ML20057E081
| ML20057E081 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/29/1993 |
| From: | Fairtile M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9310070250 | |
| Download: ML20057E081 (29) | |
Text
.
September 29, 1993 Docket No.50-029 i
LICENSEE:
YANKEE ATOMIC ELECTRIC COMPANY FACILITY:
YANKEE NUCLEAR POWER STATION i
SUBJECT:
MEETING
SUMMARY
OF SEPTEMBER 22, 1993 On Wednesday, September 22, 1993, at the NRC headquarters in Rockville, Maryland, the staff met with Yankee Atomic personnel. The licensee requested i
4 this meeting in order to update the staff on the status of the preparation of l
the Yankee Rowe decommissioning plan (D-Plan) and of the Component Removal Program.
Currently, the licensee has removed the first steam generator (SG) from the containment and plans to make the first shipment of two SGs to the i
low-level waste disposal facility at Barnwell, South Carolina in mid-November l
1993.
Yankee committed to notify local police in advance of SG shipments and to notify state authorities in advance of all radioactive waste shipments.
The licensee plans to submit the D-Plan to the NRC by the end of 1993.
For i
planning purposes the licensee has scheduled site dismantlement for the year 2000 and fuel transfer from the spent fuel pool to an onsite dry storage facility in 1996.
The staff questioned the licensee about the site industrial safety programs that are required by OSHA. We were informed that such programs are managed by i
a staff headed by a Health and Safety Supervisor and that procedures are in place to implement both OSHA and Massachusetts industrial safety requirements.
The licensee presented slides in a handout entitled, " Decommissioning Plan Overview" (Enclosure 1) which described the decommissioning program and I
presented those portions that are completed and those planned for the future.
These slides also contained an outline of the accident analyses used in the D-Pl an. A second handout entitled, " Draft Decommissioning Plan Examples" (Enclosure 2) included a draft table of contents for the entire D-Plan and samples of key pages in the plan. A List of Attendees is included as.
Original signcd by:
Morton B. Fairtile, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
1 As stated cc w/ enclosures:
NN See next page O2 N X/b MM f plSTRIBUTION:
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UNITED STATES
[.T,j NUCLEAR REGULATORY COMMISSION
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September 29, 1993 t
Docket No.50-029 i
LICENSEE:
YANKEE ATOMIC ELECTRIC COMPANY FACILITY:
YANKEE NUCLEAR POWER STATION
SUBJECT:
MEETING
SUMMARY
OF SEPTEMBER 22, 1993 l
On Wednesday, September 22, 1993, at the NRC headquarters in Rockville, Maryland, the staff met with Yankee Atomic personnel. The licensee requested this meeting in order to update the staff on the status of the preparation of the Yankee Rowe decommissioning plan (D-Plan) and of the Component Removal Program.
Currently, the licensee has removed the first steam generator (SG) from the containment and plans to make the first-shipment of two SGs to the low-level waste disposal facility at Barnwell, South Carolina in mid-November 1993.
Yankee committed to notify local police in advance of SG shipments and to notify state authorities in advance of all radioactive waste shipments.
The licensee plans to submit the D-Plan to the NRC by the end of 1993. For planning purposes the licensee has scheduled site dismantlement for the year i
2000 and fuel transfer from the spent fuel m l to an onsite dry storage facility in 1996.
The staff questioned the licensee about the site industrial safety programs that are required by OSHA. We were infonned that such programs are managed by a staff headed by a Health and Safety Supervisor and that procedures are in place to implement both OSHA and Massachusetts industrial safety requirements.
The licensee presented slides in a handout entitled, " Decommissioning Plan Overview" (Enclosure 1) which described the decommissioning program and presented those portions that are completed and those planned for the future.
l These slides also containeo an outline of the accident analyses used in the D-Pl an. A second handout entitled, " Draft Decommissioning Plan Examples" (Enclosure 2) included a draft table of contents for the entire D-Plan and samples of key pages in the plan. A List of Attendees is included as l.
hk 1 bwY Morton B. Fairtile, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page I
Ms. Jane M. Grant Yankee Rowe Docket No.50-029 cc:
Dr. Andrew C. Kadak, President Chairman, Franklin County l
and Chief Executive Office Commission Yankee Atomic Electric Company 425 Main Street l
580 Main Street Greenfield, Massachusetts 03101 Bolton, Massachusetts 01740-1398 Executive Director Thomas Dignan, Esq.
New England Conference of Public Ropes and Gray Utility Commissioners One International Place 45 Memorial Circle Boston, Massachusetts 02110-2624 Augusta, Maine 04330 Mr. N. N. St. Laurent Citizens Awareness Network Plant Superintendent P. O. Sox 83 Yankee Atomic Electric Company Shelburne Falls, Massachusetts 01370 Star Route Rowe, Massachusetts 01367 Resident Inspector Vermont Yankee Nuclear Power Station Regional Administrator, Region I U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission P. O. Box 176 475 Allendale Road Vernon, Vermont 05354 King of Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Radiation Control Program i
Massachusetts Department of Public Health l
305 South Street l
Boston, Massachusetts 02130 i
l Commissioner Richard P. Sedano Vermont Department of Public Service 120 State Street, 3rd Floor Montpelier, Vermont 05602 i
Mr. Jay K. Thayer Vice President and Manager of Operations Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398 i
Mr. David Rodham., Director ATTN: Mr. James B. Muckerheide Massachusetts Civil Defense Agency 400 Worcester Road P. O. Box 1496 Framingham, Massachusetts 01701-03173
)
i l
l
YANKEE NUCLEAR POWER STATION DECOMMISSIONING PLAN OVERVIEW E!
