp. ject provides an excellent reference base for in-depth investigation of faulting along the St. Lawrence Valley. -76- 2.271.1 Reactor Physics Computer Codes Program Officer W.A. Grant Contractor École Polytechnique of Montreal Status Work in progress Comments Original Project Description It is intended to conduct a study in which a detailed assessment is carried out of the capabilities of computer codes which can be used for reactor physics analysis of CANDU plants. The reactor physics staff at Ecole Polytechnique has developed a series of such codes which have been reported on in a number of publications. The proposed study will assess the codes and compare capabilities with reactor physics codes used in calculations performed by the industry. Code development work has been carried out at Ecole Polytechnique in an academic environment which is relatively independent of similar effort on the part of the licensees. An appropriate assessment of applications to CANDU reactors will help determine the usefulness, to AECB staff, of these independently developed codes. AECB staff intend to acquire appropriate reactor physics codes for use in the review of reactor physics matters. Results from this study will provide an evaluation of one suite of such codes.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S60k S40k SOk SlOOk Current Estimates SOk S18k $30k SOk S48k Actual Spent to Date SOk S18k S18k Progress to Date École Polytechnique and AECB staff are adapting a suite of computer codes to run on an AECB RISC based PC computer. A study of absorber rod reactivity worth for the Pickering A reactors is being used to assess the codes and to compare results with commissioning data available from a recent Pickering absorber rod refit. Computer modelling of the Pickering reactor core and structures is underway. This project is approximately 30% complete. -77-
2.272.1 Use of Acoustic Emission Techniques for Defect Detection Program Officer J. Kavanagh Contractor CANSPEC Group Inc. Status PPE initiated Comments Draft final report being reviewed.
Original Project Description This study is to examine the feasibility of using acoustic emission techniques for detection of degradation of pressure boundary components. Components in which the extent and rate of degradation can be monitored by acoustic emission are to be identified and acoustic emission techniques that could be applied in each case are to be reviewed. Techniques are needed to provide for in-service screening of pressure boundary components over areas which may bo too extensive to permit routine coverage with rigorous non-destructive examination techniques. Global screening devices can identify areas that may contain conditions which could lead to degradation and a hazard to the integrity of the pressure boundary. Use of such devices would permit early identification of degradation sites and enable follow-up detailed inspections and implementation of remedial measures. This study is needed to provide AECB staff with an evaluation of the merit of acoustic emission for use as a practical technique for on-line monitoring of degradation. Results obtained would be used as resource material to assist in the assessment of proposals by licensees for use of acoustic emission techniques (in lieu of visual inspection) or to justify a lower frequency of other non-destiuctive examinations.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S35k SOk SOk S35k Current Estimates SOk S33k S2k SOk S35k Actual Spent to Date SOk S33k S33k
Final Results The report summarized the tasks performed as part of an examination of the feasibility of using acoustic emission techniques for defect detection in CANDU nuclear power pressure boundary components. The technology behind various acoustic emission monitoring techniques was identified. An assessment was performed of acoustic emission techniques for in-service conditions similar to those in nuclear pressure boundary components. The acoustic emission testing techniques that may be applicable to CANDU components were identified and recommendations were given as to their suitability for in-service use. -78- 2.273.1 Flaw Tolerance of Steam Generator Tubes Under Accident Conditions Program Officer W.A. Grant Contractor Stern Laboratories Inc. Status Work in progress Comments
Original Project Description Experiments are required to investigate the flaw tolerance of steam generator tubes under loads (internal pressure and external thermalhydraulic load) expected under extreme accident conditions. The tests should cover a range of flaw types and sizes and should include ones similar to those found in CANDU steam generators. The steam generator tubes form a boundary between the reactor primary heat transport coolant and the secondary-side coolant. There is a need to avoid or minimize leakage across the tube boundary to prevent significant releases outside containment. Where the tubes are subject to degradation in service, eventual failure normally is detected as an indication of low leakage from a single tube. While such low leakage can be tolerated, degradation could also result in occurrence of multiple tube failures under abnormal loading conditions. The consequent high rate of loss of coolant could exceed bounds that have been examined in the safety analyses. Methods that exist for detection of steam generator tube degradation do not give reliable indication for all types of flaws. The proposed tests are needed to provide AECB staff with a measure of the flaw tolerance of tubes. This will, hence, enable assessments of the rigour required in monitoring programs aimed at reduction of the risk of multiple tube failures under accident conditions.
Results obtained will be used in the evaluation of monitoring programs and acceptance criteria proposed by licensees for steam generators at nuclear power plants.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk SlOOk S20k SOk $120k Current Estimates $0k $48k $94k SOk $142k Actual Spent to Date $0k $48k S48k Progress to Date The contractor, Stem Laboratories, has fabricated an experimental tube bundle and flow transition assembly to fit into an existing fluid-flow test rig. Commissioning tests to demonstrate that the flow rig is capable of operation in the fluid inelastic instability domain will begin in May. -79- 2.274.1 Selection of Predictive Maintenance Tasks Program Officer J. Kavanagh Contractor Wardrop Engineering Inc. Status PPE initiated Comments Draft final report being reviewed.
Original Project Description The aim of this project is to obtain a critical review and comparison of 'reliability centered maintenance1 and 'degradation mode analysis' methodologies and hence to determine which logic process provides the most beneficial means for identifying predictive maintenance tasks and activities. A significant number of nuclear power plants globally have been employing reliability centred methodologies for specification of applicable and effective maintenance tasks for their plant equipment. Approximately 60 percent of all nuclear power plants in the United States are upgrading their maintenance practices through reliability centered maintenance assessment processes which are patterned after EPRI-sponsored pilot projects. Similar optimization and maintenance activities based on reliability centred maintenance approaches have been adopted in Europe and Japan. In Canada, a reliability centered maintenance program has been considered for application at only one nuclear power facility. Degradation mode analysis has been used in the aircraft industry and has been proposed for the nuclear industry, but it has not as yet received the same attention as reliability centred maintenance.
The review of the two methodologies will provide AECB staff with sound information for assessing maintenance programs and identifying the advantages and disadvantages associated with each of them.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $40k SOk SOk S40k Current Estimates SOk $36k S4k SOk $40k Actual Spent to Date SOk $36k S36k
Final Results The report presented findings from a review of reliability centred and degradation mode analysis methods for application in the development and implementation of plant maintenance programs at nuclear power plants. An assessment of the merits of reliability-centred maintenance and degradation mode analysis and DMA for application in the nuclear industry, in general, and CANDU stations, in particular, is provided. -80- 2.275.1 Failure Rates in Piping Manufactured to Different Standards Program Officer J.Kavanagh Contractor G.D. Cooper Consultants Inc. Status Work in progress Comments Original Project Description The purpose of this project is to obtain a comparison of failure rates for piping manufactured to different standards. It will entail a review of available literature and data on failures in piping. Currently, it is assumed that failure rates of nuclear piping are less than those of conventional piping. Knowledge of the design code requirements which give rise to any of the perceived differences could make design classification of components more rational, lead to an improvement in safety and reduce undue conservatism in design requirements.
Findings from the study will assist AECB staff in the assessment of requests for changes in design code category and will facilitate specification of alternative measures needed for assessment of safety and reliability.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S50k SOk SOk S50k Current Estimates SOk S 10k $40k SOk S50k Actual Spent to Date SOk S 10k SlOk Progress to Date The collection of relevant data has been initiated through preliminary searches of local databases and contact with technical libraries. Potential sources of information in the petroleum and insurance industries have, been identified. The next stage of the project will involve identification and acquisition of relevant material. -81- 2.276.1 Independent Verification in Operations at Nuclear Power Plants Program Officer J. Kavanagh Contractor Human Factors North Inc. Status PPE initiated Comments Draft final report being reviewed.
Original Project Description The purpose of this project is to study approaches used in nuclear power plant quality assurance programs in other countries for independent verification in operations. The project is to review the approaches used and to assess their effectiveness in detecting and subsequently preventing deficiencies. The review is to include coverage of the measures taken to preserve independence relative to the performance of work on the one hand and verification activities required as part of the quality assurance program. Audits completed by AECB staff on licensee quality assurance programs show that insufficient verification is performed and that where such activities are carried out there is often a lack of independence in the implementation of the process. As a consequence, failures have arisen that could be attributed to the lack of independent verification. On occasion, the role of supervisory and independent verification activities are confused. A study is needed to provide a basis for development of a strategy that may be applied for independent verification of various areas of activity in operations.
Results of the study will aid the selection and implementation of a well-defined approach for independent verification in operations at nuclear power plants.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $0k S40k $40k S40k $120k Current Estimates $0k $30k SlOk $0k $40k Actual Spent to Date $0k S30k S30k
Final Results A critical review has been completed of the use of independent verification inspections in nuclear power plant operations in other countries. Within the scope of this project, visits to obtain first hand information from nuclear power plant facilities in the USA, Japan, France, Germany and Canada were undertaken. An assessment has been made of the effectiveness of the approaches used in these countries for the detection and prevention of deficiencies. The final report presented an assessment of the merit of independent verification and indicates areas for routine or occasional use. Policy recommendations for independent verification in operations at CANDU nuclear power plants were also given. -82-
2.279.1 Evaluation of Training Programs for Nuclear Operations Personnel Program Officer Y. Aki Contractor Mazour Associates Inc. Status PPE initiated Comments
Original Project Description It is intended to utilize the services of a person(s) with proven experience and expertise in the evaluation of Nuclear Power Plant training programs to review our evolving techniques in this area. It is anticipated that this assistance would be in the form of reviews of our current procedures and methods together with the joining of one, or more, site evaluation visits by AECB staff. Training program evaluation is considered an effective technique to provide assurance that Nuclear Power Plant personnel will have the necessary competence when performing their job functions. This technique, as a regulatory activity, is still under development but is considered a completely valid technique in providing job competence assurance.
The anticipated transfer of experience and expertise is expected to assist the AECB in performing effective training program evaluation in a shorter time span.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $6k S 14k SOk SOk S20k Current Estimates $6k $15k $0k SOk S21k Actual Spent to Date S6k S15k $21k
Final Results The consultant participated in two of the AECB training program evaluation inspections at Point Lepreau and the Ontario Hydro Western Nuclear Training Centre. The main recommendations were: 1) to ensure that each generating station's training program was "owned" by station management and was not perceived as solely a product of the training department which was dispensed to the station. The station must own, and be seen to own, the training programs which exist for its staff; 2) that the approach adopted by the AECB of identifying weaknesses and then putting the onus on supplying the plans for corrective action with the station was preferred (The alternative of offering recommendations will usually elicit specific actions to address the recommendations only); and 3) that the AECB should change its proposed topic for the next evaluation from one where it looks solely at a portion of the training process, the analysis of training requirements, to one where it looks at a complete training program. -83-
2.280.1 Structure for Human Factors Guides Documents for Nuclear Licensees Program Officer Y. Akl Contractor Rhodes & Associates Inc. Status PPE initiated Comments Original Project Description The AECB plans to develop documentation that will provide to the nuclear industry in Canada a set of human factors guidelines for use as regulatory and operational guiding principles and methods, and for use in establishing specific human factors requirements in equipment and system design and evaluation. This proposed contract would form one stage in this development process. The AECB has to indicate clearly to the licensees the nature of the human factors issues that must be addressed and the scope of the available human factors knowledge that should be applied. The proposed set of guidelines documents would form a common ground on which the application of human factors to specific projects and to specific stages of system development can occur. The products of this contract will be used as the specifications for the development of the technical content of the guidelines documents. These specifications should be sufficiently detailed so as to be portable to any chosen human factors consultant for documents development.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S48k SOk SOk SOk S48k Actual Spent to Date $48k $0k $48k
Final Results The final report specified the content, function and appearance of three proposed human factors guiding documents to be used by the AECB and its licensees. These three guiding documents were: 1) Human Factors Process Guide; 2) Human Factors Activities Guide; and 3) Human Factors Design Integration Guide. The specifications were developed by examining the best documents as identified in project 2.213.1 and a brief literature review. The best features and content were selected from existing documents and used to develop specifications to produce comprehensive and consolidated documents. -84-
2.280.2 Human Factors Guiding Documents - Part 3 Program Officer Y. Akl Contractor PHF Services Inc. Status Work in progress Comments
Original Project Description The AECB aims to develop a series of regulatory guides on specific aspects of the content of the Policy Statement on Human Factors. In this last of three parts the contractor will use the specifications developed in Part II ("Specifications for Human Factors Guiding Documents", Project No.: 2.280.1) of this series of projects, and will write the actual human factors guiding documents.
The AECB has to indicate clearly to the licensees the nature of the human factors issues that must be addressed and also the scope of the relevant professional knowledge and experience that should be applied to those issues. This project will fulfill that goal.
The results of this work will facilitate the conduct of human factors regulatory activities by providing to the licensees some indication of what is expected with regard to the application of human factors in the nuclear industry.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk SOk S50k SOk S50k Actual Spent to Date SOk SOk SOk
Progress to Date Contract awarded to PHF Sévices Inc. -85-
2.283.1 Human Factors Issues in Fuel Handling Program Officer P. Webster Contractor Human Systems Inc. Status Work in progress Comments Original Project Description This study will assess human factors issues in fuel handling at DNGS against known criteria. These issues include: tasks and their interactions and temporal interdependencies; automated sub-processes and software programs development and maintenance; the person-system interface; environmental influences on the job; manning and staffing practices; and the personnel system for the production of operators and maintainers for this system. An AECB staff review indicated that the number of fuel-handling incidents at CANDU facilities has been increasing. A first step that has been proposed to address this matter is a study at DNGS to develop audit plans for the review of fuel handling processes. This proposed human factors study will provide information on fuel-handling activities that will complement the results from the audit plan study to give the AECB a comprehensive approach to this NPP work process.
Since the AECB staff have had little regulatory involvement with fuel handling activities, improved knowledge is required for evaluation of the operation of these systems. This study will provide information to that end.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S70k SOk $0k S70k Current Estimates SOk Slk S70k SOk $7 Ik Actual Spent to Date SOk Slk Slk Progress to Date Bids have been received from various consultants in response to the Request for Proposals, and are currently under review. -86- 2.284.1 Communications Processes in NPP Maintenance Program Officer P.Webster Contractor Status Postponed Comments Original Project Description The purpose of this project is to conduct studies and interviews at designated nuclear power plants on the communications processes in maintenance activities. These should address communications links, work relationship, procedures, instrumentation, miscommunications, and responses to problems. This will require a definition of the command and control structure employed in maintenance, its communication, the need for coordination, and an assessment of the main communication links into and out from this structure. This is one of a series of studies that investigates the actual operation of the operations and maintenance work groups in a nuclear power plant. Once it has been established how communication flows occur, and where the focal points for communication are, it will be possible to develop a better understanding of the causal sequences of incidents and accidents. The results of the communication studies (this project and project 2.212.1) will be integrated with the findings from the studies being conducted simultaneously on supervision in operations and maintenance (projects 2.214.1 and 2) to clarify how these groups actually function in daily plant activities.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $0k $50k SOk SOk S50k Current Estimates SOk SOk $50k SOk $50k Actual Spent to Date SOk SOk SOk Progress to Date This project was postponed to FY 94/95. -87- 2.286.1 Guideline for Assessment of Computer Hardware Used in Safety Related Systems Program Officer Y. Akl Contractor Numct Engineering Ltd. Status Work in progress Comments
Original Project Description It is intended to perform a review of existing standards used for the design and quality assurance of computer systems (as part of safety related systems). Standards used for computer hardware design should also be reviewed and related to the standards pertaining to computer systems. Discrepancies should be noted and improvements should be proposed. The documentation that the regulatory agency should review, as a minimum, should be proposed.
Computer changes are being planned for CANDU nuclear power plants' safety related systems. Guidelines for the regulatory assessment of software used in safety related systems have already been developed. However, no similar guidelines exist for the assessment of the computer hardware used in safety systems, to ensure correcmess. completeness, reviewability and unambiguity of the specifications and to ensure that the design meets these specifications.
Results will be used in the assessment of computer hardware changes and associated documentation as well as new computer hardware design documentation for computers to be used in safety related systems.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $0k S60k SOk SOk S60k Current Estimates $0k $5k $50k $0k S55k Actual Spent to Date SOk $5k S5k Progress to Date The consultants researched existing national and international standards, codes, recommended practices, standards design requirements and relevant documented specification sources for the design and supply of computer systems and computer hardware for use in applications that involve safety. The first interim report identified twelve standards that have the potential to contribute towards the project objectives. The report also included a list of information articles other than standards, a list of standards organizations and a list of safety regulators. -88- 2.288.1 The Assessment of Field Training for Nuclear Operations Personnel Program Officer Y. Akl Contractor Safety Management Services Inc. Status PPE initiated Comments
Original Project Description It is intended to perform an assessment of field training of Nuclear Power Plant operations personnel. The initial project would concentrate on Level 3 and 4 Systems Training for the Nuclear Operator job family, at the Pickering Nuclear Generating Station. The contractor would produce a plan outlining specific areas to be studied and the expected extent of the information to be collected. Field work, with OCD staff participation, would follow, to assess field training in a chosen specific subject area (specified personnel categories and systems). A significant portion of the training given to all types of Nuclear Power Plant operations personnel is conducted in the field, over an extended period, away from the normal training environment. This training provides the bulk of the skill requirements needed to perform field work competently and safety. Mainly due to lack of resources, the quality of this vitally important training has not yet been subjected to any systematic form of assessment by OCD. This situation should be rectified by suitable ongoing assessments being performed at the earliest opportunity
In addition to providing OCD staff with detailed results of an assessment carried out as part of the project, the methodology would also form the basis of subsequent AECB reviews.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $5k $15k SOk SOk S20k Current Estimates SOk S30k SOk SOk $30k Actual Spent to Date SOk S30k $30k
Final Results The consultants conducted a study to review the on-the-job training program for Ontario Hydro Personnel. The study focussed on the field operators at Pickering NGS. The assessment process included: 1) a review of corporate policies and procedures; 2) a review of industry standards and practices 3) a review of station and training department policies and procedures; 4) field observations of job tasks by qualified operators; 5) field observations of the implementation of the on-the-job training program; 6) interviews with station and training personnel; 7) follow-up review of station documentation and 8) identification of program and implementation strengths and weaknesses. The main conclusions were that Ontario Hydro's corporate policies and procedures are generally consistent with industry guidelines requiring a systematic approach to training; the field supervisory function is key to the successful performance of field operator activities; and Pickering NGS field operator performance is not consistent with a systematic approach to training. The consultants recommended that the AECB establish the assessment process that was used in the Pickering NGS field operator on-the-job training as the basis for future assessments of on-the-job training; review the field operator on-the-job training at other stations to determine if identified conclusions are a generic issue or specific to Pickering NGS and identify the priority for assessments of on-the-job training for other work groups. -89- 2.289.1 CANDU 3 Primary Heat Transport System Erosion/Corrosion Program Officer M. Santini Contractor D. Lister Status Work in progress Comments Original Project Description It is intended that expert advice be sought to evaluate the effects of CANDU primary heat transport system erosion/corrosion concerns identified by AECB staff, to support the findings through reference to existing experimental/theoretical literature and to identify the need for experimental programs to resolve the issues. Because of erosion/corrosion concerns, a fluid velocity limit is imposed as a thermalhydraulic constraint in the sizing of CANDU primary heat transport system feeders. Based on single-phase erosion/corrosion tests performed in the early 1980s (IR-522, March 1984), AECL is proposing a single-phase fluid velocity limit for CANDU 3 feeder sizing that is 25% higher than that used in previous CANDU designs. AECB staff believe that there is insufficient evidence to warrant this 25% increase in the feeder sizing velocity limit. In addition, there are other concerns with respect to erosion/corrosion that have not been adequately addressed in the past (i.e., the effect of excess hydrogen in the Primary Heat Transport System, the effect of substantially increased feeder flows resulting from the refuelling operation, and the effect of two-phase flow on erosion/corrosion).
Consultation with an expert in the area of erosion/corrosion will aid AECB staff in assessing the acceptability of the single ended refuelling concept being proposed by AECL for the CANDU 3 design.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk SlOk SOk SOk SlOk Current Estimates SOk S18k S6k SOk $24k Actual Spent to Date SOk S18k S18k Progress to Date The contractor has reviewed a submission by AECL and erosion/corrosion effects in CANDU 3. The draft final report was in preparation by the contractor. -90- 2.295.1 Human Reliability Data Collection and Analysis Program Officer P. Webster Contractor John WreathaU & Company Inc. Status Work in progress Comments
Original Project Description It is intended to investigate the current state of the art regarding the inclusion and assessment of human performance considerations in reliability analyses. Human performance is a factor which may significantly contribute to the failure of a system to meet its design intent. Including appropriate modelling of human performance in system reliability analysis will provide for more complete system failure models and permit assessment of the level of contribution to overall system failure. This project will provide AECB staff with information on the methods currently available in human reliability analysis. The results will be used in the review of reliability submissions to determine the adequacy of the human performance modelling and recommend areas for further development and/or improvement where needed.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S45k SOk SOk S45k Current Estimates SOk $7k SOk $30k $37k Actual Spent to .Date SOk S7k $7k Progress to Date A presentation was received from the contractor on Human Reliability Analysis and its use in Regulatory Applications, with special emphasis on Probabilistic Safety Assessments. This comprises only part of the project. The remainder is on hold pending receipt of the Pickering A Risk Assessment from Ontario Hydro in mid-1994, when a decision will be made on how to proceed.
Final Results This project has been completed. The contractor, John Wreathall, gave a two-day presentation to staff of the Reliability and Risk Assessment section and the Organizational Systems and Human Engineering section of SED-E on issues associated with human reliability data collection and analysis.
The first day of the presentation was titled "State of the Art of Human Reliability Analysis, PSA and Its Use in Regulatory Applications" and covered:
1) HRA models and methods; 2) integration with PRAs; 3) uses in regulatory programs; 4) validation issues; 5) limitations and problems in application.
The second day of the presentation was titled "State of the Art of Human Reliability Data Analysis and Its Use in Regulatory Applications" and made a proposal for a new framework for deriving human error probabilities (HEPs) for use in PRAs. -91- 2.296.1 Impact of Loss of Redundancy on Availability Program Officer P.Webster Contractor CANTECH International Status Work in progress Comments
Original Project Description The current reliability model of systems such as special safety systems and safety support systems are to be reviewed. In particular, it is necessary to examine the acceptable duration of unavailability for reductions of redundancy. In order to meet the unavailability targets, redundancy of components is normally designed into the system. Component failures or faults are uncovered, but because of the built-in redundancy, the design intent can still be satisfied although the reliability is decreased. These Type 3 faults may need to have a time limit like Type 1 or Type 2 when considering both the change in system reliability and greater wear on unfailed components due to increased testing frequency. Further, the reliability models may need to be re-examined in contemplation of a possible change in probability of failure or possibility of a generic failure as opposed to a random failure.
The results of this project will provide regulatory staff with criteria for reviewing Type 3 impairments of running safety systems.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S30k SOk SOk $30k Current Estimates $0k S17k S7k SOk S24k Actual Spent to Date SOk S17k S17k Progress to Date The consultants have produced the Draft Final report, which summarizes aspects of reliability theory applicable to the treatment of redundant components in systems and applies them to an example of the Post Accident Water Cooling System at Darlington. The seminar has yet to be held. -92-
2.297.1 Higher-Level Cognitive Abilities Requirements for Candu Personnel Program Officer y. Akl Contractor Westinghouse Electric Corp. Status Work in progress Comments
Original Project Description It is intended to obtain advice on the methods and techniques that are available for the systematic assessment of the quality and effectiveness of training for authorized operating personnel at CANDU Nuclear Generating Stations (NGSs) in the area of the higher-level cognitive abilities needed to cope with unforeseen, complex plant upsets. Confronting complex, unforeseen multi-fault events requires, on the part of NGS operating staff, the combining of previously disparate and unrelated information, the evaluation of alternative conceptualization of plant states, and logical reasoning to form decisions regarding the course of action to handle the situation. This applies even when symptom-based procedures are used, but even more so when plant conditions go beyond the guidance given in Emergency Operating Procedures, such as in severe accident situations. The problem of addressing higher-level cognitive abilities in training is a complex one that is not readily dealt with by the conventional System Approach to Training (SAT) used to develop NGS operator training. OCD staff believe that efforts to address this matter should be undertaken even though the methods and techniques presently available for determining cognitive abilities training requirements may still be at a preliminary stage of development. Application of these methods and techniques by OCD staff will increase the attention of utility training departments to cognitive abilities acquisition and should, as a consequence, lead to improvements in the operator training programs.
The work should result in means for determining cognitive abilities requirements for authorized operating personnel at CANDU NGSs and for establishing a methodology for conducting assessments of the quality and effectiveness of utility training programs in the subject area.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $20k SOk SOk S20k Current Estimates SOk S6k S54k SOk S60k Actual Spent to Date SOk S6k $6k Progress to Date Contract awarded to Westinghouse Electric Corporation. -93-
2.298.1 FISST Criticality Review Program Officer W.A. Grant Contractor Ogden Environmental and Energy Services Co., Inc. Status Work in progress Comments
Original Project Description It is intended to conduct a detailed assessment of the criticality safety of the Fissile Solution Storage Tank (FISST) facility at Chalk River Laboratories (CRL). The study should also include a literature search and selective site reviews of comparable nuclear facilities in other countries.
A fissile fluid waste is generated from irradiated U-235 targets in the production of Mo-99. The fissile U-235 and acid waste are recovered and stored in a specifically-built tank (FISST). The concentration limit for U-235 in this tank was recently increased. CRL has postponed plans to construct additional fissile storage tanks, and may request further increases in U-235 concentration storage limits. An independent review of FISST criticality safety is needed to support the AECB staff assessment of the safety issues that arise.
Results of the work would be used in the licensing assessment of criticality safety margins in the FISST facility, or any similar future facilities.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $70k SOk SOk S70k Current Estimates SOk $12k S58k SOk S70k Actual Spent to Date SOk S12k S 12k Progress to Date This project was started late in fiscal year 1993/94 due to difficulties finding a suitable specialist. AECL-CRL requested, in February 1994, approval for another increase in the storage limit of their fissile solution storage tank (FISST) that is part of their Mo-99 radio-pharmaceutical production facility. The contractor is reviewing AECL's criticality control procedures, operator training and monitoring facilities for FISST and comparing and contrasting them to international requirements. This study complements work underway at AECL-CRL by acquiring information from international regulatory agencies. -94- 2.301.1 Assessment of Darlington SDS Computer Hardware Program Officer P.Webster Contractor The Liard Group Inc. Status PPE initiated Comments Original Project Description The purpose of this project is to gather additional information on observed performance of computer hardware of the type used in Darlington shutdown System (SDS) trip, display/test and monitors computers. This is to be accomplished by carrying out a critical survey of users other than those involved in the Darlington application. General Automation (GA) computers were originally specified for and installed in Darlington SDS1 trip computers as well as SDS 1 and SDS2 display/test and monitor computers. These computers have experienced a number of faults. The original design has been progressively modified. The question is whether these computers with various degree of modification can operate reliably and meet their performance requirements. AECB experience is limited since all the information on faults, explanation for their occurrences and possible remedies for such faults have come from the Darlington application. Consequently, there is a need for other sources of information which could be supplied by other users who would be surveyed for their experiences on the same type of computer hardware. The additional information from actual experience of other users with operation of similar hardware assemblies will complement the AECB staff review of the Darlington situation. The work may also uncover other potential problems with the computer hardware configuration.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $47k $0k $0k $47k Actual Spent to Date SOk S47k S47k
Final Results This project has been completed. By means of fax or telephone, the contractor made some fifty-seven contacts with potential users of GA computers. Twenty-two organizations were found who were current or former users, of whom seven had machines similar enough to Ontario Hydro's to merit further investigation. All seven users completed questionnaires enquiring about their experience with the machines. Of these, three users were visited and face-to-face discussions held with staff who had detailed knowledge of the performance of the machines. The main conclusions of the project were that there was no evidence of pattern failures or unexplained failure modes. The machines seem to be very reliable and were state-of-the-art for their day, though advances since then make some of their features seem outdated. Other conclusions were that maintenance of peripherals is important, as is environmental control as components age. -95- 2.302.1 Review of Ontario Hydro Program to Reduce Fuel Channel Gap Program Officer w.A. Grant Contractor Qualprotech (Oakville) Inc. Status PPE initiated Comments
Original Project Description It is intended to obtain expert advice on Ontario Hydro's program to design, procure, test, and implement modifications to reduce the gap in the fuel channels. The project will include a critical review of the associated documentation, a technical assessment of the impact of the changes on the fuel handling and fuel management processes and observation of some of the on-site testing. Emphasis shall be placed on the QA aspects of the design as well as component qualification and testing.
In order for AECB staff to conduct the level of in depth review demanded by this activity within the time frame available, the expertise of a consultant experienced in fuel handling and fuel management processes is required.
Results from this project will assist AECB staff in the assessment of the modifications proposed by Ontario Hydro and identify the impact of these changes on reactor safety.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $46k SOk 40k $86k Actual Spent to Date SOk $46k $46k
Final Results The report summarized the findings for a series of quality assurance audits, performed by Qualprotech (Oakville) Inc., during the development stages of several design options proposed by Ontario Hydro. The contractor investigated the procedures Ontario Hydro had in place for the development and qualification of spacer and flow straightening devices and for increasing the length of the fuel bundles. The report has been submitted for internal review and approval before publication. -96- 2.303.1 Paternal Tritium Exposure and Health Effects in Offspring: A Mouse Model Program Officer E. Rabin Contractor Hydro-Québec, Division Radioprotection Status Work in progress Comments
Original Project Description It is intended to estimate the risk of developing leukemia and lymphomas, and other birth defects in the offspring of male mice that were injected with tritiated water (HTO) before mating with unexposed females. This project is proposed because of concern among radiation workers in Canada that exposure of the father to ionizing radiation prior to conception of his children, may result in the development of diseases or other anomalies in the offspring. In 1990, M J. Gardner et al. reported that development of leukemia in children was related to the pre-conception exposure of fathers (who worked at the Sellafield nuclear plant in the United Kingdom) to ionizing radiation. Tritium is a by-product of CANDU reactor operations and is also used in other industries and research laboratories. In the form of HTO or organically-bound tritium (OBT), tritium can reach and possibly be incorporated into the sperm cells, and damage the genetic material, which is subsequently incorporated into the mother's egg cell on fertilization. It is anticipated that the results of this project will provide additional information on whether exposure of the father to ionizing radiation prior to conception can result in deleterious effects in the offspring. (The project is to be co-funded by Hydro-Québec, Ontario Hydro, COG, and the AECB. The estimated cost of the whole project is $300,000.)
- Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S20k $24k SOk $44k Actual Spent to Date $0k S20k S20k Progress to Date The strain of rodent to be used has been selected, and the animals are being bred. Irradiation and dosimetry protocols are being finalized. -97- 2.304.1 Assessment of Bundle Deformation Under Post-Dryout Condition Program Officer M. Santini Contractor Atlantis Engineering Status Work in progress Comments
Original Project Description The purpose of this project is to review an Ontario Hydro submission related to Trip Parameter Effectiveness Criteria involving fuel sheath and bundle behaviour under post-dryout and cyclic dryout/rewet conditions. This should include a review of analytical methods, assumptions used, and experimental support in terms of its validity for power reactor applications. In addition, a survey of new analytical methods and experimental evidence relevant to this submission should be carried out.
Fuel post-dryout behaviour under various accident conditions is a current licensing issue, which is generic to all CANDU reactors.
It is anticipated that the results of this study will assist the AECB staff to evaluate Ontario Hydro submissions on the acceptance criteria of trip parameters and in formulating its recommendations to the Board on a current and future licence applications.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k $47k $2k $0k S49k Actual Spent to Date $0k S47k $47k Progress to Date The consultants have submitted the draft final report, which was being reviewed and commented on by the technical evaluators. The report indicates that there may be some gaps in the experimental evidence to support the Ontario Hydro submission. -98- 2.305.1 Ergonomie Review of Guideline Specifications Program Officer Y. Akl Contractor Human Factors North Inc. Status PPE initialed Comments Original Project Description The AECB aims to develop a series of regulatory guides on specific aspects of the content of the Policy Statement of Human Factors. The second of three parts has been completed whereby the specifications for three human factors guiding documents have been written. The present requirement is for a review of the specifications to: 1) determine their ergonomie acceptability in terms of structure and presentation; 2) ensure that the guides are comprehensive in terms of content coverage. The AECB has to indicate clearly to the licensees the nature of the human factors issues that must be addressed and also the scope of the relevant professional knowledge and experience that should be applied to those issues. This project will ensure that the AECB produced human factors guiding documents that will satisfy this goal.
