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^ - f, , n 034t> - | U.S. NLMEH REGULATORY COMMISS10N 1, b /LICATION FOR: ! ' ~ | FORM 'NRC 313 6 (Ch k and/ t compAeta as tpproproet:) ! ' \ 15 19) .si h ) f APPLICATION FOR BYPRODUCT MATERIAL LICENSE s. NEW LICENSE INDUSTRIAL XX
See attached instructiorRt for details. b. AMENDMENT TO: LICENSE NUMBER j ' Completed applications are filed in duphcete with the Division of fuel Cycle and Material Safety, Officr of Nuclear Materra! Safety, ar" Safeguards. U.S. Nuclear Regulatory Commossion' Washington, DC 20S55 or opphcations may be filed in person at the Commission's office at c. REg,gg NEWAL u,g nu, OF',,, 1717 H Street, NW, Washington, O. C. or 1915 Eastern Avenue, Silver Spring, Maryland.
2, APPLICANT'S NAME (Institution, firm, person, etc.) 3. NAME OF PERSON TO BE CONTACTED REGARDING TH46 APPLICAN - glSOLTD{Tp CONTROLS CORPORATION | R bert L. Flournoy B6t}[eT ConIM Ucut 06801 i 1ELEPHONE NUMBER; ARE A CODE - NUMBE R E XTENSION TELEPHONE NUMBE R' ARE A CODE - NUMBE R EXTENSION ' 203 743 6721- 703 339-7555 4. APPLIC ANT'S MAILING ADDRESS (includelep Codel 5. STREET ADDRESS WHf RE LICENSED MATERIAL WILL SE USEC, P. O. Box 726 " " ' ' " " ' * * ' * " ' ' Springfield, Va. 22150 7213 lockport Place Lorton, Va. 22079. .; B70'/9 p/ 2 g ) (IF MORE SPACE IS NEEDED FOR ANY ITEM, USE ADDITIONAL PROPERLY KEYED PAGES.) j 6. INDIVIDUAL (S) WHO WILL USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL (See items 16 and 17 for reQuked trainong and experoence of each indtvndualnamed below) FULL NAME TITLE
a. Mr. Charles W. Peters Project Manager j
b. Mr. Eser I. Karaoglan Senior Scientist { Dr. Russell K. Sherburne Chief Scientist i .. i 1 RADIATSCN PROTECTION OFF|CEFt I A ttach a resume of person's tramong and expertence as outtoned on items |I6 and 17 and describe has responsobihties under item 15. : Mr. Robert L. Flournoy | B. LICENSED MATERIAL NAME OF MANUF ACTURER MAXIMUM NUMBER OF L ELEMENT CHEMICAL AND AND/OR AND MILLICURIES AND/OR SEALED i SOURCES AND MAXIMUM ACTI- N MASE NUMBER PHYSICAL FORM MODEL NUMBER (11 Sealed Source / VITY PER SOURCE WHICH WILL E BE POSSESSED AT ANYONE TIME j NO. A B C D %g ''a***''j U.S. Radium Corp. 20,000 mci ._, m 3H As Tritium Target. Model 508-3 3 Sources 4 , ' 55 Is tope Products,Inc. 110.1 /eCi j | Fe Plated Metal pq . Gl Model 225.* Ss M , 3 Sources ; 137 Isotope Pr :ts, It c. 110. juCi ) - can Cs Solid-Sealed Model 229-Tvoe R 2 Sources 60 Isotope Products, Inc. 110 A Ci 744 j W Co Solid-Sealed Mod.el 236-Type R 2 Sources DESCRIBE USE OF LICENSED MATERIAL E
m H will be used as target material for a 14 meV (See continuation sheet) i H g, To be used as instrument calibration source
, 33 To be used as instrument calibration source
> To be used as instrument calibration source gg9 ~ ~ ~ ' ' F ORM NRC 313 116-78) ~ , X~1 w " f 8904190481 890404 2 14'o, wJ Mb M[ ' v M fy . b, - 1 ' REG 2 LIC30 s \ 45-25035-01 PNU , ; ______
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9. STOR AGE OF SE ALED SOURCES
NAME OF MANUFACTURER MODEL NUMBER I Y CONTAINER AND/OA DEVICE IN WHICH E ACH 5EALED 1 N SOURCE WILL BE STORED OR USED. C, NO. A. B. m StOped in shipping container in Dry ---- ..-- Box Used in Mackinn Stored in lead pig ------(2)
------(3) Stored in lead pig
Stored in lead pig ------ic 10. RADIATION DETECTION INSTRUMENTS SENSITIVITY ! TYPE M ANU F ACTU R EWS MODEL NUMBER RADIATION DETECTED RANGE OF NAME NUMBER AVAILABLE , (alphe, bete, (milliroentgen / hour C4 INSTRUMENT pomme, neutron) et counts / minute) F Q A B C D E ' Eberline E-120E v/ N Geiger Inst. Co. HP-193 Probe 1 Beta-ganna 0-5 mr/hr. Ing Count Texas I*' Rake Meter. Nuclear TN917< 1 Neutrons -- Gas Flow PAC 4Gwith 1 Beta-gamma , EberlineIns .. TP 1 Probe 0-1,000,^b00 Intern.Pronor tionR1 an-p u v der to
11. CALIBRATION OF INSTRUMENTS LISTED IN ITEM 10 , Ca. CALIBRATED BY SERVICE COMPANY Gb. CALIBRATED BY APPLICANT A rtsch a sopunte sheet describing method, treauency and stenderds NAME ADDRESS, AND FREQUENCY und for conbrutino enstrum*nts. Eber1L,ne Instr. Co., SantaFe, N.M. See Rndiation Protection Manual - Physics Dept. U. of Ed. (See Rad. Prot. Appendix "D" Manual, Appendix "D") , I 12. PERSONNEL MONITORING DEVICES TYPE SUPPLIER EXCHANGE FREQUENCY (Check pd/or compiere ss approproste.) (Servoce Company) g A D
