ML20058M999
| ML20058M999 | |
| 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: ML20058M999 (29) | |
Text
Septernber 29, 1993
.o Docket No.50-029 LICENSEE: YANKEE ATOMIC ELECTRIC COMPANY
-FACILITY: YANKEE NUCLEAR POWER STATION
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 this meeting in order to update the staff on the status of the preparation of the Yankee Rowe decomissioning 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 dismantic.:ent 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 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.
These slides also contained an outline of the accident analyses used in the D-Plan. 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 signed by:
Morton B. Fairtile, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate 9310070250 93o929 Division of Operating Reactor Support
{DR ADOCK 05000029 Office of Nuclear Reactor Regulation PDR dn[(f Fyr hrfff
Enclosures:
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Docket File 50-029:
BGrimes EJordan PDRs SWeiss JParrott ONDD r/f MFairtile ACRS (10)
TMurley/FMirag1ka 22 EHylton VMcCree (17-G-21)
JPartlow OGC JLinville, RI WRussell (12-G-18)
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ONDD:PMI/3 f ONDD: C ED:D 3 Fo I on MFairtile Dudley Weiss 9/23/93 2/2f/93
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SUMMARY
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September 29, 1993 Docket No.50-029 LICENSEE: YANKEE ATOMIC ELECTRIC COMPANY FACILITY: YANKEE NUCLEAR POWER STATION
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 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 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 a staff headed by a Health and Safety Supervisor and that procedures are in place to implement both OSHA and Massachusetts industrial safety requirements.
l 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.
These slides also contained an outline of the accident analyses used in the D-Plan. A second handout entitled, " Draft Decommissioning Plan Examples" (Enclosure 2) included a draft table of contents for the entire D-Plan and samples o.f key pages in the plan. A List of Attendees is included as W b-Morton B. Fairtile, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation l
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 and Chief Executive Office Commission Yankee Atomic Electric Company 425 Main Street 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. Box 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 Massachusetts Department of Public Health 305 South Street Boston, Massachusetts 02130 Commissioner Richard P. Sedano Vermont Department of Public Service 120 State Street, 3rd Floor Montpelier, Vermont 05602 Mr. Jay K. Thayer Vice President and Manager of Operations Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398 Mr. David Rodham, Director ATTN: Mr. James B. Muckerheide Massachusetts Civil Defense Agency 400 Worcester Road P. O. Box 1496 framingham, Massachusetts 01701-03173
t 0
YANKEE NUCLEAR POWER STATION DECOMMISSIONING PLAN OVERVIEW 9
~
K. J. HEIDER j
SEPTEMBER 22, 1993
~
OVERVIEW e
PLAN STATUS PLANT PROGRAMS e
ACCIDENT ANALYSIS e
SPENT FUEL MANAGEMENT e
DECONTAMINATION AND DISMANTLEMENT PLANS RADIOLOGICAL SURVEYS (SCOPING AND CHARACTERIZATION) e e
FINAL SURVEY AND SITE RELEASE CRITERIA 1
l l
DEC0f94ISSIONING PLAN NEAILCDMPLETION DRAFT STATUS e
CH0 ICE OF ALTERNATIVE AND DESCRIPTION OF ACTIVITIES DECOMMISSIONING ALTERNATIVE
/
FACILITY DESCRIPTION
/
ACTIVITIES AND PLANNING
/
ORGANIZATIONAL STRUCTURE / RESPONSIBILITIES
/
TRAINING
/
e OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY FACILITY RADIOLOGICAL STATUS
/
RADIATION PROTECTION PROGRAM
/
RADIOACTIVE WASTE MANAGEMENT
/
ACCIDENT ANALYSIS
/
OCCUPATIONAL SAFETY PROGRAM
/
NON-RADI0 ACTIVE WASTE MANAGEMENT
/
e MISCELLANEOUS PLAN DESCRIPTIONS FINAL RADIATION SURVEY PLAN
/
COST ESTIMATE AND FUNDING PLAN
/
PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS
/
QUALITY ASSURANCE PLAN
/
l ACCESS CONTROL PLAN
/
l FIRE PROTECTION PLAN
/
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DECOMISSIONING PLAN: GENERAL u
o DECOMMISSIONING ALTERNATIVE: SAFSTOR UNTIL DISPOSAL FACILITY AVAILABLE DISMANTLEMENT SCHEDULED IN 2000 FOR PLANNING PURPOSES L
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 COMPONENTS REMOVED COMPONENT REMOVAL PROJECT DESCRIPTION INCLUDED IN APPENDIX
-ANY PROJECT CHANGES WILL BE INCORPORATED IN PLAN UPDATES o
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 ESSENTIAL ELEMENTS OF PLANT PROGRAMS DESCRIBED
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RADIATION PROTECTION PROGRAM IMPLEMENTATION WILL CONTINUE PROGRAM AND IMPLEMENTING PROCEDURES SUMMARIZED 10 CFR 20 CHANGES CURRENTLYLBEING 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
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HAZARDOUS WASTE HANDLING
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INDUSTRIAL WASTE DISPOSAL FIRE PROTECTION PLAN-OTHER~ PLANS REFERENCE 0 QUALITY ASSURANCE PLAN ACCESS CONTROL SECURITY PLAN i
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+
OFF-SITE EVENTS
+
ON-SITE NON-RADIOLOGICAL AND RADIOLOGICAL EVENTS
~
RADIOLOGICAL CONSEQUENCES BASED-ON CONSERVATIVE ASSUMPTIONS AND j
RADIOLOGICAL SCOPING ANALYSIS AIRBORNE RELEASES AT GROUND LEVEL WITH CONSERVATIVE DISPERSION FACTORS I
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' RELEASE OF SURFACE CONTAMINATION AND ANY LOOSE ACTIVATED BASE METAL ASSUMED
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DEC0ffilSS10NING PLAN: SPENT _EUEL MAIULGEMENT e
SPENT FUEL P0OL INVENTORY FUEL ASSEMBLIES FROM 1972 TO 1991 HIGH LEVEL RADIOACTIVE WASTE FROM COMPONENT REMOVAL PROJECT (PLANNED)
MISCELLANEOUS LOW LEVEL RADI0 ACTIVE MATERIAL (E.G., RACKS, NEUTRON SOURCES) e 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 e
STUDY COMPLETED TO DEVELOP SPENT FUEL MANAGEMENT STRATEGY:
CONTINUE SAFE SFP OPERATION AND IMPLEMENT ECONOMICALLY ATTRACTIVE ENHANCEMENTS l
URGE DOE TO ACCELERATE SPENT FUEL ACCEPTANCE OR TO ACCEPT FINANCIAL l
RESPONSIBILITY FOR ON-SITE STORAGE CONTINUE EVALUATIONS OF WET AND DRY STORAGE OPTIONS INITIATE PRELIMINARY DESIGN ACTIVITIES FOR DRY STORAGE FACILITY
DECOMISSIONING PLAN: SPENT FUEL MANAGEMENT (CON'T)
STUDY COMPLETED TO EVALUATE INTERACTIONS BETWEEN SPENT FUEL STORAGE e
'AND DECOMISSIONING PURPOSE: IDENTIFY SAFETY CONSIDERATIONS AND LIMITATIONS ON DECOMMISSIONING ACTIVITIES ACTIVITIES WILL NOT BE IMPLEMENTED.THAT COULD IMPACT SFP INTEGRITY DR DAMAGE FUEL DISMANTLEMENT ACTIVITY LIMITATIONS IDENTIFIED e
DELAY DISMANTLEMENT OF ION EXCHANGE PIT UNTIL FUEL REMOVED FROM SFP 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 OF 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 FOR PLANNING PURPOSES 1996 FUEL TRANSFER TO ALDRY STORAGE. FACILITY
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DECOMISSIONING PLAN: DECONTAMINATION AND DISMANTIFMFNT PLANS 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 I
DECOMMISSIONING COST AND SCHEDULE REFINEMENT DECOMISSIONING WORK PACKAGES WILL BE COMPLETED FOR-ALL ACTIVITIES e
. ENGINEERING SPECIFICATIONS SIMILAR TO ENGINEERING DESION CHANGE REQUEST PROCESS DECOMMISSIONING IMPLEMENTING PROCEDURES l
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DECOMISSIONING PLAN: DECDRIAMINATION AND_DISMANILEMENT PLANS (CON'T) e 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, e
STRUCTURES, AND COMPONENTS IDENTIFIES UNIQUE CONSIDERATIONS REFERENCES GENERAL CONSIDERATIONS AND SYSTEM DESCRIPTION
DECONIISSIONING PLAN: RADIOLOGICAL SCOPING RADIOLOGICAL SCOPING COMPLETED IN SUPPORT OF DECOMMISSI0HING PLAN e
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 ASPHALTAND' SOIL
+
SURFACE GAMMA SPECTROSCOPY RESULTS SUFFICIENT TO SUPPORT DECOM11SSIONING PLAN DEVELOPMENT VOLUME AND CURIE CONTENT OF RADI0 ACTIVE MATERIALS PERSONNEL EXPOSURE PROJECTION i.