The results of this study will aid the AECB in producing a set of guiding documents that not only offer a comprehensive content domain, but which also satisfy conventional practice in the field of ergonomics.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S3k SOk SOk S3k Actual Spent to Date $0k S3k S3k
Final Results The reviewers produced an independent assessment of the report entitled "Specifications for Human Factors Guiding Documents" written by Rhodes & Associates (Project 2.280.1). The reviewers found the report, in general, well organized, comprehensive, clear and well researched. However, they recommended that the report can be improved by including additional key references, by presenting the guidance in a way that makes it easier to access and by paying more attention to cognitive engineering principles. It was also recommended to include a vision of the ideal human factors program. Barriers to human factors application in the industry were discussed and suggestions were made to overcome them. -99-
2.306.1 Development of Safety Analysis Review Guides - Part 1 Program Officer P. Webster Contractor JDS Technologies Status Work in progress Comments
Original Project Description It is proposed to amend the scope of work of the contract under which the pilot for a set of Safety Analysis Review Guides is being developed. The amendment will revise the guide which has been produced by dividing it into two parts; one containing specific guidelines applicable to the accident under study and one containing general guidelines which apply to all accidents.
As a feasibility study, a Safety Analysis Review Guide has been developed for a large break LOCA. The guide identifies the key parameters which are required to be addressed in the safety analysis and provides guidelines on the key areas which a reviewer should examine in order to establish that the safety analysis requirements have been met. In the course of developing this guide, it has become clear that certain guidelines apply to more than one accident, so should be gathered together into a general guide rather than be repeated in each individual guide.
The amendment to this project will bring the guide into a condition where it can be presented to AECB staff and licensees, and form the basis for developing further guides. The set of guides will be used by AECB staff in reviewing safety analyses submitted by the licensees.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $46k S24k SOk S70k Actual Spent to Date SOk S46k $46k
Progress to Date The Draft Final Report has been submitted. The contractor has examined the large LOCA analysis in detail and from it has derived the key parameters which are required to be addressed in the safety analysis. The guidelines on the key areas which a reviewer should examine in order to establish that the safety analysis requirements have been met are then developed. The seminar will be held shortly. -100- 2.314.1 Formal Specification of System and Software Requirements Program Officer Y. Aki Contractor GARD Research Consulting Inc. Status Work in progress Comments
Original Project Description The AECB has an on-going program of co-operation and information exchange with the nuclear regulators in Britain, France and the United States. Since nuclear power plant designs are different in the four countries, it is difficult to compare directly the development and regulatory assessment methods for the new software-based protection systems. In order to facilitate such a comparison, the AECB, Britain's Nuclear Installations Inspectorate (Nil), France's Institut de Protection et de Sûreté Nucléaire (IPSN), and the U.S. Nuclear Regulatory Commission (USNRC) have now embarked on a demonstration project. A simplified Boiler Level Control and Protection System has been chosen as an example. Each country will contract the development of this system to a common specification. Each regulator will assess the resulting product. Results will be exchanged and compared so that we can gain a better understanding of the various approaches to software development and assessment. The AECB's approach to system development has divided the Canadian part of the project into three main tasks, or which the current demonstration project is the first. The result of this project is expected to be a set >i documents which AECB staff believe are appropriate to document fully the system, software and safety requirements, to the point where software design could begin. - Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk SOk S70k SOk $70k Actual Spent to Date SOk SOk SOk Progress to Date Contract awarded to GARD Research Consulting Inc. -101-
2.315.1 PSA Applications Program Officer P.Webster Contractor Science Applications Internationa] Corporation (S AIC) Status Work in progress Comments
Original Project Description It is intended to undertake a study to provide advice to AECB staff on applications of Probabilistic Safety Assessments (PSAs) in reactor regulation and on the necessary attributes of PSAs. The consultant will also make a brief review of the Darlington Probabilistic Safety Evaluation (DPSE) and comment on its suitability for these applications. The consultant will: 1) provide a presentation on PSA applications from a regulatory perspective and attributes that must exist in the PSAs for these applications to be valid, with examples; 2) conduct a workshop to demonstrate selected applications using fault/event tree system models; and 3) review the DPSE to determine which applications might be possible. This work is required to prepare AECB staff for its review of several PSAs which will be submitted by licensees' over the next few years. It is anticipated that the AECB will be made aware of such potential applications of PSAs, will understand the attributes that are needed in order for the applications to be valid, and will be able to avoid any pitfalls.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $9k SOk SOk $9k Actual Spent to Date SOk $9k $9k Progress to Date Bill Vesely of S AIC was retained to give a one-day presentation to an audience of AECB staff on PSA Applications, including the importance of prioritization, precursor evaluation, configuration management, maintenance assessment and regulatory interfacing. This was attended by some forty AECB staff. The consultant also gave a two-day workshop to the Reliability and Risk Assessment section of SEDE on how PRAs are used to perform certain applications. There will be no report submitted. -102-
2.316.1 Review of Current UK Nuclear PRA Analysis Program Officer P. Webster Contractor Electrowatt Engineering Services (UK) Ltd. Status Work in progress Comments
Original Project Description It is intended to determine the current state of usage of Probabilistic Risk Assessments (PRAs) in the licensing of nuclear plants in the U.K., including: 1) what PRA regulations or requirements there are; 2) how a PRA is reviewed; 3) how the objective of the PRA determines the manner in which it is carried-out; 4) how system and component interdependencies are determined; 5) what methods are used to conduct sensitivity and uncertainty analyses; and 6) how human reliability is taken into account.
Over the next three years, some half dozen PRA's will be produced by Ontario Hydro to support the continued operation of their plants. The maximum amount of data needs to be extracted from these PRA's, not only in terms of what it is they contain, but also in terms of their intended use. This contract will be the pilot for surveys of the practice in other countries (the U.S. and France are the other countries currently being considered).
The research will aid the AECB in formulating an effective and achievable set of features to be incorporated in the PRA Requirements Document which is currently under preparation.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k $20k $5k SOk $25k Actual Spent to Date $0k $20k $20k Progress to Date The Draft Final Report has been received, detailing UK PRA practice in the areas in which we had requested information. The seminar will be held shortly. -103- 2.318.1 The Use of PVC Cables in CANDU Power Plant Program Officer J. Kavanagh Contractor DJS Associates Status Work statement to PWGSC Comments
Original Project Description It is intended to undertake an assessment of the use of PVC cables in CANDU plants. The study is to include development of a strategy for re-qualification of PVC cables for continued service in existing CANDU stations. Poly vinyl chloride (PVQ insulated cables and cables with PVC jackets were widely used as control and signal cables and low voltage power cables in conventional and nuclear power plants, including all CANDU plants. In a fire (cable fires), PVC will release chlorine and hydrogen chloride which are toxic to humans and corrosive to equipment. There is a need for a review to assess the nature of the hazard and measures that can be taken to qualify existing installations for service. The results of this study would help AECB staff to evaluate the licensees' submissions on re-qualification of PVC cables in their in-service stations.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk SOk $43k SOk S43k Actual Spent to Date SOk SOk SOk -104- 2.320.1 Protection Against Electro-Magnetic Interference Program Officer J. Kavanagh Contractor Status Preparations initiated Comments Internal approval process is underway. Original Project Description It is intended to undertake an independent review of the requirements for protection against Electromagnetic Interference (EMI) in CANDU power plants. This project will study the effects of the transient electromagnetic environment in power stations. Guidelines for review of EMI qualification requirements on solid state protective relays and EMI-sensitive electronic control and data processing equipment will be developed. In an extremely high voltage switching station, interference originating during operation of switching devices might cause protective and control equipment to be damaged or to malfunction. Interference caused by switching devices has been measured in the range of thousands of volts. CANDU plants in Canada are connected to 230 KV, 345 KV and 500 KV switchyards. Low voltage dc control circuits can generate transients with very short duration but with very high instantaneous power levels. The increasing use of VHF and UHF radio transmitters for communication purposes could expose the control and protective devices to radiated electromagnetic interference. There is, hence, a need for measures which protect against undue levels of EMI. The proposed study will provide AECB staff with independent advice on the nature of the hazard and the type of measures required.
The results of this study will help AECB staff to assess the adequacy of EMI qualification of the protective relays and control equipment in CANDU nuclear power plants.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk SOk $41k SOk S41k Actual Spent to Date SOk SOk SOk -105-
2.322.1 Simulator Certification Test Reliability and Validation Program Officer A. Daza Contractor Human Resource Systems Group Ltd. Status Work in progress Comments
Original Project Description The AECB has begun implementation of performance testing on a full-scope control room simulator as part of the authorization process for nuclear power plant (NPP) operators. These new simulator tests replace certain parts of the traditional paper-and-pencil examinations. The present requirement is to determine the reliability and validity of full-scope simulator testing for NPP control room operators.
The AECB has to ensure that operators who receive authorization to operate the controls of a nuclear power plant are competent to do so. To that end, the AECB must use a testing method that will provide the means by which to discern who meets the requirements set for control room operators.
The results of this study will inform the AECB about the reliability and validity of the full-scope simulator testing method.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk SOk S57k SOk $57k Actual Spent to Date SOk SOk SOk Progress to Date Contract awarded to Human Resources Systems Group. -106- 2.323.1 Pressure Tube Fracture Transition to a Guillotine Break Program Officer W.A. Grant Contractor Battelle Status Work in progress Comments
Original Project Description It is intended to search for reports from experiments or service failures of pressurized tubes or piping that resulted in guillotine break; to review this information and prepare an assessment based on fracture mechanics principles of the causative factors in such occurrences; and, taking account of typical designs and materials, to advise AECB staff on the possibility of guillotine break resulting from axially-oriented cracks in CANDU pressure tubes. The acceptance criterion for pressure tube rupture that Ontario Hydro has proposed in connection with fuel fretting at rolled joints assumes that cracks will propagate in the axial direction. Though each of the two instances to date of in-service pressure tube rupture did result in lengthwise splits, at least one experiment since then has produced circumferential failure. Since a guillotine break has more severe consequences than Ontario Hydro has considered, AECB staff require an assessment of the potential for such an occurrence in-reactor.
An independent assessment of potential pressure tube fracture behaviour would assist AECB's review of Ontario Hydro's acceptance criterion.
- Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $0k S54k $0k S54k Actual Spent to Date SOk SOk SOk Progress to Date Preparatory work commenced. -107-
2.326.1 OP&Ps Manual For Review of Significant Event Reports Program Officer J.L. Wallach Contractor Science Applications International Corporation (SAIC) Status Work in progress Comments
Original Project Description It is intended to produce a reference document substantiating the CANDU station Operating Principles and Policies (OP&P) for use in the assessment of Significant Event Reports. This reference document will provide summary explanations for the technical design and safety reasons behind OP&P statements. The report will be prepared in both Official Languages, using appropriate terminology in use at most Canadian nuclear power stations. The first phase of this project will address all Canadian nuclear generating stations.
The AECB Event Analysis Group reviews Significant Event Reports from all CANDU nuclear power stations in Canada. These reports contain information on the event itself, the condition of the operating licence or of the OP&P which has been affected or contravened, and the immediate consequences of the event. However, the reports almost invariably do not provide sufficient detail on the technical rationale for the event to be reported, or on the potential impact of that event on the safety and operation of the reactor in terms of the OP&Ps affected. The Event Analysis Group needs to have instant access to reference material in order to interpret effectively and efficiently the operating experience and its impact on licensing and OP&P requirements. Furthermore, such a document will be of use throughout the AECB for training in licensing requirements. Documentation presently available in this area is quite sketchy. The reference document developed within this project will provide a brief but accurate summary of the technical rationale for each OP&P requirement.
The reference document will be used by the Event Analysis Group to screen reported operational events, to assess the significance of the Event Reports and to assist in prioritizing follow-up actions. The document will also be available to train new AECB staff and foreign staff on design and safety aspects of licensing requirements.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk $5k S41k SOk S46k Actual Spent to Date SOk $5k S5k Progress to Date Work on the project commenced late in fiscal year 1993/94. -108- 2.335.1 Case-Control Study of Prostate Cancer in Canada Program Officer M. Lupien Contractor John R. McLaughlin, Ph.D. Status Work in progress Comments
Original Project Description It is proposed to conduct a feasibility study of a case-control study to investigate an association between prostate cancer and the intakes of tritium and other radionuclides. The feasibility of identifying both mortality and incidence cases of prostate cancer within the cohort of National Dose Registry (NDR) between 1950 and 1993 will be examined. The availability of dose information on the intake of tritium and other radionuclides in the NDR and other sources (e.g., AECL, Ontario Hydro) will be verified. A recent case control study of nuclear workers in the U.K. has reported an increased risk of prostate cancer in workers who were internally contaminated by at least one of the following radionuclides: H-3, Cr-51, Fe-59, Co-60 and Zn-65. The risk was highest in men contaminated by tritium in the presence or absence of other radionuclides. These findings should be further investigated in Canada, since Canadian reactors are moderated with heavy water and large quantities of tritium are produced. It is anticipated that this project will determine whether a case-control study of prostate cancer within the NDR cohort is feasible.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S12k $3k SOk S15k Actual Spent to Date SOk S12k $12k Progress to Date The preliminary review has identified several features of prostate cancer and its risk factors that should be considered in a study that, examines the etiologic significance of internal exposures to ionizing radiation in occupational settings.
Final Results In response to the primary objective of this report, a nested case-control study is proposed as a design that is feasible and an efficient approach for examining the relationship between tritium exposures and the occurrence of prostate cancer. However, at this time such a study in Canada is justifiable on epidemiologic grounds only if a very large relative risk is anticipated for the effect of tritium. The limited epidemiologic data that currently exist are not consistently supportive of such a large expected relative risk. The results of the National Does Registry mortality study, which should soon be available (by December 1994), will likely provide an indication of whether tritium is associated with a greatly increased risk of prostate cancer in Canadian radiation workers. If so, then it is fully justifiable to embark on Stage I of the proposed nested case-control study. - 109-
2.337.1 Report on Faulting in Unconsolidated Sediments & Bedrock Program Officer Jl.Wallach Contractor Martha Grier Status Complete Comments
Original Project Description It is proposed to edit and finalize a report addressing the second phase of a study documenting the presence and characteristics of faults in glacial, interglacial and post-glacial sediments in the Toronto area (Project 2.263.2). This work is proposed to accelerate the report-writing process.
The results of this effort will be a report which will be ready for distribution early in fiscal year 1994/95.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk Slk S2k SOk S3k Actual Spent to Date SOk Slk Slk
Final Results A report from Project 2.263.2 was reviewed and a revised Final Report was prepared. Final Evaluation Effort expended facilitates assimilation of the data and information assembled in Project 2.263.2. -110- 3.101.2 Demonstration of the Feasibility of Directly Dating Quartz - Phase II Program Officer Jl.Wallach Contractor A.L. Odom Status Work in progress Comments
Original Project Description It is intended to obtain samples of rock, the ages of which lie for the most part within the range from about 400 million years to 1,000 million years, and date them using the electron-spin resonance (ESR) dating technique developed in phase 1. This study is proposed in order to establish conclusively that a linear relationship exists between the strength of the ESR signal and the age of the quartz. The existence of this possible relationship was suggested from the previous study in which samples ranging in age from 100 thousand to 400 million years and from 1 billion to 1.4 billion years were evaluated. However, there is a 600 million year data gap between those two groupings and this has to be filled in to confirm or deny the relationship. This work is particularly important due to the recent findings, by AECB staff, along faults parallel to, and within, the CMBBZ. There, quartz occurs as a fracture filling mineral on surfaces which are oriented parallel to the set of major lineaments and known faults which pass beneath the Pickering NGS and probably beneath Darlington as well. The fracture surfaces and the quartz both display slickensides, which is evidence of faulting along these surfaces. It is important to know what minimum age is indicated for the movements along these surfaces. It is anticipated that the results of this study, if they establish that the linear relationship exists, will be useful for determining the age of last movements along faults, even movements within the last 10,000 years. This will, in turn, provide a means for determining whether or not an area is technically stable which, of course, has implications for seismic hazard and seismic risk estimates relevant to nuclear facilities. If there is evidence of faulting in the region of nuclear power plants within that time period, the seismic hazard estimates would have to be revised to reflect an increased likelihood of tectonism and seismicity. The ages of interest in this application are much younger than those to be tested during this study. However, it is necessary to establish reliably that a linear relationship exists over the entire age range before the method can be used as a trustworthy indicator of recent tectonic stability.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S40k SOk SOk S40k Current Estimates SOk $20k S21k SOk S41k Actual Spent to Date SOk S20k S20k Progress to Date This study was commenced late in fiscal year 1993/94. It will be completed late in 1994. - Ill -
3.103.1 Absorbed Fraction of Ingested Uranium in Humans Program Officer K.P. Ho Contractor Bureau of Radiation and Medical Devices, NHW Status "Work in progress Comments
Original Project Description It is intended to determine the absorbed fraction of ingested dietary uranium (from both food and drinking water) in persons, by measuring the content of uranium in their diet and in their fecal and urinary excretions. The currently used annual limit on intake (ALI) for uranium, by ingestion, is derived using a value of 0.05 for the absorbed fraction of ingested uranium. This value is known to have a number of uncertainties, and more work should be done to improve its accuracy. The results of the study are expected to improve the value for the absorbed fraction and hence the estimate of the ALI (oral) for uranium. (This project is being done jointly with the Bureau of Radiation and Medical Devices of NHW. Their contribution consists of the laboratory analyses to be undertaken in this project.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $49k S18k $0k SOk $67k Current Estimates $65k S23k SOk SOk S88k Actual Spent to Date S65k $23k $88k Progress to Date All required samples have been collected from volunteers and controls. The Bureau of Radiation and Medical Devices are currently completing the analyses of the collected samples. -112 - 3.111.2 Evaluation of Data and Models on Uranium Metabolism - North America Program Officer E. Rabin Contractor Radiation Surveillance Associates, Inc. Status PPE initiated Comments
Original Project Description It is intended to test and validate currently available metabolic and dosimetric models for uranium. This is being done with data, obtained from animal experiments and human exposure, that have been, or will be, critically reviewed. Computed excretion patterns will be compared with observed ones. The best predictive models will be identified and improvements to them will be made, if necessary.
Several models for uranium metabolism exist at present, but none seems to describe realistically uranium transfer, retention, and excretion rates in humans. Since individual doses from occupational uranium intake are generally determined from the interpretation of bioassay data (urinalysis), the AECB's Radiation and Environmental Protection Division needs to identify and acquire a reliable tool for calculating doses in the case of exposure to uranium compounds.
It is anticipated that the study will assist in identifying and in providing AECB staff with the state-of-the-art metabolic and dosimetric models for uranium intake. Information obtained under 3.111.1 will be used to modify and verify the model using complete data sets obtained from occupational^ exposed uranium workers.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S195k $18k SOk SOk $213k Actual Spent to Date S 195k $18k S213k
Final Results The researchers have concluded the following: a) first order linear kinetic models are suitable to describe the uranium . intake, deposition, and systemic redistribution to and from the bloodstream; b) the 1CRP model for inhaled class Y compounds of uranium predicts, along with the ICRP systemic model, urinary excretion over time which is much less than that observed in humans occupational^ exposed by inhalation (a modified ICRP-30 lung model is proposed); c) skeletal retention of uranium seems to be adequately modeled by a single long-term compartment with a retention half-time of 2.4 years, other than possibly for a very fast labile compartment on bone surfaces with a residence time measured in hours; d) modeling the retention in the kidney requires two terms, 28% with a half-time of 3 days, and 1.2% with a half-time of 70 days; e) as suggested in ICRP-30, gastrointestinal absorption of 5% for soluble uranium compounds is too high; a mean value of approximately 0.7% is better supported by the literature. -113 - 3.121.3 BIOMOVS II - International Assessment of Biosphere Models Program Officer M.R. Avadhanula Contractor Status Work in progress Comments There is no contractor. This is an international co-operative research programme.
Original Project Description It is intended to participate in and partially fund the second phase of BIOMOVS (BlOspheric MOdel Validation Study) which is an international co-operative effort to test biospheric models designed to calculate the environmental transfer and bioaccumulation of radionuclides and other trace substances. BIOMOVS II is being organized and jointly funded by the Swedish Radiation Protection Institute (SSI), the Empressa Nacional de Residuos Radiactivos S A (ENRESA) and the Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (CIEMAT) of Spain, Atomic Energy of Canada Limited (AECL) Research Company and the Atomic Energy Control Board (AECB) of Canada. The first phase of BIOMOVS (3.121.1), which was mainly an international intercomparison of environmental assessment models and their predictions, was initiated in 1986 with the participation of 14 organizations from 12 countries including Canada, and was completed in 1990. At the final meeting of BIOMOVS, the participants concluded that a continuation of the effort, with additional studies and funding support, would be useful. BIOMOVS 11 continues the study of a number of issues that were identified in the first phase of the study to be of special importance in assessing the reliability and validity of environmental transfer modelling. Emphasis is placed on scenario development and model evaluation, uncertainties in the predictions of assessment models and mathematical aspects of assessment models. The study involves modellers and other scientists working in the field of safety assessment and other related disciplines, as well as experimentalists performing laboratory or field studies in these areas. The results may be used in conjunction with other model-testing studies.
Involvement of AECB and Canadian experts in this program is important in ensuring the credibility of modelling activities in Canada and in regulatory decisions based on such modelling. The results of the study will provide the AECB with a greater understanding of the validity and reliability of biosphere models used to support licensing assessments of environmental impacts from nuclear facilities.
• Past 93/94 94/95 Future Total
93/94 Program Document Estimates $220k SI 10k SllOk SI 10k S550k
Current Estimates $186k S75k SI 10k SllOk $481k Actual Spent to Date S 186k S75k $26 Ik Progress to Date The fourth workshop of BIOMOVS II took place in Vienna in September 193. The meeting was attended by about 60 representatives from organizations in 15 different countries. A series of meetings of individual Working Groups was held to discuss the progress and results of model intercomparison work. The next, fifth workshop of BIOMOVS II is planned to be held in the autumn of 1994.
Publications To date, four BIOMOVS II Progress Reports, ten BIOMOVS II Newsletters and one technical report on "Guidelines for Uncertainty Analysis" have been published. -114 - 3.123.2 In Vivo Dissolution of Inhaled Uranium Compounds Program Officer E. Rabin Contractor Centre Hospitalier Universitaire de Sherbrooke Status Work in progress Comments
Original Project Description It is intended to study, in vivo, the dissolution of uranium compounds. This project is the follow-on work to the earlier project 3.123.1 'Influence of Macrophages on Dissolution of Uranium Compounds' which consisted of two preliminary studies and a feasibility study. The current project will investigate the rates at which uranium, thorium, radium and lead (Pb-2I0), from dust samples, clear the trachéal lobe of sheep, and the subsequent translocation of the radioisotopes to, and retention by, the animals' liver, kidney, skeleton and gonads. Experimental data on the biokinetics of uranium in man are not consistently compatible with in vitro solubility rates (of the same compounds) which are widely used in current dosimetric models. Research by the French Atomic Energy Commission indicates that the solubility rate is significantly enhanced by the presence of macrophages in, and by the addition of oxygen to, simulated lung fluid. The solubility rates observed under these experimental conditions seem to represent more accurately the clearance rates observed in man. In project 3.123.1 it was observed that the macrophages did not survive long enough in vitro in the presence of uranium compounds to obtain information on the dissolution rates of the least soluble of the compounds. However, an in vivo experimental system, with a distinct advantage, is available to measure lung clearance rates directly and provide needed information on dissolution rates in lung fluid. The Centre Hospitalier de Sherbrooke has shown that the respiratory tract of sheep, with its trachea! lobe that branches directly from the trachea, lends itself to localized deposition of test materials without significantly impairing respiratory functions. The present study will use sheep as an experimental animal. Furthermore, information pertaining to the translocation of the radioisotopes to tissues, without which doses to man cannot be calculated with reasonable confidence, will be obtained.
It is anticipated that the results of the study will provide the AECB with realistic solubility parameters to be used for the determination of bioassay guidelines, and for exposure and dose calculations. (Note: The radiochemical analyses required for this project will be carried out under a separate contract with a private laboratory. The project pertaining to that contract is #3.160.2, "Radionuclide Analysis in Tissue").
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SlOk $97k S8k SOk $115k Current Estimates SOk S53k $5 Ik S12k SI 16k Actual Spent to Date SOk S53k $53k Progress to Date Sheep have been purchased and are being exposed, in separate groups, to low grade uranium dust, high grade uranium dust, uranium concentrate, uranium dioxide, titanium dioxide (an inert dust), and silicon dioxide (a biologically active, non-radioactive dust). Tissue samples taken from the exposed animals are being sent to Becquerel Laboratories Inc. (Mississauga, Ontario) for analysis of total uranium, Th-230, Ra-226 and Pb-210 content (under RSP project 3.160.2). - 115 - 3.134.1 RBE from a Microdosimetric Approach Program Officer E. Rabin Contractor Hamilton Regional Cancer Centre Status Complete Comments
Original Project Description It is proposed to conducfa critical review of the literature on the state-of-the-art of the relationship between radiation-matter interactions in cell components and the Relative Biological Effectiveness (RBE) of high linear energy transfer radiation with an emphasis on the effect of alpha radiation on the cells of human bronchial epithelium. In spite of elaborate laboratory experiments and epidemiological studies, risk coefficients for specific types of radiation are determined with uncertainties, at best, of the same magnitude as the variable being determined; in some cases, uncertainties are as large as one order of magnitude. An important parameter in establishing risk coefficients is the RBE of the type of radiation under consideration. Microdosimetry has been a powerful tool in the study of radiation-matter interaction in living cells, and of the changes induced in cell components at the molecular level. The continuous refinement of microdosimetric models has led progressively to a better understanding of radiation effects in the case of radionuclides incorporated in cell components, as well as that of exposure to external radiation. It seems, at present, that convergent efforts in epidemiology, animal experiments and microdosimetry are necessary to determine the RBE, and therefore the risk, more accurately. At a time when regulatory limits on exposure to radon daughters are under review, it is important to understand, as completely as possible, the mechanisms that lead from irradiation of lung tissues by alpha particles to malignancies.
It is anticipated that a critical review of the state-of-the-art research on the relationship between radiation-matter interaction and biological modification at the nucleus, chromosome, or gene levels in the cell will provide necessary information to AECB staff in this domain and will strengthen the scientific bases upon which regulatory decisions are made.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $16k $12k $0k $0k $28k Current Estimates $15k SlOk $0k $0k $25k Actual Spent to Date S15k SlOk S25k
Final Results The conclusions reached by the investigators included the following: 1) The physical processes determining particle track structure in cells (and tissues) were reasonably well understood and information regarding the fundamental parameters was available. 2) The efficiency of high LET radiation in producing double strand breaks (DBSs) in DNA was not much greater than that for low LET radiation and was not commensurate with the much higher ratio of efficiency for cancer induction by high LET radiation with respect to low LET radiation. 3) In certain circumstances dictated by a combination of factors including LET, dose, and dose rate, the frequency of oncogenic transformation induced by a protracted dose might be enhanced with respect to that induced by an acute dose. 4) Recent experiments involving sister chromatid exchange induction by a-particles determined very high relative efficiency for this end point and provided evidence for multi-cellular response. 5) Based upon publications reviewed in this report it was concluded that the potential existed for the calculation of risk estimates for radon daughter inhalation. Final Evaluation The evaluators and the Project Manager made it clear that this report was worth the expenditure. The reader of this report should keep in mind recent findings in the epidemiology of lung cancer in miners exposed to Rn progeny, or to Rn and As simultaneously, and in animal experiments at very low exposure and exposure rates. Some epidemiological studies seem to indicate the possibility of a threshold for the induction of lung cancer, and that indication is apparently supported by animal experimentation. Fig. E6 of the report is revealing in this respect. -116 - 3.135.1 Measurement of Tritium in Canadian Food Items Program Officer M.R. Avadhanula Contractor AECL Research - CRL Status PPE initiated Comments Final draft report under review. Original Project Description It is proposed to develop and validate techniques of tritium measurement and to conduct analyses and measurements of organically bound tritium (OBT) in Canadian food items, particularly those produced in the vicinity of tritium-emitting facilities. Tritium is a relatively important radionuclide that is released through atmospheric and aquatic pathways from CANDU nuclear generating stations (NGSs) and from other facilities and licensed activities. These releases are limited by the AECB through the setting of derived release limits which are calculated values based on the dose limit for members of the public. Reports of elevated levels of OBT relative to aqueous tritium (HTO) in food items and in human tissue have raised concern about the effect of such conditions on the validity of dose estimates based on the assumption that all tritium intake is rapidly dispersed throughout the body water and may be monitored adequately by urinalysis. The results of a critical review of the available literature presented in a recent AECB report, "The Assessment of the Significance of Organically-Bound Tritium in Environmental Materials" (INFO 0283), indicate that the specific activity of OBT was higher (in the range of 1 to 4) than that of HTO in most food items studied. The report also identified that adequate data on Canadian diet items are lacking and, further, that the meagre data, particularly on meat, as reported in the open literature are uncorroborated. The results of this project will provide information to AECB staff on the significance of the OBT contribution to tritium dose and, as well, greater confidence in regard to the derived release limits for tritium from Canadian NGSs and from other tritium-emitting facilities.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $8 Ik S5k SOk SOk S86k Actual Spent to Date $8 Ik S5k S86k
Final Results Concentrations of HTO and OBT in Perth meats and vegetables were in the range 2-10 Bq/L water equivalent. At Pickering, grocery store produce ranged from 3 to 15 Bq/L, showing little influence of atmospheric HTO emitted by the nearby Pickering Nuclear Generating Station (PNGS). Locally grown vegetables, fruits and meats reflected the elevated levels of atmospheric HTO. Concentrations ranged from 15 to 280 Bq/L at distances of 5 to 30 km from PNGS. At an experimental plot 1 km from the PNGS reactor stacks (plant boundary), concentrations in vegetables were in the range 1000-3000 Bq/L. The ratio OBT/HTO ranged from 0.3 to 4.2 with an overall average of 1.25±0.75. This ratio, which is an indicator of range of OBT levels in the food items, is useful in estimating dose from OBT in the samples where only HTO analyses are performed. -117- 3.146.1 Canadian Atmospheric Stability Indicators Program Officer M. Santini Contractor AECL Research - CRL Status Complete Comments
Original Project Pescription It is proposed to fund a study to collect data in order to develop a method for using routine meteorological data to deduce atmospheric stability at Canadian nuclear reactor sites. Atmospheric stability is a key factor in predicting atmospheric concentrations under release conditions. The method should be applicable to other licensed facilities in Canada, such as uranium refineries.
In order to calculate the concentrations of radioactivity in the air following a release from a nuclear facility, the stability of the atmosphere must be specified. Since atmospheric turbulence is difficult to measure, this is normally done indirectly through simple indicators that are known to be correlated with direct turbulence estimates. (Temperature gradients as indirect turbulence indicators, are frequently used in accident analysis and emergency response programs.) However, these correlations between the direct and indirect indicators were developed in England and in the southern U.S. and are inappropriate for the Canadian climate, particularly in the winter when the ground is snow covered.
The results of the project are intended to provide a method to deduce atmospheric stability from simple, routine meteorological measurements for the Canadian climate, and so improve the AECB's confidence in predicted atmospheric radionuclide concentrations following releases from nuclear facilities.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S24k S13k SOk SOk S37k Actual Spent to Date $24k $13k S37k
Final Results The project provides a means for using standard deviation of horizontal wind direction measurements to improve the method for predicting atmospheric stability. The revised method is site-specific, and would avoid the uncertainties in using the STability ARray (STAR) approach. The results of this work may have an impact on the CSA standards N288.1 and N288.2, and AECB licensing requirements with regard to air dispersion of radionuclides. A peer review of AECL's report was begun to assess its recommendations concerning initiating the CSA N288.6 standard on Weather Monitoring and revision of CSA N288.1 and N288.2. The report is being processed to be published as an AECB Report.
Publications A paper based on this work has been accepted for presentation at the Canadian Météorologie & Océanographie Society Congress scheduled for May 30 to June 2,1994, in Ottawa. -118- 3.151.1 Canadian Data Base for Radionuclide Transfer in the Environment Program Officer M.R. Avadhanula Contractor AECL Research - WRL Status PPE initiated Comments
Original Project Description It is intended to construct a computer database for radionuclide transfer parameters in the Canadian environment. This project is being carried out because the lack of adequate (site specific) data on parameters used to predict transfer of radionuclides in the environment often leads to global use of data from relatively few sources. However, Canada has now acquired a substantial amount of data from studies done by several industries and universities, some of them through AECB funding. These data are often preferable for Canadian applications and exist in published, but more often in unpublished, reports. There is a clear need for a central data source that represents Canadian experimental conditions and is amenable to future updates and that is easily accessible to Canadian investigators and others, including the AECB. This project will define the necessary scope of the data base, select the operating methods (software, repository of the data base, etc.), and will acquire, record and interpret suitable data.