k K. J. HEIDER k
SEPTEMBER 22, 1993
0YERYlEW PLAN STATUS PLANT PROGRAMS ACCIDENT ANALYSIS SPENT FUEL MANAGEMENT DECONTAMINATION AND DISMANTLEMENT PLANS e
RADIOLOGICAL SURVEYS (SCOPING AND CHARACTERIZATION) e e
FINAL SURVEY AND SITE RELEASE CRITERIA
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DEC_0tEISS10NIRG_ ELAN _N EAR _C_0MP LETION DRAFT STATUS CHOICE OF ALTERNATIVE AND DESCRIPTION OF ACTIVITIES DECOMMISSIONING ALTERNATIVE
/
FACILITY DESCRIPTION
/
ACTIVITIES AND PLANNING
/
ORGANIZATIONAL STRUCTURE / RESPONSIBILITIES
/
TRAINING
/
OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY FACILITY RADIOLOGICAL STATUS
/
RADIATION PROTECTION PROGRAM
/
RADI0 ACTIVE WASTE MANAGEMENT
/
ACT.19ENT ANALYSIS
/
OCCSPATIONAL SAFETY PROGRAM
/
NON-RADI0 ACTIVE WASTE MANAGEMENT
/
e MISCELLANE0US PLAN DESCRIPTIONS FINAL RADIATION SURVEY PLAN
/
COST ESTIMATE AND FUNDING PLAN
/
PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS
/
QUALITY ASSURANCE PLAN
/
ACCESS CONTROL PLAN
/
FIRE PROTECTION PLAN
/
- ~, '
v v
DECQttf1SS10NING PLAN: GEMERAL DECOMMISSIONING ALTERNATIVE: SAFSTOR UNTIL DISPOSAL FACILITY AVAILABLE DISMANTLEMENT SCHEDULED IN 2000 FOR PLANNING PURPOSES YANKEE WILL PROCEED WITH FURTHER DISMANTLEMENT IF OPPORTUNITIES ARISE
+
IMMEDIATE DISMANTLEMENT PREFERRED ALTERNATIVE
+
PLAN WRITTEN TO SUPPORT EARLIER DISMANTLEMENT PLAN WRITTEN ASSUMING STEAM GENERATORS, PRESSURIZER, AND REACTOR e
INTERNAL COMP 0NENTS REMOVED COMPONENT REMOVAL PROJECT DESCRIPTION INCLUDED IN APPENDIX ANY PROJECT CHANGES WILL BE INCORPORATED IN PLAN UPDATES e
PLAN REFERENCES MORE THAN 50 PLANT PROCEDURES CREDIT TAKEN FOR EXISTING PLANT PROGRAMS AND PROCEDURES PLANT OPERATIONS REVIEW COMMITTEE WILL REVIEW PROCEDURE MODIFICATIONS TO ASSURE DECOMMISSIONING PLAN INTENT MAINTAINED I
ESSEN11AL ELEMENTS OF PLANT PROGRAMS DESCRIBED l
l
DE0ttilSS10HIMG PLAR:__DE0ttilSSIDNING3_R0_ GRAMS RADIATION PROTECTION PROGRAM IMPLEMENTATION WILL CONTINUE PROGRAM AND IMPLEMENTING PROCEDURES SUMMARIZED 10 CFR 20 CHANGES CURRENTLY BEING IMPLEMENTED RADI0 ACTIVE WASTE MANAGEMENT INCORPORATED IN PROGRAM e
PLANT SAFETY PROGRAMS MEET THE CHALLENGES OF DECOMMISSIONING OCCUPATIONAL SAFETY PROGRAM NON-RADI0 ACTIVE WASTE MANAGEMENT PROGRAM
+
HAZARDOUS WASTE HANDLING
+
INDUSTRIAL WASTE DISPOSAL FIRE PROTECTION PLAN e
OTHER PLANS REFERENCED QUALITY ASSURANCE PLAN ACCESS CONTROL SECURITY PLAN
DEC0tfRSS10NING3_LAN;_AC.CIDERT_ ANALYSIS EPA PROTECTIVE ACTION GUIDES USED TO EVALUATE EVENT CONSEQUENCES e
WHOLE BODY 1 REM THYROID 5 REM l
SKIN 50 REM MORE RESTRICTIVE THAN 10 CFR 100 ENSURES DEFUELED EMERGENCY PLAN REMAINS ADEQUATE o
WIDE SPECTRUM 0F EVENTS ANALYZED EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY EVENTS AFFECTING PUBLIC HEALTH AND SAFETY
+
OFF-SITE EVENTS
+
ON-SITE NON-RADIOLOGICAL AND RADIOLOGICAL EVENTS RADIOLOGICAL CONSEQUENCES BASED ON CONSERVATIVE ASSUMPTIONS AND e
RADIOLOGICAL SCOPING ANALYSIS AIRBORNE RELEASES AT GROUND LEVEL WITH CONSERVATIVE DISPERSION FACTORS RELEASE OF SURFACE CONTAMINATION AND ANY LOOSE ACTIVATED BASE METAL ASSUMED
DEC0tt!ISS10NING_ ELAN;_ACfIDENLANALYSIS_ ICON ' T)
RADIOLOGICAL EVENTS THAT COULD P0TENTIALLY AFFECT PUBLIC HEALTH AND SAFETY EVALUATED DECOMMISSIONING ACTIVITIES: DECONTAMINATION, DISMANTLEMENT, PACKAGING, STORAGE, AND MATERIALS HANDLING LOSS OF SUPPORT SYSTEMS: POWER, COOLING WATER, COMPRESSED AIR FIRE AND EXPLOSIONS EXTERNAL EVENTS: SEVERE WEATHER, SEISMIC, FOREST FIRES, ETC.