RADI0 LOGICALLY AFFECTED AREAS IDENTIFIED 1.
NUREG/CR-5849 CLASSIFICATIONS USED AREAS INSIDE OWNER CONTROLLED FENCE CONSERVATIVELY ASSUMED TO BE AFFECTED' L
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' 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 APPROVAL SURVEYS CONSIDERED FOR SYSTEMS, STRUCTURES, AND COMPONENTS
~
e SURVEY CURRENTLY INACCESSIBLE' AREAS TO VERIFY ASSUMPTIONS EXPAND CONTAMINATED CONCRETE SURVEY DATABASE SURVEY REACTOR VESSEL AFTER COMPONENT REMOVAL PROJECT COMPLETED EXPAND SURVEYS OF NON-RADIOLOGICAL SYSTEMS, STRUCTURES, AND COMPONENTS i
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ON-GOING RULE MAKING POSITIONS CONSIDERED PREVIOUS DECOMMISSIONING PLANS REVIEWED SURFACE CONTAMINATION LESS THAN REG GUIDE 1.86 LIMITS d
e DIRECT EXPOSURE FROM GAMMA EMITTING RADIONUCLIDES LESS THAN 5,pR/HR e
TOTAL EFFECTIVE DOSE EQUIVALENT LIMIT FROM RESIDUAL RADIATION UNDER e
REVIEW 30 MREM /YR WITH SITE SPECIFIC ALARA OPTIMIZATION TO <10 MREM /YR
.10 MREM /YR (CONSISTENT WITH SITE DECOMMISSIONING MANAGEMENT PLAN CRITERIA) i e
GROUNDWATER QUALITY
-INCORPORATED INTO TOTAL EFFECTIVE DOSE EQUIVALENT LIMIT 40 CFR 141 LIMITS FOR COMMUNITY WATER SUPPLIES
l
- V DECOMISS10 MING PLAN: SITE REIFASE CRITERIA-(CON'T) i e
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 RADIOACTIVITY WITHIN THE DETECTION CAPABILITY OF THE FOLLOWING:
+
MATERIALS & EQUIPMENT:-DIRECT FRISKING WITH GEIGER-MUELLER OR GAS FLOW l-
. PROPORTIONAL DETECTOR
+
SMEAR SAMPLES: ANALYSIS WITH GEIGER-MUELLER OR GAS FLOW PROPORTIONAL DETECTOR
+
BULK LIQUIDS AND SOIL: ANALYSIS WITH HIGH RESOLUTION GAMMA SPECTROMETRY TO ENVIRONMENTAL LOWER-LIMITS OF DETECTION CRITERIA CONSISTENT WITH NRC GUIDANCE t
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
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YANKEE NUCLEAR POWER STATION
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DECOMMISSIONING PLAN OVERVIEW DRAFT DECOMMISSIONING PLAN EXAMPLES j
4 t
l K. J. HEIDER SEPTEMBER 22, 1993 9
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1 DRAFT TABLE OF CONTENTS t
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YNPS DECOMMISSIONING PIAN REVISION: D.4 t
TABLE OF CONTENTS.
1.
SUMMARY
OF PLAN l
l a
1.1
-Description of Decommissioning Plan and Decommissioning Alternative............................
1.1-1 j
i 1.1.1 Introdu ction...................................
1.1-1 1.1.2 _ Background...................................
1.1-2 1.13 Contents of the Decommissioning Plan...............