Radiation Management Co.8 bMONTHLY O(1) FILM BADGE 9022 A-1 Telegraph Road
d (2) THE RMOLUMINESCENCE Lorton, Virginia 22079 0 oVARTERLY ! DOSIMETER (TLD) O OTHER (Specoty): | O (3) OT H E R (Specify):
13. F ACILITIES AND EQUIPMENT (Check were appropriate and attach annotated sketch (es) and description (s). $ a. LABORATORY F ACILITIES, PLANT F ACILITIES, FUME HOODS (Include filtration,if eny), ETC. See Rad. Protection' '.anual O b. STOR AGE F ACILITIES, CONTA'INE RS, SPECI AL SHIE LDING (fixed end/or temporary), ETC. See Rad. Protection Man lal O c. REMOTE HANDLING TOOLS OR EQUIPMENT,ETC. O d. RESPIRATORY PROTECTIVE EQUIPMENT, ETC. 14. WASTE DISPOSAL a.NAMERadiation OF COMMERCIAL Management W ASTE DISPOSAL Co., SERVICE9022 A-1EMPLOYED TelegrRph Rd., Lorton, Va. 22079 j b. IF COMMERCIAL W ASTE DISPOSAL SERVICE IS NOT EMPLOYED. SUBMIT A DETAILED DESCRIPTION OF METHODS WHICH WILL BE USED FOR DISPOSING OF R ADIOACTIVE WASTES AND ESTIMATES OF THE TYPE AND AMOUNT OF ACTIVITY INVOLVED IF THE APPLICATION IS FOR SEALED SOURCES AND DEVICES AND THEY wtLL BE RETURNED TO THE MANUFACTURER,SO STATE.
Not Applicable t
~ / FORM NRC 313146 78)
' ' .y - 2 $ $. w - t. . O . 0 0- .
~%
INFORMATION REQUIRED FOR ITEMS 15,16 AND 17 Describe in detail the information required for items 15,16 and 17. Begin each item on a separate page and key to the application as follows: (1) Senior Personnel Qualifications Statement, Attached. SEE:(2) Radiation Protection Manual, Attached. 15. RADIATION PROTECTION PROGRAM. Describe the radiation protection program as appropriate for the material to be used including the duties and responsibilities of the Radiation Protection Officer, control measures, bioassay procedures Ilf needad>, day-today general safety instruction to be followed, etc. If the application is for sealed source's also submit leak testing procedures, or if leak testing will be performed using a leak test kit, specif y rnanufacturer and model number of the leak test kit.
16. FORMAL TRAINING IN R ADIATION SAFETY. Attach a resume for each individual named in items 6 and 7. Describe individual's formal training in the following areas where applicable, include the name of person or institution providing the training, duration of training, when training was received, etc.
a. Principles and practices of radiation protection.
b. Radioactivity measurement standardization and monitoring techniques and instruments.
c. Mathematics and calculations basic to the use and measurement of radioactivity.
d. Biological effects of radiation.
17. EXPERIENCE. Attach a resume for each individual twned in Items 6 and 7. Describe individual's work experience with radiation, including where experience was obtained. Work experience or on- the job training should be commensurate with the proposed use, include list of radioisotopes and maximum activity of each used.
18. CERTIFICATE (This stem must be completed by appiscont)
. I ' The app!> cant and any offocial esecuteng this certifocare on behatt of the sophcant named on item 2,
. certofy that this apolocation os prepared un conformtry with Totle 10, Code of federal Reputations, Part 30, and that all informstron contained hereon, oncluding any supplements attached hereto, is true and correct to the twst of our knowirdge and belief.
| W ARNING.-18 USC. Sect on 1031; Act of June 25,1948; C2 Stat. 749; makes it a criminal off ense to make a wittf ully false statement or representat.c n to any department or apeney & Dneted States ~as,so ' any metter within its jurisdiction. N' n?. '3 . g a. LICENSE FE E REQUIRED b. CERT YING OFFICI A,L (5,gnorurel (Sow Secten 170.31,10 CFR 170) ' ' ~
$190 $N AME (Type or prmti OG S ELI | n"q- ' Charles '4. reters __ d TITLE 0) LICENSE FEE CATEGORY: h- pp gg yg gp WeM *3
' '' (2) LlLENSE F EE ENCLOSED s 190.00 November 28, 1973
F ORM N RC,313 1 16-78) ______. _. _ .