It is anticipated that this project will provide AECB staff v/ith convenient access to a comprehensive and centralized data source, which can be used for evaluating licensees' submissions for emission limits.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $55k $2k $0k $0k S57k Actual Spent to Date S55k S2k $57k
Final Results A Canadian database was constructed to record future radionuclide transfer parameter data systematically and completely, and to record particularly important existing data. This database supports element-specific parameters. The data are indexed by geographic and physiographic regions in Canada. The database is constructed using dBase IV and the entry screens and programming were developed on an IBM-PC. The database details are given in a summary report and the manual for the "Canadian Database for Radionuclide Transfer in the Environment" describes the operation of the software program. -119- 3.160.2 Radionuclide Analysis in Tissue Program Officer E. Rabin Contractor Becquerel Laboratory Inc. Status Work in progress Comments
Original Project Description It is intended to measure the quantities of U-238, Th-230, Ra-226, and Pb-210 in tissue samples taken from the lung, liver, kidney, skeleton, and gonads of sheep, which have been subjected to deposition of uranium dust in the trachea! lobe of their lungs. The Centre Hospitalier Universitaire de Sherbrooke (Québec) is carrying out a research project for the AECB, aimed at determining the influence of lung macrophages on the solubilization of radionuclides contained in uranium ore particles, as well as their subsequent translocation to and retention by five tissues which are of importance to dosimetry in man (AECB project #3.123.2, "In Vivo Dissolution of Inhaled Uranium Compounds"). The radiological analyses required by that study are to be carried out under a separate contract with a private radiochemistry laboratory, and comprise the subject of this project. It is anticipated that the results of this project will provide the radiochemical analyses required for achieving the objectives of AECB project* 3.123.2. (NOTE: A more detailed description of the overall program of research for projects 3.123.2 and 3.160.1 is provided in the description of project 3.123.2.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S104k S35k SOk $139k Current Estimates SOk S68k $69k SOk S 137k Actual Spent to Date SOk S68k S68k Progress to Date Samples of sheep tissues, received from the contractor of RSP project 3.123.2, are being analyzed for total uranium, Th-230, Ra-226 and Pb-210 content. -120- 3.162.1 Monitoring Uranium Emissions from a UF6 Plant Stack Program Officer E. Rabin Contractor Autolycus Research Status Complete Comments
Original Project Description It is the purpose of this project to evaluate the static isokinetic sampling device and technique currently used in measuring the paniculate emissions through the process exhaust stack on CAMECO's West uranium hexafluoride production plant in Port Hope, Ontario, and on the basis of this evaluation, to assess the validity of the data on the uranium discharged to the atmosphere from that source. The quality of these data is in doubt for two reasons. First, because the design of the stack causes turbulence in the process exhaust flow, it is believed that this leads to non-uniform distribution of paniculate material across the stack. These effects raise questions about the consistency and representativeness of the samples taken from the stream. Secondly, in a test run to compare the two methods, there was a marked difference between data from the static isokinetic sampling device and data derived using the Ontario Ministry of the Environment Method 5 Source Testing Code.
It is anticipated that the findings from this project will enable AECB staff to assess the accuracy and soundness of the data on the uranium emissions from this source. This information is required for determining compliance with limits prescribed in the facility operating licence.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates $63k Slk SOk SOk S64k Actual Spent to Date $63k Slk S64k
Final Results The research found that the design of the Cameco stack precluded credible sampling by any recognized method and that the TSI sampler was not a suitable instrument for sampling in the stack as it was operating well outside both its velocity and particle size range. The contractor has recommended that the stack be increased in height and provided with a half area baffle or orifice to ensure uniform distribution of aerosol in the stack and that an alternative continuous sampling system be installed. Final Evaluation The contractor provided-the AECB with the best possible assessment that can be expected regarding the measurement of uranium releases from the UF6 stack at the CAMECO Port Hope plant. -121 - 3.170.1 MAGNEC Five-Year Progress Report Program Officer LL.Wallach Contractor Grier, M. Status Complete Comments
Original Project Description It is intended to compile the information and to prepare the 5-year report on all geoscientific work undertaken under the auspices of MAGNEC. This project will receive partial funding from the Geological Survey of Canada. Several projects in the MAGNEC program have been funded by the AECB during the past 5 years. This project is proposed in order to put together a coherent summary of all MAGNEC-related work conducted to date, along with conclusions and inferences from that work, and recommendations for future studies.
It is anticipated that the results of this report will demonstrate the achievements that have been made in attempting to improve seismic hazard assessments.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates $16k SOk SOk SOk S16k Actual Spent to Date S 16k SOk S 16k
Final Results The report records work done and conclusions rendered by MAGNEC over a five-year period. It serves as the first of two volumes, the second being an indexed volume of all of the Minutes of the meetings. Final Evaluation The project provides a cohesive record of diverse and disaggregated information from MAGNEC meeting Minutes and reports. Publications Published by GSC as Open File Report 2728. -122-
3.175.1 Further Development of the CHERURB Urban Contamination Model Program Officer K.P. Ho Contractor AECL - CRNL Status Work in progress Comments Original Project Description It is intended to develop further and to test a computer model [developed in the AECB research project entitled: "Significance of Urban Pathway in Assessing Public Dose: (3.145.1)], in order to refine the assessment of the radiological impacts of nuclear facilities on the public. The CHERURB urban contamination and dose model is a tool for assessing potential doses to humans (inhalation, external, immersion) as a result of atmospheric contamination of urban environments from nuclear facilities. Several nuclear facilities in Canada are located in the vicinity of large urban environments, and thus routine or accidental releases of radioactivity could affect urban populations. The urban environment has unique features that generally are not taken into account when assessing natural or semi-natural environments. Such features relate mainly to deposition (dry or wet) and retention of radionuclides on urban surfaces, to transfer processes within the urban environment and to the calculation of external and internal radiation doses. This was especially recognized in European urban areas following contamination from the Chernobyl accident in 1986. Assessment of the potential impacts of nuclear facilities by AECB staff must give consideration to urban contamination concerns, and requires reliable tools. Further development work will increase the reliability of CHERURB and the AECB's capability to assess radiological impact through: (i) provision of a more accurate dosimetric model for assessing external doses; (ii) provision of model routines for evaluating uncertainties in results; and (iii) provision of model routines for evaluating the effects of weathering, runoff and decontamination processes on doses. Model improvements will be made in light of relevant post-Chernobyl research, such as those being discussed within the VAMP program of the IAEA. The updated code will be run on a test case to evaluate its reliability, and to identify limitations and sources of uncertainty.
The results of this project, an updated and documented version of CHERURB, will provide AECB staff with a useful decision-aiding tool for assessment of radiological impacts to the public following atmospheric contamination of urban environments from nuclear facilities.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $30k $45k SOk SOk S75k Current Estimates SOk $45k S48k SOk S93k Actual Spent to Date SOk $45k S45k Progress to Date The contractor has participated in the VAMP meeting in Vienna (July 1993) and has completed the scheduled information exchanges. An extensive literature review of the subject was also being conducted. -123- 3.183.1 Environmental Research Seminars Program Officer M.R. Avadhanula Contractor Ontario Hydro Status Work in progress Comments Specialists in various fields of expertise are invited, from time to time, and this is an on-going
Original Project Description It is intended that the AECB invite specialists, who are carrying out studies related to the areas of environmental protection and assessment, to make presentations on their studies in seminars and in information exchange sessions with AECB staff. Environmental Protection and Environmental Impact Assessment are new responsibilities at the AECB. In order to perform these tasks effectively, AECB staff should be provided with information on current issues, knowledge, information, research and related activities.
These sessions will provide AECB staff with further information and good contacts to carry out their responsibilities effectively in the environmental protection and environmental impact assessment areas.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk Slk S15k S15k S31k Actual Spent to Date SOk Slk Slk Progress to Date Two scientists from Ontario Hydro were invited to present Ontario Hydro's environmental program and they discussed, with AECB staff, technical aspects related to environmental monitoring programs in general. -124-
3.184.1 Mesoscale Atmospheric Model for Complex Environments Program Officer M. Santini Contractor Environment Canada Status Work in progress Comments
Original Project Description It is proposed to participate in a joint project with Environment Canada (EC) to produce a mesoscale atmospheric dispersion modelling system which can be used to predict off-site contamination levels for releases from installations located on lake shores and in complex terrain environments. This is a multi-year project with EC taking the role of the lead agency which is responsible for the overall management of the project, and with other agencies participating as advisors to the project manager.
In order to predict the contamination levels for the primary zone of significant risk to the public and the environment, the AECB needs more than just the meteorological data from the nearest weather station. This is particularly true if the affected zone is located in a complex terrain comprising obstructions (such as hills or large structures) or near large bodies of water. What the AECB needs could be accomplished by merging BLFMESO, a 3-dimensional Boundary Layer Flow Mesoscale atmospheric forecast model with PDDM, a Pollution Dispersion and Deposition Model. Further development of the above sub-models will be required before they will be made operational on a fast-running personal computer.
This modelling system would be valuable in providing an independent assessment of the public and environmental impact due to postulated or actual releases from conventional or nuclear facilities. In addition, due to its fast-computation characteristic and capability to delineate zones of potential hazard, this system would be an effective tool for monitoring emergencies involving releases of contaminants.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk $15k S17k S34k $66k Actual Spent to Date SOk $15k S15k Progress to Date The mesoscale model development was presented to AECB staff in a seminar. Validation against atmospheric data at Pickering was being performed. In addition, the code AQPAC was delivered along with a workshop presentation to demonstrate its use. -125- 3.186.1 Microsimulation for Tracking Chemical and Radionuclide Releases Program Officer M. Samini Contractor Beak Consultants Ltd. Status Work in progress Comments
Original Project Description It is intended to assemble a user-friendly airborne dispersion and concentration/dose model with a graphical interface to track chemical and radionuclide plume footprints. This model will have the capabilities of real-time calculation of plumes and concentrations, and the ability to overlay a calculated plume on a selected digitized map. The model will be tailored to the needs of AECB staff in training and emergency monitoring. The program will include the CS A N288.2 standard algorithms and the instant mixing capabilities for any release inventory, such as reactor inventories.The consultant is to use all the coding available at the AECB in a cost-effective manner. In addition, provisions will be made to facilitate the addition of alternative atmospheric models and to allow the data to be interchanged with a contaminant transport code available to the AECB.
At present, the AECB only has non-graphical models to estimate concentration and dose. Further, these models have no capability for effectively tracking and determining plume footprints together with their corresponding hazard levels.
This model would be valuable in providing the AECB with an independent capability to monitor rapidly the whereabouts and the hazard levels of real and postulated releases, from our regulated facilities, in emergency situations The Training Centre would also make use of the microsimulation model to enhance its internal and external training programs.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates
Current Estimates $0k S3 Ik S14k $0k $45k Actual Spent to Date $0k S3 Ik S3 Ik Progress to Date The model was under development. Demonstrations of the user interface have been carried out in two progress meetings. The program is structured in a modular way to facilitate the inclusion of future improved dispersion models. The model will contain two user modes: (a) training mode with pre-defined cases; and (b) analysis mode with more flexibility in input parameter modification. The latter is for scoping calculations and for preparation of additional pre-defined cases in (a) above. -126- 4.101.3 Study of the Health Effects of Inhaled Uranium Ore Dust - Phase 3 Program Officer M.R. Avadhanula C on t ra ct or AECL Research - CRL Status Work in progress Comments
Original Project Description It is intended tc continue with the third phase of the ongoing project to study the health effects (induction of cancer of the lung, cellular defects) on experimental animals exposed to different concentrations of airborne high grade uranium ore dust. Inter-organ transfer of uranium and the rate of clearance from the lung will also be studied. This study was undertaken because Canadian uranium miners are exposed to airborne mineral dust that contains uranium, thorium, and all their decay products, some of which are highly radiotoxic. In high grade ore mines, uranium content in the dust may reach several tens of percent and may represent the predominant occupational radiation hazard. Since uranium miners have always been exposed to a mixture of external gamma radiation and internal radiation from radon decay products and ore dust, it has not been possible to separate the contribution of each component to the observed rale of lung cancer. This was of little consequence as long as radon daughters were the predominant hazard, but thiy becomes an issue in today's Saskatchewan mines. Since the initiation of the project, the dust generators, dust concentration monitors and the nose-only inhalation apparatus were built and tested; the adequacy of the rat strain has been verified; and the maximum dust concentration tolerable without acute toxicity effects has been determined. On the advice of the Review Panel, the experimental procedure for the final, full-scale experiment has been prepared.
In addition to the partial information already obtained, it is anticipated that this study will indicate whether inhaled high grade uranium ore dust induces lung cancer in rats whose response to radon daughters is already known. An attempt will be made to quantify the dose-response relationship. Short- and long-term metabolism of uranium will also be studied and the data will be used to refine current internal dosimetric models.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $260k S300k $140k $220k $920k Current Estimates $211k 5375k $248k SOk $834k Actual Spent to Date S211k S375k S586k Progress to Date Exposure of 252 Sprague-Dawley rats to uranium ore dust (0,15 and 50 mg/m-3) has been in progress since January 1993. The rats were being exposed on an average for 4 h/day, 5 days/week. Preliminary results of uranium analysis in lung tissues suggested that concentrations of uranium in rat lungs appeared to have increased linearly during the first year of exposure. Estimations of dose indicated that the rats were receiving large enough doses to study the health effects in them, especially induction of cancer of the lung. -127-
4.103.2 Physical Characteristics and Solubility of Long-Lived Airborne Particulates in Uranium Producing and Manufacturing Facilities Program Officer K.P. Ho Contractor MacLarcn Plansearch Inc. Status Work in progress Comments
Original Project Description It is intended to continue with this project to determine experimentally the size distribution, the activity distribution and the solubility of airborne uranium-bearing aerosols in all Canadian uranium mines and mills, refineries, conversion facilities and fuel fabrication plants. This work was undertaken to quantify the hazard presented by airborne radioactive long-lived materials in the concerned facilities. The parameters (size distribution, activity distribution, radionuclide composition and dissolution rate in simulated lung fluid) which are necessary to calculate the committed effective dose equivalent from exposure data must be determined in order to evaluate quantitatively, this specific radiation hazard.
It is anticipated that this study will indicate the magnitude of the risk from long-lived particulates in uranium producing and manufacturing industries. It will also provide supporting information for any forthcoming determination of the AL1 for long-lived dust and will facilitate interpretation of bioassay data for the purpose of the radiation protection of the workers at these facilities.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $287k S60k $15k $0k $362k Current Estimates $349k $39k $0k $0k $388k Actual Spent to Date S349k $39k $388k Progress to Date The dissolution rates of the radionuclides of interest, in all collected samples have been determined and the contractor is currently preparing the draft final report. -128 - 4.106.5 Ontario Miners Mortality Study - Phase 5 Program Officer V. Elaguppillai Contractor Statistics Canada Status Work in progress Comments
Original Project Description It is intended to update the mortality, exposure and smoking data of Ontario uranium miners for the period 1988 tol991. This update will be used in a future study to determine the risk of lung cancer due to exposure to radon progeny. The previous phases of the Ontario Miners Mortality Study have revealed that the update on an annual basis of mortality and histology data, as well as of exposure and smoking histories, is useful for detecting any annual trend in the mortality pattern, and any influence of yearly variation of smoking habits on the incidence of lung and other cancers among the aging population of Ontario uranium miners. Furthermore, the annual update may be pooled together about every five years and the updating of risk estimates may be achieved with minimum delay and cost. It is anticipated that the results of this study will considerably improve the efficiency of the five-year mortality analysis for lung cancer risk estimates. Furthermore, the annual update will enable the AECB to detect annual trends in the mortality pattern, and the influence of confounding factors on the induction of lung and other cancers among the uranium miners. (This project is a joint study with Ontario Ministry of Labour (OML) and Workers' Compensation Board of Ontario (WCB) on a one-third, cost-sharing basis.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S15k $10k S 10k $20k S55k Current Estimates SOk S27k S6k $0k S33k Actual Spent to Date SOk S27k S27k Progress to Date Mortality among Ontario uranium miners was updated to 1989. Preliminary results indicated that nearly 150 additional lung cancers occurred among the aging population of Ontario uranium miners. A further update to 1991 is expected by the end of next fiscal year.
Publications Mortality from Lung Cancer in Ontario Uranium Miners. Kusiak, R.A., Ritchie, A.E., Muller, J., Springer, J., Brit J. of Industrial Medicine 1993,50,920-928. -129-
4.106.6 Genetic Mutations Associated with Lung Cancer Among Ontario Miners Program Officer V. Elaguppillai Contractor Status Cancelled Comments Work statement is prepared. Arrangements are being made to constitute a review panel to review the design, conduct and results of the study.
Original Project Description It is intended to investigate the role of genetic mutations in the induction of lung cancer among uranium miners in Ontario. Histological samples obtained from lung cancer cases will be analyzed to determine the presence and type of mutations of the Ki-ras genes and the P53 genes. The genetic mutations will be correlated with the level of exposure to radon daughters and cigarette smoking. Ionizing radiation is a recognized mutagen, and it causes numerous DNA lesions, including strand breaks, base modifications and protein-DNA crosslinks. Mammalian cells repair high-LET radiation-induced DNA damage less efficiently than they repair low-LET radiation-induced damage, but the specific cancer-related gene targets of alpha particles from radon progeny are unknown. Because mutations in the tumor-suppressor gene P53, and the proto-oncogene Ki-ras are common in human lung cancers, these cancer-related genes are good candidates for assessment of radon-induced damage. A recent analysis of the histological specimens obtained from lung cancer cases among New Mexico uranium miners has found the presence of large amounts of P53 protein, while mutations in the Ki-ras proto-oncogene were fewer than expected, implying that the mechanism of the lung cancer caused by radon progeny might be different from that caused by other carcinogens. This observation, if confirmed by studies in other cohorts of uranium miners, might help to elucidate the mechanism of radiation-induced lung cancers, and reduce the uncertainties in the risk estimates for lung cancer ascribed to radon progeny. Therefore, it is important to assay these cancer-related genes in lung cancer cases among Ontario uranium miners. It is anticipated that the results of this study will help to explain the mechanism of lung cancer ascribed to radon progeny, and to reduce the uncertainties in the risk estimates for lung cancer owing to exposure to radon progeny. (This project is expected to be funded jointly by the Atomic Energy Control Board, Ontario Ministry of Labour, Workers' Compensation Board of Ontario, U.S. National Cancer Institute, University of New Mexico Tumor Registry. The total cost of this project is $250k, with the AECB and the contribution expected to be $56k, during the entire period of the study.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk Slk S25k S31k S57k Actual Spent to Date SOk Slk Slk -130-
4.118.2 A Case - Control Study of Beaverlodge Uranium Miners from 1950-1980 Program Officer V. Elaguppillai Contractor Epidemiologic Consulting Services Status Work in progress Comments
Original Project Description It is proposed to conduct a case-control study of lung cancer among Beaverlodge uranium miners. The mortality in a case-control group of 195 miners (65 cases and 130 controls) for the mortality period 1950-1980 will be analyzed. The individual revised exposure estimates of the 195 miners, obtained in an earlier AECB funded study (4.118.3), will be used in this study to calculate revised risk estimates for lung cancer due to radon progeny. Additionally, an estimate of the measurement errors on exposure estimates will be obtained in this analysis. The risk estimates for lung cancer obtained from the previous cohort mortality analysis of the Beaverlodge uranium miners for the period 1950-1980 were about three to ten times greater than the values reported for other mining cohorts (Ontario, Port Radium, Newfoundland, Colorado, New Mexico, Sweden). There were some concerns, both nationally and internationally, about theaccuracy of the exposure estimates used in the study. Consequently, the AECB funded a study (project 4.118.1) to determine revised radon progeny concentrations at different work places and in different mines in the Beaverlodge complex. Subsequently, another study (project 4.118.3) was funded to determine revised individual exposures of a case-control group of 195 miners, based on information obtained from their personal records and other relevant mining data. Revised individual exposures will be used in a case-control study, to re-evaluate risk estimates for lung cancer due to radon progeny exposure. Additionally, it is important to use the data from this study to estimate the measurement errors in exposure estimates.
It is anticipated that the results of this study will provide more reliable estimates for lung cancer due to radon progeny exposures. Additionally, quantitative estimates of the measurement errors obtained from this study will be used in a future (4.118.5) cohort analysis to determine risk estimates for the entire cohort.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $13k $25k S25k $0k $63k Current Estimates S5k Silk $17k $0k $33k Actual Spent to Date $5k Silk $16k Progress to Date Exposure estimates for the 195 cases and controls were re-evaluated Risk models have been developed and the revised data were incorporated into the models. -131 -
4.118.3 Radon Progeny Exposures of Beaverlodge Miners Program Officer V. Elaguppillai Contractor SENES Consultants Ltd. Status PPE initiated Comments
Original Project Description It is intended to re-calculate individual exposures of all Beaverlodge uranium miners to radon progeny, using revised estimates of work place concentration of radon progeny and the time (months) spent by individual miners in their respective work places.
Of the three major Canadian epidemiological studies (Ontario and Beaverlodge uranium miners, Newfoundland fluorspar miners), both Ontario and Newfoundland studies have been subjected to a rigorous and systematic re-examination of the methods of radon progeny exposure estimation for individual miners. The Beaverlodge uranium miners study, though the subject of exhaustive analytical treatment over the past several years, had not undergone a careful examination of the exposure records of individual miners. As a consequence, the AECB sponsored a study (4.118.1) in which the concentration of radon progeny in the work place was re-evaluated using more detailed information on the design, operation, ore output of the mine and the worker history profile. This revised radon progeny concentration, together with an accurate estimation of the time spent by the miners in their respective work places and taking into account their employment records at other hard rock or uranium mines, will be used to calculate the exposures of individual miners. The revised exposure estimates obtained in this study (4.118.3) will be used in 4.118.2 to refine the evaluation of risk for lung cancer due to radon progeny exposure.
It is anticipated that the revised radon progeny exposures of individual miners will be used to improve the accuracy of the risk of lung cancer per unit exposure to radon progeny.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S25k S5k SOk $0k $30k Current Estimates $26k $6k SOk SOk $32k Actual Spent to Date $26k S6k S32k
Final Results The results indicated that the revised estimates of radon progeny exposures of the uranium miners who worked at the Beaverlodge were, globally, higher by a factor of 1.5 - 2.0 than the previous estimates. Consequently, the risk estimate for the Beaverlodge uranium miners based on the revised exposures appeared to be lower by a factor of 1.5 - 2.0 than the old estimates. -132-
4.118.4 Radon Progeny Exposures of Beaverlodge Uranium Miners - Phase 2 Program Officer V. Elaguppillai Contractor SENES Consultants Status Work in progress Comments
Original Project Description It is intended to calculate the revised exposures (in WLM) of the cohort of nearly 8500 uranium miners who worked at the uranium mines in Beaverlodge during the period from 1950-1980. This will be done by developing a matrix of exposures based on mine-wide average conditions for each year of employment and job classification. Revised radon progeny concentrations (in WL) at the workplaces in the Beaverlodge uranium mine complex were obtained in project 4.118.1, and the results indicated that the previous estimates of concentrations were underestimated by a factor of about 2. Subsequently, in project 4.118.3, a detailed estimate of individual exposures (in WLM) of a selected number of miners (195 miners including 65 cases of lung cancer and 130 control miners), who were a part of a previous case-control study by Howe et al. in 1987, was completed. These revised exposures will be used in a case-control study (project 4.118.2) to re-calculate the risk of lung cancer based on the 65 observed lung cancers up to the year 1980. Since 1980, more lung cancer deaths are known to have occurred among the Beaverlodge cohort, but their exposure estimates have not been revised. Since it would be very expensive and time consuming to make detailed, individual exposure estimates of the entire cohort of nearly 8500 uranium miners, to develop a matrix of revised exposures for the entire cohort. It is anticipated that the revised exposure estimates will be used in a cohort study to obtain the risk estimates for lung cancer owing to exposure to radon progeny. Additionally, the revised exposure estimates for the entire cohort will enable pooling of this data with other international data bases (Colorado, New Mexico, Ontario, Port Radium, Newfoundland, France, Czechoslovakia, Australia, China, Sweden) to obtain a pooled estimate of the risk of lung cancer among miners exposed to radon progeny.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $20k $7k SOk $27k Actual Spent to Date $0k $20k S20k Progress to Date An algorithm has been developed to project exposures of the entire cohort of Beaverlodge uranium miners. This algorithm is currently being tested on a case control group of 195 miners (in Project 4.118.3). -133 -
4.122.1 Transgenic Potential of Natural Uranium Decay Chain Progeny Program Officer M.li. Avadhanula Contractor AECL - CRL Status Work in progress Comments Contracting in progress.
Original Project Description It is intended to investigate the potential for radionuclides of the natural uranium decay chain to induce genetic damage in males, which is subsequently transmitted to offspring. This study will take advantage of the current animal (rats) experiment being conducted in AECB project 4.101.3 "Study of the Health Effects of Inhaled Uranium Ore Dust - Phase 3". A recent epidemiological study suggests that there is a higher than expected incidence of leukemia in the offspring of the general population in and around Elliot Lake, Ontario. Although the observed incidence rate is not statistically significant, it is conceivable that the higher than expected incidence of leukemia in children in and around Elliot Lake may be the result of the transmission of "leukemic" genes from fathers exposed to background and occupational levels of radionuclides (the "Gardner effect") of the natural uranium decay chain. In the proposed study, appropriate reproductive organs from male rats, which are exposed to high-grade uranium ore dust (4.101.3), will be analyzed for U-238, U-234, Th-230, Ra-226, Pb-210 and Po-210. Sections of the tissue samples will be subjected to autoradiography and will also be examined for chromosomal changes. The autoradiography will focus primarily on the distribution and location of alpha-and beta-emitting radionuclides in the sensitive germinal cells, as well as in mature sperm. The results of this study will provide AECB staff with a better understanding of the transgenic potential of natural uranium decay chain progeny.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S20k S20k SOk $40k Current Estimates SOk $3k $28k S16k $47k Actual Spent to Date SOk S3k $3k Progress to Date Available samples of testicular tissues of rats which died were analyzed for uranium and other radionuclides. -134-
4.125.2 Independent Evaluation of the Report for Project 4.125.1 Program Officer E. Rabin Contractor AECL Status PPE initiated Comments Original Project Description It is proposed to obtain evaluations of the report "The Effect of Exposure Rate on Risk of Lung Cancer Induced by Exposure to Radon Decay Products" (author Dr. G.R. Howe) from independent experts in the fields of epidemiology, radiobiology, and exposure reconstruction in uranium mining. This project is proposed because the report referenced above concludes that the risk of lung cancer induced by radon decay products (RDP) increases with decreasing rate of exposure, i.e. the risk of lung cancer per unit exposure is greater at lower exposure rates. These findings may have an influence on the assessment of the risk of lung cancer due to RDP exposure, and hence impact on the relevant regulatory dose limit. A critical review of the report is needed to clarify the following areas of concern, and their potential impact on the conclusion: 1. biological plausibility of the inverse dose-rate effect; 2. validity of the exposure measurements, i.e. possibility of systematic errors in the exposure data used; and, 3. potential impact ef confounding factors.
It is anticipated that the results of this project will provide justification for any actions taken by the Board that pertain to the dose limits for RDP.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S13k SOk SOk S13k Actual Spent to Date $0k S13k S13k
Final Results Detailed comments on the report "The Effect of Exposure Rate on Risk of Lung Cancer Induced by Exposure to Radon Decay Products" by Dr. G.R. Howe, have been received from five independent experts in the fields of epidemiology, radiobiology, and exposure reconstruction in uranium mining. None of trie experts found fault with the statistical method of analysis used by the author of the report, but several experts questioned the author's interpretation of the results (and provided their own alternatives), and one expert questioned the reliability of the doses attributed to the miners. - 135 - 4.130.1 Evaluation of Radon Daughter Exposures of Port Radium Miners Program Officer V. Elaguppillai Contractor SENES Consultants Status Work in progress Comments Original Project Description It is intended to re-evaluate the radon daughter exposures (in working level months (WLM)) received by nearly 2100 miners who worked at the uranium mines in Port Radium in the Northwest Territories for the period from 1930 to 1960, and who may have had previous or later exposures to radon daughters in other mines. The risk estimate for lung cancer obtained from the previous study of Port Radium uranium miners, by Howe et al., was 0.27% per WLM. This value is at the lower end of the range of relative risk estimates (0.3 to 3.3 % per WLM) reported for Canadian and international studies (Ontario uranium miners 1.3%, Newfoundland fluorspar miners 0.9%, Beaverlodge uranium miners 3.3%, U.S. Colorado uranium miners 0.8%, Czechoslovakian uranium miners 1.8%, and Swedish iron miners 1.4%). Among the Canadian studies, exposures received by both the Ontario uranium miners and Newfoundland fluorspar miners were re-evaluated using improved techniques and additional information on exposure histories, which resulted in better agreement between their respective revised risk estimates (as shown above). The exposures received by the Beaverlodge uranium miners are being re-evaluated (project 4.118.1) and the results will be used in an updated mortality analysis (4.118.2). Therefore, it is important to re-evaluate the exposures of individual miners who worked in the uranium mines in Port Radium, taking into account exposures received by them in other mines, as well as their work histories, and the design characteristics of the mines.
It is anticipated that the results of this study will give the AECB improved exposure estimates for Port Radium uranium miners. These estimates will be used in an updated mortality analysis of Port Radium uranium miners (Project 4.130.2) to derive improved risk estimates for lung cancer due to exposure to radon daughters.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SlOk S30k S25k SOk S65k Current Estimates $0k $24k $25k SOk $49k Actual Spent to Date SOk S24k S24k Progress to Date Exposure histories, mine ventilation and output data were being collected and reviewed. Efforts are being made to obtain bonus contract information, from which additional information on past exposures could be inferred. -136-
4.132.1 Smoking Histories of Fluorspar Miners Program Officer M. Lupien Contractor Health & Welfare Canada - Cancer Division Status PPE initiated Comments
Original Project Description It is intended to update the smoking histories of former fluorspar miners in St. Lawrence, Newfoundland from 1978 to 1992. This information will be used to determine the extent of interaction between smoking and exposure to radon daughters on the incidence of lung cancer among the former fluorspar miners, and to calculate the risk of lung cancer per unit exposure to radon daughters, taking the effect of smoking into account. The previous smoking history survey of the fluorspar miners in St. Lawrence, Newfoundland was completed in 1978. A total of 755 miners were contacted in this survey, funded by the Atomic Energy Control Board. To date, nearly 720 miners of this cohort are known to be alive in the St. Lawrence region. Furthermore, nearly 40% of these miners are estimated to have quit smoking during the past 13 years since the last survey. If this estimation is accurate, it might influence the risk estimate for lung cancer due to radon daughters, because of the known interaction between smoking and radon daughters. It is therefore important to conduct a survey to determine the actual number of current smokers among the former miners. It is anticipated that the results of this survey will provide information on the interaction between smoking and exposure to radon daughters, and will improve the accuracy of risk estimates for lung cancer owing to exposure to radon daughters, in the absence of radioactive dust, in the working environment.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $38k $2k $0k SOk $40k Current Estimates $30k SlOk SOk SOk S40k Actual Spent to Date $30k $10k $40k
Final Results Candidates for this survey were chosen from those interviewed in 1978. Miners were interviewed either by phone or in person. Proxy interviews were conducted in cases where the miner was deceased or attempts to contact the miner directly were unsuccessful. Of the questionnaires administered, approximately 28% were proxy interviews. Results were obtained for 592 miners. Of these 592 miners, ninety-four (15.9%), died between 1978-1993. The mean age of the miners interviewed was 59. Of the miners who were alive at the time of the interview approximately 86% had lifetime smoking histories. Approximately 10% of the miners interviewed had smoked cigars or pipes. Only 5% admitted prior use of chewing tobacco. Of those who still smoked, almost 70% smoked more than a pack a day. -137- 4.133.1 Lung Cancer Among Uranium Miners in Germany Program Officer V. Elaguppillai Contractor Dr. W. Burkart, Dr. W. Ullmann, Dr. J. Muller, Mr. R. Kusiak Status Contract in place Comments Original Project Description It is intended to conduct an epidemiological study of lung cancer among uranium miners in Germany, jointly with federal German authorities, and to evaluate the risk of lung cancer per unit exposure to radon daughters, taking confounding factors present in the work place into account. Nearly 500,000 uranium miners are known to have had significant exposure to radon daughters during their employment in underground uranium mines in the former East Germany. A detailed epidemiological study of these miners, the single largest group of uranium miners in the world, is expected to produce the most accurate risk estimates for lung cancer owing to exposure to radon daughters, because of the statistical power afforded by the very large numbers involved. The scientists at the Institute for Radiation Hygiene of the Federal Health Office, in Germany, are currently developing appropriate methodologies to carry out a full-scale epidemiological study of this large cohort of uranium miners. They are seeking Canadian participation in the areas of record linkage and radon daughter exposure re-evaluation, areas in which Canadian expertise is fully recognized worldwide. Canadian participation in this very important study will have an influence on the quality of the results which, in turn, will play an important role in the future evolution of exposure limits in uranium mines. It is anticipated that the results of this study will improve the accuracy of the risk estimates for lung cancer owing to exposure to radon daughters, and will improve our understanding of the influence of various confounding factors on these risk estimates. (This is expected to be a joint study with the Institute for Radiation Hygiene (GSF) of the Federal Health Office, Neuherberg, Germany, and the Atomic Energy Control Board. The major contribution of S 1.5 million will come from the GSF. The AECB will contribute technical expertise, costing about S20K per year, totalling about $90k during the anticipated four-year period of this study.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S20k $20k S40k S80k Current Estimates SOk S5k $30k $45k $80k Actual Spent to Date SOk $5k $5k Progress to Date The initial protocol of the study was developed in collaboration with German and Canadian scientists. Work was ongoing in Germany. -138- 4.136.1 Representativeness of Open-Face Dust Samples Program Officer E. Rabin Contractor CANMET Elliot Lake Laboratory Status Work in progress Comments Original Project Description It is proposed to determine the collection efficiency of open-face filters used as dust samplers. The collection efficiency will be determined under various sampling conditions and dust particle sizes. This type of equipment is used routinely in uranium mine and mill facilities to measure the concentration of radioactive long-lived dust in air. The accurate determination of radioactive long-lived dust concentration in the working environment is necessary in order to evaluate the contribution of this pollutant to the total annual radiation dose received by the workers. In facilities where high-grade ore is extracted or processed, or even in low-grade facilities, long-lived radioactive dust may be a major contributor to the total annual radiation dose. It is, therefore, critical that dust concentrations be measured with an acceptable accuracy. The collection efficiency of dust particles in an air stream is a function of the air stream velocity, dust particle diameter, filter holder diameter, sampling head flow rate, and the orientation of the filter relative to the air stream. Under certain conditions, the collection efficiency of particles with diameters typically found in mines and mills may be lower than 50%. Since the activity of a particle is proportional to the cube of its diameter, a low collection efficiency for large particles may result in a large underestimation of radioactive dust measurements. To date, the collection efficiency of sampling equipment and the sampling procedures used by the uranium industry have not been thoroughly tested. As a consequence, the AECB is not in a position to evaluate, with confidence, the contribution of long-lived dust to the total annual radiation doses to workers. The results of this study will indicate the sampling efficiency of currently used dust monitoring equipment for a ra>ige of dust particle sizes, air stream velocities, and filter-holder orientations. The gathered information will enable the AECB staff to interpret dust measurements taken in uranium mines and mills and to calculate doses more accurately.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $70k $29k $0k $0k S99k Actual Spent to Date $70k S29k $99k Progress to Date The laboratory trials were proceeding. The list of tasks has been expanded to improve the analysis of the dust collected on the filters, and to add one, custom-made, isokinetic sampler, for comparison with a commençai one. -139 - 4.138.1 Processing and Reading of PAD Detectors Program Officer E. Rabin Contractor CANMET, Elliot Lake Laboratory Status Work in progress Comments
Original Project Description It is intended to develop at the CANMET National Radon Thoron Test Facility (NRTTF), the capability and procedures for evaluating the performance of personal alpha dosimetry (PAD) services and equipment used in Canadian uranium mines and mills. This project is proposed because the AECB needs to verify, in accordance with the requirements of Consultative Document, C-106: 'Technical and Quality Assurance Specifications for Dosimetry Services", that all sources of uncertainty in the doses attributed to workers are controlled and minimized. To achieve this objective, the AECB needs to have access to a means for verification at the designated national reference laboratory, which is independent of the uranium industry and the commercial dosimetry services. It is anticipated that upon completion of this project, the NRTTF will be able to provide the AECB with the services it needs to monitor compliance of commercial personal alpha dosimetry services used in Canadian uranium mines and mills in accordance with the requirements of C-106.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $10k $60k SOk SOk S70k Current Estimates SOk $72k SOk SOk S72k Actual Spent to Date SOk S72k $72k Progress to Date The laboratory equipment and procedures for evaluating the performance of personal alpha dosimetry services available to Canadian mining and milling facilities were being tested and refined. -140-
4.142.1 Update on Acute Toxicity Levels of Hydrogen Fluoride Program Officer M. Lupien Contractor David M. Halton Status Complete Comments
Original Project Description It is proposed to update the INFO 0143 report (Toxicity Levels to Humans during Acute Exposure to Hydrogen Fluoride). This will be done by conducting a comprehensive literature review and data evaluation. The data and findings of the relevant references will be summarized under four categories: animal studies, controlled human studies, community exposure and industrial exposure.