1.1-3 l
1.2 Major Tasks, Schedules, and Activities.....................
1.2 l 1.2.1 Descriptio:. of Major Activities.....................
1.2-1 l
1.2.2 Final Release Criteria...........................
1.2-5 L23 Schedule for Decommissioning Activities.............
1.2-5 13 Decommissioning Cost Estimate and Availability of Funds......
13-1 1.3.1 Decommissioning Cost............................
13-1 13.2 Fu nding Pl an..................................
13-1 i
1.4 Regulatory Basis for Administration of the Decommissioning Plan.................................
1.4-1 l
r 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 j
2.1.2 Decommissioning Alternative Justification.............
2.1.1 -
i i
2.2 Facility Description...................................
2.2-1 l
i 1
2.2.1 General Description.............................
2.2-1 1
2.2.2 Reactor Vessel.................................
2.2-1 2.23 St eam G en erators................................
2.2-3 2.2.4 Main Coolant System............................
2.2-3 I
1 l
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YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS 2.2.5 Pressure Control and Relief System.................
2.2-4 2.2.6 Charging and Volume 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 Radia9n Monitoring System......................
2.2-10 2.2.17 VC Ventilation and Purge System...................
2.2-13 2.2.18 VC Heating and Cooling Syste n....................
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 Equipment 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 Heating System................................
2.2-20 2.2.?2 Ventilation System..............................
2.2 20 2.233 Fire Protection and Detection System................
2.2-21 2.234 Primary Pump Seal Water System...................
2.2-21 2.235 Safe Shutdown System...........................
2.2-22 2.236 Water Cleanup System...........................
2.2-22 2.237 Vapor Container......'.........................
2.2-22 2.238 Reactor Support Structure........................
2.2 24 2.239 Vapor Container Polar Crane......................
2.2-24 2.2.40 Radiation Shielding.............................
2.2-25 2.2.41 Neutron Shield Tank............................
2.2-26 2.2.42 Pipe Chases...................................
2.2-27 2.2.43 Fuel Transfer Chute.............................
2.2 27 2.2.44 Yard Area Crane and Support Structure..............
2.2-28 ii
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YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS
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2.2.45 Ion Ex change Pit...............................
2.2-28 2.2.46 Primary Vent Stack.............................
2.2-29 j
2.2.47 Spent Fuel Pit and Spent Fuel Pit Building............
2.2-29 2.2.48 New Fu el Vault................................
2.2-30 l
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 i
2.2.52 Safe Shutdown System Building....................
2.2-31 2.2.53 Potentially Contaminated Area Storage Buil' ings 1&2 and l
d Ware h o us e....................................
2.2-31 2.2.54 Compactor Building............................
2.2-32' i
2.2.55 Service Building................................
2.2-32 2.2.56 Miscellaneous Tanks............................
2.2-32 j
2.2.57 Site Characteristics..............................
2.2-34 t
23 Decommissioning Activities and Planning...................
23-1 23.1 Int rod u ction...................................
23-1 23.2 Activities Prior to Decommissioning Plan Approval......
23-1 233 Safe Storage Period.............................
23-4 l
23.4 Decontamination and Dismantlement Plan-
- General Information.............................
23-5 23.5 Decoutamination and Dismantlement Plan:
Syste ms, Structures and Components................
2 3-14 23.6 Schehle of Decommissioning Activities..............
23-47 3
23.7 Decommissioning Personnel Exposure Projection.......
23-47 23.8 Decommissioning Radioactive Waste Projections.......
23-48 2.4 Decommissioning Organization and Responsibilities...........
2.4-1 i
2.4.1 Yankee Atomic Commitment......................
2.4-1 2.4.2 Yankee Organization and Functions During SAFSTOR..
2.4-2 2.43 Organization and Functions During Dismantlement 2.4-4 2.4.4 Safety Review Committees........................
2.4-4 j
2.5 Contractor Responsibilities.............................
2.5-1 i
i 2.5.1 Use of Contractors..............................
2.5-1 2.5.2 Contractor Scope of Work........................
2.5-1 2.53 Contractor Qualifications and Experience.............
2.5-1 l
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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-l
2.6.2 - Certified Fuel Handler...........................