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I 1 Application Continua tion Sheet
| No. 8, E, (1) Texas Nuclear Neutron Generator (Model 9400). The neutron output of this machine vill be limited nornally to 107 neu- trons/vac. Occasionally, the nachine will be operated to produce 100 neutrons /& Appropriate shielding will be used at that time. (See attached Radiation Protection Manual, Appendix "E", Figures 2 and 3.)
No. 15 Leak-testing - Scaled sources vill be leak tested once each half- year by the R.S.O. Smear wipes will be taken on each sealed source using Whatman 41 paper smears. Smears will be assayed using a gas- flow internal proportional counter as described in item 10 of this a pplication.
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'l SE1IOR PERSONNEL QUALIFICATIONS
STAT 9EIT , i 1
CONSOLIDATED CONTROLS CORPORATION j
ICRTON, VIRGEilA
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Projeet 14anarer
Mr. Charles N. Peters 8525 Cyrus Place | Alexandria, Va. 22309 ! i D.0.3. - 12/19/27 |
| Mr. Peters received his A.B. in Physics from Indiana University in 1950. He
| pursued graduate work in physics at the University of Maryland between 1953
and 1957 From 1950 to 1970 he worked as a Supervisory Research Physicist for the Naval Research Laboratory, Washington, D. C. In this capacity he was responsible for developing radiation detection systems for the Navy and other departments of the hecutive Branch of the U. S. Government. From 1970 to 1976 Mr. Peters worked as a physical scientist for the U.S. En- vironmental Protection Agency. Radiation hperience: NRL-Used Kaman neutron generators with a capacity of
up to 10 neutrons per rec. Used isotopic sources on a daily basis of 10 to
30 C1. EPA-Evaluated environmental radiation measuring instru- ments - chaired the Federal Inter-Agency Task Force on Emergency Instrumen-
tation for Nuclear Incidents - Evaluated health hazards involved in using uranium
, tailings for construction materials - Designed concept for a Nation-Wide-Radia-
tion Dose Assessment System.
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. Chief Scientist
Dr. Russell K. Sherburne 6220 Cumberland Ave., Apt. 203 Springfield, Va. 22150
* D.O.B. 9/20/21 .- Dr. She burne received his A.3. in mathematics in 1942 from Dartmouth College,
Hanover, N.H. He received his M.Sc. in 1948 and Ph. D. in 1950. Both were in physics from Brown University, Providence, R.I. From 195C to 1959, Dr. Sherburne served as Chief Physicist and Professor of Physics at the Physical Science-Laboratory, New Mexico State University, University Park, New Mexico. From 1959 to 1963 he worked as Chief Scientist, Wite Sands Missile Range, New Mexico. From 1963 to 1965 he was Senior Staff Scientist for the Institute for Defense Analysis, Arlington, Virginia. In 1965 he became Program knager at NASA Headquarters, Wshington, D. C. In 1967 he became Senior Special- /to 1971 ist - fcience and Technology at the Library of Congress. From 1969, Dr. Sherburne provided technical consultation to NASA, DOT, DGA International and the Army Re- search Office. In 1971 he formed the firm of I.T.E., Inc. to provide technical con- sultation and service to NASA, the U.S. Naval Observatory, Harry Diamond Laboratories,
etc. Dr. Sherburne became associated with Consolidated Controls Corporation in 1978 after a career of technical management that included many projects that involve sources of ra-
diation.
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'rE . Senior Scientist
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.. Mr. Eser I. Karaoglan 4030 N. Washington Blvd., Apt. #1 Arlington, Va. 22201
D.O.B. 11/23/43 '' Fr. Karaoglan received his 3.S. in Physics from the University of Ankara in Ankara, Turkey in 1968. He received his M.S. in physics from the University of Ankara in 1970. He has completed the requirements for a PhD. at Georgetown ,
, University, Washington, D. C. From 1968 to 1970 Mr. Karaoglan worked for the International Atomic Energy Agency at - , its Ankara Nuclear Research Center in Ankara, Turkey. From 1971 to 1978 he worked
as a graduate student for Georgetown University, Washington, D. C. In 1978 he .became associated with Consolidated Controls Corporation as Senior Scientist.
| Radiation Exoerience: _ IAEA - Used 14 ME7 Neutron Generator to carry out physics ' experiments. Georgetown University - As physicist in charge of the Nuclear Physics. Laboratory, carried out experiments on 2 5 MEv van de Graar at Georgetown and on - cyclotrons at Indiana University, University of Maryland and the Naval Research laboratory.
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, Radioleirical Safetv Officer
Mr. Robert L. Flournoy 8203 Blairton Road Springfield, Va. 22152
D.O.3. 9/14/30 Mr. Flournoy received his A.B. from Iavier University in 1954 He took graduate
, work at the University of Cincinnati in 1957 in Radiological Safety. He completed additional courses in Radiological Health in 1957 and Reactor Safety in 1963 These courses were given by the U.S. Public Health Service at Cincinnati.