SPENT FUEL STORAGE EVENTS ANALYSIS RESULTS INCORPORATED INTO DECOMMISSIONING PLAN ALL POTENTIAL CONSEQUENCES ARE SIGNIFICANTLY LESS THAN EPA PAGs DECOMMISSIONING ACTIVITY / SFP OPERATION RESTRICTIONS IDENTIFIED DECOMMISSIONING PROCESS REQUIREMENTS TABULATED WITH REFERENCES TO PLAN SECTIONS
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DEC0tf!IS.SIONINGEAR:_SP_ENI_EUEL_ MANAGEMENT e
SPENT FUEL POOL INVENTORY FUEL ASSEMBLIES FROM 1972 TO 1991 HIGH LEVEL RADI0 ACTIVE WASTE FROM COMPONENT REMOVAL PROJECT (PLANNED)
MISCELLANE0US LOW LEVEL RADI0 ACTIVE MATERIAL (E.G., RACKS, NEUTRON SOURCES)
LOW DECAY HEAT RATE REDUCES CONSEQUENCES OF LOSS OF SFP COOLING DOES NOT ELIMINATE NEED TO MAINTAIN COOLING CAPABILITY AT ALL TIMES AS OF 1/94, >4 WEEKS AVAILABLE TO RE-ESTABLISH COOLING OR TO ADD MAKE-UP WATER LESS THAN 1 GPM MAKE-UP RATE NEEDED TO REPLACE EVAPORATION LOSSES T
e STUDY COMPLETED TO DEVELOP SPENT FUEL MANAGEMENT STRATEGY:
CONTINUE SAFE SFP OPERATION AND IMPLEMENT ECONOMICALLY ATTRACTIVE ENHANCEMENTS URGE DOE TO ACCELERATE SPENT FUEL ACCEPTANCE OR TO ACCEPT FINANCIAL RESPONSIBILITY FOR ON-SITE STORAGE CONTINUE EVALUATIONS OF WET AND DRY STORAGE OPTIONS INITIATE PRELIMINARY DESIGN ACTIVITIES FOR DRY STORAGE FACILITY
DEC0fEISS10NING PLAth_SEERT_EUEL11ANAGEMERT_it0N'T)
STUDY COMPLETED TO EVALUATE INTERACTIONS BETWEEN SPENT FUEL STORAGE AND DECOMMISSIONING PURPOSE: IDENTIFY SAFETY CONSIDERATIONS AND LIMITATIONS ON DECOMMISSIONING ACTIVITIES ACTIVITIES WILL NOT BE IMPLEMENTED THAT COULD IMPACT SFP INTEGRITY OR DAMAGE FUEL e
DISMANTLEMENT ACTIVITY LIMITATIONS IDENTIFIED DELAY DISMANTLEMENT OF ION EXCHANGE PIT UNTIL FUEL REMOVED FROM SFP l
LIMIT CASK USAGE IN AND OVER THE SFP TO TECHNICAL SPECIFICATION LIMITS ISOLATE FUEL TRANSFER CHUTE FROM SFP EXCLUDE ACTIVITIES THAT COULD RESULT IN A DROP 0F A HEAVY LOAD INTO OR ONTO THE SFP OR FUEL TRANSFER CHUTE ENSURE THAT DISMANTLEMENT ACTIVITIES DO NOT RESULT IN A CONFIGURATION THAT COULD FAIL DURING AN EXTERNAL EVENT AND ADVERSELY AFFECT SFP l
e FOR PLANNING PURPOSES 1996 FUEL TiMNSFER TO A DRY STORAGE FACILITY ASSUMED l
DEC0ffilSS10 RING PLAft_DEC0NIMINAT10fLAND_DISMANILEMENT PLANS e
YAEC INTENDS TO BE DECOMMISSIONING OPERATIONS CONTRACTOR DIRECT CONTROL AND OVERSIGHT OF ALL DECOMMISSIONING ACTIVITIES SIMILAR TO POWER OPERATIONS AND COMPONENT REMOVAL PROJECT e
DETAILED IMPLEMENTATION PLANS WILL BE DEVELOPED DETAILED ENGINEERING ACTIVITIES ALARA PROGRAM IMPLEMENTATION RESOURCE REQUIREMENT ESTIMATION DECOMMISSIONING COST AND SCHEDULE REFINEMENT f
a DECOMMISSIONING WORK PACKAGES WILL BE COMPLETED FOR ALL ACTIVITIES ENGINEERING SPECIFICATIONS SIMILAR TO ENGINEERING DESIGN CHANGE REQUEST PROCESS DECOMMISSIONING IMPLEMENTING PROCEDURES I
e l
DECMtilSS10NING_fLAft_DEC0NIAMINAILON_AND_DISMANILEMENT PLANS _RON'T)
GENERIC CONSIDERATIONS DEVELOPED FOR PLANNING DECONTAMINATION AND DISMANTLEMENT ACTIVITIES, FOR EXAMPLE.
