S30 - i7-os DECOMMISSIONING PLAN CE WINDSOR SITE 2000 DAY HILL ROAD WINDSOR, CONNECTICUT 06095 Preparedfor: Combustion Engineering, Inc. 2000 Day Hill Road Windsor, Connecticut 06095 Preparedby: MACTEC Constructors Golden, Colorado 80401 April 2003 @/MACTEC, Inc. information in this record was deieted in accordance with the Freedom of Information Act, exemptions i. :D- / FOIA BA ,33coar zJIJ;/1 4300.5 ' 4 .00.11 7-6, DECOMMISSIONING PLAN CE WINDSOR SITE 2000 DAY HILL ROAD WINDSOR, CONNECTICUT 06095 Preparedfor: Combustion Engineering, Inc. 2000 Day Hill Road Windsor, Connecticut 06095 Preparedby: MACTEC Constructors Golden, Colorado 80401 April 2003 4/MACTEC, Inc. /33 a0s zJ^J)/X;; ~,4 i OV --I DECOMMISSIONING PLAN CE WINDSOR SITE WINDSoR, CONNECTICUr US NRC LICENSE NUMBER 06-00217-06 DocKET NUMBER 030-03754 (APRIL 4, 2003) 1 2 3 0 0 5 tF.Sw!,-,^,I MATERIALS -C2 TABLE OF CONTENTS SECTION TITLE PAGE NO. List of Tables ........................ v List of Figures .................... vi List Of Effective Pages ........................ Vii Abbreviations and Acronyms .......................... x References .......................... xii 1.0 EXECUTIVE SUMMARY . .......................... -- 1-1 1.1 SITE AND LICENSEE INFORMATION .1-2 1.2 SUMMARY OF LICENSED ACTIVITIES .1-2 1.3 NATURE AND ExTENT OF SITE CONTAMINATION............................................................ 1-2 1.4 DECOMMISSIONING OBJECTIVE .1-3 1.5 SITE SPECIFIC DCGLS .1-3 1.6 ALARA ANALYSIS .1-.................................................4 14 1.7 START AND END DATES ................................................. 1-4 1.8 POST-REMEDIATION ACTIVITIES ................................................. 1-4 1.9 AMENDMENT TO LICENSE TO INCORPORATEDP .1-4 2.0 FACILITY OPERATING HISTORY....................................................................... 2-1 2.1 LICENSE NUMBER, STATUS, AND AUTHORlIE ACTIVITIES . .2-1 2.2 LICENSE HISTORY .. 2-1 2.3 PREVIOUS DECOMMISSIONING ACTIVITIES .. 2-2 2.3.1 Building 21 .................................. 2-2 2.3.2 Building Complexes 2, 5, and 17 .................................. 2-2 2.4 SPILLS .. 2-2 3.0 FACILITY DESCRIPTION . ........................ 3-1 3.1 SITE LOCATION AND DESCRIPTION .3-1 3.2 POPULATION DIBUTIoN..3-1 3.3 CURRENT AND FUTURE LAND USE .3-3 3.4 GEOLOGY .3-3 3.5 HYDROGEOLOGY. 3-4 3.6 SURFACE WATER HYDROLOGY .3-5 3.7 ECOLOGY/ENDANGERED SPECIES .3-6 4.0 RADIOLOGICAL STATUS OF TIE FACILITY. 4-1 4.1 CoNTAMINATED STRUCTURES .. 4-1 4.1.1 Building 2 Complex ........................................ 4-2 4.1.2 Building 5 Complex ........................................ 4-5 4.1.3 Building 17 Complex ........................................ 4-9 4.1.4 Building 6A Complex ........................................ 4-12 4.2 CONTAMINATED SYSTEMS AND EQUIPMENT ...................................... 4-14 4.2.1 Industrial and Radiological Waste Lines ........................................ 4-14 4.2.2 Sanitary Waste Lines ........................................ 4-17 4.2.3 Storm Water Lines ........................................ 4-19 4.2.4 Underground Utilities ........................................ 