~ From 1956 to 1961 Mr. Flournoy was employed by the General Electric Company at its ! Aircraft Nuclear Propulsion project as an Industrial Hygienist-Health Physics ;
! Specialist. In this capacity he established working procedures for nuclear fuel processing and handling. From 1961 to 1971 Mr. Flournoy served as Assistant RSO and head of the Survey and Evaluation Section at the Naval Research I4boratory, Washington, D. C. In this capacity he established and directed all health physics I. i surveillance and evaluation programs at NRL. Coverage included a 1 ney Reactor, ; | a 2 5 meV Trituim Beam Van de Graaf, a 14 meV Neutron generator, a sector focusing
cyclotron, a 55 meV Linae and kilocurie amounts of sealed and unsealed by. product 4
1 materials. In 1976 he provided health physics services to the Metropolitan Edison Company at its Three Mile Island Reactor (Harrisburg, Penna.) during a refueling
and major maintenance operation. In 1977 he provided health physics coverage to j i the Consolidated Edison Company at its Indian Point Reactor (New York) during najor maintenance and refueling. In 1778 he provided health physics coverage at the Northern States Power Company reactor located at Redwing, Minn. during a refueling ard major maintenance outage.
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RADIATION PROTECTION PJ3UAL
CONSOLIDATED CONTROLS CORPORATION
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Prepared b ]M . 1 - :- Robert L. Flcjdrnoy #f Radiological Safety Officer Approved by: N '*/" M Charles W. Peters Project Manager
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' . . o 1- O , . ' l.0 GEERAL REQUIRIEDTS
^ 1.1 Description- .This section of the manual sets forth the radiation rules and procedures re- quired for compliance with 10 CFR 20. All procedures are in keeping with accepted Standard Health Physics practices.
1.2 Responsibilities 1.2.1. Individuals The individual worker has the following radiation protection respon-
sibilities. (1) Comply with rules and procedures set down in this manual. (2) Take special care to assure that he is free of all removable con- tamination before leaving the controlled area. (3) Correctly record his exposure upon leaving the controlled area.
- (4) Eliminate unnecessary exposure by not lingering in radiation fields
. and by utilizing existing shielding.
' (5) ' Report all wounds and skin contamination received while in the con-
trolled area to the RSO or the Project Manager. (6) Wear dosimetry devices whenever he is in the controlled area. 1.2.2. The Project Manager The Project Manager has the following radiation protection responsibilities: (1) Report any case of. skin contamination or any suspected over exposure to the RSO immediately. (2) Insure that all individuals that enter the controlled area are pro- perly equipped with dosimetry devices. (3) Assure that visitors to the facility are not subjected to project
related radiation.
1.2 3 The RSO The RSO has the following radiation protection respor.sibilities:
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-'- (1) Establish'and operate a radiation dosimetry and bioessay program
| - capable of providing sufficient data so that exposures in excess of
1 those limits' laid down in 10 CFR 20 can be avoided. 1 (2) Provide written dose-rate surveys of the controlled area and ad- joining areas to minimize exposure through the use of adequate shielding and distance. (3) Provide smear sur ays on a routine basis during periods when the neutron generator is being operated to control the spread of Tritiun contamination. (4) Providespecialsmearsurveys'NheneverItheneutrongenerator '%..- vacuum system is broken either for maintenance or to install or
remove a Tritiun target. 9- (5) Assess air borno concentrations in the control area of Tritiun '" through the use of appropriate instrumentation. (6) Assess releases of Tritiun to unrestricted area through the use of ,
appropriate instrumentation. (7) Provide sufficient training to workers to keep radiation exposures at a minimum level. (8) Maintain all records of exposure to external radiation and records of bioassay that are required by law.
2.0 AREA CONTROL
2.1 Definitions (1) Unrestricted Any area of the facility which is not controlled for purposes of protection of individuals from exposure to radiation and radioactive materials. Such areas are the offices and conference rooms on both the first floor and the mezzanine.
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i That area which can be entered only by passing through an access control point. This area normally consists of the laboratory portion of the facility and does not include the offices or conference areas. (3) -Posted Area Areas of radiation and/or contamination within the Restricted Area- which requires posting under the provisions of 10 CFR 20. 2.2 Radiation and Contamination Limits 2.2.1. Unrestricted Areas All operations will be conducted so the levels of radiation in uncontrolled areas and the concentrations of radioactive materials in effluents to unrestricted areas will be within the limits set forth in 10 CFR 20 for unrestricted areas. Removable surface contamination in unrestricted 2 2 areas will be kept below 10 dpm/100 cm alpha and 100 dpm/100 cm beta- gamma, as determined by smear tests. Beta-gamma fixed contamination will- be kept below 0.2 mrad /hr at 1 cm average measured through not more than- 7mg/cm2 of total absorber.
2.2.2. Restricted Areas
i All operations will be conducted so that the levels of radiation in occupied, restricted areas shall not result in a doce to any individual I' in excess of the limits specified in 10 CFR 20. Removable surface con- tamination will be kept at below 20 dpm/100 cm alphaand1000dpm/100cm2 beta-gamma as determined by smear tests. Restricted areas will be posted
* as noted below in part 2.2 3
I 2.2 3 Posted Areas (1) Radiation Areas Any area accessib.'' to personnel in which radiation exists, originat- . ing in whole or in part within licensed material, at such levels that
, a major position of the body could receive in any one hour a dose in
: ' excess of 5 mren, or in any 5 consecutive days a dose in excess of
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. .- < 100 mrem will be barricaded or roped and conspicuously posted with
, , the radiation symbol and the words, " Caution, Radiation Area". (2) High Radiation' Area Any area accessible to personnel in which. radiation exists, or-
iginating in whole or in part within license material, at such levels that a major portion of the body could receive in any one hour a dose in excess of 100 mrem will be barricaded or roped and con-
spicuously posted with the radiation symbol and the words, " Caution:.~ High Radiation Area".