In January 1984, the AECB requested a study of the toxicity (particularly the lethality) of hydrogen fluoride (HF) which is used at a uranium processing facility. This request was directly related to the AECB's responsibility for regulating the nuclear fuel cycle in Canada, including considerations of health and safety. The 1984 study considered the literature that was available at that time. Since then, more data have been published.
It is anticipated that the results of this study will further improve our understanding of the toxicity of hydrogen fluoride.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S 10k SOk SOk SOk SlOk Actual Spent to Date SlOk $0k SlOk
Final Results Literature published in the last ten years suggest that HF exposures up to 10 ppm for periods up to an hour cause irritation effects but are neither lethal to human populations nor impair an individual's ability to take protective actions. However, when people inhale high concentrations of HF, death is almost certainly caused by the corrosive action of the gas rather than its toxicity. New data also indicate that the potential lethality of an HF exposure can be greatly enhanced by simultaneous skin contact. No new animal data have been published to merit modification of the original extrapolations from animal LC-50 data. (LC-50 is the concentration at which 50% of the exposed population dies.) However, previous derivations of LC-LO at 50 ppm for 5 minutes are probably conservative and estimates of LC-50 values at 50 ppm for 30 minutes are probably very conservative. The LC-50 is the concentration of a substance in air which, when inhaled by test animals, will cause death in 50% of the population after a specified exposure time. Unless otherwise stated the quoted values for LC-50 are for a four hour exposure time. The LC-LO (Lethal Concentration, Lowest) is sometimes also called the LC Min (minimum) and is the lowest lethal concentration. Final Evaluation The reviewers' consenus was that the report produced by the contractor was fully satifactory. The follow-up work suggested in the report does not appear to be useful to AECB. -141 - 5.127.2 Radionuclide Concentrations in Fish: Phase 2 (Detailed Analyses) Program Officer MR. Avadhanula Contractor Laurentian University Status Complete Comments Final report is being reviewed by AECB staff. Original Project Description It is intended to continue"to determine the concentrations of radionuclides (uranium, thorium, polonium, and lead) in fish and in the associated water and sediments, taken during the Phase 1 program, from the fish-stocked lakes found downstream of the Elliot Lake uranium mines in the Serpent River Basin. Further, it is intended that transfer parameters be calculated for each radionuclide (from sediments to water to fish to consumer).
Transfer parameters for the uranium and thorium decay series in aquatic ecosystems are important components in the estimation of public dose arising from uranium mining activities. Results of a recent report, 'Survey of Data on the Radionuclide Content of Fish in Canada1 INFO 0231-1, indicated that there were very few studies of radionuclide concentrations in fish and their habitats (water and sediments) which have been conducted in Ontario or elsewhere. This project is proposed because additional data would be very useful to estimate more accurately the dose to the public resulting from consumption offish in the Elliot Lake area, an area which accounts for all of Ontario's uranium production.
It is anticipated that the results of this study will provide reliable information to assess the dose from ingestion offish by people in the Elliot Lake area.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S52k Slk SOk SOk $53k Actual Spent to Date 852k Slk $53k
Final Results Fish, water, and sediments taken in a watershed with U operations near Elliot Lake, Ontario, carried measurably higher levels of 210Pb, 210Po, and U than those from an adjacent, non-industrialized, watershed. Levels of 230Th, 232Th, and Th in fish tissues did not differ significantly by site. Bioconcentration of 210Pb and U was observed from water and "gut" material (taken as a surrogate for diet) to bone in laketrout and whitefish, and of U from water to muscle in whitefish but not from sediments to tissues. Estimates of intakes of 210Pb, 210Po, 230Th, 232Th, and U by human consumers of one fish meal a week would, in aggregate, account for an annual effective dose of less than 15% of the public dose limit (5 mSv). -142- 5.144.1 Groundwater Inflow into Deep Underground Mines - Phase I Program Officer J.L. Wallach Contractor Raven Beck Environmental Ltd. Status Complete Comments
Original Project Description It is intended to carry out a two-phase study of the geological, hydrogeological, geochemical and geotechnical conditions at deep underground excavations located on the Canadian Shield. The study will involve a literature search to obtain information on deep underground mines with special emphasis on groundwater inflow into the mines as a function of time, depth and stress conditions. The study should consider the mines with underground openings at depths in excess of 500 meters, irrespective of the rock types and the ore mined. This study is proposed because groundwater flow is recognized as the dominant factor for radionuclide release and transport from a repository to the biosphere. Due to limitations of the site investigation methods the assessment and the long-term predictions of the hydrogeological conditions in a repository will be difficult. In order to increase the confidence in these assessments, it is believed that studies of deep underground mines could be helpful, because they can provide additional perspective and support for the possible conditions that could exist in a repository.
It is anticipated that the results of this study will be used in the review of the Canadian Nuclear Fuel Waste Management Program and as a support to AECB input in the Concept Review.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S40k $9k SOk SOk $49k Actual Spent to Date S40k S9k S49k
Final Results Geoscientific data available from deep underground mines in the Canadian Shield were compiled, reviewed and assessed to identify future geoscientific studies at selected candidate mines for use in evaluating the Canadian concept for disposal of nuclear fuel wastes. Geological, geomechanical, hydrogeological and geochemical data were collected from 59 operating mines with openings below 500 m depth. Data were collected from review of published information, circulation of a questionnaire to mine operators and collection and analysis of groundwater samples from selected mines. The available data show that zones of continuous groundwater inflow below 500 m depth are restricted to major structural discontinuities such as fracture zones, faults and shear zones. Such inflows are typically saline to brine Ca/Na Cl waters although inflows of fresh CaHCO3 waters were also found. Evidence of high pre-mining rock stresses in massive crystalline rocks was also noted in this study. The results of this study indicated that significant amounts of valuable geoscientific data could be collected at deep underground mines through on-site inspection, mapping and testing. -143 - 5.144.2 Groundwater Inflow Into Deep Underground Mines - Phase II Program Officer J.L. Wallach Contractor Raven Beck Environmental Ltd. Status Complete Comments
Original Project Description It is intended to carry out the second phase of this study which will involve a reconnaissance field investigation of up to 5 or 6 mines. This study is proposed to" provide a first-hand assessment of the attributes of candidate mines, identified in phase 1, relative to achieving the long-term objective of obtaining information on subsurface hydrogeological conditions which are relevant to the deep disposal of radioactive waste.
This study is proposed to select at least one or more mines for the detailed investigation to be conducted during phase 3.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S190k SOk SOk SI 90k Current Estimates SOk S22k SOk SOk S22k Actual Spent to Date SOk S22k S22k Progress to Date Field work was completed in five mines. It involved observation of conditions and data and sample collection. Based on the study, one of the mines has been selected for an in-depth study in the next phase of this series. -144 - 5.144.3 Groundwater Inflow Into Deep Underground Mines - Phase III Program Officer Jl. WaUach Contractor Raven-Beck Environmental Ltd. Status Preparations initiated Comments Original Project Description It is intended to carry out the third phase of a three-phase study of the geological, hydrogeological, geochemical and geotechnica] conditions at deep underground excavations located on the Canadian Shield. The study will be undertaken in the field and will examine conditions in deep underground mines with special emphasis on groundwater inflow into the mines as a function of time, depth and stress conditions. The study should consider mines with underground openings at depths in excess of 500 meters, irrespective of the rock types and the ore mined. This study is proposed because groundwater flow is recognized as the dominant factor forradionuclide release and transport from a repository to the biosphere. Due to limitations of the site investigation methods, the assessment and the long-term predictions of the hydrogeological conditions in a repository will be difficult In order to increase the confidence in these assessments, it is believed that studies of deep underground mines could be helpful, because they can provide additional perspective and support for the possible conditions that could exist in a repository. It is anticipated that the results of this study will be used in the review of the Canadian Nuclear Fuel Waste Management Program and as a support to AECB input in the Concept Review.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S 190k SOk SOk SI 90k Current Estimates SOk SOk S90k SlOOk $190k Actual Spent to Date SOk SOk SOk - 145- 5.146.1 Thermal Consolidation Effects Around a High Level Waste Repository Program Officer LL.Wailach Contractor Carleton University - Faculty Status Complete Comments Original Project Description It is intended to design and construct a lab-scale model (2 m x 2 m x 2 m) of a HLW repository and record its thermal-mechanical-hydrological behaviours.
AECB staff is assessing the Canadian concept of high level waste disposal. As part of this assessment, we are examining the significance of coupling between thermal, hydrological and mechanical processes on the performance of the repository. The theory describing this coupling is called thermal consolidation. Staff has recently completed a literature review, and performed a mathematical simulation of thermal consolidation near a repository. Some preliminary conclusions can be drawn from the above work; nevertheless, to gain more confidence in the mathematical models used, a laboratory experiment should be performed to validate them.
The results of this project would be used to perform validation of AECB's mathematical models of thermal consolidation and provide data to improve these models if necessary.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates $50k $26k SOk SOk $76k Actual Spent to Date $50k $26k $76k
Final Results This research program involved the development of a laboratory experimental facility for the simulation and study of hygro-thermo-mechanical processes in saturated geomaterials with low permeability. The experimentation involved a synthetic porous material made of cement grout which possessed permeabilities in the range of dense unfractured sandstones or shale. Specially-manufactured pore-pressure transducers were installed within the cylindrical block at locations adjacent to a plane free boundary. The block was saturated with the periodic application of a vacuum. In its saturated state, the plane-boundary of the block was subjected to heating via a circular heater, the temperature of which was maintained constant. The resulting pore pressure generation along with temperature at these locations was monitored continuously. The results of a series of experiments were documented and further extensions to the overall scope of the experimental research program were also discussed. Final Evaluation The scope of the investigation was altered considerably from that proposed in the RSP document. The results obtained do confirm effects predicted in computer simulations of hygro-thermal processes in porous rock. -146-
5.147.1 Assessment of the Underground Disposal of Tailings Concept Program Officer M.R. Avadhanula Contractor Morwijk Enterprises Ltd. Status Work in progress Comments
Original Project Description It is proposed to determine if the concept of underground disposal of tailings, produced from the milling of uranium ore, is practical, and assess the impact of removing the tailings from their current location on the surface and returning them to the mine. Currently in the Elliot Lake area several mines are closing down and beginning the process of decommissioning. During the operational life of these mines, the tailings resulting from the milling of uranium ore have been placed on the surface and contained within a system of dams. One of the options for decommissioning these tailings areas is to return at least some of the tailings to the underground portions of the mine. In order to assess proposals of this nature made by the licensee, there is a need to understand the implications and impacts of this decommissioning approach. The results of this project will be used to assess the decommissioning approaches proposed by the licensee.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S25k S25k SOk SOk S50k Current Estimates SlOk $27k $3k SOk S40k Actual Spent to Date SlOk $27k S37k Progress to Date The selection and review of the literature was completed. The draft final report was being prepared. - 147- 5.149.1 Radiological Impact of Uranium Mining: Ontario Program Officer M.R. Avadhanula Contractor Laurentian University, C.I.M.M.E.R. Status Work in progress Comments Completion date has been extended to FY 94/95. Original Project Description It is intended to obtain appropriate data suitable as input to an impact assessment model to assess the combined regional radiological impact of operational, non-operational, and idle mines in Elliot Lake, Ontario and the contribution of each site to that impact. Currently, there is insufficient information on either the combined regional radiological impact of facilities in all stages of their life cycle, or the contribution of each facility to the overall impact.
It is anticipated that the results of this study will enable a decision to be made on whether there is a need for mitigative measures at individual sites to be identified, and will enable the assessment of the efficacy of any proposed mitigative measures in terms of the combined radiological impact.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S25k $50k SOk SOk S75k Current Estimates S5k $4Uk Slk SOk $46k Actual Spent to Date S5k $40k S45k Progress to Date Relevant data has been collected from the literature, uranium mining companies, federal and provincial departments. The draft final report was being prepared. -148- 5.153.1 Development and Testing of Environmental Transport Pathway Code - ETP Program Officer M.R. Avadhanula Contractor Beak Consultants Ltd. Status PPE initiated Comments Original Project Description It is intended to enhance the capabilities of the Environmental Transport Pathway (ETP) code by incorporating: i) probabilistic simulation; ii) database viewer and editor; and iii) risk assessment. It is also proposed that the upgraded ETP code be compared with relevant national and international codes. During the course of study on AECB research project number 5.143.1, to reassess the regional radiological impact of uranium mining in northern Saskatchewan., the Board staff acquired the ETP model which is a Macintosh-based, user-friendly environmental assessment code. Unlike traditional numerical codes, the ETP model is generic and easy to customize for a variety of sites. The code was revised in project 5.143.2. The model supports multiple sources, receptors, and multiple pathways from source to critical groups. However, the usefulness of the code will be greatly enhanced by incorporating the additional capabilities noted above, and by testing its validity and reliability. The proposed improvements to the ETP model will provide AECB staff with the ability to quantify uncertainty in simulation results, view and change input parameters and probability distribution functions, and to calculate risk from both radionuclides and trace elements. Comparisons of the ETP code with relèvent national and internationally-used codes and verification with Canadian test data will define the limitations of the simplified models used in ETP, and their range of validity.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S40k S25k SOk SOk $65k Current Estimates $35k S33k SOk SOk S68k Actual Spent to Date S35k S33k $68k
Final Results The ETP model was upgraded to include probabilistic simulation, database viewer and editor, and risk assessment capabilities. The upgraded model is now named IMPACT (Integrated Model for the Probabilistic Assessment of Contaminant Transport). -149- 5.153.2 Integration of IMPACT with GIS and Mapping Interface Program Officer M.R. Avadhanula Contractor Beak Consultants Limited Status Work in progress Comments
Original Project Description It is intended to integrate the environmental assessment code called IMPACT (Integrated Model for the Probablistic Assessment of Contaminant Transport) with Geographic Information System (GIS) software and an online mapping interface. AECB staff use a predictive environmental assessment code called IMPACT (formerly called ETP) to enhance confidence in licensing decisions based on review of licensee proposals. Provision of an interface with Geographic Information Systems (GIS) will complete the development of the code to provide it with an efficient and effective means of conducting licensing assessments, including those involving cumulative regional impacts. New GIS databases could be created using GIS software and a digitizing technology, or existing GIS database files in a variety of formats (e.g., Arclnfo, AutoCad, etc.) could be used. Digitizing of polygon outlines would be done in a Macintosh GIS software package such as Maplnfo. Once a site is digitized, users could create an export file that could be read directly into IMPACT; IMPACT would then create and display polygons based on the information in the GIS file. Adding online mapping capabilities to IMPACT would provide a powerful visualization tool that would allow IMPACT to display the changing concentrations or doses in all polygons as a simulation is running. Integrating IMPACT with GIS software will allow AECB staff to define reference environments around nuclear facilities, and to import this information to IMPACT for performing pathways analyses and calculating the dose or risk to receptors. Online mapping will provide a type of visualization that will be useful for assessment, presentation and training purposes.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $20k S28k SOk S48k Actual Spent to Date SOk $20k S20k Progress to Date The contractor has reviewed a number of PC-based GIS systems for possible use with the IMPACT model. A recommendation was made by the contractor to select MapINFO as the GIS software to use in conjunction with IMPACT. -150-
5.154.1 Workshop on Current Knowledge and Developments in Containment Structures Program Officer M.R. Avadhanula Contractor Shawinigan Inc. Status PPE initiated Comments
Original Project Description It is intended to organize-a workshop on the current knowledge and techniques used in the evaluation of the long-term integrity of water-retaining containment structures. The Federal-Provincial Joint Review Group (JRG) is responsible for assessing the adequacy of decommissioning plans submitted by Rio Algom Limited and Denison Mines Limited for their Elliot Lake waste management facilities, particularly the tailings areas. One of the most critical components of these tailings areas, with respect to long-term integrity, are the tailings containment dams. In conducting its assessments of these water-retaining structures, the JRG must factor in the latest developments in such issues as: recognized and generally acceptable good engineering construction practices; provision for and judgement of adequacy for long-term (> 1000 year) dam stability, including resistance to erosional and seismic forces; and prudent provisions for long term inspections, maintenance and remedial work, including cost estimates for these functions.
The scope of the workshop would be to address these and other relevant assessment issues and would ideally be led, over a period of two days, by a group of several experts in this field. As part of the workshop a practical inspection would be conducted of a representative sample of containment structures in the Elliot Lake area.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SlOk S39k SOk $0k $49k Actual Spent to Date SlOk $39k $49k
Final Results The workshop was held in Sudbury, Ontario, on October 19 and 20,1993. Thirty-two participants representing federal and provincial agencies concerned with licensing and decommissioning of uranium mill tailings, attended the workshop. Presentations and panel discussions were given by specialists in the fields of geotechnical, geo-environmental and hydrotechnical engineering. Reference material consisting of an overview of relevant research, state-of-the-art procedures, practical measures and current discussions in the field of decommissioning of uranium mill tailings facilities was provided to all the participants in a binder. The post-workshop evaluation indicated that the workshop was very well conducted. - 151 - 5.156.1 Waste JRock Sampling Manual - Phase II Program Officer M.R. Avadhanula Contractor CANMET Status Work in progress Comments CANMET is managing tins joint study and SENES Consultants, Toronto, Ontario, is doing the actual work. Original Project Description It is intended to participate in MEND program (Mine Environment Neutral Drainage) and partially fund the second phase of the preparation of a waste rock sampling manual. The Phase II manual is a further delineation of the available waste rock sampling techniques and suggested methodologies applicable for the various stages of mine development. The objective is to ensure that appropriate data is collected to evaluate properly the contamination potential of the waste rock, including acid mine drainage and the leaching characteristics of heavy metal contaminants and radionuclides. Appropriate use and siting of the waste rock are essential in avoiding additional handling, remedial action or unnecessary contamination of the environment. The formulation of the waste rock manual will provide AECB staff the opportunity to evaluate and recommend appropriate methodologies to characterize this waste material. Proper evaluation improves AECB staffs decision-making process in accepting assessment, operational and decommissioning plans from its licensees. This contract will be managed by the MEND coordinator at CANMET. EMR.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk SlOk SOk SOk SlOk Actual Spent to Date SOk SlOk SlOk Progress to Date The contractor has compiled a second draft manual based on the results of an international questionnaire on rock sampling methodologies. An international workshop was arranged by the contractor which is preparing the proceedings. - 152- 5.162.1 Research on Biophysical Impacts of U Mine Effluents Program Officer M.R. Avadhanula Contractor Golder Associates Ltd. Status Work in progress Comments
Original Project Description It is intended to conduct a critical review of existing research studies into biophysical effects associated with effluent discharges from Canadian uranium mining facilities. Over the past 25-30 years, several research studies have investigated potential biophysical impacts to terrestrial and aquatic ecosystems as a result of contaminant releases from uranium mining facilities in Canada. Although the significance of these impacts in terms of ecosystem structure and function is difficult to assess, it appears that changes in water quality and in the health of aquatic and terrestrial biota have occurred. The results of these studies into biophysical effects are available from diverse sources, such as scientific journals, environmental impact assessments of uranium mine developments, government reports and monitoring reports from uranium mine facilities. A compilation and synthesis of the results of these studies would be useful to identify information gaps and future research needs in this area. The results of this comprehensive and critical review will better define our current understanding of documented ecosystem impacts. The study will assist AECB staff in focusing their efforts in the evaluation of the environmental impacts of uranium mining in Canada, and in defining more precisely areas in which additional biophysical effects research is necessary.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S4k $32k SOk $36k Actual Spent to Date $0k $4k S4k Progress to Date The first phase of a literature search was completed. Databases searched through the CAN/OLE database system included ENVIROLINE, IMS, AQUAREF, BOREAL, ASFA, CISTIMON, and NTIS. The CURRENT CONTENTS database was also searched. -153 - 5.163.1 Stress Corrosion Cracking of Steel in Stagnant Environments Program Officer J.K. Pereira Contractor CANMET Status Work in progress Comments
Original Project Description This is a proposal for participation in a jointly-funded experimental investigation into parameters which influence the propagation of stress corrosion cracks in steel. The experimental work is being undertaken at the CANMET laboratory in Ottawa.
The assessment of the integrity of high level waste containers in long term storage requires understanding of the nature of degradation processes which could affect container materials. Stress corrosion cracking is a mechanism which affects steel container components. Various environmental conditions including microbiological activity could influence the susceptibility of steel to stress corrosion and the propagation of stress corrosion cracks. There is a need for AECB staff to obtain information on the significance of environmental factors in stress corrosion processes which could arise in long term storage of waste containers. The CANMET project aims to address similar issues for oil industry pipeline steels. Participation in the jointly-funded project will enable AECB access to data from this investigation as well as information from related studies done at CANMET and in industry.
Results from the study will be applied in AECB staff assessments of designs proposed by industry for high level waste containers.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $15k S2k SOk S17k Actual Spent to Date SOk $15k $15k Progress to Date The AECB became a participant in this CANMET/industry funded project early in 1994. Preparations were then in hand for the first stress corrosion test on a section of gas transmission line pipe. The last Technical Advisory Group meeting for the project was held in December 1993. The next one will be held in June 1994. -154-
6.113.1 Doses from Radioactive Waste in Municipal Systems Program Officer K.P. Ho Contractor Atlantic Nuclear Services Ltd. Status Work in progress Comments
Original Project Description It is intended to determine the doses to members of the public from radioactive materials that have been disposed of in municipal waste systems in accordance with currently accepted practices. This project is proposed in order to assess doses to members of the public from current disposal practices of radioisotope licensees, such as hospitals, universities and research laboratories. In order to assess the radiation exposures to members of the public, it will be necessary for this project to proceed in two phases. The objective of the First phase will be to measure or otherwise monitor those components of municipal waste systems that may comprise a source of radiation exposure to members of "the public. Municipal waste systems that are to be examined include, but are not necessarily limited to, incinerators, sewage treatment systems and landfill sites. Several Canadian cities will be included in this study. The second phase of this project wiU use the results from Phase I and theoretical models to determine the doses to members of the public.
It is anticipated that the results of this project will confirm that the disposal practices approved by the AECB do not result in unacceptable doses of radiation to members of the general public.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S19k Silk S40k SOk S70k Current Estimates $19k Silk $60k $0k $90k Actual Spent to Date $19k Silk $30k Progress to Date A sampling protocol has been developed by the contractor, and preliminary samples have been analyzed. The protocol and the results of the analyses were being evaluated by AECB staff. -155 - 6.118.1 Assessment of Tc-99m in Nuclear Medicine Environments Program Officer K.P. Ho Contractor Health Sciences Centre, University of Manitoba Status Work in progress Comments Original Project Description It is intended to investigate the frequency and magnitude of Tc-99m internal radioactive contamination among workers in nuclear medicine environments. Identification and selection of an affordable instrument for the Tc-99m bioassay screening program will be carried out. The work will be conducted in hospital nuclear medicine departments and in radiopharmacies. This project is proposed because the AECB has not previously investigated, in detail, the actual intake of Tc-99m by workers in nuclear medicine environments. In addition, there is a need to identify an affordable instrument capable of detecting Tc-99m according to the requirements of "Bioassay Guideline 5 - Guideline for Tc99m Bioassay", a draft report produced by the Federal-Provincial Working Group on Bioassay and In-vivo Monitoring Criteria.
It is anticipated that the results of this study will provide useful information on Tc-99m intake by workers in nuclear medicine environments. A number of factors will be determined for selecting suitable Tc-99m bioassay instruments. This will allow AECB staff to detennine whether regular personnel monitoring of nuclear medicine workers is necessary or not.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S5Ok S33k S27k $8k $118k Current Estimates $49k $36k $4 Ik S37k $163k Actual Spent to Date $49k $36k $85k Progress to Date A monitoring program protocol has been developed by the contractor. In addition, a monitoring instrument has been proposed as the bioassay instrument for the remaining phases of this project. These were being evaluated by AECB staff. -156- 6.120.1 Doses from Industrial Radiographie Exposure Devices Program Officer K.P. Ho Contractor Thurber Engineering Ltd. Status Work in progress Comments Contract issued.
Original Project Description It is intended to initiate a study to determine the fractionated doses received by trainees and qualified operators of industrial radiographie exposure devices while performing the various tasks in radiography, under varying working conditions. AECB radiography licensees employ over 1,500 trainees and qualified operators. Currently, these employees constitute one of the most highly exposed groups of atomic radiation workers in Canada. The AECB is concerned about the recorded high doses received by this group of workers and proposes to carry out this investigation by splitting the procedure of a radiography job into its basic elements by recording the respective doses received by workers, at each phase of the procedure. It is anticipated that the results of this study will provide information, to the AECB and to operators of radiographie exposure devices, as to how to reduce annual radiation doses to workers by improving the radiation protection safety practices of each phase of the job.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S 10k S40k S30k SOk S80k Current Estimates SOk SOk S65k $21k S86k Actual Spent to Date $0k SOk SOk - 157 -
7.106.2 Effects of In Utero Exposure on Central Nervous System Program Officer V. Elaguppillai Contractor Status Preparations initiated Comments Internal approval being sought.
Original Project Description It is intended to continue a full-scale study of the health effects on the central nervous system (CNS) of experimental animals (mammals) following in utero exposure to ionizing radiation. Pregnant animals will be exposed to different doses and dose rates of ionizing radiation at different stages of gestation and the corresponding morphological and physical changes in the brain will be assessed quantitatively. It is anticipated that an increasing number of young women will seek and find employment in the Canadian nuclear industry, where, in some cases, exposure of embryos or fetuses may occur. Very little information is available in the literature about the effect of in utero irradiation on the development and structure of the central nervous system. A feasibility study (84.8.8) completed in 1986 recommended a full-scale study to make quantitative estimations of the risk of health defects on the CNS following in utero irradiation taking dose, dose rate, and the stage of gestation into account.
The results of the full-scale study will be used to extrapolate, from animals to humans, the risk estimates for radiation-induced developmental defects. (This is a joint study between the University of Manitoba, the University of California (Davis) and the AECB. The total cost of the projects is S750,000, AECB's share is $150,000.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SlOk S40k $40k $60k $150k Current Estimates SOk SOk S25k S125k S 150k Actual Spent to Date SOk $0k SOk
Review Panel 01 Comment Review panel reviewed the work statement and suggested a number of changes. Review panel comments were incorporated into the final work statement. -158 -
7.107.2 Teratogenic Effects of Ionizing Radiation and Chemical Substances - Phase
Program Officer M. Lupien Contractor R. Narbaitz Status PPE initiated Comments
Original Project Description It is intended to determine whether it is feasible to evaluate, experimentally, the teratogenic effects of simultaneous exposure of pregnant female animals, to selected chemicals and radiation. The risk of radiation-induced teratogenic effects (such as Down's Syndrome) can be altered by the presence of chemical agents (such as ethanol). Information on the subject is scanty, and has not been considered in most epidemiological studies. Although the influence of chemical exposures at the low levels which are typical in the workplace is expected to be small, new evidence is required to rule out the likelihood of a strong synergism. This project is proposed as a follow-on to the recently completed Project 7.107.1, "Identification and Monitoring of Non-Radiological Carcinogens", which produced a catalogue of chemicals found in the workplace. It is anticipated that this project will produce needed quantitative information on the extent to which chemical exposures alter the risk of radiation:induced, teratogenic effects in mammals.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk $50k SOk SOk S50k Current Estimates SOk S17k S4k SOk S21k Actual Spent to Date SOk $17k S17k Progress to Date Work complete.
Final Results The contractor proposes an experimental plan to investigate, in a laboratory rodent (Rat), possible interactions between chemical teratogens and ionizing radiations. The chemical teratogen best suited for such a study had to be chosen, from those chemical substances to which workers at nuclear plants and Nuclear Medicine facilities in Hospitals are exposed most frequently. It was agreed, between the contractor and the AECB staff that cadmium (Cd) was the best candidate for an individual study.
The detailed experimental plan suggests two combinations: radiation plus acute Cd administration (imitating human accidental exposure) and radiation plus chronic Cd administration (imitating chronic human exposure in the workplace). In both series of experiments, the objective would be to establish whether combined exposure to subteratogenic doses of both agents might resulfin a detectable teratogenic response). Since subteratogenic doses in the animal are comparatively higher than those to which women are usually exposed in the workplace, the absence of a detectable effect would indicate that combined exposures to both teratogens presents very small risk for the human. If however, should an effect be detected, additional experiments would have to be conducted in order to establish the minimum doses for which an effect becomes reasonable. -159-
7.107.3 Teratogenic Effects of Ionizing Radiation and Chemical Substances - Phase II Program Officer M. Lupien Contractor University of Ottawa Status Preparations initiated Comments Internal approval being souçht.