2.6-2 1
2.6.3 Radiation Worker Training........................
2.6 2 i
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 l
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 f
3.1.1 Facility Operating History.........................
3.1-1 3.1.2 Radiological Scoping Survey.......................
3.1-2 j
3.1.3 Scoping Survey Results: System, Structures, and Compon e n ts....................................
3.15 3.1.4 Scoping Survey Results: Soil and Groundwater.........
3.1-10 3.1.5 Radiological Emironmental Monitoring Program.......
3.1-15 3.1.6 Radiologically Affected Areas Identification...........
3.1-18
'i 3.1.7 Site Characterization Surveys......................
3.1-19
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3.2 Radiation Protection Program...........................
3.2-1 3.2.1 Introd u ction...................................
3.2-1 I
3.2.2 M anage ment Policy.............................
3.2-1
-l 3.2.3 Radiation Protection Organization and Functions.......
3.2-4 l
3.2.4 Radiation Protection Training and Qualification........
3.2-7 3.2.5 ALARA Program...............................
3.2-8 i
3.2.6 ' Administrative Dose Control......................
3.2-9 3.2.7 Radiation Work Permits..........................
3.2-10
- 1 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 i
3.2.13 Surveillan ce...................................
3.2-15 l
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YNPS DECOMMISSIONING PIAN REVISION: D.4 i
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3.2.14 Instrumentation.................................
3.2 15 3.2.15 Review and Audit 3.2-15 3.2.16 Radiation Protection Program Performance Analysis.....
3.2-15' t
33 Radioactive Waste Management.........................
33-1 33.1 Spent Fuel Management Plan......................
33-1 33.2 Solid Radioactive Waste Processing..................
33-5 1
333 Liquid Radioactive Waste Processing................
33 33.4 Gaseous Radioactive Waste Processing...............
33 9 33.5 M ix e d Wast e................................... 3 3-10 3.3.6 Radioactive Waste Minimization 33-10 3.4 Accident Analysis....................................
3.4-1 3.4.1 Ove rvi ew.....................................
3.4-1 1
3.4.2 Event Identification Process.......................
3.4-3 3.43 Events Affecting Occupational Health and Safety.......
3.4-4 l
3.4.4 Events Affecting Public Health and Safety............
3.4-5 3.4.5 Decommissioning Activity Events...................
3.4-8 1
3.4.6 Loss of Support System Events......
3.4-13 3.4.7 Fir e Eve nts...................................
3.4-16 3.4.8 Explosion Events...............................
3.4-17 3.4.9 Ext e rnal Eve n ts................................
3.4-19 i
3.4.10 Spent Fuel Storage Events........................
3.4-23
'1 3.4.11 Summary of Results.............................
3.4-26 i
3.5 Occupational Safety Program............................
3.5-1 '
l 3.5.1 Introdu ction...................................
3.5-1 3.5.2 Management Policy Statement..............._......
3.5-1 3.53 Health and Safety Organization and Functions.........
3.5-1 3.5.4 Yankee Occupational Safety Program................ _
3.5-2~
3.5.5 Safety Training and Meetings......................
3.5 2
't 3.6 Non. Radioactive Waste Management......................
3.6-1 3.6.1 Introdu ction...................................
3.6-1 3.6.2 Management Policy Statement.....................
3.61-3.63 Hazardous Material Management...................
3.6-1 V
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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_
l 3.6.7 Training......................................
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 l
4.1.2 Material Release Criteria.........................
4.1-3
.i 4.2 Final Survey Methodology..............................
4.2-1 4.2.1 Ove rvi ew.....................................
4.2-1.
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4.2.2 Instru m e nt ation................................
4.2-1 4.2.3 Docu m entation.................................
4.2-2 i
4.2.4 Qu ality Assurance..............................
4.2-2 4.2.5 Independent. Verification.........................
4.2-2 j
5.
DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN 5.1 Decommissioning Cost Estimate........................
5.1-1 5.2 Decommissioning Funding..............................
5.2-1 i
6.
DECOMMISSIONING TECHNICAL AND ENVIRONMENTAL SPECIFICATIONS 6.1 D e s crip tion.........................................
6.1-1 7.
DECOMMISSION 1NG OUALITY ASSURANCE PLAN 7.1 Policy Statement.................. _..................