(3) Airborne-Radioactivity Area
Any area in which airborne' radioactive materials exist in concentra- tions of 25T of the limits for restricted areas as tabulated in Appendix B. Table I, Column 1 of 10 CFR 20, will be barricaded or
~ roped and will be conspicuously posted with a magenta and yellow sign or signs bearing a radiation symbol and the words " Caution, - Airborne-Radioactivity Area". All exposed surfaces in an Airborne- Radioactivity Area are assumed to be contaminated. (4) Contaminated Area Any area accessible to personnel in which surface-contamination exists above 10 dpm/100 cm2 alpha ad/or 100 dpm/100 cm 2beta-gamma, as determined by smear tests, will be barricaded or roped and con- spicuously posted with the radiation symbol and the words, " Caution,
Contaminated Area". ; | (5) Radioactive Materials Area l
Any area accessible to personnel in which there exists radioactive ) L
materials in an amount which exceeds 10 time Appendix C, 10 CFR 20 ;
will be barricaded or roped and conspicuously posted with the ra- ; diation symbol and the words, " Caution, Radioactive Materials Area".
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b--______u . . , | . ~ 'c ~ .: 0; . O n. 2.3~ Access Control - . 'The following are requirements for access into the restricted area. For the pur-
poses of this manual all individuals are considered visitors except the Project Manager, the Project Scientists, the RSO or his designate. L (1) No visitor will be permitted to enter the restricted area while ' -| radiation is being produced by the machine (14 meV Neutron Generator). |
(2) Any individual permitted to enter the restricted area shall be , 'provided with a radia %on monitoring device (TLD). (3) Any individual permitted to enter a " Contamination Area" will wear i sufficient protective clothing to assure that his personal clothing and/or his body are not contaminated above 10 dpm/100 cm alpha and/ or 100 dpm/100 cm beta-gamma of removable contamination as deter . mined by smear tests. (4) No visitor will be permitted to enter a " Contaminated Area". ' (5) No individual will be permitted to enter an " Airborne Radioactivity Area" without a . contained breathing device. (6) Visitors must be escorted by Project personnel whenever they enter the restricted area. 3 0 Personnel Protection and Control 31 Indoctrination (1) All personnel, other than escorted visitors, must be indoctrinated in radiological safety, security, the handling of emergencies and
fire-protection. (2) All personnel, other than escorted visitors, must read and certify that they have read, understand, and agree to follow the provisions of this manual.
3 2 Permissible Accumulated Dose (PAD) 3 2.1. External Dose - Nhole Body. Mead and Trunk. Active Blood Forming Orcans, Iens 3 2.1.1. , i
- of Eves, or Gonads
. . . w_ _ - _ _ -__ _ _ _ . _ .__ . ______. _ - _ _ - _ _ _ .. .. . - - - __ 6- ' G .. rn \ ) e per=issiblo accumuisted doso (FAU) ,to thOs3 Most critic 21 . Ii organs shall not exceed 1.25 rem in any calendar quarter. . This ,
(, quant 2.ty dose-limit may, under special circumstances, be in- sased to 3 rem / quarter calendar year provided it can be dem-- -.strated that the dose, d en added to the individuals permiss- ible accumulated dose, does not exceed
PAD = 5(N-18) rem dere N equals the individuals age at his last birthday and is greater than 18. 3 2.1.2. Skin of the Wole Body The dose in any calendar quarter to the skin of the W ole body shall not exceed 7 5 rem. 3 2.1 3 Hands and Forearms. Feet and Ankles The dose in any calendar quarter to the hands and forearms and/o2
- feet and ankles shall not exceed 18 75 rems. Note: " Calendar Quarter" as used in this manual is defined in 10 CFP. 20. 3 2.2. Medical Dese Fxposure to ionizing radiation for medical reasons shall not be recorded on the radiation record. However, exoosures received for medical reasons should be reported to the RSO. 323 Dnergenev Ercosures It is possible that emergencies may arise in Wich over exposure may be accepted in order to prevent serious bodily injury. An emergency dose of
25 rems or a fraction of this dose to the whole body or a major portion ; thereof,cccurring only once in a lifetime of an individual, may be accepte: under extreme circumstances. 3 2.h. Miners (individuals under 18 years of age) will not be permitted to enter the restricted area of the facility or to receive a dose of ionizing ra-
diation from the restricted area. Minors will only be permitted in the 37513
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' ' unrestricted area. or= the facility if escorted by ,n . employee of the facility.