SPENT FUEL MUST NOT BE AFFECTED BY DISMANTLEMENT AIRBORNE RADI0 ACTIVITY MUST BE FILTERED AND MONITORED DURING DISMANTLEMENT
+
VC VENTILATION AND PURGE SYSTEM MUST BE IN OPERATION
+
VENTILATION SYSTEM MUST BE IN OPERATION IN VENTILATED AREAS
+
LOCAL HEPA FILTRATION SYSTEMS MUST BE USED TO CONTROL AIRBORNE RADI0 ACTIVITY VAPOR CONTAINER ISOLATION CAPABILITY MUST BE MAINTAINED CONTAMINATED LIQUIDS MUST BE PROCESSED BY THE LIQUID WASTE PROCESSING SYSTEM MECHANICAL CUTTING METHODS RECOMMENDED FOR CONTAMINATED COMPONENTS SPECIFIC CONSIDERATIONS PRESENTED FOR INDIVIDUAL PLANT SYSTEMS, STRUCTURES, AND COMPONENTS IDENTIFIES UNIQUE CONSIDERATIONS REFERENCES GENERAL CONSIDERATIONS AND SYSTEM DESCRIPTION
DECDttilSSIONIRG_ELAft__RADIDLO_GLCAL_SIDPlNG RADIOLOGICAL SCOPING COMPLETED IN SUPPORT OF DECOMMISSIONING PLAN SURVEYS INSIDE STRUCTURES
+
CONTACT AND AREA DOSES FOR PIPING, COMPONENTS, & STRUCTURES
+
LIMITED ISOTOPIC ANALYSES OF PIPE SAMPLES
+
PAINT AND CONCRETE SAMPLES FROM STRUCTURAL SURFACES SURVEYS OUTSIDE STRUCTURES
+
CORE BORINGS AND OBSERVATION WELLS
+
SURFACE SAMPLES OF ASPHALT AND S0IL
+
SURFACE GAMMA SPECTROSCOPY RESULTS SUFFICIENT TO SUPPORT DECOMMISSIONING PLAN DEVELOPMENT
?
VOLUME AND CURIE CONTENT OF RADI0 ACTIVE MATERIALS PERSONNEL EXPOSURE PROJECTION RADI0 LOGICALLY AFFECTED AREAS IDENTIFIED NUREG/CR-5849 CLASSIFICATIONS USED i
AREAS INSIDE OWNER CONTROLLED FENCE CONSERVATIVELY ASSUMED TO BE AFFECTED l
l l
DEC0fEISSIONING_PIAR;_SIIE_CHARACIERIZAILON SITE CHARACTERIZATION SURVEYS WILL BE USED TO SUPPORT DECOMMISSIONING ACTIVITIES SYSTEMS, STRUCTURES, AND COMPONENTS: SUPPORT DECONTAMINATION AND DISMANTLEMENT ACTIVITIES SOIL AND GROUNDWATER: SUPPORT DETAILED PREPARATION OF SITE FOR FINAL SURVEY SITE CHARACTERIZATION SURVEYS NOT NEEDED FOR DECOMMISSIONING PLAN e
APPROVAL SURVEYS CONSIDERED FOR SYSTEMS, STRUCTURES, AND COMPONENTS o
SURVEY CURRENTLY INACCESSIBLE AREAS TO VERIFY ASSU,MPTIONS EXPAND CONTAMINATED CONCRETE SURVEY DATABASE SURVEY REACTOR VESSEL AFTER COMPONENT REMOVAL PROJECT COMPLETED EXPAND SURVEYS OF NON-RADIOLOGICAL SYSTEMS, STRUCTURES, AND COMPONENTS
DEC_0fffISSIONIKG_PJ. Aft _ SITE _ CHARACIERIZAIL0fLiCON 'T)
.]
