ML20059L340
| ML20059L340 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/27/1994 |
| From: | Fairtile M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9402040091 | |
| Download: ML20059L340 (18) | |
Text
Docket No.50-029 January 27, 1994 LICENSEE: YANKEE ATOMIC ELECTRIC COMPANY FACILITY:
YANKEE NUCLEAR. POWER STATION
SUBJECT:
MEETING
SUMMARY
- SECOND PHASE OF COMPONENT REMOVAL On Tuesday, December 21, 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 plant status and to describe the proposed second phase of component removal. These components include the primary pumps and motors, potentially contaminated asbestos, and certain other contaminated piping systems. The discussior, included the engineering and planning done by the licensee including preparation of 10 CFR 50.59 safety evaluations and use of the NRC decommissioning criteria as supplied in the NRC Staff Requirements Memorandum of January 14, 1993. The outline of this program is provided in Enclosure 1.
Yankee, subsequent to this meeting, submitted a letter, dated December 30, 1993, that describes the proposed funding of this program. The staff has this letter under review.
Enclosure I contains all of the slides presented by Yankee at this meeting. A List of Attendees is included as Enclosure 2.
Among the slides in Enclosure 1 are those showing the levels of occupational-doses received by plant workers during the recently completed first phase of the component removal program.. The total doses were below the ALARA program estimates and no individual worker received a dose as high as the plant administrative limit which is set below the NRC requirements.
.The staff was informed that four of about thirty shipping cask loads of radioactive materials planned to be shipped to Barnwell, South Carolina, have been shipped.
About thirty percent of the reactor vessel internals, that qualify as low level waste, were shipped in some of these casks. The licensee hopes to complete these low level waste shipments by' mid-Spring 1994.
Original signed by:
Morton B. Fairtile, Senior Project Manager Non-Power Reactors and_ Decommissioning Project Directorate Division of Operating Reactor Support i
Office of Nuclear Reactor Regulation
Enclosures:
As stated cc.w/ enclosures:
See next page DISTRIBUTION:[MTGSUM12.MBF] (Fairtile-lb)
Docket Files No.'50-029' M. Fairtile i
PDRs NRC Attendees, not listed above J
ONDD R/F Region I T. Murley/F. Miraglia E. Jordan 1
W. Russell ACRS (10)
J. Roe J. Linville, RI R. Wood W. McDowell, IG B. Grimes 0100"3 OGC
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Docket No.50-029 January 27, 1994 LICENSEE: YANKEE ATOMIC ELECTRIC COMPANY FACILITY: YANKEE NUCLEAR POWER STATION
SUBJECT:
MEETING
SUMMARY
- SECOND PHASE OF COMPONENT REMOVAL On Tuesday, December 21, 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 plant status and to describe the proposed second phase of component removal. These components include the.
primary pumps and motors, potentially contaminated asbestos, and certain other contaminated piping systems. The discussion included the engineering and planning done by the licensee including preparation of 10 CFR 50.59 safety evaluations and use of the NRC decommissioning criteria as supplied in the NRC Staff Requirements Memorandum of January 14, 1993. The outline of this program is provided in Enclosure 1.
Yankee, subsequent to this meeting, submitted a letter, dated December 30, 1993, that describes the proposed funding of this program. The staff has this letter under review.
Enclosure I contains all of the slides presented by Yankee at this meeting. A List of Attendees is included as Enclosure 2.
Among the slides in Enclosure 1 are those showing the levels of occupational doses received by plant workers during the recently completed first phase of the component removal program.
The total doses were below the ALARA program estimates and no individual worker received a dose as high as the plant administrative limit which is set below the NRC requirements.
The staff was informed that four of about thirty shipping cask loads of radioactive materials planned to be shipped to Barnwell, South Carolina, have been shipped. About thirty percent of the reactor vessel internals, that qualify as low level waste, were shipped in some of these casks.
The licensee hopes to complete these low level waste shipments by mid-Spring 1994.