- 325 Exposure to the Unborn Fetus
I- "n '' Instruction to female workers will be given prior to assignment to work
in the restricted area. These instructions shall include problems asso- ciated 4th. prenatal exposure risks to the developing embryo and fetus. The instruction will insure that the female worker understands:- (1) that the NCRP has recommended that, during the entire gestation period, the maximum permissible dose equivalent to the fetus from occupational ex- posure of the expectant mother should not exceed 0 5 rem and'(2) the reasons for this recommendation as defined in Regulatoy Guide 8.13. . 3 2.6. Internal Exoosure' Individuals L11 not be exposed to concentrations of radioactive material in excess of those defined in 10 CPR 20.
~ 33 Personnel Monitoring Techniones
331.- Dcternal Monitoring
~ External monitoring.'is accomplished using TLD, direct reading dosimeters and neutron film badges. Official exposure is obtained from the TLD results (beta and gama). for whole_ body and skin of the whole body and u | . . - . - from the film badge (neutron) for whole body. | 3 3 2 . Internal Monitoring Internal monitoring for beta emitting radioisotopes (specifically tritium). is accomplished by urinalysis. The time and frequency is determined by the Radiological Safety Office. 34 Personnel Contamination Control The following are methods employed by Consolidated Controls Corporation, Iorton laboratory to protect personnel from radioactive contamination. 3 4.1. Protective Clothing
The use of protective clothing and the proper procedure for exiting a _
. Contamination Area at a designated exit point with protective clothing
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_ 3 4.2. Protective Ecuipment (Supplied Air Hoods) The use of supplied air breathing apparatus is detailed in Appendix "A" of this manual. 4.0 Eauiment Control
The purpose of equipment control is to prevent the spread of radioactive con-
tamination into unrestricted areas from restricted areas. The release of tools and equipment from posted contamination areas to clean areas may be permitted only after it has been demonstrated that removable surface con- tamination 1:. 100dpm/100cm of beta-gamma contamination and that beta-gamma fixed contamination is less than 0.2 a ad/hr at lem from the surface as measured throty;h not more than 7 mg/cm af total absorber. Liquids and solids that contain radioactive materials must meet the requirements of 10 CFR 20 and 10 CFR 30 for non-license material before an unconditional re- lease can be given. Any material which does not meet the above is handled as radioactive material and requires by-product license verification and compliance with The Department of Transportation (DOT) regulations for removal and shipment off-site.
50 Radioactive Material Handling Procedures for the handling of radioactive materials such as vaste shipments, target handling, source receipt and shipnent, etc. are covered in Appendix 3 cf this manual.
6.0 Radiati_on Occurrences ; 6.1 General
A course of action is required to deal with radiation occurrences. This
is necessary to determine compliance with licenses and regulations, and to de- termine the adequancy of the radiation protection program. Outlined below are ' the criteda and reporting requirements and the course of action necessary.
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' ... 6.2 Criteria for' Judging Radiation Occu p ences f Radiation occurrences are events involving radioactive materials or radiaticn. - They are events not normally expected and therefore not normally anticipated. They can result from rule violations and carelessness. In general they consist oft (1) Unexpected contamination (personnel and area) (2) Unexpected high radiation exposures. (3) Unexpected internal deposition of radioactive material. (4) Unauthorized radioactive material release to the environment
outside the facility. (5) Unexpected release of radioactive materials inside the facility. (6) Loss of radioactive materials. 6 3 Reporting Radiation Occurrences Each individual has the responsibility to report detected radiation occurrences to the Radiological Safety Officer or his designate. . ! 6.4 Action Required, '" The R60 or his designate will indicate the action to be taken in the event a .,i radiation occurrence takes place. He will make all notifications required by the conditions of the NRC issued license and comply with both federal, state and -local laws and regulations which cover such events.
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| ! A P P E N D I X "A"
PROTECTTIE CLOTHr!G AND EQUIPME47
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' _ _ _ _ - ____- - - _ _ _ _ _ . - ___ .. + o - 11 - o a- 1.0 : General Di'seussion . This appendix'is designed to list the anti-C protective clothing and equip - ment used at the Consolidated Controls Corporation, I.orton Laboratories in con- . junction with the operation of a 14 meV neutron generator. Policies and proce- dures governing the use of anti-C clothing and equipment are also outlined herein. The intent of using anti-C clothing and equipment is to keep personnel and their - personal effects free from radioactive contamination and to control the spread of contamination from posted areas.
2.0 Clothine Tyres
2.1 Coveralls - Coveralls are worn whenever a posted contamination area must be entered for any reason- other than visual inspection. Only personal under garments may be worn with coveralls. '2.2 Lab Coats - Lab coats are worn whenever the restricted areas are entered. 23 Cloth Gloves - Cloth gloves are worn whenever a posted contamination
' area is entered.
, 2.4 Rubber Gloves - Rubber gloves are worn whenever work is performed on the designated target area of the machine (14 meV neutron generator). A thin pair of cloth gloves are worn beneath rubber gloves. NOTE: Rubber gloves are to be taped at wrists whenever they are used in connection with the handling of a tritium target. NOTE: Dosimetry devices are to be worn inside coveralls to protect them from contamination. 30 Clothing Removal Procedure:
31 Removing I.ab Coats - Care must be taken when removing lab coats: (a) To leave the lab coat at the designated point inside the restricted area. (b) To remove dosim4.try devices from the leb coat whenever the lab coat is
taken off. 32 Removine Coveralls - Coveralls should be removed at the edge of the posted
contamination area and deposited in a plastic lined drun provided for that
= purpose. Care should be exercised to prevent the spread of conta::ination i 3?513 .. t - . . _ - _- _ - _ - ______.