SURVEYS CONSIDERED FOR S0IL AND GROUNDWATER ANALYZE SOIL TO VERIFY LATERAL AND VERTICAL EY, TENT OF CONTAMINATION IDENTIFIED DURING SCOPING SURVEYS ANALYZE SOIL UNDER BUILDINGS TO THE EXTENT PRACTICABLE ESTABLISH SACKGROUND CONCENTRATION OF CESIUM-137 DEVELOP ADDITIONAL GROUNDWATER WELLS AND DEVELOP A GROUNDWATER MODEL i
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DEC0ttfISS10NING_ PIAN;_SIIE_ RELEASE _CRIIERIA SITE RELEASE CRITERIA SELECTION UNDER MANAGEMENT REVIEW ON-GOING RULE MAKING POSITIONS CONSIDERED PREVIOUS DECOMMISSIONING PLANS REVIEWED e
SURFACE CONTAMINATION LESS THAN REG GUIDE 1.86 LIMITS DIRECT EXPOSURE FROM GAMMA EMITTING RADIONUCLIDES LESS THAN 5 pR/HR e
TOTAL EFFECTIVE DOSE EQUIVALENT LIMIT FROM RESIDUAL RADIATION UNDER REVIEW 30 MREM /YR WITH SITE SPECIFIC ALARA OPTIMIZATION TO <10 MREM /YR 10 MREM /YR (CONSISTENT WITH SITE DECOMMISSIONING MANAGEMENT PLAN CRITERIA)
GROUNDWATER QUALITY INCORPORATED INTO TOTAL EFFECTIVE DOSE EQUIVALENT LIMIT 40 CFR 141 LIMITS FOR COMMUNITY WATER SUPPLIES
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DECDtEISS10NINGlLAR:_SIIE_ RELEASE _CRIIERIA_LCDW T)
CRITERIA FOR RELEASE OF MATERIALS DURING DECOMMISSIONING MATERIALS LEAVING RADIATION CONTROL AREA SURVEYED TO ASSURE RADI0 ACTIVE MATERIALS NOT INADVERTENTLY DISCHARGED MATERIALS WILL BE RELEASED IF NO DISCERNABLE PLANT RELATED RADI0 ACTIVITY WITHIN THE DETECTION CAPABILITY OF THE FOLLOWING:
+
MATERIALS & EQUIPMENT: DIRECT FRISKING WITH GEIGER-MUELLER OR GAS FLOW PROPORTIONAL DETECTOR
+
SMEAR SAMPLES: ANALYSIS WITH GEIGER-MUELLER OR GAS FLOW PROP 0RTIONAL DETECTOR
+
BULK LIQUIDS AND SOIL: ANALYSIS WITH HIGH RESOLUTION GAMMA SPECTROMETRY TO ENVIRONMENTAL LOWER LIMITS OF DETECTION CRITERIA CONSISTENT WITH NRC GUIDANCE e
FINAL SURVEY METHODOLOGY METHODOLOGY WILL BE CONSISTENT WITH DRAFT NUREG/CR-5849 DETAILED PLAN AND PROCEDURES WILL BE DEVELOPED PRIOR TO FINAL SURVEY
l esemsuae 2 I
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i YANKEE NUCLEAR POWER STATION DECOMMISSIONING PLAN OVERVIEW i
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DRAFT DECOMMISSIONING PLAN EXAMPLES 4
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K. J. HEIDER SEPTEMBER 22, 1993 l
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DRAFT TABLE OF CONTENTS e
i J
j YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS 1.
SUMMARY
OF PLAN 1.1 Description of Decommissioning Plan and Decommissioning Alternat;ve........
1.1-1 1.1.1 Introduction...
1.1-1 1.1.2 Background.
1.1-2 1.1.3 Contents of the Decommissioning Plan..
1.1-3 l
1.2 Major Tasks, Schedules, and Activities....................
1.2-1 1.2.1 Description of Major Activities...........
1.2-1 1.2.2 Final Release Criteria 1.2-5 1.2.3 Schedule for Decommissioning Activities.........
1.2-5 1.3 Decommissioning Co3t Estimate and Availability of Funds...
1.3-1 i
1.3.1 Decommissioning Cost........
1.3-1 1.3.2 Funding Plan.
1.3-1 1.4 Regulatory Basis for Administration of the Decommissioning Plan 1.4-1 i
1.5 Adminstrative Controls During the Transition Period Prior to Approval of the Decommissioning Plan..............
1.5-1 2.
CHOICE OF DECOMMISSIONING ALTERNATIVE AND DESCRIPTION OF ACTIVITIES 2.1 Alternative Selection and Justification.....................
2.1-1 2.1.1 Decommissioning Alternative......................
2.1-1 2.1.2 Decommissioning Alternative Justification...........
2.1.1 2.2 Facility Description.........
2.2-1 2.2.1 General Description.
2.2-1 2.2.2 Reactor Vessel................
2.2-1 2.2.3 Steam Generators 2.2-3 2.2.4 Main Coolant System.
2.2-3 i
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YNPS DECOND11SSIONING PLAN REVISION: D.4 i
TABl E OF CONTENTS 2.2.5 Pressure Control and Relief System.................
2.2 4 2.2.6 Charging and Voiame Control System 2.2-4 2.2.7 Chemical Shutdown System.......................
2.2-5 2.2.8 Purification System..............................
2.2-5 2.2.9 Component Cooling Water System............
2.2-5 2.2.10 Primary Plant Corrosion Control System.
2.2-6
.2.2.11 Primary Plant Sample System...
2.2-6 2.2.12 Waste Disposal System...
2.2-7 2.2.13 Shutdown Cooling System.....
2.2-9 2.2.14 Primary Plant Vent and Drain System....
2.2-9 2.2.15 Emergency Core Cooling System 2.2-9 2.2.16 Radiation Monitoring System......................
2.2-10 2.2.17 VC Ventilation and Purge System....................
2.2-13 2.2.18 VC IIeating and Cooling System............
2.2-13 2.2.19 Post-Accident Hydrogen Control System 2.2 14 2.2.20 Containment Isolation System..
2.2-14 2.2.21 Fuel Handling Equipmert System........
2.2-14 2.2.22 SFP Cooling and Purification System...........