Original Project Description It is intended to investigate the combined effects, on the mammalian fetus, of exposures to chemical substances and to ionizing radiation foundin nuclear facilities. This animal study will be carried out on mice. The risk of radiation-induced teratogenic effects (such as Down's Syndrome) can be altered by the presence of chemical agents (such as ethanol). Information on the subject is scanty, and has not been considered in most epidemiological studies. Although the influence of chemical exposures at the low levels which are typical in the workplace is expected to be small, new evidence is required to rule out the likelihood of a strong synergism. This project is proposed as a follow-on to "Teratogenic Effects of Ionizing Radiation and Chemical Substances - Phase I" which produced a protocol for testing, experimentally, the teratogenic effects or simultaneous exposures to chemical and radiation of pregnant female animals and recommended appropriate procedures for conducting an animal experiment in this domain. It is anticipated that this project will produce needed quantitative information on the extent that chemical exposures alter the risk of radiation-induced teratogenic effects in mammals.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k SOk S50k $30k $80k Actual Spent to Date SOk SOk SOk -160- 7.117.1 Hospital Record-Keeping System for Epidemiological Studies Program Officer K.P. Ho Contractor University of Ottawa Status Work in progress Comments Original Project Description It is intended to continue a feasibility study to modify hospital record-keeping systems to facilitate inexpensive case-control epidemiological studies of radiation-induced cancers. Case-control studies of radiation-induced cancer can be conducted inexpensively using hospital records. However, the record-keeping systems in Canadian hospitals are not currently in a format that facilitates such studies.
It is anticipated that the results of the study will determine the feasibility of modifying hospital record-keeping systems to facilitate epidemiological studies. If the modification is feasible, several epidemiological studies of radiation-induced health effects can be conducted inexpensively to improve the accuracy of risk estimates. (NHW and provincial ministries of health are co-operating in the project.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $30k $20k $0k SOk S50k Current Estimates $30k $20k $0k SOk S50k Actual Spent to Date S30k $20k $50k Progress to Date The contract has investigated the various hospital record-keeping systems in use throughout Canada and, from this survey, is proposing a minimum set of identifying information required to carry out epidemiological record-linkage studies. -161- 7.135.1 Mechanism of Radiation-Induced Mental Retardation Program Officer V. Elaguppillai Contractor Mr. W.J. Schull Status Work in progress Comments
Original Project Description It is intended to continuerfunding laboratory experiments to study the effect of low doses of ionizing radiation on the migratory characteristics of neurons in mice and in non-human primates. Embryonic neural cells will be cultured, and exposed to different doses of ionizing radiation at different stages of neuronal development. The subsequent changes in the cellular surface structures, the number of cells present to migrate and the rates and the extent of migration of the neurons will be assessed quantitatively using a variety of monoclonal antibodies. Recently, magnetic resonance imaging and autopsy data have established that a substantial fraction of the radiation-related cases of mental retardation seen in Hiroshima and Nagasaki bomb survivors exhibits evidence of a gross impairment of neuronal migration, seen as ectopic grey matter, largely circumventricular in distribution. It is important to understand the relationship between exposures and impaired migration and the cellular and molecular nature of this impairment in order to derive a quantitative value for the risk of mental retardation following in utero exposure to ionizing radiation.
It is anticipated that the results of this study will provide quantitative information on the mechanism of the impairment of the neuronal migratory processes. This understanding will lead to a better estimate of the risk of mental retardation due to in utero exposure to ionizing radiation. (This is a joint study with the Radiation Effects Research Foundation of Japan, Kyoto Prefectural University of Medicine (Japan), and the University of Texas Health Sciences Center in Houston. The total cost of the project is about S280k, shared among all sponsors, with an AECB contribution of about S80k over 3 to 4 years.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S71k S2k SOk SOk S73k Actual Spent to Date $7 Ik S2k S73k Progress to Date A new method of cultivating expiants of the developing rat cerebral cortex was developed satisfactorily. This method was subsequently used to test the migrational pattern of the neurons following exposure to 5,10,15 and 20 cGy of gamma radiation. The cells were labeled with H-3 thymidine at embryonic day 16 (E16) and the number of heavily labeled cells within each zone of the cortex were counted in autoradiographic sections. The results indicated that exposure to 10-20 cGy significantly slows the neuronal migration without increasing cell death. The results at 5 cGy do not show any significant impairment of neuronal migration. -162- 7.137.1 Study of Childhood Cancer Associated with Maternal X-Irradiation - Phase 1 Program Officer M. Lupien Contractor University of Toronto Status Work in progress Comments
Original Project Description It is intended to assess the feasibility of determining the incidence of childhood cancer among (i) those children who had abnormal delivery (such as breech presentation) or birth defects (such as Down's Syndrome), but whose mothers were not subjected to irradiation during pregnancy, and (ii) those who received in utero exposure to X-rays, both groups to be compared with suitably selected control populations. Some controversial studies have indicated an association between maternal exposure to low doses of ionizing radiation (i.e., at levels in the neighbourhood of regulatory dose limits) and the incidence of excess childhood cancers. On the other hand, some recent studies have reported an association between abnormal pregnancy cases (such as breech presentation and Down's Syndrome) and excess childhood cancers, even in the absence of exposure to X-rays during pregnancy or delivery. It is therefore possible that the reported association between maternal irradiation and excess childhood cancer was essentially due to those cases of abnormal pregnancies and deliveries and not necessarily due to maternal irradiation.
The results of this study will demonstrate whether it is possible to improve our understanding of the qualitative association between childhood cancer and maternal irradiation and may improve the quantitative risk estimates for radiation-induced cancers. (The feasibility study will be followed, if justified, by a full-scale study.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Slk $43k SOk SOk $44k Current Estimates $2k SlOk $40k SOk S52k Actual Spent to Date $2k SlOk S12k Progress to Date Preliminary results have identified two limitations in the available Saskatchewan databases: (1) it may be necessary to conduct a review of patient medical charts to collect complete data on exposure to medical irradiation, and (2) several sources may need to be accessed in order to ensure that mothers are found for all children in the cohort.
Final Results This feasibility study evaluated a population-based case-control study in Saskatchewan, which involved the linkage of multiple sources of health services and vital statistics records. The feasibility of the design was in part made apparent by the fact that numerous previous studies in Saskatchewan have demonstrated that these databases can be linked. Indeed, the combination of Canadian expertise in record linkage studies and the availability of population-based health and vital statistic databases, distinguishes Canada as one of the few countries where such a study is feasible. Through close consultation with representatives of the agencies responsible for these databases in Saskatchewan it was possible to develop detailed procedures and to estimate costs. -163- 7.141.1 Response of Mice to Gamma Rays Delivered at Low Dose Rates Program Officer E. Rabin Contractor AECL Research - CRL Status Work in progress Comments
Original Project Description It is intended to expose CBA/H mice to Co-60 gamma rays at low doses (1 Gy, 0.1 Gy) and low dose rates (0.004 Gy/hr, 0.02 Gy/hr, 0.1 Gy/hr; 0.5 Gy/hr) and score the subsequent incidence of myeloid leukemia in the animal population. In addition, an investigation of the effect of heat stress on the rate of induction of myeloid leukemia in mice subsequently exposed to gamma radiation is to be carried out. The primary hazards of exposure to low levels of radiation at low dose rates are generally considered to be the induction of cancer and of genetic changes. For these end points a task group has recently observed, in ICRU Report No. 40, that the appropriate quality factors for gamma rays and x-rays have been derived almost exclusively from laboratory studies on particular end points, such as the induction of somatic mutations in micro-organisms (Tradescantia). Data obtained recently suggest that doses of gamma rays up to about 1 Gy, delivered at dose rates of about 0.008 Gy/hr, have comparatively little effect on the induction rate of mammary tumours in Sprague-Dawley rats. This finding suggests that the risk due to exposure to gamma rays that are delivered in low doses may decrease to zero at low dose rates for this particular end point. If this observation were confirmed, this could lead to a reduction of the quality factor for gamma radiation delivered at low dose rates, and therefore to a re-evaluation of risk estimates for radiation-induced cancers in humans from gamma radiation. Other studies that have the induction of cancers as their end points are required to investigate the risk of gamma rays when delivered at low dose rates. It is anticipated that this study may provide justification for reducing the quality factor (below the current value of unity) for gamma rays delivered in low doses and at low dose rates. This would impact on the risk estimates for radiation-induced cancer for humans from exposure to gamma rays. (This project is being cost-shared wtih AECL on an approximate one-third (AECB)Awo-thirds (AECL) basis with a total project cost estimate of S560k.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S92k $43k $41k $0k S176k Current Estimates S 159k 343k $0k SOk $202k Actual Spent to Date $159k $43k $202k Progress to Date All irradiations of the mouse colony have been completed. The animals are living out their lives and are being assessed for the incidence of myeloid leukaemia Approximately 12% of the animals have died to date. Animals which appear to be sick are being euthanized. -164-
7.142.1 Mortality Analysis of the Fluorspar Miners from 1985-1990 Program Officer M. Lupien Contractor Health & Welfare Canada - Cancer Division, LCDC Status Work in progress Comments
Original Project Description It is intended to update the mortality analysis of the fluorspar miners in St. Lawrence, Newfoundland, from 1985 to 1990. The risk of lung cancer per unit exposure to radon daughters is being recalculated using the additional mortality information and previously estimated exposures to radon daughters. The previous analysis considered lung cancer mortality only up to 1984. Since that time, more deaths have occurred among fluorspar miners as a result of the natural aging of this cohort. Since the fluorspar miners were in a unique situation, in which they were exposed to neither gamma radiation nor radioactive dust, it is important to analyze their mortality data to obtain improved risk estimates for lung cancer in a 'pure' radon daughter environment.
It is anticipated that the results of this study will further improve the risk estimates for lung cancer from exposure to radon daughters in the absence of gamma radiation and radioactive dust. (This is a joint project with the Department of National Health and Welfare and Statistics Canada.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S25k S15k $10k SOk $50k Current Estimates $25k S 15k SlOk $0k $50k Actual Spent to Date $25k S15k $40k Progress to Date LCDC is collecting the information and updating the database. -165 - 7.143.1 Canadian Cancer Data Base Program Officer K.P. Ho Contractor Statistics Canada Status PPE initiated Comments
Original Project Description It is intended to continue the funding to update the Canadian Cancer Data Base (CCDB) in order to include data up to 1988. This work will also identify multiple records of cancer incidence for the same individual. In addition, a set of microfiche of the CCDB will be created in various format sequences to facilitate manual checking of the completeness of the updated file.
This approach is to be followed in order to reduce the labour required when the cancer data files are being used in the follow-up of radiation studies. Past studies have included the Canadian fluoroscopy study, the Eldorado Nuclear Limited cohort, and the Atomic Energy of Canada Ltd. study.
The results of this study will help to determine whether the occurrence of cancer is significantly higher in study groups exposed to radiation compared to non-exposed control groups. (This project, plus its update, will be cost-shared with Statistics Canada. Statistics Canada is to contribute S 10k and the AECB S35k.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $18k S2k SOk SOk S20k Current Estimates S20k SOk SOk SOk S20k Actual Spent to Date S20k SOk S20k
Final Results All internal linkages between 1969-1988 have been performed. Two further years of data, 1989 and 1990, are available and the contractor is proposing to include them in the Canadian Cancer Data Base. This work is to be carried out in Project 7.143.5. -166- 7.143.5 Canadian Cancer Data Base - Phase H Program Officer K.P. Ho Contractor Statistics Canada Status Work in progress Comments Continuation of project 7.143.1.
Original Project Description It is intended to extend the update of the Canadian Cancer Data Base (CCDB) to include two more years of data, that is, up to and including 1990. This work, as its predecessor, 7.143.1, will also identify multiple records of cancer incidence for the same individual. In addition, a set of microfiche of the CCDB will be created in various format sequences to facilitate manual checking of the completeness of the updated file.
This approach is to be followed in order to reduce the labour required when the cancer data files are being used in the follow-up of radiation studies. Past studies have included the Canadian fluoroscopy study, the Eldorado Nuclear Limited cohort, and the Atomic Energy of Canada Ltd. study.
The results of this study will help to determine whether the occurrence of cancer is significantly higher in study groups exposed to radiation compared to non-exposed control groups.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $0k $15k SOk S15k Actual Spent to Date SOk SOk SOk -167 - 7.156.2 Tritium Levels in the Environment and Birth Defects Program Officer V. Elaguppillai Contractor Health & Welfare - Cancer Division Status PPE initiated Comments
Original Project Description It is intended to examine the correlation between (revised) tritium levels in the environment (as obtained from environmental monitors) and birth defects around the Pickering nuclear generating station for the period from 1971 to 1988. A previous study of birth defects around the Pickering nuclear generating station (7.156.1) examined the correlation between environmental levels of tritium and birth defects, and reported no significant correlation. The environmental tritium data used in the study were supplied by the Bureau of Radiation and Medical Devices (BRMD). Recently, the BRMD informed the AECB that the tritium data used in the previous analysis (7.156.1) had a systematic error due to the use of a wrong conversion factor. Subsequently, the tritium levels were re-calculated using the correct conversion factor. It is important to re-examine the correlation between the revised environmental levels of tritium and birth defects around the nuclear facility at Pickering.
It is anticipated that the results of this study will clarify whether there exists any correlation between the environmental levels of tritium and birth defects around the Pickering Nuclear Generating Station. (This is expected to be a joint project with the Laboratory Centre for Disease Control (NHW) and the Atomic Energy Control Board. The total cost of the project is expected to be $20k, of which the AECB's share is S15k.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S5k SlOk SOk SOk S15k Actual Spent to Date S5k $10k $15k
Final Results The corrections to the airborne tritiated water vapour monitoring data resulted in reducing ttritium concentration values than the values used in the previous analysis for the winter seasons from 1985 through 1988. The possible associations between Down Syndrome and the monitored levels of tritium in the air during the first trimester of pregnancy were analyzed and, no statistically significant associations were found. -168- 7.160.1 Metabolism and Fetal Dosimetry of Tritium Program Officer E. Rabin Contractor National Radiological Protection Board Status Work in progress Comments Original Project Description It is intended to conduct a series of experiments on pregnant rats to determine the uptake, distribution and retention of tritium and of organically bound tritium within the conceptus of rats following the ingestion of tritium. There will be two separate sets of experiments using: 1) tritiated water and 2) tritiated food. Additionally, the off-spring from these rats will be observed for leukemia incidence during their maturation. Tritium is a by-product of CANDU reactor operations and is also used in other industries and research laboratories, and therefore it is important to be able to assess realistically the committed doses received by the fetus following the ingestion of tritiated food and water by the mother. This project is proposed because, in assessing the risks to the developing conceptus from exposure to tritium, many factors, such as tissue specific activity, location and metabolism of tritiated compounds, must be taken into consideration. Tritium can be incorporated into organic molecules within the cell, and into the nuclei of proliferating cells. Tritium incorporated in this way is retained in the body four times longer than tritiated water (ICRP 56). Of particular importance, oocytes and latent stem cells of the hematopoietic (blood forming) system are long-lived tissues which may retain tritium at elevated concentrations. For the adult, the fraction of tritium incorporated into organic molecules, including DNA, is higher for tritium ingested in the form of tritiated food than for tritiated water, and results in a committed dose which is higher than that from tritiated water by a factor of about two (ICRP 56). Although little is known about the fate of tritium incorporated into the animal conceptus, evidence from earlier research on mice (Commerford et al., 1982) suggests that about six times as much tritium will be incorporated into the DNA of the developing conceptus in comparison to the adult. It is anticipated that the findings from this project will enable AECB staff to evaluate more accurately the dose and subsequent risk to the fetus from ingestion by the mother of tritiated water and food contaminated with tritium. The results of this study may impact on the application of the proposed amendment to the Atomic Energy Control Regulations that pertains to limiting the dose to the fetus of pregnant ARWs.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S60k $80k S50k S50k S240k Current Estimates SOk $30k $109k $196k S335k Actual Spent to Date $0k $30k $30k Progress to Date The experimentation programme has begun with the administration of tritiated glucose to rats. Review Panel 24 Comment The review panel discussed the research protocol with the contractor at the project initiation meeting. Agreement was reached on suitable methods of administration of tritiated glucose. . -169-
7.162.1 Assessment of Biases Due to Measurement Errors on Risk Estimates Program Officer M. Lupien Contractor Dr. Geoffrey R. Howe Status PPE initiated Comments
Original Project Description It is intended to develop an appropriate statistical methodology for assessing the effect of errors in radiation dose or exposure measurements on subsequent risk estimates, and to apply this methodology to quantify the effect of measurement errors on the risk estimates for radiation-induced leukemia, breast and lung cancer. The errors in estimating radiation exposures used in major epidemiological studies can introduce substantial biases into the risk estimates for radiation-induced cancers. A recent AECB-sponsored study, "The Selection and Use of Control Groups in Epidemiologic Studies of Radiation-Induced Cancers", Project 7.118.1, by the National Cancer Institute of Canada has concluded that measurement errors were likely to be the most important biases introduced into the risk estimates for radiation-induced cancers. To date, little or no attention has been given to dealing with these biases involved in risk estimates. For example, risk estimates reported in the recent BEIRIV and BEIR V reports did not take such measurement errors into account in estimating the risk of cancer due to low- and high-LET radiations. There have been a number of recent developments in the field of statistical methods to take into account measurement errors in making risk estimates, and this new information may be used to re-examine the errors associated with the risk estimates derived from Canadian and other major epidemiological studies of radiation-induced cancers.
It is anticipated that the results of this study will enable the AECB to understand the extent of the biases introduced by exposure measurement errors on currently-used risk estimates (which form the basis of the Canadian regulatory dose limits). Additionally, the study will provide the AECB with a detailed guide for addressing this problem in a number of AECB-funded, on-going and future, epidemiological studies of radiation-induced cancer and developmental disorders. (This project is expected to be a joint study with the National Cancer Institute of Canada, University of New Mexico, and the University of Southern California on an equal cost sharing basis. The cost to the AECB is expected to be about S50k.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates $46k $2k $0k SOk $48k Actual Spent to Date $46k S2k S48k
Final Results This report described and developed statistical methods for assessing and adjusting for the effect of measurement error in doses on risk estimates derived from epidemiological studies of radiation and cancer. It was concluded that estimates of risk based on the BEIR V models for radiation-induced breast and lung cancer and leukemia mortality were unlikely to be in error by a factor of more than 10 percent due to measurement error in doses. The coefficients of the risk models would be changed from 1.220 to 1.341 excess relative risk per Gray (female breast cancer mortality), 1.295 to 1.455 (female lung cancer mortality) and 0.636 to 0.715 (male lung cancer mortality). -170-
7.164.2 Improved Cytometry Method - Phase 2 Program Officer E. Rabin Contractor Health Canada Status Work in progress Comments
Original Project Description ll is intended to automate further the computer-assisted system for dicentric chromosome analysis used in radiation accident dosimetry at the Radiation Protection Bureau (RPB) of Health Canada. This additional phase of the work will further automate the analytical process for identifying dicentric chromosomes in the metaphase spreads of white blood cells from a person who has received an accidental exposure to ionizing radiation. The earlier project, "Improved Cytometry Method" (RSP project # 7.164.1), co-sponsored by RPB and the AECB, increased the speed of the analysis of metaphase spreads by a factor of 10 greater than the unassisted manual method. The addition of automated searching for analyzable metaphase spreads ( 1000 to 1500 spreads per recipient) which does not require operator intervention, and which could be run overnight or during weekends, could save an additonal 25 to 50 hours of operator time, thereby reducing the cost, as well as speeding up the turn-around time for the analysis. This further automation requires purchasing additional hardware for the system as well as developing suitable software. The AECB funding contribution to the work will be used for software development and quality assurance, and increasing the "clock speed" of the computer that drives the system. As with the previous project, it is anticipated that the system developed by this project will result in the AECB obtaining better dosimetric information from RPB on radiation accident victims, and obtaining this information more rapidly than is currently possible. (This project will be a collaborative effort by the AECB and RPB. The total cost for acquisition, installation and testing of hardware and software is estimated to be 550,000. RPB will purchase much of the hardware, and provide laboratory and technical facilities and technical direction for the performance of the work. The AECB will enter into a research agreement with RPB for the performance of the work.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates $0k $0k $20k $0k $20k Actual Spent to Date $0k $0k SOk Progress to Date Contracting has been completed. The work is scheduled to start in early FY 94/95. -171- 7.167.1 Risk Estimates for Radiation-Induced Genetic Disorders Program Officer V. Elaguppillai Contractor State University of Leiden, The Netherlands Status Work in progress Comments
Original Project Description It is intended to conduct a study to obtain improved risk estimates for radiation-induced genetic disorders. This study consists of two parts, laboratory experiments and mathematical modelling. In the first part, biological samples obtained from humans who are known to have inherited disorders, including multifactorial disorders, will be analyzed and the mutation rates for a variety of end points will be estimated. The rates will then be compared with the results obtained from animals exposed to different doses of ionizing radiation, and. subsequently, a set of probable values of relevant genetic parameters will be deduced. These parameters will be substituted into a suitably developed mathematical model, and improved risk estimates will be obtained. The mathematical model will be used to calculate the uncertainty in the risk estimates. Currently-used risk estimates for radiation-induced genetic disorders are derived from the observations of dominant and recessive types of genetic disorders, which constitute only 1-2% of the total genetic load in the offspring of the exposed parents. Contribution to the risk estimates, from the remaining 98-99% of the disorders (multifactorial disorders) have been estimated using a number of assumptions, and some of these assumptions are now known to be associated with large uncertainties. Consequently, the overall risk estimates for radiation-induced genetic disorders may be associated with large uncertainties. The possible uncertainties in these assumptions have been discussed in the recent reports of the BEIR V and UNSCEAR 1988 Committees. Professor Sankar (a consultant to UNSCEAR) and Professors Yasuda of Japan, and Czeizel and Tusnady of Hungary, who are international experts in the field of radiation-induced genetic disorders have come up with a design to conduct a study to overcome this major uncertainty. It is anticipated that the results on this study will improve the risk estimates for radiation-induced genetic disorders, which, in turn, will help to improve the weighting factors used to calculate the effective dose equivalent. (This is a joint study with: State University of Leiden, the Netherlands; National Institute of Radiological Sciences, Chiba, Japan; Mathematical Academy of Sciences, Budapest, Hungary; and National Institute of Hygiene, Budapest, Hungary. An additional grant has been made to this project by the Commission of the European Communities. The total cost of this multi-year project is expected to be S900k, with a total contribution from the AECB of about SlOOk).
Past 93/94 94/95 Future Total 93/94 Program Document Estimates $65k S15k SlOk SlOk S 100k Current Estimates $67k $47k $14k $0k S 128k Actual Spent to Date $67k $47k SI 14k Progress to Date Several mathematical models for assessing multifactorial disorders were developed. The biological parameters derived from the blood samples analyses and clinical observations of certain inherited disorders were fitted into these models. The models will be revised based on the fitting of the biological parameters. Review Panel 25 Comment The review panel reviewed the models and suggested a number of changes. The review panel comments were incorporated, and revised models are expected ul.'hin the next several months. - 172-
7.171.1 Canadian Coordinating Committee on Chernobyl Program Officer V. Elaguppiilai Contractor various Status Work in progress Comments
Original Project Description It is intended to examine the possibility of conducting joint studies of health effects on the Chernobyl population who were exposed to ionizing*radiation during the nuclear accident in 1986. There is a wealth of unique information to be gained from the effects of the Chernobyl accident, but the complexity of the processes from which the information is being gathered is such that co-operative efforts are required. AECB staff want to determine the most effective way of participating in joint studies on the health effects of the Chernobyl accident. To achieve this objective, the AECB is requesting the services of several specialists to provide advice on the suitability, design and conduct of epidemiological studies of the Chernobyl population. The studies may be conducted in collaboration with other Canadian organizations (AECL Research, NCIC, Health and Welfare Canada) and other organizations (US-DOE, US-NCI, CEC).
It is anticipated that this project will bring to the AECB valuable information on the possible effects of an accident at a commercial nuclear reactor.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $25k S 10k SlOk SlOk $55k Current Estimates S27k $6k $7k S5k S45k Actual Spent to Date S27k $6k S33k Progress to Date Dr. G. Howe attended 3 meetings with US-DOE, US-NCI, CEC, WHO and officials of Ukraine to discuss the design of the study of leukemia and thyroid cancer among children in Ukraine, exposed to Chernobyl-related radiation. The design of the study has been approved. Further work is in progress. -173 -
7.176.1 Biological Dosimetry Workshop Program Officer E. Rabin Contractor AECL Research - CRL Status Complete Comments
Original Project Description It is intended to convene a workshop on the topics of the current status of biological dosimetry, strategies for developing and validating biological indicators of exposure to radiation, and implementing biological dosimetry as part of radiation dose monitoring. In preparation for the workshop, it is proposed to undertake a detailed review and critique of published literature that pertains to existing techniques of biological dosimetry, including an assessment of their accuracy, sensitivity, reproducibility of results, and other important parameters with respect to monitoring low-level radiation exposure. The starting point for the review is to be the Atomic Energy of Canada Report "Bio-indicators for Radiation Dose Assessment", AECL-10245 (December 1990). This project is to be divided into two phases: the first phase comprising the review and critique of the recently published literature, and the second phase, the biological dosimetry workshop.
This workshop is proposed because the assessment of dose to workers following unexpected exposure to ionizing radiation may involve interpreting biological data from various organ, tissue and fluid samples taken from the exposed individuals. Obtaining tfie required information requires the application of diverse techniques from a variety of scientific disciplines. This workshop will bring together physicists, chemists and radiobiologists to discuss current practices and to consider new methods for determining absorbed dose. The review and critique of the literature will provide AECB staff in attendance at the workshop with up-to-date information needed to assess the presentations by the experts in the field, and to stimulate further discussion.
It is anticipated that this workshop will allow AECB staff to gain new perspectives and information pertaining to appropriate techniques for determining the dose to workers for different inadvertent exposure scenarios. (AECL is the lead agency for convening the workshop. AECL is also seeking funding support for the workshop from Ontario Hydro.)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $12k SlOk $0k SOk S22k Current Estimates $12k $0k SOk SOk Sl2k Actual Spent to Date S12k SOk S 12k
Final Results No single biodosimetric technique has been identified that reliably measures occupational exposures at the current levels of sensitivity of conventional dosimetry services. Most of the biotechniques are applicable to the detection of relatively high radiation exposures (> 0.1 Gy) for relatively short times after exposure. Some bio-indicators have been identified that may offer alternatives for routine dosimetry needs. Practical implementation of these methods must be evaluated. The researchers have concluded that the prospects of making accurate individual dose estimates are better when a battery approach is adopted, utilizing several different biological dosimetry systems on the same batch of samples. Final Evaluation The review of the field carried out by the contractor, and the final report given to the AECB, have achieved the purpose of providing up-to-date information on biological dosimetry. The information produced is also used by the AECB to monitor progress made in the most promising directions, that is, the analysis of chromosomal aberrations and dosimetry methods based on Electron Spin Resonance. -174- 7.185.1 Influence of TLD Position on the Estimate of Fetal Dose Program Officer E. Rabin Contractor Science Applications International Corporation Status Work in progress Comments
Original Project Pescription It is intended to investigate the need for double-badging pregnant technologists working in nuclear medicine departments. Double-badging is meant to signify the wearing of two dosimeters: one on the front of the abdomen and the other on the back, at waist level. This project is proposed because during recent public meetings organized by the AECB (Sept.-Dec., 1992), nuclear medicine technologists pointed out that they are occasionally exposed to ionizing radiation that is incident from the back in their work environments. However dosimeters are normally worn on the front where radiation fields are expected to be highest. Consequently, nuclear medicine technologists expressed concern that if they were pregnant and if in some work situations their dose due to ionizing radiation incident from the back exceeds that due to radiation incident from the front, the dose to the fetus may be greater than that estimated from a dosimeter worn at the front of the abdomen. Routinely double-badging these workers is one method of more confidently ensuring that the dose to the fetus is not underestimated. However, double-badging can lead to various administrative and handling problems. Therefore, it is necessary to determine whether exposure from the back is a significant component of a nuclear medicine technologist's exposure. It is anticipated that the results of this study will provide AECB staff with information with which to assess the need for double-badging pregnant nuclear medicine technologists.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk S30k SOk SOk S30k Current Estimates $0k $10k $22k SOk $32k Actual Spent to Date SOk SlOk SlOk Progress to Date The draft of the hospital presentation material has been completed, forwarded to AECB for comment and approved; TLDs and holders have been ordered; initial contact with each of the hospitals has been made. -175-
7.195.1 Quality Assurance Programs in Medical Institutions Program Officer M. Lupien Contractor Status Contracting in progress Comments
Original Project Description It is intended to investigate the radiation protection practices and quality assurance programs in medical institutions with a view to assessing the implementation of the ALARA principle. A thorough analysis of radiation protection practices in medical institutions including the management of quality assurance activities involving radioactive sources will provide information necessary to assess whether the ALARA principle is being applied, and will provide insight to help reduce the frequency and severity of unnecessary exposures.
It is anticipated that the proposed study will provide descriptions of the quality assurance programs in Canadian and foreign medical institutions and include a current listing of literature on these programs.
• Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S25k SOk SOk S25k Current Estimates SOk SOk S53k $0k S53k Actual Spent to Date SOk SOk SOk - 176- 7.200.2 International Study on Nuclear Industry Workers Program Officer K.P. Ho Contractor International Agency for Research on Cancer Status Work in progress Comments
Original Project Description It is intended that the AECB contribute financially to, and participate in, a new international, epidemiological study entitled: "International Collaborative Study of Cancer Risk among Nuclear Industry workers". This study is being coordinated by the International Agency for Research on Cancer (IARC) located in Lyon, France. IARC is an agency of the World Health Organization. This multinational study has twelve participating countries: Australia, Belgium, Canada, Finland, France, Germany, Japan, Spain, Sweden Switzerland, UK, USA. The cohort population for this study is expected to be some 900,000 nuclear industry workers. Canada's contribution to the epidemiological data base will come from several sources: radiation doses from the National Dose Registry managed by the Bureau of Radiation and Medical Devices of Health and Welfare Canada, and health information from Statistics Canada and the National Cancer Institute of Canada.
Current radiation risk estimates are based primarily on studies of atomic bomb survivors from Hiroshima and Nagasaki and to some extent, on medically irradiated individuals who were exposed to acute high doses of ionizing radiation. Although these studies have provided the best available data base for the evaluation of human cancer risk associated with exposure to ionizing radiation, they do not provide direct information on the effect on humans of long-term low-level occupational exposures. To fill this gap in information, a study group was formed by IARC, in late 1988, with members from the participating countries. Their task was to investigate the feasibility of implementing an international collaborative study of cancer risk among nuclear industry workers, using a cohort design. The feasibility study was completed in December 1991. It was concluded by the study group that a large-scale study was feasible and moreover, that it should be carried out and be based on a common protocol. The common protocol was eventually prepared and was accepted by the participating countries. The protocol will ensure data compatibility in this cohort study.
The main objective of this cohort study is to derive, from actual radiation dose, morbidity, and mortality data, cancer risks at low dose and low dose rates of occupational ionizing radiation, for comparison with the risk estimates derived from high dose, high dose rate studies. This information will provide a direct test of the accuracy of the various extrapolation models currently used for risk estimates and for the setting of radiation protection standards. This study will keep AECB staff informed of the latest findings in this unique multinational study and will improve current understanding of the cancer risks at low dose and low dose rates of occupational ionizing radiation. (The proposed time frame for mis study is five and half years beginning about October, 1992 and ending about March, 1998. The estimated total cost for this study is $1.63 M (US).)
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $50k $50k $150k S250k Current Estimates SOk $43k $50k $150k S243k Actual Spent to Date SOk $43k $43k Progress to Date An international agreement between the International Agency for Research on Cancer and the AECB has been signed (November 9,1993). The first financial support payment has been sent. -177- 7.201.1 Medical Radiation Exposures in Canada Program Officer M. Lupien Contractor Vancouver General Hospital Status Work in progress Comments
Original Project Description It is intended to update the report of the Advisory Committee on Radiological Protection (ACRP) entitled "ACRP-9, Radiation Doses From Diagnostic Medical Procedures". This report was approved for publication by the Board in 1986, but was never published. In light of the proposed changes to regulatory dose limits, to regulatory guides on ALARA, and to personnel monitoring, the ACRP recommends that report ACRP-9 be updated and published. In addition, the data contained in the updated report would enable the AECB to assist Canada in fulfilling its commitment to UNSCEAR to provide such data.
Although the medical radiation doses dealt with in the report are outside the scope of the Atomic Energy Control Regulations, it is anticipated that this project will provide valuable information concerning significant, controlled exposures to ionizing radiation of Canadians. This information may, in conjunction with other epidemiological research, find use in refining the estimates of the coefficients of risk on which the AECB's regulatory dose limits and radiation protection practices are based.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S12k SOk SOk S12k Current Estimates S 14k SOk SOk SOk $14k Actual Spent to Date S 14k SOk $14k Progress to Date Information is being collected from hospitals and relevant medical institutions. - 178 - 7.205.1 Radiation-Induced Papillary Carcinoma of the Thyroid Program Officer M. Lupien Contractor Status Cancelled Comments The information seems to be available in CEC reports. The fiscal year 1993/94 expenditure was for preliminary meetings with specialists, after which the project was cancelled. Original Project Description It is intended to conduct a review of the literature on the subject of the risk factor and occurrence of papillary carcinoma of the thyroid following exposure to radioiodine, and to external ionizing radiation. Additionally, information on the the latent period (interval between radiation exposure and the clinical diagnosis of the cancer) for the induction of the papillary carcinoma of the thyroid will be reviewed and collected.