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- - ways be removed from the body inside-out. Dosimetry devices are removed before dspositing coveralls in the plastic lined drum. 33 Gloves Removal - Gloves (rubber or cloth) should be removed inside-out and. carefully be placed in the disposal container placed for that purpose at the edge of the posted contamination area.
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APPENDIX "3."
OPERATIC'IS
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' ' #. 1.0 -General Discussion
| The purpose of this appendix is to describ'e'in detail operations which have . radiological safety implications. That is, these operations could result in significant radiation doses to participants, the release of airborne radio- active contaminants to unrestricted areas or the spread of surface contamin- ation in the event of a mishap. The operations thus far planned that would fit in tne above described category would bes (a) Target loading or unloading and 1 (b) Operation of 14 meV machine with ~R target.
2.0 Target Loading
2.1 Initial Leading 2.1.1. Place target container in glove box. 2.1.2, Place glove box on the target port of the accelerator drift tube. . 2.13. Turn on the blowers to provide a continuous negative pressure to ' the glove box. . 2.1.4. Open the target container using the glove box gloves. A pair of cloth gloves must be worn inside the glove box gloves. 2.15. Remove the target from the target container using a tweezer. Never touch the target by hand. 2.1.6. Place the target inside the grooves of the target holder port and close the port immediately. Seal the port for vacuum. 2.1 7. Turn on the fore vacuum pump 2.1.8. Exhaust tha glove box for at least 20 minutes before removing the
glove box from the target port of the accelerator drift tube. 2.1 9. Smear check all exposed surfaces in the vicinity of loading operations. 2.1.10 Submit urine samples as required by the Is.boratory Bioassay Program.
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*' 2.2 Exchange of Targets
L2.2.1. Place target containar and a paper napkin and a plastic bag.in the . glove box.
2.2.2. Place glove box on the target port of the accelerator drift tube. Seal off the glove box. 2.2 3 Turn.on the blovers-to provide a continuous negative pressure to the glove box. 2.2.4. Open the target container using the glove box gloves. 2.2 5 Remove the old target with a tweezers and place it on the paper napkin inside the glove box. 2.2.6. Place the new target inside the grooves of the target holder port and close the port immediately. Seal the port for vacuum. 2.2 7 Place the old target in the target ' container and seal the container. 2.2.8. Insert the paper napkin in the plastic bag using the tweezers. ..
Put any other trash from the glove box in the plastic bag. Put the
' tweezers in the plastic bag. 2.2 9 Turn on the fore vacuum pump.- 2.2.10. Exhaust the glove box for at, least 20 minutes before removing the
glove box from the target port of the accelerator drift tube. 2.2.11. Smear check all exposed surfaces in the vicinity of loading operations.
30 Kachine Ooeration It is anticipated that the neutron generator (machine) will operate normally 7 below its design output. Normal operation will result in an output of 10 neutrons ! per sec. Any operation which results in a flux above this number will only be permitted after surveys have been made to assure that human exposures will
remain within statuatory limits. 31 !!ormal Ooerations |~ j 3 1.1. Access - Access to the restricted area during nornal machine operation ; .. _ _ - _ _ . _ _
' 'O; - te - O: ln. e .<; . _! I- :* - 'will be limited to employees of Consolidated Controls Corp. who have a
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- legitimate need to enter the area. 3 1.2. Desimetry - Anyone entering the restricted area during normal machine operation rust be equipped with TLD and a neutron film badge. . Dosimetric
devices are worn on the trunk of the body. 313 Machine Adjustments - No adjustment may be made to the machine or its essential parts while the machine is operating in a mode which produces
neutrons. 3 1.4. Surveys - Surveys to establish isodose-lines and define " Posted areas" are made weekly during times when the machine is operated to produce neutrons. Additional surveys wil.:. be made whenever the machine is re- started to produce neutrons after a shut down. 32 Non-Routine Ooerations
" ' Non-routine operations are defined as those that' will result in the production of neutron output of greater than 10 7neutrons /sec. , 3 1.1. Access - Access to various parts of the facility will depend on the re- sults of instrument surveys made at the start of the operation. . During such operations, the restricted area vill be adjusted to encompass all
| areas,shown to be above 2 neutrons /cm per second. 3 2.2. Operational Plan - Any non-routine operation must be covered by a written 1' | operational plan developed, reviewed and approved prior to the operation. Review is accomplished by the RSO or his designate. Approval is given by the Project Manager. 323 Surveys - Surveys to estaolish isodose lines and define restricted and posted areas must be made whenever a non-routine operation is carried
out.