4-20 4.3 SURFACE AND SUBSURFACE SOIL CONTAMINATION . ................................4-20 4.4 SURFACE WATER ................................... ...... 4-20 4.5 GROUNDWATER ...................................... 4-22 Decommissioning Plan Page i Revision 0 CE Windsor Site April 2003 TABLE OF CONTENTS SECTION TITLE PAGE NO. 5.0 DOSE MODEING................................................................................................. 5-1 6.0 ALTERNATIVES CONSIDERED AND RATIONAL FOR CHOSEN ALTERNATIVE .......... 6-1 7.0 ALARA ANALYSIS....................................................................................................7-1 7.1 INTRODUCTION .. 7-1 7.2 DETERMINATION OF BENEFITS .. 7-2 7.2.1 Collective Dose Averted Benefit .7-2 7.2.2 Regulatory Cost Avoided Benefit .7-2 7.2.3 Changes in Land Value Benefit .7-2 7.2.4 Esthetics Benefit .7-3 7.2.5 Reduction in Public Opposition .7-3 7.3 DETERMINATION OF COSTS.. 7-3 7.3.1 Determination of Total Costs .7-3 7.4 DETERMINATION OF RESIDUAL RADioAcrmTy LEVELS THAT ARE ALARA .. 7-5 7.4.1 ALARA Analysis .7-5 7.5 CONCLUSION .. 7-7 8.0 PLANNED DECOMMISSIONING ACIVITIES ................................... 8-1 8.1 CONTAMINATED STRUCTURES . .8-1 8.1.1 Building Demolition .8-1 8.1.2 Radiation Protection Methods .8-2 8.1.3 Structural Steel Removal ................................. 8-2 8.1.4 Concrete, Masonry and Pavement Removal .8-2 8.1.5 Procedures Authorized Under Existing License .8-3 8.1.6 Decontamination Techniques .8-3 8.2 CONTAMINATED SYSTEMS AND EQUIPMENT . .8-4 8.2.1 Remediation Tasks .8-4 8.2.2 Decontamination Techniques .8-4 8.2.3 Radiation Protection Methods .84 8.2.4 Equipment to be Removed. 84 8.2.5 Procedures Authorized Under Existing License. 84 8.2.6 Use of Procedures .8-4 8.3 SOIL AND SUBSURFACE UTILITIES . .8-5 8.3.1 Removal/Remediation Tasks .8-5 8.3.2 Techniques Employed to Remove or Remediate Surface and Subsurface Soil.8-5 8.3.3 Radiation Protection Methods .8-5 8.3.4 Procedures Authorized Under the Existing License .8-5 8.3.5 Use of Procedures .8-5 8.4 SURFACE AND GROUDwATER . .8-5 8.4.1 Remediation Tasks Planned for Ground and Surface Water .8-5 8.5 SCHEDULES . .8-5 9.0 PROJECT MANAGEMENT AND ORGANIZATION .9-1 9.1 DECOMMISSIONING MANAGEMENT ORGANIZATION . .9-1 9.2 DECOMMISSIONING MANAGEMENT POSITIONS AND QUALIFICATIONS . .9-1 9.2.1 Project Manager .9-1 Decommissioning Plan Page ii Revision 0 CE Windsor Site April 2003 TABLE OF CONTENTS SECTION TITLE PAGE No. 9.2.2 Site Manager ................................... 9-1 9.2.3 Site Health, Safety & Radiological Safety Officer ................................... 9-1 9.2.4 Quality Assurance Manager....................................................................................9-3 9.2.5 Radiation Safety Officer ................................... 9-3 9.3 DECOMMISSIONING TASK MANAGEMENT . .9-3 9.4 TRAINING .. 94 10.0 RADIATION SAFETY AND HEALTH PROGRAM DURING DECOMMISSIONING.........................................................................................10-1 10.1 RADIATION SAFETY CONTROLS AND MONITORING FOR WORKERS .10- 10.1.1 Workplace Air Sampling Program . 10-1 10.1.2 Respiratory Protection Program . 