2.2-15 2.2.23 Main Steam System...........
2.2-16 2.2.24 Feedwater System 2.2-16 2.2.25 Steam Generator Blowdown System..
2.2-16 2.2.26 Emergency Feedwater System....
2.2-17 2.2.27 Service Water System............................
2.2-17 2.2.28 Demineralized Water System......................
2.2-18 2.2.29 Compressed Air System...............
2.2-18 2.2.30 Electrical System...............
2.2-19 2.2.31 H eating System................................
2.2-20 2.2.32 Ventilation Systeu 2.2-20 2.2.33 Fire Protection and Detection System................
2.2-21 2.2.34 Primary Pump Seal Water System...................
2.2-21 2.2.35 Safe Shu tdown System...........................
2.2 2.2.36 Water Cleanup System...........................
2.2-22 2.2.37 Vapor Container......................
2.2-22 2.2.38 Reactor Support Structure...
2.2-24 2.2.39 Vapor Container Polar Crane......................
2.2 24 I
2.2.40 Radiation Shielding...........
2.2-25 2.2.41 Neutron Shield Tank...........................
2.2-26 2.2.4 2 Pipe Chases...................................
2.2-27 2.2.43 Fu el Transfer Chu t e.............................
2.2-27 2.2.44 Yard Area Crane and Supprn Structure..............
2.2-28 11
YNPS DECOMMISSIONING PIAN REVISION: D.4 t
TABLE OF CONTENTS 2.2.45 Ion Exchange Pit 2.2-28 2.2.46 Primary Vent Stack.............................
2.2-29 2.2.47 Spent Fuel Pit and Spent Fuel Pit Building............
2.2 29 2.2.4 8 N ew Fu el Vault................................
2.2-30 2.2.49 Primary Auxiliary Building.........................
2.2-30 2.2.50 Diesel Generator Building........................
2.2-30 2.2.51 Waste Disposal Building..........................
2.2-31 2.2.52 Safe Shutdown System Building....................
2.2-31 2.2.53 Potentially Contaminated Area Storage Buildings 1&2 and War e h ou s e..,.................................
2.2-31 2.2.54 Compactor Building.............................
2.2-32 2.2.55 Service Building.....................
2.2-32 2.2.56 Miscellaneous Tanks............................
2.2-32 2.2.57 Site Characteristics........... ?.................
2.2-34
. 2.3 Decommissioning Activities and Planning...................
23-1 23.1 Introduction...
23-1 23.2 Activities Pria.. Decommissioning Plan Approval......
23-1 233 Safe Storage Period.
23-4 23.4 Decontamination and Dismantlement Plan:
G eneral Information............................
23-5 23.5 Decontamination and Dismantlement Plan:
Systems, Structures and Components 2 3-14 23.6 Schedule of Decommissioning Activities..............
23-47
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2.3.7 Decommissioning Personnel Exposure Projection 23-47 l
23.8 Decommissioning Radioactive Waste Projections 23-48 i
2.4 Decommissioning O*n..azm and Responsibilities...........
2.41 l
2.4.1 Yankee Atol P,nmit m e nt.....................
2.4-1 i
2.4.2 Yankce Organization and Functions During SAFSTOR 2.4-2 l
2.43 Organization and Functions During Dismantlement 2.4-4 2.4.4 Safety Review Committees.......................
2.4-4 l
2.5 Contractor Responsibilities.....
2.5-1 i
2.5.1 Use of Contractors..............................
2.5-1 2.5.2 Contractor Scope of Work......................
2.5-1 l
2.53 Contractor Qualificaticas and Experience.............
2.5-1 1
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YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS 2.5.4 Contractor Administrative Controls..................
2.5-1 2.6 Training Program 2.6-1 2.6.1 General Employee Training.......................
2.6 1 2.6.2 Certified Fuel Handler...........................
2.6-2 2.6.3 Radiation Worker Training........................
2.6-2 2.6.4 Specific Job Training..........................
2.6-3 2.6.5 Non-Radiation Worker Indoctrination................
2.6-3 2.6.6 Training Staff Qualifications 2.6-3 2.6.7 Training Records.
2.6-4 3.
PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY 3.1 Facility Radiological Status...
3.1-1 3.1.1 Facility Operating History....
3.1-1 3.1.2 Radiological Scoping Suney.....
3.1-2 3.1.3 Scoping Survey Results: System, Structures, and Components.
3.1-5 3.1.4 Scoping Suney Results: Soil and Groundwater 3.1-10 3.1.5 Radiological Erwironmental Monitoring Program.......
3.1-15 3.1.6 Radiologically Affected Areas identification 3.1-18 3.1.7 Site Characterization Surveys.........
3.1-19 3.2 Radiation Protection Program.
3.2-1 3.2.1 Introdu ction......................
3.2-1 3.2.2 M anagem e nt Policy.............................
3.2-1 3.2.3 Radiation Protection Organization and Functions.......
3.2-4 3.2.4 Radiation Protection Training and Qualification........
3.2-7.
3.2.5 ALARA Program........................
3.2-8 3.2.6 Administrative Dose Control......................
3.2-9 3.2.7 Radiation Work Permits.
3.2-10 3.2.8 Area Definitions and Postings...............
3.2-11 3.2.9 External Dosimetry.