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APPENDIX "C"
RADIOIDGICAL SIRVEYS
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1.0 Radiological Surveys '
. The purpose of making radiological surveys is to insure against the uncon-
trolled spread of radioactive contamination and to prevent unnecessary exposure
' of individuals to ionizing radiation. *-
2.0 Area , Surveys 2.1 Smear Survevs - Smear surveys are made weekly of the entire facility. Addi- tional surveys are made whenever the vacttum is broken on the machine in such
a way as to be able to release tritium fron the nachine. Smear survey re-
ports are kept on file. 2.2 Instruyent Survevs - Instrument Surveys (Fast Neutron) are nade whenever the nachine is restarted to produce neutrons and on a routine weekly basis. The
results of instrunent surveys are recorded and kept on file. - 23 Air Samoline - Air samples consisting of bubbling air through water willbe
i taken in the restricted area on a weekly basis and whenever work is performed on the machine that requires breaking the machine vacuum. Such air samples will be analyzed using liguid scintillation counting and computed :encentra-
tions recorded and kept on file.
30 Bicassay Surveys
' 31 Routine survevs - Routine bicassay surveys will be made on a weekly basis
while tritium targets are used. 32 Non-Routine Survevs - Bioassay sautples will be obtained prior to any work that- directly involves the handling of the tritium target. Additionally, anyone involved directly in the handling of tritium targets must submit at least a 10cc portion of second void after the work is completed for bioassay analysis.
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APPENDIX "D"
| RADIOIDGICAL INSTRUMrJTATION
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. 'l. 0. General The purpose of this apoendix is to identify the instm: mentation used at f - the Consolidated Controls Corporation Iorton laboratory for Radiological Safety purposes. In addition, instrument calibration is discussed. Method, frequency and standards used in calibrating the instruments are given. 2.0 Neutron Survev Instrumentation A Texas Nuclear Model 5 9175 Neutron Log Count Rate-Meter is used to es- tablish isodose lines during the operation of the 14 meV neutron generator.
The::e lines are routinely checked whenever the machine is re-started after shut I down and when adjustments are made on the machine that could effect its output.
2.1 Calibration
The neutron count rate-meter vill be calibrated by nenbers of the University of Maryland Physics Department. Calibration vill be accomplished by com- paring the CCC instrument to an instrument whose respranse has already been established. A 14 meV neutron generator vill be used as a source of neutron for this calibration. Incidentally, the proposed project for which the CCC machine vill be used entails quantification of the recoil alpha particles ' incident to the deuterium - tritium reaction. A relationship between the number of neutrons produced and the detected alpha particles vill be drawn and utilized often to verify the proper operation and calibration of the neutron log count rate-meter. The minimum interval between calibrations vil
be one year. 30 Seta-Gama Survev Instrumentation An Eberline Model E-1205 portable beta-gamma geiger counter with an fiF-190
end vindow hand probe is used to make beta-ganma surveys. 31 Calibration .. The geiger counter will be initially calibrated by the factory (Eberline
- Instrument Corporation). Upon receipt the calibration vill be verified by 137 comparison with a 10 uei and a 100 uci Cs source. These sources will be . purchased from Isotote Products. Inc. ,Surbank, California. They will be
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, N- established in a fixed geometry to facilitate future calibration. Records
w E.* . ill be kept of all calibrations. A curve will be developed using the
-At . , ' formula A = Ao e where
A is the activity of the source at some original time o L A is the activity remaining after a time interval, t ; e is the base of natural logarithms
m. A is the decay constant for the particular radioisotope ! L t is elapsed time
; This curve will be used each time the instrument is calibrated to correct for decay. 4.0 Contamination Assav Instrumentation
. An Eberline Model PAC 4G with a Model TP-1 tritium probe and a Model SH-5 : l i sample holder will be used.to assay tritium surface contamination smears
- 3- ('4hatman 41). - 4
4.1 countine Efficienev i r i Counting efficiency and background will be established at least once each ; day when the instrument is used. Records of both will be maintained. j .55 137 Certified test sources ( Fe and Cs) obtained from Isotope Products, | i Incorporated will be used for this purpose.
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APPDIDIX "E"
CONSOIZDATED CO:JTROLS CORPORATION
IDRTON M30RATORY
THE FACIIITY
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.,. The facility occupies an area 48' x 48' in the Northeast corner of an in-
'' ~dustrial building. The remainder of the building is used primarily for warehousing operations. The one exception to this consists of a display repair operation which is housed on the second floor immediately to the west of the CCC facility. The building is located in an industrial park (See Figure No.1). , The firstifloor of the facility is divided in half north to south. The east half and the south one-third of this floor form a single room. The east half is two stories (20') high. The remainder of the south one-third of the facility is divided into two stories. The northwest two thirds of the first floor has been partitioned with standard vall board into office area (See Figures 2 and 3). The second floor of the facility consists of a mezzanice that runs the length of the facility from north to south. This area is used for CCC offices and con- forence rooms. The entire area is 48' x 24'. The hi-bay area on the eastern side of the facility is equipped with a ceiling : fan which operates at 500 C.TM. A flexible exhaust line will be attached from this fan to a dry box that is used to store any tritium target on hand and not mounted in the machine. The building is of masonry construction with a conerste slab roof. It has no basement and sits on a concrete slab poured directly on the ground. The north and east sides of the facility are faced outside with brick. An 8' wide metal roll-up
door is centered on the north side of the facility.
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