10-2 10.1.3 External Exposure Determ ination.........................................................................10-3 10.1.4 Internal Exposure Determination . 10-4 10.1.5 Summation of External and Internal Exposures . 10-4 10.1.6 Contamination Control Program . 10-4 10.1.7 Instrumentation Program......................................................................................10-6 10.2 NUCLEAR CRITICALITY SAFETY . 10-7 10.3 HEALTH PHYSICS AUDITS, INSPECTIONS AND REcoRD-KEEPING PROGRAM ........... 10-7 11.0 ENVIRONMENTAL MONITORING AND CONTROL PROGRAM . 11-1 11.1 ENVIRONMENTAL ALARA EVALUATION .. 11-1 11.1.1 Management Commitment . 11-1 11.1.2 Procedures, Process Controls, and Engineering Controls . 11-2 11.1.3 ALARAReviews . 11-2 11.2 EFFLUENT MONITORING PROGRAM .. 11-2 11.2.1 Baseline Concentrations . 11-2 11.2.2 Expected Concentrations ............................ 11-2 11.2.3 Physical and Chemical Characteristics .11-2 11.2.4 Discharge Locations .11-2 11.2.5 Sample Collection and Analysis . 11-3 11.3 EFFLUENT CONTROL PROGRAM .. 11-3 11.3.1 Procedures, Process Controls, and Engineering Controls .11-3 11.3.2 Action Levels .114 11.3.3 Releases to Sanitary Sewer .11-5 11.3.4 Estimates of Doses to the Public .11-5 12.0 RADIOACTIVE WASTE MANAGEMENT PROGRAM .12-1 12.1 PROGRAM DESCRIPTION .. 12-1 12.2 WASTE SEGREGATION ......................... ... 12-1 12.2.1 Management of Mixed and LLW .12-2 12.3 WASTE PACKAGING .. 12-3 12.4 DISPOSAL FACILITY .. 12-4 12.5 LICENSED MATERIAL INVENTORY AND ACCOUNTABILITY . 12-4 13.0 QUALITY ASSURANCE PROGRAM .13-1 13.1 D&D CONTRACTOR ORGANIZATION . 13-1 13.2 QUALITY ASSURANCE PROGRAM .13-1 Decommissioning Plan Page iii Revision 0 CE Windsor Site April 2003 TABLE OF CONTENTS SECTION TITLE PAGE No. - 13.3 DOCUMENTCONTROL ....................................... 13-2 13.4 CONTROL OF MEASURING AND TEST EQUIPMENT ................................. 13-3 13.5 CORRECTIVE ACTION ................................. 13-3 13.6 RECORDS ................................. 13-4 13.7 AUDITS AND SURVEILLANCES ................................. 13-4 13.8 PROGRAM CHANGES ....................................... 13-4 14.0 FACILITY RADIATION SURVEYS ................................. 14-1 14.1 RELEASE CRITERIA . .14-1 14.2 CHARACTERIZATION SURVEys . ..................................14-1 14.3 REMEDIAL ACTIoN SUPPORT SURVEYS . .14-1 14.3.1 General .14-1 14.3.2 Survey Design .14-2 14.3.3 Conducting Surveys .14-2 14.3.4 Evaluating Survey Results .14-2 14.4 FINAL STATUS SURVEY DESIGN . .14-2 14.4.1 Overview..4-2 14.4.2 Investigation Levels ....................................... 14-6 14.4.3 Instruments and Methods ............................................... 14-6 14.4.4 Reference Areas ............................................... 14-6 14.4.5 Reference Coordinate System ............................................... 14-6 14.4.6 Summary of Statistical Tests ....................................... 14-7 14.4.7 Control and Handling of Samples for Laboratory Analysis ................................. 14-7 15.0 FINANCIAL ASSURANCE .15-1 Decommissioning Plan Page iv Revision 0 CE Windsor Site April 2003 List of Tables Table 2-1 Authorized Radionuclides NRC License No. 06-00217-06 CE Windsor Site, Windsor Connecticut