3.2-11 3.2.10 Internal Dosimetry Control and Monitoring.........
3.2-12 3.2.11 Respiratory Protection Program....................
3.2-13 3.2.12 Radioactive Material Controls.....................
3.2-13 3.2.13 Sunreillance 3.2-15 jV i
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-a Am YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS 3.2.14 Instrum entation................................
3.2-15 3.2.15 Review and Audit 3.2-15 i
3.2.16 Radiation Protection Program Performance Analysis.....
3.2-15 3.3 Radioactive Waste Management 3.3-1 3.3.1 Spent Fuel Management Plan...................
3.3-1 3.3-5 3.3.2 Solid Radioactive Waste Processing..
3.3.3 Liquid Radioactive Waste Processing................
3.3-8 3.3.4 Gaseous Radioactive Waste Processing...............
3.3-9 3.3.5 Mixed Waste 3.3-10 3.3.6 Radioactive Waste Minimization 3.3-10 3.4 Accide nt Analysis.............................
3.4-1 3.4.1 Ove rview............
3.4-1 3.4.2 Event Identification Process....................
3.4-3 3.4.3 Events Affecting Occupational Health and Safety.......
3.4-4 3.4.4 Events Affecting Public Health and Safety............
3.4-5 3.4.5 Decommissioning Activity Events...................
3.4-8 r
3.4.6 Loss of Support System Events.....................
3.4-13 i
3.4.7 Fire Events 3.4-16 3.4.8 Explosion Events......
3.4-17 3.4.9 Ext e rn al Eve n ts................................
3.4-19 3.4.10 Spent Fuel Storage Events...................
3.4-23 3.4.11 Summary of R esults............................
3.4-26 3.5 Occupational Safety Program....
3.5-1 3.5.1 Introduction....
3.5-1 3.5.2 Management Policy Statement 3.5.....................
3.53 Health and Safety Organization and Functions......
3.5-1 j
3.5.4 Yankee Occupational Safety Program................
3.5-2 3.5.5 Safety Training and Meetings........
3.5-2 3.6 Non-Radioactive Waste Management............
3.6-1 3.6.1 Introd u ction..................................
3.6-1 3.6.2 Management Policy Statement 3.6-1 3.6.3 Hazardous Material Management...................
3.6-1 1
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1 YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS 3.6.4 Hazardous Waste Management.....................
3.6-1 3.6.5 Sampling and Remedial Actions....................
3.6-3 3.6.6 Industrial Waste Management 3.6-3 3.6.7 Trai ni ng......................................
3.6-4 4.
FINAL RADIATION SURVEY PLAN 4.1 Final Release Criteria.................................
4.1-1 4.1.1 Site Release Criteria 4.1-1 4.1.2 Material Release Criteria 4.1-3 i
4.2 Final S u n'ey M e th od ol ogy...............................
4.2-1 4.2.1 Oveniew.
4.2-1 4.2.2 Instrumentation.
4.2-1 l
4.2.3 Documentation 4.2-2 4.2.4 Ouality Assurance 4.2-2 4.2.5 Independent Verification........
4.2-2 5.
DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN 5.1 Decommissioning Cost Estimate 5.1-1 l
5.2 Decommissioning Funding......
5.2-1 6.
DECOMMISSIONING TECHNICAL AND ENVIRONMENTAL SPECIFICATIONS 6.1 Description..........
6.1-1 7.
DECOMMISSIONING OUALITY ASSURANCE PLAN i
7.1 Policy Statement..
7.1-1 7.2 Introduction 7.2-1 7.3 Organization............
7.3-1 7.4 Decommissioning Ouality Assurance Plan.............
7.41 1
I 7.4.1 Design Control..............
7.4-1 7.4.2 Procurement Document Control.............
7.4-1 7.4.3 Instructions, Procedures and Drawings...............
7.42 l
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i YNPS DECOMMISSIONING PLAN REVISION: D.4 i
TABLE OF CONTENTS i
7.4.4 Docum e nt Cont rol..............................
7.4-3 7.4.5 Control of Purchased Material, Equipment, and Services..
7.4-3 7.4.6 Identification and Control of Materials, Parts, and Component 7.4-4 7.4.7 Control of Special Processes........................
7.4-4 r
7.4.8 Inspection 7.4-4 7.4.9 Te st Co n t r o1....................................
7.4-5 7A 10 Control of Measuring and Test Fquipment.............
7.4-5 7.4.11 Handling, Storage, and Shipping..
7.4-5 7.4.12 Inspection, Test, and Operating Status................
7.4-6 7.4.13 Nonconforming Materials, Parts, or Components.........
7.4-6 7.4.14 Corrective Action.
7.4-6 7.4.15 Ouality Assurance Records.......................
7.4-7 7.4.16 Audits.......
7.4-7 8.
DECOMMISSIONING ACCESS CONTROL PLAN i
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8.1 Permanently Defueled Security Plan 8.1-1 8.2 Site Access Control........
8.2-2 9.
FIRE PROTECTION 9.1 Program Description 9.1-1 9.2 Fire Protection Program Implementation.............
9.2-1 s
9.2.1 SAFSTOR Period 9.2-1 9.2.2 Dismantlement Period..........
9.2-1 APPENDICES t
i A.