Following the nuclear reactor accident at Chernobyl (near the town of Pripyat) in 1986, the incidence of thyroid and other cancers among the nuclear workers, and the general public in Ukraine, Belarus, Russia and other republics in the former U.S.S.R. have been closely monitored by local and international organizations. More recently, a report of the World Health Organization (WHO) has indicated the occurrence of an unusually high excess of a particular type (papillary) of thyroid cancer among the children in the Republic of Belarus. The WHO report has raised concern in the scientific community about the validity of the currently-used risk estimates for radiation-induced thyroid cancer. Furthermore, the report concluded that the papillary type carcinoma of the thyroid observed among the children in Belarus was of a more aggressive type, with a much shorter latent period, than the one observed among the bomb survivors in Hiroshima and Nagasaki, and the nuclear test-fallout victims of the Marshall Islands. In view of these concerns, it is important to collect and analyze up-to-date information on the risk factor and occurrence of papillary carcinoma of the thyroid following exposure to radioiodine, and to external radiation and to compare the magnitude of the risk from both types of exposures.
It is anticipated that the results of this study will provide up-to-date information on the risk coefficients for the papillary carcinoma of the thyroid, following exposure to radioiodine and to external radiation.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk $45k $50k S75k S170k Current Estimates SOk Slk Slk Actual Spent to Date SOk Slk Slk -179-
7.206.1 Effects of Measurement Errors on Radon Progeny Risk Factor Program Officer M. Lupien Contractor Epidemiologic Consulting Services Status PPE initiated Comments
Original Project Description It is intended to develop a method to assess the effect of uncertainties in radiation dose or exposure estimates or measurements on risk estimates, and to use this method to quantify the effect of such uncertainties on the risk estimates for lung cancer due to exposure to radon progeny. The method developed in 7.162.1 can be modified for application to the present study. A previous study (7.162.1) assessed the effect of uncertainties in exposures or doses on the risk estimates for low-LET radiation-induced leukemia, breast and lung cancer. Recent developments in the field of statistical methods (project 7.162.1), may be used, with some modifications, to re-examine the uncertainties associated with the risk estimates derived from Canadian and other major epidemiological studies of high-LET radiation-induced lung cancers. It is anticipated that the results of this study will enable the AECB to assess the biases introduced by uncertainties in exposure on currently-used risk estimates (which form the basis of the Canadian regulatory dose limits). Additionally, the study will provide the AECB with a detailed guide for addressing this problem in a number of AECB-funded, on-going and future, epidemiological studies of radiation-induced cancer and developmental disorders, where there is a need to quantify the effect of uncertainties on the risk estimates for the respective health disorders. (This project is a joint study with the National Cancer Institute of Canada, University of New Mexico, and the University of Southern California on an equal cost sharing basis. The cost to the AECB is about S70k.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S30k S40k SOk SOk S70k Current Estimates S30k $35k S5k SOk $70k Actual Spent to Date S30k $35k S65k Progress to Date The following tasks have been accomplished: 1. An extensive review of the methodology employed in exposure estimation in the 11 miners' studies of radon and lung cancer has been completed. An assessment of the likely random measurement error in these estimates has been conducted. Potential systematic errors in these estimates have also been identified. 2. Appropriate computer software for conducting simulation studies of the possible effect of random measurement error in exposure on risk estimates has been developed. 3. The simulation model has been applied to examine the effect on risk estimates of random measurement error to the data for Beaverlodge (representing a relatively modem low exposure mine) and Port Radium (representing an earlier and high exposure mine). 4. A preliminary assessment of the impact of random measurement error on the recently completed combined analysis of the 11 miners' studies has been carried out
Final Results The present report extends the assessment of bias in various epidemiologic studies on which the BEIR V and RDP/lung cancer risk models were based, to specifically consider the impact of measurement error in dose/exposure estimates. The following topics are considered: (a) the statistical principles involved in assessing the impact of, and making adjustments for, measurement error, (b) a qualitative and quantitative assessment of measurement error in the Canadian fluoroscopy study, and a statistical analysis of the possible impact of measurement error on risk estimates for breast and lung cancer mortality in that study, (c) an assessment of the possible effect of measurement error in the A-bomb study, (d) a discussion of the overall impact of measurement error on risk of low LET induced breast and lung cancers and leukemia, (e) an assessment of uncertainty in exposure estimates with respect to radon and its decay products in the 11 cohort studies of underground miners which contributed to the recent updated combined analysis, and (f) an assessment of the possible impact of measurement error on risk models for RDP induced lung cancer. -180- 7.208.1 Workshop: The Molecular, Genetic and Cellular Basis of Radiosensitivity Program Officer E. Rabin Contractor British Columbia Cancer Research Centre Status Work in progress Comments
Original Project Description It is proposed to co-sponsor a workshop on the molecular, genetic and cellular basis of radiosensitivity at clinically relevant doses, to be convened in Vancouver, B.C., May 9-13,1993. The Atomic Energy Control Board has received notice of the intent of the British Columbia Cancer Research Centre to host the workshop described above. The workshop will discuss the recent evidence of inducible repair in cells of damage from low doses of ionizing radiation. The possible mechanisms for such repair will also be discussed, as will directions for future research. Such discussions may help explain recent, unexpected dose rate effects that have been observed in AECB sponsored and other research. It is anticipated that this workshop will allow AECB to gain new insight into the biomolecular processes that underlie the response to ionizing radiation, of cells and organisms. This information should elucidate what is behind epidemiological observations which are the basis of risk estimates, and hence dose limits. (British Columbia Cancer Research Centre (BCCRC) is the lead agency for convening the workshop. The operating budget for the workshop is estimated at S65k. BCCRC is also seeking funding support for the workshop from National Cancer Institute and other sources.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates S7k $3k $0k $0k SlOk Actual Spent to Date S7k S3k $10k Progress to Date The workshop was convened. AECB staff are awaiting receipt of the workshop proceedings, which are to be publishedjn the journal Radiation Research. -181- 7.209.1 Acute Lymphoblastic Leukaemia and Maternal X-Ray Exposure Program Officer M. Lupien Contractor Hôpital Ste-Justine, Montréal Status Work in progress Comments
Original Project Description It is intended to conduct a feasibility study to determine whether a case-control study should be undertaken to examine the association between acute lymphoblastic leukemia (ALL) and maternal x-ray exposure during pregnancy after accounting for confounding factors. One of the oustanding problems in relation to radiogenic leukaemogenesis is to determine the risk of childhood leukemia due to maternal x-ray exposure during pregnancy. From the Oxford Survey of Childhood Cancer, it was estimated thai 1 mGy spread out evenly over the whole of fetal life would increase the normal risk of childhood leukemia in England and Wales by 11.1%. Excess risk.however, in the first trimester, was 9-10 times greater than that in the following trimesters. It was suggested that the exposure in the first trimester would have resulted mainly from non-obstetric radiation examination which may produce higher doses of radiation to the embryo and fetus. Despite the fact that risk of leukemia due to radiation exposure is closely studied, there are still uncertainties concerning the association between childhood leukemia and maternal x-ray exposure during pregnancy. Further work is needed to quantify the risk and, particularly, to determine the relative effect of x-ray exposures at the different stages of embryo and fetus, especially after accounting for potential confounding factors.
The results of this study will demonstrate whether it is possible to investigate further the effect of maternal x-ray exposure during pregnancy on the risk of ALL.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $34k $56k SlOk S 100k Actual Spent to Date $0k $34k S34k Progress to Date A satisfactory questionnaire has been prepared. The contractor has indicated that the questionnaire can be used with reasonable confidence to-estimate the relation between estimated dose of x-rays and incidence of ALL in children. -182 - 7.210.1 Participation in the International System for Occupational Exposure (ISOE) Program Officer K.P. Ho Contractor AECL Research - CRL Status Work in progress Comments
Original Project Description The AECB intends to contribute financially and scientifically to the activities of the International System for Occupational Exposure (ISOE). The other Canadian contributor is Atomic Energy of Canada Limited/Candu Owners Group (AECL/COG). The implementation of the ISOE is coordinated by the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD). The ISOE receives and shares information regarding occupational exposures received by the personnel of over ninety power reactors in eight different countries. At the end of a two-year pilot project, in 1990, conducted under the aegis of the OECD/NEA, involving eight countries, including Canada, it was found highly desirable to centralize information and data on occupational exposure at nuclear plants around the world. In participating in this international effort, the AECB will have access to the most comprehensive information system on nuclear reactor occupational exposure and events. Ultimately, access to this body of information and experience from others will guide the AECB staff in further development of the application of the principle of optimization in radiation protection at nuclear power plants. This project will provide AECB staff with access to information volunteered by eight countries, concerning over ninety reactors. It will also open opportunities for comparison of practices and experiences among all the contributors, thereby providing a pragmatic basis for a more efficient application of the principle of optimization (As Low As Reasonably Achievable, or ALARA). In addition, this project will demonstrate AECB's continuing interest, participation, and support of national and international activities pertaining to the improvement of safe working conditions in nuclear reactors. The Canadian financial contribution will be shared equally between AECB and AECL.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $15k $22k $22k S59k Actual Spent to Date SOk $15k $15k Progress to Date The AECB sent its contribution to the NEA, and an AECB staff member attended a meeting co-ordinated by the NEA. -183- 7.211.1 A Portable Spectrometer-Based Neutron Dosimeter Program Officer E. Rabin Contractor Bubble Technology Industries Status Work in progress Comments Original Project Description It is intended to develop a neutron probe for use with the Bubble Technology Industries (BTI) Microspec, a portable computer-based multichannel analyzer. BTI, a Canadian-owned company, has developed a small, portable computer-based multichannel analyzer (Microspec) which is currently being used with NaI(Tl) crystal assemblies and appropriate software to function as a gamma-ray spectrometer and dosemeter for radiation survey measurements. AECB staff require a neutron survey meter that automatically adjusts for the incident neutron spectrum when calculating neutron dose. The system that will ultimately result from this project will be able to calculate neutron doses for any neutron spectrum with energies ranging from thermal to 20 MeV, readily adjusting to changes in neutron energy quality factors as may be recommended by the ICRP or ICRU.
It is anticipated that the survey meter that ultimately results from development of a suitable neutron probe will greatly enhance the capability of AECB staff to verify compliance with the AEC regulations at accelerators and at other licensed facilities that use or handle neutron sources. (This project is to be cost-shared by the AECB and BTI on a 60%-40% basis.)
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S17k $51k SOk S68k Actual Spent to Date SOk S17k S17k Progress to Date Work is underway to select the best combination of neutron detectors and to develop the electronics for neutron spectrum analysis. -184-
8.105.3 Leakage Testing on Packages for the Transport of Radioactive Materials - III Program Officer M. Lupien Contractor W.R. Taylor Status Work in progress Comments Original Project Description It is intended to continue supporting the attendance of Mr. W.R. Taylor at the working group ISO/TC85/SC5/WG10 which is involved in developing an international standard for leakage testing on packages for the transport of radioactive materials. This project concerns the attendance at ISO meetings to be organized, in Canada or abroad, in FY 94/95. Mr. Taylor has been participating in the development of this standard for the past several years. The AECB has benefited from his participation and has funded his attendance at previous workshop meetings.
It is anticipated that the AECB will benefit from direct and up-to-date information on the development of this international standard.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S6k S6k SOk SOk S12k Current Estimates SOk Slk Silk SOk S 12k Actual Spent to Date SOk $lk Slk Progress to Date Standards Council of Canada has distributed the draft standard for comment. -185- 9.109.3 Design of AECB Corporate Identity with Program Symbol and Standards Manual Program Officer J. Kavanagh Contractor Ove Design Group Inc. Status Work in progress Comments
Original Project Description It is intended that a consultant be engaged to research and design an AECB corporate identity (house style), complete with a program symbol for use on print materials, and to prepare a standards manual for design management purposes. The basic design principles which govern the AECB's corporate identity are governed by the Federal Identity Program (FIP), a Treasury Board policy. However, in the interests of public awareness there is a requirement to highlight the AECB's unique mandate and its independence through an appropriate, customized, and uniform look in all its visual identity items, consistent with the FIP guidelines. This should incorporate a special graphic symbol to focus attention on the AECB's regulatory program. The result of this support project will be used to enhance the visual image of the AECB on initial implementation, and to maintain it in future.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates SOk $50k SOk SOk $50k Current Estimates SOk S42k S6k SOk S48k Actual Spent to Date SOk S42k S42k Progress to Date A corporate identity and graphic program symbol has been developed for the AECB in consultation with the Office of Public Information. The selection process for the graphic symbol involved focus group testing of various AECB staff members before presentation to and approval by the Executive Committee. A standards manual for design management purposes has been prepared and submitted in draft form. -186- * 9.109.4 National Public Awareness Survey Program Officer J. Kavanagh Contractor Canada Communication Group Status Work in progress Comments Original Project Description It is intended that the national public awareness survey conducted in 1988 be repeated. The 1988 survey provided a demographic profile of the Canadian public regarding awareness of the AECB, attitudes towards the agency, significant strengths and weaknesses, and confusion of identity with AECL. A number of communications and visibility initiatives have been taken since the national poll was conducted, and a survey is needed to evaluate their effectiveness.
The results of this study would be used in planning the strategy and tactics for corporate communications over the next three to five years.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S65k SOk SOk S65k Current Estimates SOk $36k SOk SOk S36k Actual Spent to Date SOk $36k S36k Progress to Date The survey to determine the Canadian public's awareness of and attitude toward the AECB was conducted by Environics Research Group in March 1994 and involved 2020 Canadians. This survey was essentially a repeat of the one conducted in 1988. Analysis of the results will be performed by Canada Communication Group and will identify the general public's awareness of the AECB's role, functions and achievements. Comparisons between the findings of the 1988 and 1994 surveys will be provided. The draft final report will be submitted in April 1994. -187- 9.121.1 Nuclear Terminology (English/French) Data Bank Program Officer M. Lupien Contractor Terminology and Linguistic Services Directorate (TLSD) Status Complete Comments
Original Project Description It is intended to acquire and examine samples of English-French terminology (from existing data banks) covering terms, idioms and expressions, used in the nuclear industry and by national regulatory agencies. The purpose is to explore the extent of work required to compile a comprehensive, bilingual nuclear terminology data bank for use in Canada. Both freelance and staff translators working on AECB material have limited terminological resources at their disposal when it comes to the jargon of such activities as reactor regulation and radiation protection. Other AECB staff creating original text in French, particularly those based on English references, are similarly handicapped. There is a consequent tendency to create mini-lexicons for personal use, with resulting problems in corporate standardization (uniformity) and accessibility. Where the AECB interfaces with francophone licensees, (e.g., in operator certification) lack of a standard lexicon can present difficulties.
The data bank will be used by all AECB personnel involved in producing or reviewing French text. Access to it will be maximized so that many others will profit from its use (cost-sharing basis).
Past 93/94 94/95 Future Total
93/94 Program Document Estimates $30k $30k SOk SUk S6Uk Current Estimates $12k $38k SOk SOk S50k Actual Spent to Date S 12k $38k $50k
Final Results The TLSD made an exhaustive inventory of all terminology data banks and documentation concerning seven nuclear subfields: reactor safety; nuclear fuel cycle; radioactive waste management; radiation protection; medical and industrial applications of radioisotopes; and radioactive material transportation. The TLSD made recommendations to the AECB for the establishment of a nuclear terminology database using a TERMIUM "compartment". In its report, TLSD provided a very extensive and thorough review of the existing sources of terminology information in all the domains of concern. The quality, reliability, and completeness of the information contained in samples of every source have been analyzed and, on that basis, TLSD has proposed methods for producing, one technical area at a time, a bilingual nuclear terminology data bank for use in Canada. Final Evaluation The consensus opinion of the evaluators was that TLSD made a very thorough review and evaluation of the existing terminology resources (French - English and English - French) worldwide. -188 - 9.121.2 French-English Glossary of Power-Reactors Terminology Program Officer M. Lupien Contractor Science Applications International Corp. - Canada Status Complete Comments Original Project Description It is intended to compile a glossary of the technical and regulatory terminology used by the operators of nuclear power reactors. This compilation will be station specific in that it will reflect the technical and regulatory terminology as it exists at present with respect to Gentilly-2 and Point Lepreau Stations, and will include a classification index for components and systems. Such a compilation would substantially increase the efficiency of the review process of three types of Significant Event Reports from Gentilly-2 (Rapport D'événement préliminaire; Analyse d'événement significatif, et Rapport d'événement), and to a lesser extent the effectiveness of that process. Additional benefits not necessarily limited to Power Reactor Divisions would be: 1 ) the increased transparency of the Significant Events or other occurrences at Gentilly-2 to other groups within the AECB, and 2) the initiation of a standardization process in technical and regulatory bilingual terminology for power reactors, which is expected to be useful in other tasks such as production of Regulatory Documents and other formal publications.
The purpose of this work is primarily to increase the efficiency of the event review process within the power reactors area.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates $34k SOk SOk SOk S34k Actual Spent to Date S34k $0k S34k
Final Results A French-English lexicon has been developed for use by AECB staff in the review of Significant Event Reports from Gentilly-2. The current version of this lexicon covers a significant fraction of the technical terminology used at Gentilly-2 and Point Lepreau Generating Station. A database program called AFEL (AECB French-English Lexicon) has been concurrently developed to facilitate the use, updating and maintenance of the lexicon. The lexicon, in its present state, is expected to be a useful technical language tool directly applicable to CANDU-600 technology. With further work, it can be anticipated to become a basis for effective review of French-English nuclear documentation and for standardization of commonly used nuclear terminology. Final Evaluation * The users of the glossary appreciate highly the new tool they have now and they indicate that their work is done more efficiently and thoroughly with the glossary. -189-
9.121.3 Banque de terminologie nucléaire (anglaise/française) - Phase II Program Officer M. Lupien Contractor Direction de la terminologie et la documentation (PWGSC) Status Contract in place Comments
Original Project Description II est proposé d'uniformiser la terminologie, relative aux techniques nucléaires et à la protection radiologique, employée dans les textes publiés par la CCEA.
La CCEA a demandé à la Direction de la terminologie et des services linguistiques (DTSL), en 1993-1994, d'entreprendre une étude de faisabibté sur la création d'une banque de données terminologiques dans le domaine du nucléaire (Projet 9.121.1). Le bilan semi-annuel des travaux exécutés pour le projet 9.121.1 font ressortir qu'il est possible de construire une telle banque terminologique complète et performante, et d'intégrer cette banque terminologique, sous forme de "tiroir", dans la grande banque terminologique canadienne appelée TERMIUM. La DTSL, qui a une large expérience en terminologie, offre à la CCEA d'alimenter le tiroir TERMIUM à partir de la documentation recueillie lors de l'étude de faisabilité.
Les résultats des travaux permettront de mettre à la disposition de tout le personnel de la CCEA une terminologie uniformisée dans les deux langues officielles. Cette terminologie sera disponible sous forme de "tiroir" de la banque terminologique TERMIUM.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk SOk S59k SOk S59k Actual Spent to Date $0k SOk SOk -190- 9.127.1 Recommended Criteria for the Evaluation of On-Site Nuclear Power Plant Emergency Response Plans Program Officer M. Lupien Contractor Canada Communication Group (subcontract to Safety Management Status PPE initiated Comments Original Project Description It is proposed to write guidelines that establish criteria against which on-site nuclear power plant emergency response plans can be measured. The AECB requires operators of nuclear power plants to prepare emergency response plans. In addition, the AECB may develop and promulgate guidance to assist nuclear power plant operators in the preparation of these emergency response plans. This project is concerned with accidents at nuclear power reactors that might have impact on worker and public health and safety. Many of the planning elements to be contained in the guide may be useful for planners at test and research reactors, fuel processing plants, or other facilities using large quantities of radioactive material. The guide will also include the benefits of international expertise and some obvious lessons learned during and after the Chernobyl accident. Special attention will be given to Notification Methods and Procedures, Emergency Communications, Public Education and Information, Emergency Facillies and Equipment, Accident Assessment and Exercise Drills. AECB regard all of the planning standards identified above as essential for adequate radiological emergency plans.
These guidelines will provide AECB staff with criteria for assessing on-site emergency response plans in which the overall objective is to try to reduce any significant on-sile or off-site radiological doses.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates S58k S2k SOk SOk S60k Current Estimates S69k SOk SOk SOk $69k Actual Spent to Date S69k SOk S69k
Final Results The contractor identified areas in a plant's response capability that required management attention and upgrading. In support of the project to develop recommended criteria for the evaluation of on-site nuclear power plant emergency plans, four documents were produced. 1) The "Recommended Criteria for the Evaluation of On-Site Nuclear Power Plant Emergency Plans" and its assessment forms; 2) The "Basis Document" which provided the background information to support the recommended criteria; 3) A report of the validation exercise performed at AECB offices during the week of January 17,1994 which*involved the assessment of Pickering NGS documentation; 4) A report of the training workshop of April 6 and 7,1994. -191- 9.129.1 Improvement of MORIS and Similar Data Bases Program Officer M. Santini Contractor Ajja Information Technology Consultants Inc. Status Complete Comments
Original Project Description It is proposed to engage the service of a consultant to examine and investigate possible improvement to MORIS, the Regulatory Research and Support Program (RSP) database. The consultant will recommend various possibililities to improve MORIS including but not necessarily limited to the following areas: (i) The current host-and-guest problem with the MORIS (and the REPD data base which is using the same commercial application software ); (ii) Extension of MORIS or proposal of an alternative solution to incorporate a 'bulletin board' service for tracking the progress of the research projects; and (iii) Investigation of the compatibility of such data bases with corporate standards. As part of its day-to-day operations, staff of the Research and Support Divisions (RSD) must have quick access to the the status of research projects to provide answers to inquiries from potential contractors or internal clients, from other AECB divisions. MORIS and other data bases using a version of File Maker do not allow quick access to the information due to the host-and-guest problem mentioned above which has hampered the accessibility of these data bases. In addition, there is a need for a quick reporting scheme for the RSP projects. This tracking system, which could be built on what we already have in MORIS, would also allow RSD staff to plan the work more effectively and to spot potential delays on sonie particular projects. In addition, for situations where the Project Manager of a project is not available, this tracking board would be particularly useful since it would provide the key information for other staff members to respond to routine queries on the Research Program Officer's behalf. As part of the vision to share the information with others, an investigation on the feasibilitites of making these data bases compatible with the network will be carried out.
The results of this project will increase the efficiency of the RSD operation and improve the services to the internal clients as well as enhance the AECB image as a responsive and business- like organization to external clients. This improved access to the RSP information will also help our production of the RSP BMD and the Annual Report to the Board.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates $15k S12k $0k SOk $27k Actual Spent to Date $15k S12k $27k Progress to Date Significant improvement has been made to MORIS and REPD databases. The REPD database was in the last stage of development and awaiting users' feedback. -192- 9.130.1 Improvement of RaPPID Data Base Program Officer M. Santini Contractor Ajja Information Technology Consultants Inc. Status Work in progress Comments Original Project Description The project is intended to provide services to improve the data base as requested by AECB staff on an as-needed basis. The graphical and statistical functions of the RaPPID data base are to be fully automated to ensure consistent descriptions of licensees' radiation protection performance. In order to automate the functions within the database as much as possible, a computer consultant is sought to ensure that these tasks are performed as efficiently as possible. The data base has been developed using the application Excel. RaPPID is used to analyze licensees' annual dosimetry data and to generate quickly indicators of licensees' radiation protection performance. It is intended to locate the data base RaPPID on the AECB's computer network and thus be accessible by all AECB employees. It is anticipated that the results of this project will provide AECB staff with the tools necessary to assess licensees' radiation protection programs and facilitate the production of annual reports describing the effectiveness of such programs. RaPPID will allow users to quickly and easily compare licensees' radiation protection performances over time, by work groups within a facility and by type of facility.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk Slk $4k SOk S5k Actual Spent to Date SOk Slk Slk Progress to Date Significant improvement has been made to the RaPPID database during this period. -193-
9.132.1 A Short Course in Systems Engineering Program Officer P.Webster Contractor Thomas W. Woods Status Work in progress Comments
Original Project Description It is intended that a specialist(s) from outside the AECB provide a short course in systems engineering to selected AECB staff. Systems engineering is a process that has only recently been recognized to be essential in the orderly evolution of man-made systems. This process involves a series of steps accomplished in a logical manner and directed toward the development of an effective and efficient system or product. The requirement for systems engineering is brought about because many of the engineering specialists in one or more of the conventional engineering areas (such as civil engineering, mechanical engineering, electrical-electronic engineering) are not sufficiently experienced to ensure that all elements of the system are considered in a proper and timely manner. Systems engineering has been used extensively and successfully in the military, aerospace and communications industries and has been recently recommended by the U.S. Department of Energy for application to the U.S. High Level Nuclear Waste Management Program.
This course will serve to educate AECB staff in a state-of-the-art systems engineering process which has been successfully applied to large, complex and multi-participant programs. It will also provide a background for comparison when auditing the quality of new reactor projects such as the CANDU-3, and will aid in the development of future AECB safety and licensing requirements.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S9k $9k SOk $18k Actual Spent to Date SOk S9k S9k Progress to Date The first draft has been received of the topics to be presented at the course, which will be held over two days in early May. The consultant will cover the origin, practice and application of the Systems Engineering approach, with emphasis on the CANDU-3 project and its use in a regulatory oversight program.
Final Results This project has been completed. The contractor, Tom Woods, presented a two-day Course on Systems Engineering to an audience of about forty AECB staff. He was also available for one further day for detail discussions with individual members of the AECB.
The Course was titled "Principles of Practical Systems Engineering in Ongoing Nuclear Energy Systems' Design Programs", and included: 1) systems thinking, the emerging need, and the systems engineering process; 2) mission analysis: defining the problem, system boundaries and external interfaces; 3) feasibility, achievable performance and new technology; 4) system functional definition, functional dependencies and internal interfaces; 5) requirements identification, tracking, compliance and analysis; 6) solutions; evaluation and modelling; 7) systems engineering management; 8) systems engineering and business management, planning and organizational choices; 9) program analysis, process improvement, TQM, quality and systems engineering; 10) building a regulatory oversight program with systems engineering; 11) implementation: applying systems engineering after a design/development program is underway; 12) summary: the cost of systems engineering, its applicability, advantages and disadvantages; 13) epilogue: systems engineering's "coming of age". -194 -
11.103.5 Participation in Working Group on External Dosimetry-5 Program Officer E. Rabin Contractor Mr. A.R. Jones Status Complete Comments Mr. Jones' has extensive experience in the field of external dosimetry, and his participation at the meeting was very valuable.
Original Project Description It is proposed to obtain the services of Mr. Alun R. Jones, of Deep River, Ontario, as a consultant at the meeting of the AECB Working Group on External Dosimetry, which is to take place the 3rd of June, 1993 at CRL, Chalk River. His participation in the deliberations of the working group is being sought because Mr. Jones is an internationally renowned expert in the field of external dosimetry. Mr. Jones, who was formerly a member of the working group before his retirement, is thoroughly familiar with the mandate of the working group and has provided incisive comments at previous meetings.
It is anticipated that the participation of Mr. Jones in the meeting will significantly advance the progress of the the working group towards fulfilling its mandate.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk Slk SOk SOk Slk Actual Spent to Date SOk $lk Slk
Final Results Mr. Jones participated actively in the discussions which were held at the June 3rd meeting of the Working Group on External Dosimetry. He made a formal presentation to the working group on sources for testing beta personal dosimeters, pointing out the advantages and disadvantages of each. Mr. Jones explained that if one beta source is to be used, then the one with ûie least number of disadvantages is Tl-204. -195-
11.133.1 Peer Review of AECB Consultative Document C-6 Program Officer J.K.Pereira Contractor Abbey Nuclear Consultancy (United Kingdom) Status Complete Comments
Original Project Description The intent of this project is to obtain a peer review of a revised version of Consultative Document C-6. It will avail the views of an expert who is independent of the Canadian nuclear industry. The published version of Consultative Document C-6 was issued in June 1980 for trial use and comment Points raised over the period since then are to be incorporated in a 1992 revision of the document. A peer review, by an independent expert, is needed to confirm the rigour of the approach adopted in the revised document.
The review report will afford input to the revision of Consultative Document C-6. It will serve to identify any technical weaknesses or omissions in the approach used or the scope of coverage provided.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SlOk SOk SOk SOk SlOk Actual Spent to Date SlOk SOk SlOk
Final Results The contractor completed a critical review of the draft of AECB Consultative Document C-6. Findings, which comprised both general and detailed comments, have been presented to the AECB in two written submissions. The comments addressed principles associated with various sections of the document, the strategy adopted for development and specification of requirements and the need for clarification on certain issues. The contractor also participated in an extended debriefing session with AECB staff in Ottawa. Final Evaluation The review and comments provided by the contractor were very thorough. The study was of value in that it provided an independent view on approaches that have been espoused for many years in the Canadian CANDU industry. -196- 11.136.2 Specialist Advice on Reactor Physics Issues - Phase II
Program Officer J. Kavanagh Contractor Diamond International Consulting Ltd Status PPE initiated Comments
Original Project Description This project is intended to provide AECB staff with the services of an independent specialist to support AECB reviews of safety submissions in the general area of reactor physics. This support will entail critical assessment of licensee submissions in response to specific requests from the AECB. Comments and recommendations will be documented for consideration by the AECB.
Reactor physics is an area in which the AECB is having to devote an increasing amount of effort to assess the merit of analyses completed by licensee as part of of safety submissions supplied in support of application for licensing of the reactors. To ensure that such assessments are done with adequate rigor and in a timely fashion, there is a need for commitment to more specialist effort than is available at the AECB. In a previous phase of this project, Dr D. Diamond, an independent specialist, was retained to provide consultancy support in this area. The present project entails a placement of a repeat contract with Dr Diamond.
Results from the project will enable timely and thorough assessment of submissions received from licensees.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S35k SOk SOk S35k Current Estimates SOk S6k SOk SOk S6k Actual Spent to Date SOk S6k S6k
Final Results The study assessed reactivity effects which could arise as a consequence of coolant flow reversal during a large LOCA. The review was primarily based on documentation submitted by Ontario Hydro in response to AECB requests and focussed on the analysis performed for Bruce NGSA. However, other issues considered included the appropriate void worth uncertainty to use, the validity of the SMOKIN code, and whether or not prompt-criticality should be used as an additional acceptance criterion for the short-term behaviour following a large break. The findings of this review indicated that Ontario Hydro was addressing the primary reactor physics issues that relate to LOCA analysis with fuel relocation. It was recommended that the issues discussed in this report be reviewed when additional related material is submitted to the AECB by the utility. -197 -
11.136.3 Specialist Advice on Reactor Physics Issues - Phase III
Program Officer J. Kavanagh Contractor Diamond International Consulting Ltd. Status Work in progress Comments Contract has been sent to the contractor [orsignature.
Original Project Description This project is intended to provide AECB staff with the services of an independent specialist to support AECB reviews of safety submissions in the general area of reactor physics. This support will entail critical assessment of licensees' submissions in response to specific requests from the AECB. Comments and recommendations will be documented for consideration by the AECB.
Reactor physics is an area in which the AECB is having to devote an increasing amount of effort to assess the merit of analyses completed by its licensees as part of safety submissions supplied in support of application for licensing of the reactors. To ensure that such assessments are done with adequate rigour and in a timely fashion, there is a need for commitment to more specialist effort than is available at the AECB. In previous phases of this project. Dr. D. Diamond, an independent specialist, was retained to provide consultancy support in this area. The present project involves additional work by Dr. Diamond.
Results from the project will enable timely and thorough assessment of submissions received from licensees.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates SOk S35k SOk SOk S35k Current Estimates SOk SOk S37k SOk $37k Actual Spent to Date SOk SOk SOk -198- 11.146.1 Characterization Methods for Fractures in Intact Crystalline Rocks Program Officer J.K. Pereira Contractor Raven Beck Environmental Limited Status Complete Comments
Original Project Description The purpose of this project is to conduct a critical review of methods that are available for characterization of crystalline rocks at sites that are being considered for placement of spent fuel repositories. It is expected that the AECL Environmental Impact Statement for a spent fuel repository will propose that the repository be constructed with the vault in an "envelope" of intact rock which will act as a major barrier to the migration of radionuclides from the repository to the geosphere. AECL will need to demonstrate that the capability exists for characterization of intact rock to required fracture detection limits. Assessment of the merit of AECL's proposal will require access to in-depth information on methods that may be applied for characterization of rock. This study sets out to acquire such information and to develop AECB staff expertise in this area.