7.1-1 d
7.2 Introd u ction.......................................
7.2-1_
7.3 O rg anization.......................................
7.3-1 7.4 Decommissioning Quality Assurance Plan.................
7.4 1 i
7.4.1 De sign Control.................................
7.4-1 7.4.2 Procurement Document Control....................
7.4-1
)
7.4.3 Instructions, Procedures and Drawings............... 7.4-2 1
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YNPS DECOMMISSIONING PLAN REVISION: D.4 TABLE OF CONTENTS 7.4.4 Docume nt Control..............................
7.4-3 7.4.5 Control of Purchased Material, Equipment, and Services..
7.4-3 7.4.6 Identi5 cation and Control of Materials, Parts, and Component 7.4-4 7.4.7 Control of Special Processes........................
7.4-4 7.4.8 Insp e ct io n.....................................
7.4-4 7.4.9 Te st Control....................................
7.4 5 7.4.10 Control of Measuring and Test Equipment.............
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 Au dit s..........................
7.4-7 8.
DECOMMISSIONING ACCESS CONTROL PLAN 8.1 Permanently Defueled Security Plan.....................
8.1-1 8.2 Sit e Access Control..................................
8.2-2 9.
FIRE PROTECTION 9.1 Program Description..................................
9.1-1 9.2 Fire Protection Program Implementation...................
9.2-1 9.2.1 SAFSTO R Pe riod.............................
9.2-1 9.2.2 Dismantlement Period..........................
9.2-1 APPENDICES A.
COMPONENT REMOVAL PROJECT DESCRIPTION B.
SUMMARY
OF SIGNIFICANT RADIOLOGICAL CONTAMINATION EVENTS C.
PIANT DRAWINGS REFERENCED IN THE DECOMMISSIONING PIAN
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e EXAMPLE OF ACCIDENT ANALYSIS REQUIREMENTS TABLE 9
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Accident Analysis Plan Section Analysis Section Requirement Reference 3.4.5.4 Radioactive materials stort.ge areas will be located and arranged such that multiple containers or 3.3.2.2 3.4.8.2 components will not be signifi antly 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 coveeed and sealed to minimize the spread of contamination after 2.3.4.3 dismantlement and before on-site transtartation.
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 Bleed lleat Exchanger 2.3.5.5 Shells; Bleed Line Piping Containers.
3.4.6.1 Back-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.I 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 lost.
3.4.7 The following fire protection features will be maintained through implementation of the Fire 9.1 Protection Program:
- Fire detectio equipment and systems
- Fire barrier maintenance and control
- Personnel training and qualification programs
- Fire Protection Program procedures
- Control of tranJent combustible materials and ignition sources 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.
EXAMPLE OF P
SYSTEMS DECONTAMINATION AND DECONTAMINATION SECTION l
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23.5.5 Charcine and Volume Control System (Section 2.2.6)
The Charging and Volume Control System and components are located in the Vapor Container, Lower Pipe Chase, and Primary Auxiliary Building. The system is not required in a permanently defueled condition or to support decommissioning activities.
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 23.43. The following are specific system considerations:
The Charging and Volume Control System should be isolated at the 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, Primary Plant Sample, Safe Shutdown, Emergency Feedwater, and Primary Plant Vent and Drain systems.
Sludge should be removed from the Imw Pressure Surge Tank prior to e
dismantlement of the system. The tank should be dismantled into manageable sections in the tank cubicle.
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 handling accident occurs.
The charging pumps, motors, and drive units should be separated from the e
baseplate prior to removal from the pump cubicles.
The Low Pressure Surge Tank Cooling pump and Iow 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 Maiq_ 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 23.43. The following are specific system considerations:
e No specific considerations.
9 a
F-ENCUDSURE 3 YANKEE ATOMIC ENERGY CO. MEETING - ROCKVILLE, MD.
4 SEPTEMBER 22, 1993 ESME ORGANIZATION 1.
Mort Fairtile NRC/0NDD l
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.
John Austin NRC/NMSS 9.
Jane Grant Yankee Atomic Elec. Co.
- 10. Russ Mellor Yankee Atomic Elec. Co.
- 11. Ken Heider Yankee Atomic Elec. Co.
1
- 12. Seymour H. Weiss NRC/NRR l
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