COMPONENT REMOVAL PROJECT DESCRIPTION j
B.
SUMMARY
OF SIGNIFICANT RADIOLOGICAL CONTAMINATION EVENTS i
C.
PLANT DRAWINGS REFERENCED IN THE DECOMMISSIONING PLAN 1
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EXAMPLE OF i
ACCIDENT ANALYSIS REQUIREMENTS TABLE G
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_m YNPS DECOMNilSSIONING PLAN REVISION D.4 TAIIII 3.4-3 (CONTINUED)
Accident Analysis Plan Section Analysis Section Requirement Reference 3.4.5.4 Radioactive materials storage areas will be located and arranged such that multiple containers or 3.3.2.2 3.4.8.2 components will not be significantly affected by a fire, gas bottle, or collision event causing a 3.4.9.7 release of airborne radioactivity exceeding the bounding materials handling event.
3.4.5.5 Openings in components will be covered and sealed to minimize the spread of contamination after 2.3.4.3 dismantlement and before on-site transportation.
3.4.5.5 The following components will be handled and transported on-site as single containers or 2.3.5.2 3.4.9.7 components to reduce the consequences of a materials handling event: Reactor Vessel Casks; Main 2.3.5.3 Coolant System Piping Containers, Valve Containers, and Pumps; Feed and 111eed lleat Exchanger 2.3.5.5 Shells; Illced Line Piping Containers.
3.4.6.1 11ack-up power sources will be maintained to support spent fuel cooling requirements.
2.2.30 3.4.6.2 If service water is not available to the Vapor Container fire hose reels, an alternate source of 9.1 water will be established within one hour in accordance with the Fire Protection Plan.
3.4.6.3 Decommissioning activities in areas ventilated by the VC Ventilation and Purge System or the 2.3.4.3 Ventilation System will be suspended if ventilation capability is Jost.
3.4.7 The following fire protection features will be maintained through implementation of the Fire 9.1 Protection Program:
Fire detection equipment and systems
- Fire barrier maintenance and control Personnel training and qualification programs Fire Protection Program procedures Control of transient combustible materials and ignition sources I
3.4.8 Explosives will not be used at YNPS without completion of a separate safety analysis. The 2.3.4.3 analysis must include the effects of the use of explosives both on the Spent Fuel Pit Building and Fuel Transfer Chute structural integrity and on the potential release of airborne radioactivity.
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EXAMPLE OF SYSTEMS DECONTAMINATION AND DECONTAMINATION SECTION e
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4 2.3.5.5
. Charging and Volume Control System (Section 2.2.6) t The Charging and Volume Control System and components are located in the Vapor Container, Lower Pipe Chase, and Primary Auxiliag Building. The system is not
{
required in a permanently defueled condition or to support decommissioning actisities.
This system does not directly impact Spent Fuel Pit operations. However, sections of this system are interconnected with and are in close proximity to the SFP Cooling and Purification System. Safe load paths and protective zones must be established to prevent interactions with spent fuel cooling.
General decontamination and dismantlement considerations are presented in Section 2.3.4.3. The following are specific system considerations:
The Charging and Volume Control System should be isolated at the o
connections to the Shutdown Cooling, Component Cooling, Purification, Chemical Shutdown, Emergency Core Cooling, Primary Plant Corrosion Control, Service Water, Demineralized Water, Main Coolant, Pressure Control and Relief, Primag Plant Sample, Safe Shutdown, Emergency Feedwater, and Primary Plant Vent and Drain systems.
t Sludge should be removed from the Low Pressure Surge Tank prior to e
dismantlement of the system. The tank should be dismantled into manageable sections in the tank cubicle.
i The Feed and Bleed Heat Exchangers contain a significant amount of e
contamination. Each of the four shells must be handled individually to minimize the release of airborne radioactivity in the unlikely event that a
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handling accident occurs.
The charging pumps, motors, and drive units should be separated from the e
baseplate prior to removal from the pump cubicles.
l The Low Pressure Surge Tank Cooling pump and Low Pressure Surge e
Tank Cooler should be removed intact through the Primary Auxiliary Building corridor and double doors.
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2.3.5.22 Main Steam System (Section 2.2.23)
The Main Steam System and components are located in the Vapor Container, Turbine Building, and Yard Area. The system is not required in a permanently defueled condition or to support decommissioning activities. This system does not impact Spent Fuel Pit operations.
General decontamination and dismantlement considerations are presented in Section 2.3.4.3. The following are specific system considerations:
No specific considerations.
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ENCLDSURE 3 YANKEE ATOMIC ENERGY CO. MEETING - ROCKVILLE, MD.
SEPTEMBER 22, 1993 NAME ORGANIZAT[9H 1.
Mort Fairtile NRC/0NDD 2.
Jack Parrott NRC/LLWM 3.
Paul Gunter NIRS 4.
Fred Katz CAN 5.
Tony Llorens Southern California Edison 6.
Drew Spiker Southern California Edison 7.
Tim Henderson Yankee Atomic Elec. Co.
8.
dohn Austin NRC/NMSS 9.
Jane Grant Yankee Atomic Elec. Co.
10.
Russ Mellor Yankee Atomic Elec. Co.
11.
Ken Heider Yankee Atomic Elec. Co.
12.
Seymour H. Weiss NRC/NRR I
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