Information obtained will be used in the AECB staff review of AECL's Environmental Impact Statement for a spent fuel repository.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates S 13k S12k SOk SOk S25k Actual Spent to Date S13k S 12k S25k
Final Results An evaluation was carried out of the ability of hydraulic test techniques, seismic methods and ground penetrating radar to detect fractures in crystalline rock. The theoretical basis of each method was assessed by means of scoping calculations for prescribed test cases, and also by reviews of application and verification case studies reported on in the literature. Results from the study indicated that remote detection of fracture zones and large single fractures could be easily accomplished by hydraulic testing because of the small radius of influence of the technique in massive crystalline rocks. However, remote fracture detection by ground penetrating radar and seismic methods was possible for certain situations. The former method was capable of detecting metre-wide fracture zones at distances of 50 m and possibly 100 m if the groundwater salinity was not high. Similar detection ranges arc possible with seismic methods. Final Evaluation A comprehensive report was submitted. Besides a review of international data and scoping studies, the report presented assessment studies completed by expert sub-contractors. The study provided background information which will be of use in the assessment of design proposals for spent fuel repositories. -199- 11.150.1 Francisation du programme de la recherche et du soutien Program Officer M- Lupien Contractor Canada Communication Group Status PPE initiated Comments
Original Project Description II est proposé d'entreprendre une étude pour déterminer dans quelle mesure la CCEA devrait faire des appels d'offres en français pour ses contrats de recherche. Le programme de la recherche et du soutien de la CCEA est réalisé par l'intermédiaire de contrats de recherche dont la plupart sont adjugés à la suite d'appels d'offres publics. Les appels d'offres sont rendus publics par Approvisionnement et Services Canada. Les appels d'offres sont généralement rédigés en anglais, ce qui peut entraîner une faible réponse des entrepreneurs compétents dont la langue de travail est le français. Afin d'évaluer l'ampleur de ce problème, l'étude proposée fera l'inventaire des ressources qu'offre la communauté scientifique et industrielle francophone du Canada dans les domaines liés au Programme de la recherche et du soutien à la réglementation. Les résultats de cette recherche aideront à: a) identifier les entrepreneurs francophones qui pourraient éventuellement contribuer à l'exécution du programme de la recherche et du soutien de la CCEA; b) determiner les moyens appropriés poor mettre ces entrepreneurs au courant des appels d'offres de la CCEA; c) déterminer dans quels domaines il serait nécessaire ou inutile, de rédiger les appels d'offres à la fois en anglais et en français.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates S28k $2k SOk $0k S30k Current Estimates S61k Slk SOk SOk $62k Actual Spent to Date S61k Slk S62k
Final Results Suite aux enquêtes téléphoniques et postales, Price Waterhouse résumé ses recherches en trois conclusions: a) II existe 92 fournisseurs francophones potentiels réel, b) Tous les fournisseurs potentiels contactés souhaitent soumissionner ou augmenter la fréquence à laquelle ils soumissionnent sur les projets de la CCEA. et c) D'autre part, il est mentionné dans le rapport final que la CCEA devrait faire un effort pour mieux fair son rôle et des besoins en recherche, et devrait s'inspirer des pratiques en cours dans les pays européene multi-linques. -200-
11.153.1 Task & Attribute Description for an Audit & Evaluation Officer Program Officer W.A. Grant Contractor Salconsult Inc., Management Consultants Status PPE initiated Comments
Original Project Description It is intended to have an independent expert review the position profile for the AECB Secretariat's "Audit & Evaluation Officer" [A&E] position.
With the expansion and the many changes that have been introduced over the past few years, a need has arisen to review and revise the description for the Secretariat's Audit & Evaluation Officer position. Among aspects that need to be reviewed are: a) the existing documentation, philosophy and approach to audit and evaluation; b) the views of the office of the Auditor General and the office of the Controller General regarding functional requirements for the A&E position; c) position profiles and remuneration for A&E position at other organizations that are similar to the AECB (ex. CRTC, NEB, etc.); and, d) AECB staff perceptions of the organization's needs and the A&E function. Recourse to the services of an external expert will enable completion of a critical and independent review of the needs of the AECB in this area.
The review will provide the AECB with a revised description for the Audit and Evaluation Officer position. The new description will be suited to the present needs of the AECB and to the current practice for organizations similar to the AECB.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S4k SOk SOk S4k Actual Spent to Date SOk S4k S4k
Final Results The final report by SalConsuIt Inc., of Ottawa, facilitated finalization of the task and attribute profile for this AECB staff position. This position has now been filled.
Publications No report will be placed in the public domain. -201 - 11.154.1 Review of Uncertainty Calculations on Exposure Measurements Program Officer E. Rabin Contractor Carleton University, Statistical Consulting Centre Status PPE initiated Comments
Original Project Description It is proposed to verify the method and calculations used by AECB staff to determine the uncertainty in the radon daughter exposures attributed to mine workers. This project is proposed because the Atomic Energy Control Board intends to establish limits on the uncertainty in the estimates of aggregate dose for uranium workers due to temporal variability in workers' exposures to such contaminants as radon progeny and long-lived radioactive dust, where such exposures are calculated from data obtained using grab sampling/ occupational time monitoring methods. Data was collected from two uranium mines under research contract 4.137.1 "Collection of Exposure Data in Uranium Mines", and AECB staff have calculated the uncertainties in the derived occupational exposures. However, due to the complexity of the statistical analysis, it is prudent to have the methods used and the calculations reviewed by an accredited, external statistician. It is anticipated that the results of this project will assist AECB staff in preparing a regulatory guide on the uncertainty in workers' exposures to such contaminants as radon progeny and long-lived radioactive dust, which are based on grab sampling/ occupational time monitoring data.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $5k SOk SOk S5k Actual Spent to Date SOk $5k S5k
Final Results A critical review of the method used by AECB staff to calculate the uncertainty in the estimates of radon progeny exposures of mine workers has been carried out. Using sample data provided by AECB staff the contractor found that airborne radon progeny concentrations measured at different locations in the mine were not statistically independent. The correlations between measurements had to be accounted for in the calculation of the uncertainty in the exposure estimates. A discussion of other factors was also presented in the report, such as stationariness in the data, which have to be investigated before arriving at a correct estimate of the uncertainty. -202-
11.155.1 Attendance at the Workshop: "Intakes of Radionuclides" Program Officer E. Rabin Contractor Frost.S.E. Status Complete Comments No PPE required.
Original Project Description The project will pay the travel expenses incurred by Mr. S.E. Frost, and the cost of his registration at the workshop entitled "Intakes of Radionuclides", which is to be held at Bath, United Kingdom, September 13 to 17, 1993. Recently the AECB has established, and provides funds for, a working group on internal dosimetry. To ensure the development of practicaLguidelines on internal dosimetry for AECB licensees, the working group must consider input from industry, as well as other sectors. Mr. S.E. Frost, a recognized Canadian expert in the field of the dosimetry of radiocompounds found at the front end of the nuclear fuel cycle, is considered to be a valuable source of information on the perspective of industry. To assist Mr. Frost in keeping apprised of the state of the art, internationally, the AECB has requested he attend the workshop and participate in the discussions and presentations.
It is anticipated that Mr. Frost will use his expertise, including the knowledge he acquires at the workshop, to provide an essential contribution to the work of the AECB Working Group on Internal Dosimetry for developing regulatory guidelines.
Past 93/94 94/95 Future Total
93/94 Program Document Estimates Current Estimates SOk $4k SOk SOk S4k Actual Spent to Date SOk S4k $4k
Final Results Mr. Frost attended the workshop entitled "Intakes of Radionuclides", convened at Bath, United Kingdom, September 13 to 17,1993. Subsequently Mr. Frost provided AECB staff with a report on the discussions at the meeting. -203-
11.156.1 Westlakes Workshop on Childhood Cancer Clusters and Radiation Program Officer V. Elaguppillai Contractor Dr. Geoffrey R. Howe Status PPE initiated Comments
Original Project Description It is proposed to fund the travel expenses of Professor Geof. Howe of the National Cancer Institute of Canada to attend the Westlakes Workshop on Childhood Cancers and Radiation, to be held at the Westlakes Research Institute, Moor Row, Cumbria, U.K, during October 4-7,1993. Prof. Howe has been invited as a specialist to participate at the discussions of the workshop. The Commission of the European Communities(CEC), Westlakes Research Institute, U.K., U.S. Department of Energy and the Atomic Energy Control Board has decided to sponsor a workshop on childhood cancer clusters and radiation. The workshop will review the progress of the studies on childhood cancer around nuclear facilities. In addition, it will conduct discussions on the influence of genetic predisposition, methodological difficulties, statistical interpretations, molecular mechanism, affecting the incidence of childhood cancer clusters around nuclear facilities. Several international experts have been invited to participate at the discussion.
It is anticipated that the workshop will shed more light to the understanding of the problems affecting the interpretation of the results of studies of leukaemia and other childhood cancer clusters around nuclear facilities.
• Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S5k SOk SOk S5k Actual Spent to Date SOk S5k S5k
Final Results Dr. G. Howe attended the workshop on Childhood Cancer Clusters in West Lakes, U.K. He presented the experience of Canadian investigators on the subject. One of the major items of conclusions of the workshop was that the Gardner findings of an association between paternal exposure and subsequent development of childhood leukemia may not necessarily be related to radiation exposure of the fathers. Other factors, such as viral infection and social factors, might have played a role in the observed excess of childhood leukemia. -204- 11.160.1 Survey of Canadian Hospital Emergency Plans Program Officer M. Lupien Contractor Status Contracting in progress Comments Original Project Description It is intended to explore the state of preparedness of Canadian hospitals in respect of radiation emergency planning. At the 25th plenary meeting of the Group of Medical Advisers (GMA), held in Toronto on 17-18 November 1993, the theme of medical preparedness in response to radiation emergencies was re-visited by AECB Medical Advisers. Subsequent to a discussion with physicians from the Radiation Trauma Unit of the Toronto General Hospital, emergency preparedness specialists from Ontario Hydro, and outside consultants, it was concluded that there was a need to define more closely the level of preparedness of radiation emergency plans in Canadian hospitals. For example, even though a previous document on emergency preparedness (GMA-3) was distributed to over 700 hospitals in Canada, it was subsequently determined that in many cases this document was not specifically forwarded to the hospital's Emergency Department, as intended. In addition, little information is currently available to determine which hospitals have established radiation emergency plans. The GMA suggested that qualitative research is needed to ascertain the state of radiation emergency plans in Canadian hospitals. The results of this survey will provide information to the AECB on the state of preparedness of radiation emergency plans in Canadian hospitals, as well as providing suggestions for improvements.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk Slk S22k $0k $23k Actual Spent to Date SOk Slk Slk -205-
11.161.1 Environmental Qualification of Equipment for the CANDU 3 Reactor Program Officer J.K. Perdra Contractor Mu-Sigma Engineering Consultants Status PPE initialed Comments Final report under review.
Original Project Description It is intended to undertake a critical review of an environmental qualification program, a program implementation plan and qualification methods proposed for equipment designed for the CANDU 3 reactor. The review is to be completed by a specialist with experience in the field of environmental qualification of equipment
Several submissions have been received from AECL in response to AECB requirements for design of safety-related systems and equipment for reliable operation in environments likely to arise as a consequence of system failures or accidents. The submissions propose a program for environmental qualification of equipment. AECB staff requires the support of specialists, with experience in environmental qualification of equipment, to complete a thorough assessment of AECL's proposal.
The project will enable an effective review of the proposed environmental qualification program and interaction with ihe external specialists will also facilitate development of AECB staff capability in this area.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk Silk SOk SOk Silk Actual Spent to Date SOk Silk Silk
Final Results An assessment has been completed of the adequacy of the approach and the implementation plan proposed by AECL for the CANDU-3 reactor. Aspects addressed included the design, verification, implementation and preservation of qualification. The report made recommendations with respect to the treatment of ageing degradation and preservation of qualification in service. It also identified two areas where additional qualification for harsh environments should be considered. - r.06 - 11.162.1 Methodologies for the Assessment of the Costs & Benefits of Regulatory Decision Making Program Officer W.A. Grant Contractor Price Waterhouse Status Work in progress Comments
Original Project Description The purpose of this project is to examine the basis of approaches which could be used for the review of the costs and benefits of regulation. Discussions and reviews undertaken over the past year of regulatory activities in the energy industry have identified a need for a review of the costs and benefits of regulation. The AECB has, as a consequence, accepted an action to investigate, with industry, approaches which could be adopted for carrying out such reviews. The study will provide a basis for work on the development of approaches which may be used for reviews of the costs and benefits of regulation.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk S19k S36k SOk S55k Actual Spent to Date SOk S19k S19k Progress to Date Price Waterhouse has prepared a discussion document and assisted AECB staff with a February 1994 meeting with representatives from industry. The contract has been extended to include a review of other regulatory nuclear agency approaches to cost and benefits assessments. - 207 -
11.163.1 Safety Culture Seminar Program Officer A. Daza Contractor Center for Chemical Process Safety Status PPE initiated Comments
Original Project Description This seminar is intended for the AECB to gain concepts aimed at assessing the safety culture of its major licensees. The International Nuclear Safety Advisory Group (INSAG) defines safety culture as that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. INSAG also stales that this definition relates safety culture to personal attitudes and habits of the style of organizations, which are generally intangible. In addition safety culture requires all duties important to safety to be carried out correctly, with alertness, due thought and full knowledge, sound judgement and a proper sense of accountability.
The concepts gained will assist the AECB in its development of a comprehensive inspection program for Canadian nuclear power plants.
Past 93/94 94/95 Future Total 93/94 Program Document Estimates Current Estimates SOk $3k SOk SOk S3k Actual Spent to Date SOk $3k $3k Progress to Date Seminar and workshop held.
Final Results A presentation was given on process safety management, safety management auditing processes and results identified from measurements of the effectiveness of process safety management approaches. The seminar was followed by a workshop in which applications of this safety culture were examined.
[WLM PAGE(S) left BLANK! -209- APPENDIX C
Inactive Projects: Categories 2 and 3, Cancelled or Postponed
2.102.1 Design, Analysis and Testing Tools for Real-Time Software
2.105.2 Crack Propagation in Tough Ductile Materials - Carbon Steel
2.126.2 Critical Channel Power Uncertainty Measurement
2.148.2 Molten Fuel/Moderator Interacti on
2.152.6 CATHENA Support Service for CANDU - 3
2.179.2 Performance of Steam Generator Emergency Water Injection - Phase II
2.192.1 Effect of Sheath Strain on Critical Heat Flux
2.193.1 Studies of Hydrogen Combustion Phenomena in CANDU Nuclear Power Plants
2.200.1 A Safety Course for Pressure-Tube Type Reactors
2.204.1 Pressure Tube Rupture in A Closed Tank - Thermalhydraulic Loadings
2.224.1 Emissivity of Zirconium Alloy Surfaces
2.225.1 Estimates of Fission Product Grain-Boundary Release
2.230.1 Testing for Software Reliability in Computer Systems
2.231.2 Functional Graphical Languages for Process Control - Phase 2
2.234.2 Evaluation of Tools and Methods for the Development of Safety Critical Software
2.234.4 Review of Trip Computer System Specifications
2.234.5 Review of Trip Computer Redesign
2.234.6 Review of Trip Computer Testing
2.235.1 Processes in Radioactivity Removal
2.237.1 Assessment of Psychological Capacities Requirements
2.238.2 Review of Computer Code MODTURC - Phase 2
2.241.2 Technical Review of the CANDU-3 PSA (Phase 2) -210-
2.242.3 Stratigraphy in Paleozoic Rocks in the CMBBZ - Phase 3
2.244.2 Elevation Determinations of Stratigraphie Contacts in the CMBBZ and the GBLZ
2.245.1 Acceptability of Spacer-Pad Wear Allowance
2.246.1 The Behaviour of Zirconium Alloys in Reducing Environments
2.248.3 Seismic Assessment of Systems and Components at Pickering A NGS
2.249.2 Compliance with Bundle and Channel Power Limits - Phase II
2.258.1 Definition of Systems in Nuclear Power Plants
2.259.1 Review of the Bruce A Fuelling Machine System
2.261.1 Protection and Bus Transfer Schemes at CANDU Power Stations
2.266.1 Approach for Management of Ageing in CANDU Nuclear Power Plants
2.268.1 Stratigraphy in Paleozoic Rocks Adjacent to the GBLZ
2.269.2 Brittle Faulting Along the St. Lawrence Valley Fault System - Phase 2
2.270.1 Application of LANDSAT Imagery to Assessing Deep Fault Structures in Southern Ontario
2.277.1 Void Reactivity Calculations
2.281.1 Implications of Computer Generates Procedures
2.282.1 Supervisory Control Capabilities Development
2.285.1 Assessment of Safety Critical Software Development Teams
2.290.1 PRA Review Techniques
2.291.1 Dependency Analysis in Reliability Submissions
2.292.1 Sensitivity Analysis in Reliability Submissions
2.293.1 PSA/Reliability as a Tool for AECB Project Officers
2.294.1 State-Space Methods 2.317.1 A Reassessment of CANDU Fuel Behaviour During Large Break LOCA Power Transients -211-
3.135.2 Dosimetry of Organically Bound Tritium Derived from Diet
3.150.3 Effect of Low-Level Radiation on Aquatic Invertebrates (Chironomids): 2
3.154.1 Impact of Occupational Dose Reduction on Doses to the Public
3.157.1 A Field Evaluation of Convoluted Laminations
3.164.1 Carbon-14 in Lakes: Appropriate Risk Assessment
3.168.3 Effect of Chronic Exposure of Sheep in Low Levels of H2S/SO2
3.169.1 Computer Software Quality Assurance
3.171.1 Bioavailability of Iodine in a Simplified Aquatic Food Chain
3.172.1 Use of Evergreen Needles to Assess Airborne Radioactivity
3.173.1 Review of Soil to Plant Transfer Models
3. i 74.1 Uncertainty in Environmental Pathways Analysis Models
3.177.1 Uncertainty in Air Quality Modelling
3.178.1 A User-Friendly Code for CSA Standards Calculations
3.179.1 Radionuclide Transfer to Humans and Other Biota Through Fungi
3.180.1 Pathways Assessment for Fruits
3.181.1 Cs-137 Bioaccumulation Factors for Fish
3.182.1 Bioconcentration of Radionuclides by Aquatic Plants
3.185.1 Environmental, Ecological and Socio-Economical Model (DEEP)
4.108.2 Methodology for Determining the AMAD of Long-Lived Dust
4.108.3 Time Variability of AMAD of Long-Lived Radioactive Dust
4.126.1 Computerized Mortality Search Procedures
4.130.2 Mortality Analysis of Port Radium Uranium Miners (1950-1989)
4.134.1 Tools for Measuring the Unattached Fraction in Uranium Mines -212-
4.135.1 A Generic Method for Measuring Uranium in Dust Samples
4.139.1 Limitations of Mine Ventilation Radiation Models
4.139.2 Simulation of Least Favorable Mine Radiation Conditions
4.140.1 Transfer of Dietary Ra-226 to Vole Offspring
4.141.1 Transfer of Uranium from Mother to Fetus
4.143.1 Mechanism of Radiation-Induced Lung Cancer Among Ontario Uranium Miners
4.146.1 PAD Response to Rn-222 Progeny and Long-Lived Radioactive Dust
5.146.2 Thermal Consolidation Effects Around a High-Level Waste Repository - Phase 2
5.148.1 Reassessment of the Deep Lake Disposal of Uranium Tailings
5.150.1 Concentrations of Radionuclides in Wild Rice
5.152.1 Effects of Low-Level Radiation on Fish - Phase I
5.155.1 Soil Residence Time(s) Database
6.104.2 Production of a Hospital Radiation Safety Officer's Handbook - II
6.119.1 Occupational Radiation Doses to Health Care Workers
6.121.1 Ergonomics in Industrial Gamma Radiography
6.122.1 Unsealed Radioactive Materials in the Oil and Gas Industry
7.116.1 Cancer Morbidity Follow-Up Feasibility Study
7.122.2 Cancer Incidence Linkage following Multiple Fluoroscopies
7.127.1 Dose Response of Human Lymphocytes to Carcinogens
7.128.1 The Relative Impact of Radiation-Induced Genetic Disorders
7.135.2 Mechanism of Radiation-Induced Mental Retardation - Phase 2
7.143.2 Development of a New 1951-1990 Master Identification File
7.143.3 Linkage of National Dose Registry to the Canadian Cancer Data Base -213-
7.161.1 Literature Review : Interaction Radiation - Co-Carcinogens
7.163.1 Alteration of Immune Surveillance and DNA Repair Capacity
7.165.1 The Influence of Radon Daughter Exposure on Cell Mitosis Rate
7.166.1 Birth Defects Due to In Utero Exposure to Ionizing Radiation
7.168.2 Indicators for Assessing Impacts on Forest Ecosystems
7.169.1 Ra-226 in Deciduous Teeth of Residents Living Near Mining Areas
7.176.2 Biological Dosimetry
7.177.1 Distribution of Fatal Risk in "Safe" Industries: An Update
7.178.1 Impact of Low Doses of Radiation on Cell Signalling
7.180.1 Ethics of Identifying Radiosensitive Individuals
7.181.1 Cluster Elucidation: Genetic Factors
7.182.1 Feasibility of Performing Placenta! Perfusion Research
7.183.1 Genetic Risk from Exposure to Ionizing Radiation
7.184.1 Genetic Defects and Clustering Phenomena
7.186.1 Uncertainty in Risk Estimation
7.188.1 Role of Confounding Factors on the Occurrence of Down Syndrome
7.190.1 Guide on Radiation Epidemiology
7.191.1 Delayed Cancer and Genetic Effects from Occupational Exposures
7.192.1 Creation of a Canadian Birth Outcome Data Base
7.193.1 Bioaccumulation of Polonium 210 and Lead 210 in the Fetus
7.194.1 Environmental Contamination Model
7.197.1 Atlas of Childhood Leukemia in Ontario
7.199.1 An Improved High Sensitivity TLD Dosimeter -214-
7.202.1 Influence of Prior Dose on Subsequent Radiation in Cells
7.203.1 Radiation-Induced Mutations in Human Germ Cells
7.204.1 Radiation Protection Against Genetic Disorders
7.207.1 Cytotoxicity and Genotoxicity of Tritium
7.214.1 In Vitro Radiobiological Assessments: Guidelines for Quality Control
9.131.1 Delivery of Level II Course on Fundamentals of Power Reactors
11.152.1 Development of a Terrestrial Consequence Assessment Model
11.159.1 Review of Benefits and Costs of Regulation
11.164.1 Seminar on Combined Analysis of Lung Cancer Mortality Among Miners -215- APPENDIX D Projects Undergoing Review of Final Report or Post-Project Evaluation Only
2.117.2 Documentation of Real-Time Power Reactor Software (H)
2.117.3 International Standards for Safety Critical Software
2.127.5 Statistically Valid Random Testing for Real-Time Software
2.174.2 Hydrogen Absorption-Desorption at Metal Surfaces - Phase 2
2.187.1 Operational Readiness of Emergency Filtered Air Discharge Systems - Phase I
2.219.1 Validation Methods for Probabilistic Safety Assessments
2.220.1 Impact of Expert Systems
2.242.2 Stratigraphy in Paleozoic Rocks in the CMBBZ
2.243.2 Seismic Stratigraphy of Paleozoic Bedrock in Western Lake Ontario
2.255.1 Formal Methods for Computerized, Real-Time, Safety-Critical Systems
2.257.1 Modification of the SECT Computer Program
2.264.1 Human Performance Investigation Process (HPEP) Feasibility Study
3.106.3 Transfer of Radionuclides to Human Milk - Phase 3 Pilot Study
3.111.1 Evaluation of Data and Models on Uranium Metabolism - Europe
3.121.1 BIOMOVS - Intercomparison of Environmental Assessment Models
3.124.1 Assessment of Errors in Airflow Measuring Instruments (U Mines)
3.131.2 Neotectonic Investigations in Southern Ontario - Phase 2
3.133.1 Carbon-14 in Food and in Excretions
3.144.2 Liquefaction Features in the Chicoutimi Area
3.145.1 Significance of Urban Pathway in Assessing Public Dose -216-
3.150.1 Different Biological End-Points to Study Radiation Effects
3.150.2 Effects of Radiation on Species Other than Man: Aquatic Organisms
3.156.1 An Analysis of Brittle Structures in the Saguenay Earthquake Areas
3.161.1 Radiation Facts Booklet
3.163.1 The Origin of Conical Hills, Charlevoix Seismic Zone
3.168.1 Environmental Health Scoping Study at BHWP
4.101.1 Study of the Health Effects of Inhaled Uranium Ore Dust
4.101.2 Modification of Equipment for Uranium Ore Dust Study
4.113.1 Tracer Gas Method for Assessing Ventilation Efficiency
4.119.1 Evaluation of Mine Ventilation Monitoring Devices
4.121.2 The Proliferative Cells of the Human Bronchial Epithelium
4.127.1 Rapid Determination of Radon Daughter Concentrations
4.129.1 Temporal Variation of Airborne Radioactivity in Mines
5.127.1 Radionuclide Concentrations in Fish: Phase I Screening Program
5.136.1 Hydrology of Quirke and Panel Tailings Basins
5.142.1 Feasibility of Monitoring Tailings Sites Using Remote Sensing
5.143.1 Radiological Impact of Uranium Mining: Northern Saskatchewan .
5.143.2 Radiological Impact of Uranium Mining: Northern Saskatchewan - Phase II
6.105.1 Radiation Exposures of Non-Monitored Hospital Personnel
7.107.1 Exposure Levels of Non-Radiological Carcinogens at Nuclear Facilities
7.111.1 In Vitro and In Vivo Studies of Health Effects of Ionizing Radiation Effects on the Developing Central Nervous System 7.122.1 Computerized Linkage of National Cancer Incidence Data -217-
7.130.1 Ionizing Radiation in Tumour Promotion or Progression
7.152.1 Transport of Compounds from Mother to Foetus
7.153.1 RBE of Tritium and Co-60 Gamma Rays at Low and High Dose Rates
7.164.1 Improved Cytometry Method
7.168.1 Recovery of Boreal Forest Vegetation
9.128.1 Prototype for A New Information Inventory System
11.101.1 Audit of Radiochemistry Procedures
11.111.1 Laboratory Testing of An Instant Radon Progeny Monitor
11.119.1 Examination of Deformation in the Rouge River Valley - Toronto
11.126.1 Presentation of "Cognitive Skills for Nuclear Power Plants Personnel Training"
11.127.1 Presentation of "Evaluation of Full Scope Simulator Testing Methods"
11.128.1 Radiation Index Survey
11.130.1 Validation of Radiological Assessment Models
11.136.1 Specialist Advice on Reactor Physics Topics
11.151.1 A Literature Review of Other Government Communications Policies and Procedures Manuals
[NEXT PAGE'S) left Rl AN* -219- APPENDIX E Fiscal Year 1993/94 Project List 2.102.1 Design, Analysis and Testing Tools for Real-Time Software Appendix C 2.105.2 Crack Propagation in Tough Ductile Materials - Carbon Steel Appendix C 2.111.2 International Piping Integrity Research Group - 2 Appendix B 2.117.2 Documentation of Real-Time Power Reactor Software (II) Appendix D 2.117.3 International Standards for Safety Critical Software Appendix D 2.126.2 Critical Channel Power Uncertainty Measurement Appendix C 2.127.5 Statistically Valid Random Testing for Real-Time Software Appendix D 2.128.5 Review of a Fire Drill at DNGS Appendix B 2.148.2 Molten Fuel/Moderator Interaction Appendix C 2.152.5 CATHENA Support Service Appendix B 2.152.6 CATHENA Support Service for CANDU-3 Appendix C 2.162.4 Gardner Seminar on Childhood Leukemia Appendix B 2.174.2 Hydrogen Absorption-Desorption at Metal Surfaces - Phase 2 Appendix D 2.179.1 Performance of Steam Generator Emergency Water Injection Appendix B 2.179.2 Performance of Steam Generator Emergency Water Injection - Phase II Appendix C 2.184.3 Ballooning of CANDU Pressure Tubes-Construction of a Test Facility Appendix B 2.184.4 Ballooning of CANDU Pressure Tubes - Experiments with Degraded Appendix B Tube Material 2.187.1 Operational Readiness of Emergency Filtered Air Discharge Systems- Appendix D Phase I 2.187.3 Behaviour of EFADS Filters Under Harsh Conditions-Phase 3 Appendix B 2.192.1 Effect of Sheath Strain on Critical Heat Flux Appendix C 2.193.1 Studies of Hydrogen Combustion Phenomena in CANDU Nuclear Appendix C Power Plants 2.196.1 Statistical Review of Pressure Tube Inspection Data Appendix B 2.200.1 A Safety Course for Pressure-Tube Type Reactors Appendix C 2.204.1 Pressure Tube Rupture in A Closed Tank - Thermalhydraulic Loadings Appendix C 2.211.1 Tritium Surface Contact Dosimetry Appendix B 2.213.1 Review of Human Factors Guidelines Appendix B 2.214.1 Review of Supervisory Functions in Nuclear Power Plants Appendix B 2.214.2 Review of Supervisory Functions in Nuclear Power Plants - Phase II Appendix B 2.216.2 Validation of Positive Void- Phase II Appendix B
2.217.1 Seismic Monitoring East and North of Toronto Appendix B -220- 2.219.1 Validation Methods for Probabilistic Safety Assessments Appendix D 2.220.1 Impact of Expert Systems Appendix D 2.224.1 Emissivity of Zirconium Alloy Surfaces Appendix C 2.225.1 Estimates of Fission Product Grain-Boundary Release Appendix C 2.228.2 Steam Generator Fitness-For-Service Guidelines Appendix B 2.230.1 Testing for Software Reliability in Computer Systems Appendix C 2.231.1 Functional Graphical Languages for Process Control Appendix B 2.231.2 Functional Graphical Languages for Process Control - Phase 2 Appendix C 2.234.1 Review of "Sub-Tier" Software Standards Appendix B 2.234.2 Evaluation ofTools and Methods for the Development of Safety Critical Appendix C Software 2.234.3 Review of Prototype Application of Software Standards Appendix B 2.234.4 Review of Trip Computer System Specifications Appendix C 2.234.5 Review of Trip Computer Redesign Appendix C 2.234.6 Review of Trip Computer Testing Appendix C 2.235.1 Processes in Radioactivity Removal Appendix C 2.237.1 Assessment of Psychological Capacities Requirements Appendix C 2.238.2 Review of Computer Code MODTURC-Phase 2 Appendix C 2.241.2 Technical Review of the CANDU-3 PSA (Phase 2) Appendix C 2.242.2 Stratigraphy in Paleozoic Rocks in the CMBBZ Appendix D 2.242.3 Stratigraphy in Paleozoic Rocks in the CMBBZ - Phase 3 Appendix C 2.243.1 Marine Geophysics in Western Lake Ontario Appendix B 2.243.2 Seismic Stratigraphy of Paleozoic Bedrock in Western Lake Ontario Appendix D 2.243.3 Marine Geophysics in Western Lake Ontario, Lake Simcoe and the Appendix B Kawartha Lakes 2.244.1 Elevation Determinations of Stratigraphie Contacts in the CMBBZ Appendix B 2.244.2 Elevation Determinations of Stratigraphie Contacts in the CMBBZ and Appendix C the GBLZ 2.245.1 Acceptability of Spacer-Pad Wear Allowance Appendix C 2.246.1 The Behaviour of Zirconium Alloys in Reducing Environments Appendix C 2.247.1 Load Factors for the Design of CANDU Concrete Structures Appendix B 2.247.2 Reliability of CANDU Concrete Containment Structures Under Seismic Appendix B Loads 2.248.2 Seismic Analysis of a Mechanical System at Pickering NGS Appendix B 2.248.3 Seismic Assessment of Systems and Components at Pickering A NGS Appendix C -221- 2.24 8.4 Seismic Response of the Pickering Pressure Relief Duct to the 1985 - Appendix B Nahanni Earthquake 2.248.5 Laboratory Testing of Reinforced Concrete Column Specimens Appendix B 2.248.6 Assessment of Reinforced Concrete Column Specimens Appendix B 2.249.1 Compliance with Bundle Power and Channel Power Limits Appendix B 2.249.2 Compliance with Bundle and Channel Power Limits- Phase II Appendix C
2.250.1 Pressure Tube Inspection Capability Appendix B 2.252.1 Training for Troubleshooting Skills Appendix B 2.255.1 Formal Methods for Computerized, Real-Time, Safety-Critical Systems Appendix D 2.257.1 Modification of the SECT Computer Program Appendix D 2.258.1 Definition of Systems in Nuclear Power Plants Appendix C 2.259.1 Review of the Bruce A Fuelling Machine System Appendix C 2.260.1 Review of Reactor Regulating System Software Appendix B 2.261.1 Protection and Bus Transfer Schemes at CANDU Power Stations Appendix C 2.263.2 Faulting in Unconsolidated Sediments and Bedrock in Metro Toronto - Appendix B Phase 2 2.264.1 Human Performance Investigation Process (HPIP) Feasibility Study Appendix D 2.266.1 Approach for Management of Ageing in CANDU Nuclear Power Plants Appendix C 2.267.1 Fire Hazards and Fire Protection Systems Design for CANDU 3 Appendix B Reactor Facilities 2.268.1 Stratigraphy in Paleozoic Rocks Adjacent to the GBLZ Appendix C 2.269.1 Brittle Faulting Along the SL Lawrence Valley Fault System - Phase 1 Appendix B 2.269.2 Brittle Faulting Along the SL Lawrence Valley Fault System - Phase 2 Appendix C 2.270.1 Application of LANDSAT Imagery to Assessing Deep Fault Structures Appendix C in Southern Ontario 2.271.1 Reactor Physics Computer Codes Appendix B 2.272.1 Use of Acoustic Emission Techniques for Defect Detection Appendix B 2.273.1 Raw Tolerance of Steam Generator Tubes Under Accident Conditions Appendix B 2.274.1 Selection of Predictive Maintenance Tasks Appendix B 2.275.1 Failure Rates in Piping Manufactured to Different Standards Appendix B 2.276.1 Independent Verification in Operations at Nuclear Power Plants Appendix B 2.277.1 Void Reactivity Calculations Appendix C 2.279.1 Evaluation of Training Programs for Nuclear Operations Personnel Appendix B 2.280.1 Structure for Human Factors Guides Documents for Nuclear Licensees Appendix B 2.280.2 Human Factors Guiding Documents - Part 3 Appendix B -222- 2.281.1 Implications of Computer Generated Procedures Appendix C 2.282.1 Supervisory Control Capabilities Development Appendix C 2.283.1 Human Factors Issues in Fuel Handling - Darlington Appendix B 2.284.1 Communications Processes in NPP Maintenance Appendix B 2.285.1 Assessment of Safety Critical Software Development Teams Appendix C 2.286.1 Guideline for Assessment of Computer Hardware Used in Safety Appendix B Related Systems 2.288.1 The Assessment of Field Training for Nuclear Operations Personnel Appendix B 2.289.1 CANDU 3 Primary Heat Transport System Erosion/Corrosion Appendix B 2.290.1 PRA Review Techniques Appendix C 2.291.1 Dependency Analysis in Reliability Submissions Appendix C 2.292.1 Sensitivity Analysis in Reliability Submissions Appendix C 2.293.1 PSA/Reliability as a Tool for AECB Project Officers Appendix C 2.294.1 State-Space Methods Appendix C 2.295.1 Human Reliability Data Collection and Analysis Appendix B 2.296.1 Impact of Loss of Redundancy on Availability Appendix B 2.297.1 Higher-Level Cognitive Abilities Requirements for Candu Personnel Appendix B 2.298.1 FISST Criticality Review Appendix B 2.301.1 Assessment of Darlington SDS Computer Hardware Appendix B 2.302.1 Review of Ontario Hydro Program to Reduce Fuel Channel Gap Appendix B 2.303.1 Paternal Tritium Exposure and Health Effects in Offspring: A Mouse Appendix B Model 2.304.1 Assessment of Bundle Deformation Under Post-Dryout Condition Appendix B 2.305.1 Ergonomie Review of Guideline Specifications Appendix B 2.306.1 Development of Safety Analysis Review Guides - Part 1 Appendix B 2.314.1 Formal Specification of System and Software Requirements Appendix B 2.315.1 PSA Applications Appendix B 2.316.1 Review of Current UK Nuclear PRA Analysis Appendix B 2.317.1 A Reassessment of CANDU Fuel Behaviour During Large Break Appendix C LOCA Power Transients 2.318.1 The Use of PVC Cables in CANDU Power Plant Appendix B 2.320.1 Protection Against Electro-Magnetic Interference Appendix B 2.322.1 Simulator Certification Test Reliability and Validation Appendix B 2.323.1 Pressure Tube Fracture Transition to a Guillotine Break Appendix B 2.326.1 OP&Ps Manual For Review of Significant Event Reports Appendix B -223- 2.335.1 Case-Control Study of Prostate Cancer in Canada Appendix B 2.337.1 Report on Faulting in Unconsolidated Sediments & Bedrock Appendix B 3.101.2 Demonstration of the Feasibility of Directly Dating Quartz-Phase II Appendix B 3.103.1 Absorbed Fraction of Ingested Uranium in Humans Appendix B 3.106.3 Transfer of Radionuclides to Human Milk-Phase 3 Pilot Study Appendix D 3.111.1 Evaluation of Data and Models on Uranium Metabolism-Europe Appendix D 3.111.2 Evaluation of Data and Models on Uranium Metabolism -North Appendix B America 3.121.1 BIOMOVS - Intercomparison of Environmental Assessment Models Appendix D 3.121.3 BIOMOVS II - International Assessment of Biosphere Models Appendix B 3.123.2 In Vivo Dissolution of Inhaled Uranium Compounds Appendix B 3.124.1 Assessment of Errors in Airflow Measuring Instruments (U Mines) Appendix D 3.131.2 Neotectonic Investigations in Southern Ontario - Phase 2 Appendix D 3.133.1 Carbon-14 in Food and in Excretions Appendix D 3.134.1 RBE from a Microdosimetric Approach Appendix B 3.135.1 Measurement of Tritium in Canadian Food Items Appendix B 3.135.2 Dosimetry of Organically Bound Tritium Derived from Diet Appendix C 3.144.2 Liquefaction Features in the Chicoutimi Area Appendix D 3.145.1 Significance of Urban Pathway in Assessing Public Dose Appendix D 3.146.1 Canadian Atmospheric Stability Indicators Appendix B 3.150.1 Different Biological End-Points to Study Radiation Effects Appendix D 3.150.2 Effects of Radiation on Species Other than Man: Aquatic Organisms Appendix D 3.150.3 Effect of Low-Level Radiation on Aquatic Invertebrates (Chironomids): Appendix C 2 3.151.1 Canadian Data Base for Radionuclide Transfer in the Environment Appendix B 3.154.1 Impact of Occupational Dose Reduction on Doses to the Public Appendix C 3.156.1 An Analysis of Brittle Structures in the Saguenay Earthquake Areas Appendix D 3.157.1 A Field Evaluation of Convoluted Laminations Appendix C 3.160.2 Radionuclide Analysis in Tissue Appendix B 3.161.1 Radiation Facts Booklet Appendix D 3.162.1 Monitoring Uranium Emissions from a UF6 Plant Stack Appendix B 3.163.1 The Origin of Conical Hills, Charlevoix Seismic Zone Appendix D 3.164.1 Carbon-14 in Lakes: Appropriate Risk Assessment Appendix C 3.168.1 Environmental Health Scoping Study at BHWP Appendix D 3.168.3 Effect of Chronic Exposure of Sheep in Low Levels of H2S/SO2 Appendix C -224- 3.169.1 Computer Software Quality Assurance Appendix C 3.170.1 MAGNEC Five-Year Progress Report Appendix B 3.171.1 Bioavailability of Iodine in a Simplified Aquatic Food Chain Appendix C 3.172.1 Use of Evergreen Needles to Assess Airborne Radioactivity Appendix C 3.173.1 Review of Soil to Plant Transfer Models Appendix C 3.174.1 Uncertainty in Environmental Pathways Analysis Models Appendix C 3.175.1 Further Development of the CHERURB Urban Contamination Model Appendix B 3.177.1 Uncertainty in Air Quality Modelling Appendix C 3.178.1 A User-Friendly Code for CSA Standards Calculations Appendix C 3.179.1 Radionuclide Transfer to Humans and Other Biota Through Fungi Appendix C 3.180.1 Pathways Assessment for Fruits Appendix C 3.181.1 Cs-137 Bioaccumulation Factors for Fish Appendix C 3.182.1 Bioconcentration of Radionuclides by Aquatic Plants Appendix C 3.183.1 Environmental Research Seminars Appendix B 3.184.1 Mesoscale Atmospheric Model for Complex Environments Appendix B 3.185.1 Environmental, Ecological and Socio-Economical Model (DEEP) Appendix C 3.186.1 Microsimulation for Tracking Chemical and Radionuclide Releases Appendix B 4.101.1 Study of the Health Effects of Inhaled Uranium Ore Dust Appendix D 4.101.2 Modification of Equipment for Uranium Ore Dust Study Appendix D 4.101.3 Study of the Health Effects of Inhaled Uranium Ore Dust-Phase 3 Appendix B 4.103.2 Physical Characteristics and Solubility of Long-Lived Airborne Appendix B Particulates in Uranium Producing and Manufacturing Facilities 4.106.5 Ontario Miners Mortality Study - Phase 5 Appendix B 4.106.6 Genetic Mutations Associated with Lung Cancer In Ontario Miners Appendix B 4.108.2 Methodology for Determining the AMAD of Long-Lived Dust Appendix C 4.108.3 Time Variability of AMAD of Long-lived Radioactive Dust Appendix C 4.113.1 Tracer Gas Method for Assessing Ventilation Efficiency Appendix D 4.118.2 A Case - Control Study of Beaverlodge Uranium Miners from Appendix B 1950-1980 4.118.3 Radon Progeny Exposures of Beaverlodge Uranium Miners Appendix B 4.118.4 Radon Progeny Exposures of Beaverlodge Uranium Miners - Phase 2 Appendix B 4.119.1 Evaluation of Mine Ventilation Monitoring Devices Appendix D 4.121.2 The Proliferative Cells of the Human Bronchial Epithelium Appendix D 4.122.1 Transgenic Potential of Natural Uranium Decay Chain Progeny Appendix B 4.125.2 Independent Evaluation of the Report for Project 4.125.1 Appendix B -225- 4.126.1 Computerized Mortality Search Procedures Appendix C 4.127.1 Rapid Determination of Radon Daughter Concentrations Appendix D 4.129.1 Temporal Variation of Airborne Radioactivity in Mines Appendix D 4.130.1 Evaluation of Radon Progeny Exposures of Port Radium Miners Appendix B 4.130.2 Mortality Analysis of Port Radium Uranium Miners (1950-1989) Appendix C 4.132.1 Smoking Histories of Fluorspar Miners Appendix B 4.133.1 Lung Cancer Among Uranium Miners in Germany Appendix B 4.134.1 Tools for Measuring the Unattached Fraction in Uranium Mines Appendix C 4.135.1 A Generic Method for Measuring Uranium in Dust Samples Appendix C 4.136.1 Representativeness of Open-Face Dust Samples Appendix B 4.138.1 Processing and Reading of PAD Detectors Appendix B 4.139.1 Limitations of Mine Ventilation Radiation Models Appendix C 4.139.2 Simulation of Least Favorable Mine Radiation Conditions Appendix C 4.140.1 Transfer of Dietary Ra-226 to Vole Offspring Appendix C 4.141.1 Transfer of Uranium from Mother to Fetus Appendix C 4.142.1 Update on Acute Toxicity Levels of Hydrogen Fluoride Appendix B 4.143.1 Mechanism of Radiation-Induced Lung Cancer Among Ontario Appendix C Uranium Miners 4.146.1 PAD Response to Rn-222 Progeny and Long-Lived Radioactive Dust Appendix C 5.127.1 Radionuclide Concentrations in Fish: Phase I Screening Program Appendix D 5.127.2 Radionuclide Concentrations in Fish: Phase 2 (Detailed Analyses) Appendix B 5.136.1 Hydrology of Quirke and Panel Tailings Basins Appendix D 5.142.1 Feasibility of Monitoring Tailings Sites Using Remote Sensing Appendix D 5.143.1 Radiological Impact of Uranium Mining: Northern Saskatchewan Appendix D 5.143.2 Radiological Impact of Uranium Mining: Northern Saskatchewan- Appendix D Phase H 5.144.1 Groundwater Inflow into Deep Underground Mines - Phase I Appendix B 5.144.2 Groundwater Inflow Into Deep Underground Mines - Phase II Appendix B 5.144.3 Groundwater Inflow Into Deep Underground Mines - Phase HI Appendix B 5.146.1 Thermal Consolidation Effects Around a High Level Waste Repository Appendix B 5.146.2 Thermal Consolidation Effects Around a High-Level Waste Repository Appendix C - Phase 2 5.147.1 Assessment of the Underground Disposal of Tailings Concept Appendix B 5.148.1 Reassessment of the Deep Lake Disposal of Uranium Tailings Appendix C 5.149.1 Radiological Impact of Uranium Mining: Ontario Appendix B -226- 5.150.1 Concentrations ofRadionuclides in Wild Rice Appendix C 5.152.1 Effects of Low-Level Radiation on Fish -Phase I Appendix C 5.153.1 Development and Testing of Environmental Transport Pathway Code- Appendix B ETP 5.153.2 Integration of IMPACT with GIS and Mapping Interface Appendix B 5.154.1 Workshop on Current Knowledge and Developments in Containment Appendix B Structures 5.155.1 Soil Residence Time(s) Database Appendix C 5.156.1 Waste Rock Sampling Manual - Phase II Appendix B 5.162.1 Research on Biophysical Impacts of U Mine Effluents Appendix B 5.163.1 Stress Corrosion Cracking of Steel in Stagnant Environments Appendix B 6.104.2 Production of a Hospital Radiation Safety Officer's Handbook - II Appendix C 6.105.1 Radiation Exposures of Non-Monitored Hospital Personnel Appendix D 6.113.1 Doses from Radioactive Waste in Municipal Systems Appendix B 6.118.1 Assessment of Tc-99m in Nuclear Medicine Environments Appendix B 6.119.1 Occupational Radiation Doses to Health Care Workers Appendix C 6.120.1 Doses from Industrial Radiographie Exposure Devices Appendix B 6.121.1 Ergonomics in Industrial Gamma Radiography Appendix C 6.122.1 Unsealed Radioactive Materials in the Oil and Gas Industry Appendix C 7.106.2 Effects of In Utero Exposure on Central Nervous System Appendix B 7.107.1 Exposure Levels of Non-Radiological Carcinogens at Nuclear Facilities Appendix D 7.107.2 Teratogenic Effects of Ionizing Radiation and Chemical Substances - Appendix B Phase 1 7.107.3 Teratogenic Effects of Ionizing Radiation and Chemical Substances - Appendix B Phase II 7.111.1 In Vitro and In Vivo Studies of Health Effects of Ionizing Radiation Appendix D Effects on the Developing Central Nervous System 7.116.1 Cancer Morbidity Follow-Up Feasibility Study Appendix C 7.117.1 Hospital Record-Keeping System for Epidemiological Studies Appendix B 7.122.1 Computerized Linkage of National Cancer Incidence Data Appendix D 7.122.2 Cancer Incidence Linkage following Multiple Fluoroscopies Appendix C 7.127.1 Dose Response of Human Lymphocytes to Carcinogens • Appendix C 7.128.1 The Relative Impact of Radiation-Induced Genetic Disorders Appendix C 7.130.1 Ionizing Radiation in Tumour Promotion or Progression Appendix D 7.135.1 Mechanism of Radiation-Induced Mental Retardation Appendix B 7.135.2 Mechanism of Radiation-Induced Mental Retardation-Phase 2 Appendix C -227- 7.137.1 Study of Childhood Cancer Associated with Maternal X-Irradiation - Appendix B Phase 1 7.141.1 Response of Mice to Gamma Rays Delivered at Low Dose Rates Appendix B 7.142.1 Mortality Analysis of the Fluorspar Miners from 1985-1990 Appendix B 7.143.1 Canadian Cancer Data Base Appendix B 7.143.2 Development of a New 1951-1990 Master Identification File Appendix C 7.143.3 Linkage of National Dose Registry to the Canadian Cancer Data Base Appendix C 7.143.5 Canadian Cancer Data Base - Phase II Appendix B 7.152.1 Transport of Compounds from Mother to Foetus Appendix D 7.153.1 RBE of Tritium and Co-60 Gamma Rays at Low and High Dose Rates Appendix D 7.156.2 Tritium Levels in the Environment and Birth Defects Appendix B 7.160.1 Metabolism and Fetal Dosimetry of Tritium Appendix B 7.161.1 Literature Review: Interaction Radiation - Co-Carcinogens Appendix C 7.162.1 Assessment of Biases Due to Measurement Errors on Risk Estimates Appendix B 7.163.1 Alteration of Immune Surveillance and DNA Repair Capacity Appendix C 7.164.1 Improved Cytometry Method Appendix D 7.164.2 Improved Cytometry Method - Phase 2 Appendix B 7.165.1 The Influence of Radon Daughter Exposure on Cell Mitosis Rate Appendix C 7.166.1 Birth Defects Due to In Utero Exposure to Ionizing Radiation Appendix C 7.167.1 Risk Estimates for Radiation-Induced Genetic Disorders Appendix B 7.168.1 Recovery of Boreal Forest Vegetation Appendix D 7.168.2 Indicators for Assessing Impacts on Forest Ecosystems Appendix C 7.169.1 Ra-226 in Deciduous Teeth of Residents Living Near Mining Areas Appendix C 7.171.1 Canadian Coordinating Committee on Chernobyl Appendix B 7.176.1 Biological Dosimetry Workshop Appendix B 7.176.2 Biological Dosimetry Appendix C 7.177.1 Distribution of Fatal Risk in "Safe" Industries: An Update Appendix C 7.178.1 Impact of Low Doses of Radiation on Cell Signalling Appendix C 7.180.1 Ethics of Identifying Radiosensitive Individuals Appendix C 7.181.1 Cluster Elucidation: Genetic Factors Appendix C 7.182.1 Feasibility of Performing Placental Perfusion Research Appendix C 7.183.1 Genetic Risk from Exposure to Ionizing Radiation Appendix C 7.184.1 Genetic Defects and Clustering Phenomena Appendix C 7.185.1 Influence ofTLD Position on the Estimate of Fetal Dose Appendix B -228- 7.186.1 Uncertainty in Risk Estimation Appendix C 7.188.1 Role of Confounding Factors on the Occurrence of Down Syndrome Appendix C 7.190.1 Guide on Radiation Epidemiology Appendix C 7.191.1 Delayed Cancer and Genetic Effects from Occupational Exposures Appendix C 7.192.1 Creation of a Canadian Birth Outcome Data Base Appendix C 7.193.1 Bioaccumulation of Polonium 210 and Lead 210 in the Fetus Appendix C 7.194.1 Environmental Contamination Model Appendix C 7.195.1 Quality Assurance Programs in Medical Institutions Appendix B 7.197.1 Atlas of Childhood Leukemia in Ontario Appendix C 7.199.1 An Improved High Sensitivity TLD Dosimeter Appendix C 7.200.2 International Study on Nuclear Industry Workers Appendix B 7.201.1 Medical Radiation Exposures in Canada Appendix B 7.202.1 Influence of Prior Dose on Subsequent Radiation in Cells Appendix C 7.203.1 Radiation-Induced Mutations in Human Germ Cells Appendix C 7.204.1 Radiation Protection Against Genetic Disorders Appendix C 7.205.1 Radiation-Induced Papillary Carcinoma of the Thyroid Appendix B 7.206.1 Effects of Measurement Errors on Radon Progeny Risk Factor Appendix B 7.207.1 Cytotoxicity and Genotoxicity of Tritium Appendix C 7.208.1 Workshop: The Molecular, Genetic and Cellular Basis of Appendix B Radiosensitivity 7.209.1 Acute Lymphoblastic Leukaemia and Maternal X-Ray Exposure Appendix B 7.210.1 Participation in the International System for Occupational Exposure Appendix B (ISOE) 7.211.1 A Portable Spectrometer-Based Neutron Dosimeter Appendix B 7.214.1 In Vitro Radiobiological Assessments: Guidelines for Quality Control Appendix C 8.105.3 Leakage Testing on Packages for the Transport of Radioactive Materials Appendix B -m 9.109.3 Design of AECB Corporate Identity with Program Symbol and Appendix B Standards Manual 9.109.4 National Public Awareness Survey Appendix B 9.121.1 Nuclear Terminology (English/French) Data Bank Appendix B 9.121.2 French-English Glossary of Power-Reactors Terminology Appendix B 9.121.3 Banque de terminologie nucléaire (anglaise/française) - Phase II Appendix B 9.127.1 Recommended Criteria for the Evaluation of On-Site Nuclear Power Appendix B Plant Emergency Response Plans 9.128.1 Prototype for A New Information Inventory System Appendix D -229- 9.129.1 Improvement of MORIS and Similar Data Bases Appendix B 9.130.1 Improvement of RaPPID Data Base Appendix B 9.131.1 Delivery of Level II Course on Fundamentals of Power Reactors Appendix C 9.132.1 A Short Course in Systems Engineering Appendix B 11.-101.1 Audit of Radiochemistry Procedures Appendix D 11.103.5 Participation in Working Group on External Dosimetry-5 Appendix B 11.111.1 Laboratory Testing of An Instant Radon Progeny Monitor , Appendix D 11.119.1 Examination of Deformation in the Rouge River Valley-Toronto Appendix D 11.126.1 Presentation of "Cognitive Skills for Nuclear Power Plants Personnel Appendix D Training" 11.127.1 Presentation of "Evaluation of Full Scope Simulator Testing Methods" Appendix D 11.128.1 Radiation Index Survey Appendix D 11.130.1 Validation of Radiological Assessment Models Appendix D 11.133.1 Peer Review of AECB Consultative Document C-6 Appendix B 11.136.1 Specialist Advice on Reactor Physics Topics Appendix D 11.136.2 Specialist Advice on Reactor Physics Issues - Phase II Appendix B
11.136.3 Specialist Advice on Reactor Physics Issues - Phase in Appendix B
11.146.1 Characterization Methods for Fractures in Intact Crystalline Rocks Appendix B 11.150.1 Francisation du programme de la recherche et du soutien Appendix B 11.151.1 A Literature Review of Other Government Communications Policies Appendix D and Procedures Manuals 11.152.1 Development of a Terrestrial Consequence Assessment Model Appendix C 11.153.1 Task & Attribute Description for an Audit & Evaluation Officer Appendix B 11.154.1 Review of Uncertainty Calculations on Exposure Measurements Appendix B 11.155.1 Attendance at the Workshop: "Intakes of Radionuclides" Appendix B 11.156.1 Westlakes Workshop on Childhood Cancer Clusters and Radiation Appendix B 11.159.1 Review of Benefits and Costs of Regulation Appendix C 11.160.1 Survey of Canadian Hospital Emergency Plans Appendix B 11.161.1 Environmental Qualification of Equipment for the CANDU 3 Reactor Appendix B 11.162.1 Methodologies for the Assessment of the Costs & Benefits of Appendix B Regulatory Decision Making 11.163.1 Safety Culture Seminar Appendix B 11.164.1 Seminar on Combined Analysis of Lung Cancer Mortality Among Appendix C Miners
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APPENDIX F
Regulatory Research and Support Program Specific Objectives for Fiscal Year 1993/94 and How Each Was Met
1. To keep current in research activities, in Canada and abroad, in domains relevant to the AECB mandate; (Measure: Courses and training sessions attended; papers published and presentations delivered by staff.) The following training courses, seminars and conferences were attended: - Water Reactor Safety Meeting, Washington, D.C., 25 to 28 October, 1993. AECB Technical Overview Course Part 1,17 to 21 January and 31 January to 4 February, 1994. CEC / OECD / IAEA Specialists' Meeting on Non-Destructive Examination and Results, the Netherlands, 8 to 10 March, 1994. Technical specialists' meeting of the International Piping Integrity Research Group, Columbus, Ohio, USA, 28 February and 4 March, 1994. - CRPA Conference, Toronto, June 22-24,1993. CEC-DOE-IPSN Workshop on Inhaled Radionuclides, Bath, UK, September 1993. (Presented an invited paper : "Radiation protection in uranium mines: Two challenges".) Seminar given at University of Toronto: "Radon Risk: Myth or reality?", December 1993. Review of uncertainties in radioactive dust sampling and measurement. Presentation of the review to UFD staff, Saskatoon, June 1993. Directed in-house research on the fundamentals of the measurement of unattached radon progeny, and production of an operating manual for AECB inspectors. Final draft report completed. In-house research: Influence of the reliability of exposure data on the determination of risk factors for lung cancer due to the inhalation of radon progeny. External examiner for a PhD thesis (Nuclear Mass Spectrometric Studies of Radon Progeny Clusters in Gaseous H2O and SO2), University of Toronto, December 1993. Software Safety Workshop organized by the Institute for Risk Research, Ottawa, June 1993. Four-country Meeting on Safety-Critical Software, Ottawa, May 1993. SARJ-93 (Severe Accident Research in Japan) Meeting. (An AECB staff member chaired the session on NSRR (Nuclear Safety Research Reactor)). Technical Review Meeting, Tokyo, November 1993. Course on Radiopharmaceutical Internal Dosimetry, Oak Ridge, Tennessee, USA, 23-26 April 1993. IAEA's VAMP (International Coordinated Research Project on Validation of Model Predictions) Meeting, Vienna, July 1993. Health and Environmental Seminars "Initiation-Promotion Model of Carcinogenesis in Mice From Radiation Exposure" by Francis A. Cucinotta, NASA Langley Research Centre, Hampton, VA, 28 October 1993, AECL Chalk River. NCRP Annual Meeting Course given at Carleton University on Radiation Protection -232-
2. To initiate research projects in the RSP for FY 93/94 according to priorities set in the ranking document within available funding; (Measure: Number of projects initiated. Reasons for not initiating a project will be documented.) Contracts have been issued for 18 of the Category 1 and 2 projects listed in the 1993/94 RSP. The approval process is under way for another 13 such projects. A total of 15 Category 1 and 2 projects have been either cancelled or postponed during the year. Reasons for these cancellations include the following: information not needed immediately or not any more. discussions with sponsoring divisions on the required scope of study have not yet progressed to firm conclusions delays because of policy directions which are still to be decided on awaiting information from another research project or from industry 3. To complete research projects whose completion was planned to occur during FY 93/94, within the budget and time estimated in the RSP; (Measure: Number of projects completed on time and within budget. Reasons for not completing a project on time and within budget will be documented.) The status for projects which have end dates within FY 93/94 is as follows: Projects completed, or which will be completed within 93/94, and within budget: 33; Projects planned for, but not completed within 93/94, or not within budget: 52, with the following break-down: (a) completed within 93/94, but with increased budget 4 (b) delayed, but will be completed in 94/95 18 (c) delayed, out will be completed beyond 94/95 2 (d) postponed to 94/95 18 (e) cancelled 10 4. To respond to new, urgent requests for initiating research projects that do not appear in the RSP document for FY 93/94; (Measure: Number of requests received, responded to, and number of such projects initiated.) During the year, requests were received for a total of 38 new projects. Contracts have been let for 27 and proposals for a further 10 are at various stages in the project approval process; one project was postponed. A total of 10 Category 3 projects in the 1993/94 RSP have been upgraded to Category 1 during the year. Contracts have been let for 5, and the other 5 are being processed for approval. 5. To complete Post Project Evaluations (PPEs) within six months of the termination date of the contracts; (Measure: Number of PPEs completed versus number of projects completed.) Eight Post-Project Evaluations were completed. 6. To develop and maintain a computerized tool for keeping up-to-date status (schedule, financial, post-project evaluation) of all projects, with a view to maximizing the use of the -233-
allocated resources; (Measure: Tool availability and its use by Research Program Officers and others; immediate access to financial status; identification of sources of delay in the initiation, management, and evaluation of projects.) Computerized Tools MORIS is an information tool which assists the overall management of projects within the < AECB's Regulatory Research and Support Program. As developed, it provides a database structure to capture important project information (including contractors' information and SSC financial data, which are available for queries from all RSD staff), and a report generator which produces all required reports and forms. MORIS was recently modified to report on the committed and uncommitted funds for each responsibility centre.
An additional database (TRACKING) is being developed to deal specifically with a project's contractual and financial aspects. Presently, this database is separate from MORIS. However, it can be integrated to the MORIS system so that the additional information is accessible (on-line) to RSD staff. 7. To develop four new subprograms: two in health physics area and two in reactor safety; (Measure: Number of subprograms initiated.)
In addition to the three existing sub-programs, five new sub-programs were prepared, in fiscal year 1993/94, for initiation in fiscal 1994/95: (a) Pressure Boundary Integrity (b) Integrity of Concrete Structures (c) Human Factors (d) Internal Dosimetry (e) Studies of Health Effects in Human Populations 8. To develop (with CSSP) a standard format for contracts issued directly from the AECB; (Measure: Availability of a standard contract format.) A standard format has been prepared, and is in use, for contracts which are issued by the AECB, under the Regulatory Research and Support Program and under the Canadian Safeguards Support Program. The standard contract (in English and French) was prepared in consultation with AECB Legal Services, who will be further consulted only in special circumstances. Standard contracts are now prepared by the Contracting Officer within RSD.
9. To transfer some administrative duties from Research Program Officers to the directorate's Contracting Officer; (Measure: Number and extent of duties transferred.) The issuance of AECB contracts is done by the Contracting Officer within RSD. (See item 8 above). A database tracking system has been developed by the Contracting Officer which: (a) keeps track of important contract dates such as milestone payment dates and contract termination; (b) allows diverse and specialized reporting (e.g., financial reconciliation, NAFTA and Treasury Board reporting). -234-
In addition, the Contracting Officer: (a) advises Program Officers on contracting options and regulations; (b) liaises with contractors. PWGSC (formerly DSS), AECB Finance, etc., on any contractual matters. 10. To develop a procedure for developing and managing subprograms; (Measure: Availability of this procedure.) A written procedure has been prepared (in draft form) for the development and management of sub-programs, under a Supervisor and Research Program Officer in RSD. This procedure is expected to be available for implementation by staff by March 31, i994. 11. To conclude Memoranda Of Understanding on co-operation in research related to radiation protection and reactor safety with IPSN (CEA - France) and on research related to radiation protection with CEC; (Measure: Signatures on the MOUs.) (a) Progress on an AECB/Commission of the European Communities (CEC) Memorandum of Understanding (MOU) has been slowed, pending the current consultations between Canada and the CEC on the high-level Agreement on Science and Technology. (b) Concerning the proposed MOU between IPSN (France) and the AECB, the AECB has received a counter proposal from IPSN, whose text should be close to the final version. Signing of" the agreement is expected within a few months. 12. To coordinate and participate in information exchanges with COG members and other Canadian &i.d foreign institutions active in domains pertinent to the RSP; (Measure: Number and nature of such coordinated events .) The following information exchanges were carried out, involving participation by RSD staff: - UNSCEAR 1993,2 weeks, Vienna, May 1993. - UNSCEAR 1994,1 week, Vienna, March 1994. AECB - AECL Annual info exchange meeting on environmental research, 2 days, Ottawa, October 1993. AECB - AECL Annual info exchange meeting on health effects, 2 days, Chalk River Labs., September 1993. AECB - AECL - COG Annual info exchange meeting on reactor engineering, software and human factors, 1 day, Chalk River Labs., May 1993. AECB - AECL - COG Annual info exchange meeting on reactor safety analysis, 2 days, Whiteshell Labs., Pinawa, September 1993. Exchange of information on epidemiology of lung cancer in uranium miners, Institute of Radiation Hygiene (BFS), Munich, Germany, September 1993. Presentation of AECB research program before CEA - IPSN staff, Fontenay-aux- Roses, France, June 1993. Liaison with CEA (Institut des sciences du vivant); research on the effects of low doses and low dose rates, June 1993. Critical review of, and comments on, the ICRP Special Document on Radon, July 1993. Exchange of information, by correspondence, with prominent researchers in the fields of radon-induced lung cancer (Dr. G. Saccomanno, Prof. B.L. Cohen). Info exchange with Bell Northern Research on software. Info exchange with the National Research Council Software Group. -235-
- Info exchange with NHW / CEC, Ottawa, April 22,1993. Info exchange meetings, and by correspondence with USNIH, USNCI, and USDOE. 13. To convene a meeting of the Advisory Panel for the ballooning of pressure tubes series of projects to review results from Projects No. 2.184.3 and a proposal for Project No. 2.184.4.; to place a contract for Project No. 2.184.4 and to commence the degraded specimen tests to be carried out on that project; (Measure: Convening of meeting, contract issued, tests initiated.) The two ballooning tests which were part of Project No 2.184.3 were completed in October, 1993. Results from the tests and the draft final report for the project were sent to members of the Advisory Panel. At a meeting held in Ottawa on 22 November, 1993, the Panel reviewed the results with AECB staff and the contractor. In a subsequent session with AECB staff, the Panel advised on the selection of a test matrix for a degraded specimen test program (Project No 2.184.4). Preparations are at present under way for a contract to undertake the degraded specimen ballooning test work. 14. To participate in AECB technical and coordinating working groups. (Measure: Number and nature of such events.) Participation by RSD staff in AECB technical and coordinating working groups was as follows: Working Group for C-130: Monitoring requirements for uranium mines and mills. Working group-2 of the Group of Medical Advisors, which is concerned with the following: a) hospital emergency plans for the management of minor radiation accidents, and b) tertiary hospital emergency plans for the management of major radiation accidents. AECB representative to the emergency response exercises at Gentilly. ACRP-WG-12: Organizing committee for the "Symposium on Molecular Biology and Radiation Protection". Working Group for C-129: Consultative document on the requirement to keep all exposures as low as reasonably achievable. Computer hardware working group. Consultative document C-6 review on safety analysis of CANDU reactors. Computer code documentation. - Fire drill at Darlington NGS. Working group on standard problems for atmospheric dispersion computerized models used by various agencies for emergency preparedness. Working Group on generic action item 90G02, "core cooling without forced flow". Working Group on "consequence of pressure tube failure". Geosphere working group Special Assignment: Support group which provides advice to the Government of Canada's lawyers and the AECB witnesses in the legal challenge of the Nuclear Liability Act by Energy Probe. Special Assignment: Report on alternate sourcing of AECB activities. - Special Assignment: STARS "think tank".