Original signed 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:
As stated cc w/ enclosures:
See next page DISTRIBUTION:[MTGSUM12.MBF] (Fairtile-lb)
Docket Files No.50-029 M. Fairtile PDRs NRC Attendees, not listed above ONDD R/F Region I T. Murley/F. Miraglia E. Jordan W. Russell ACRS (10)
J. Roe J. Linville, RI R. Wood W. McDowell, IG B. Grimes OGC S. Weiss E. Hylton V.
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UNITED STATES 1'
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waswinovow, o.c. 2oss5-oooi January 27, 1994 Docket.No.50-029 LICENSEE: YANKEE. ATOMIC ELECTRIC COMPANY FACILITY: YANKEE NUCLEAR POWER STATION
SUBJECT:
MEETING
SUMMARY
- SECOND PHASE OF COMPONENT REMOVAL On Tuesday, December 21, 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 plant status and to describe:the' proposed second phase of component removal. These components include the primary pumps and motors, potentially contaminated asbestos ~, and certain other contaminated piping systems. The discussion included the engineering and planning done by-the licensee including preparation of 10 CFR 50.59 safety evaluations and use of the NRC decommissioning criteria as supplied in the NRC Staff Requirements Memorandum of January 14, 1993.
The outline-of this-program is provided in Enclosure 1.
Yankee, subsequent'to this meeting, submitted a letter, dated December 30, 1993, that describes the proposed
' funding of this program. The staff has this letter under review.
! contains all of the slides presented by Yankee-at this meeting. A List of Attendees is included as Enclosure 2.
Among the slides in Enclosure 1 are those showing the levels of occupational-doses received by plant workers during the recently completed first phase of the component removal program. -The total doses were below the ALARA program estimates and no individual worker received a dose as high as the plant administrative limit which is set below the NRC requirements.
The staff was informed that.four of about thirty shipping cask loads of radioactive materials planned to be shipped to Barnwell, South Carolina, have been shipped. About thirty percent of the reactor vessel internals, that-qualify as low level waste, were shipped in some of'these casks. The licensee hopes to complete these low level waste shipments by mid-Spring 1994.'
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 4
Docket No.50-029 i
cc:
Dr. Andrew C. Kadak,. President Chairman, Franklin County and Chief Executive Officer 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 Karl Abraham, Region I Robert M. Hallisey, Director U.S. Nuclear Regulatory Commission Radiation Control Program 475 Allendale Road Massachusetts Department of Public King of Prussia, Pennsylvania 19406 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 i
ENCIOSURE 1 4
YANKEE NUCLEAR POWER STATION DEC0lWIISSIONING NUCLEAR REGULATORY COMISSION DECEMBEn 21, 1993
OVERVIEW STATUS OF CURRENT ACTIVITIES
SUMMARY
0F 1994 PLANNED ACTIVITIES
- DECOPMISSIONING FUND ACCESS FOR ADDITIONAL ACTIVITIES 1
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YANKEE R0WE STATUS DECOMMISSIONING PLAN AND ENVIRONMENTAL REPORT SUBMITTED e
SUBMITTAL DATED 12/20/93 ADDITIONAL COPIES DISTRIBUTED:
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ELECTED OFFICIALS
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~ LOCAL LIBRARIES
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OTHERS COMMUNITY MEETING PLANNED FOR -END OF JANUARY l
e COMPONENT REMOVAL PROJECT-STEAM GENERATORS AND PRESSURIZER DISPOSAL COMPLETED REACTOR INTERNAL COMPONENTS REMOVAL UNDERWAY
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PLANNING FOR ADDITIONAL-ACTIVITIES UNDERWAY
t ADRITIORAL ACTIVITIES PLANNED FOR 1994 SITE CHARACTERIZATION RADIOLOGICAL SURVEYS-ASBESTOS REMOVAL INSIDE RADIATION CONTROL AREA CONTAMINATED AND POTENTIALLY CONTAMINATED COMPONENT REMOVAL
- MAIN STEAM AND FEEDWATER SYSTEMS (INSIDE VC)
SAFETY INJECTION SYSTEM- (OUTSIDE VC)
CHARGING : AND VOLUME CONTROL SYSTEM.(OUTSIDE :VC)
. CHEMICAL SHUTDOWN SYSTEM (OUTSIDE VC).
. VALVE STEM LEAK-OFF SYSTEM (OUTSIDE VC) e MAIN COOLANT PUMP. DISPOSAL L
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SITE CHA MCTERIZATION l
' CONTINUATION OF RADIOLOGICAL SURVEY PROCESS e
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PURPOSE: VERIFY EXTENT AND MAGNITUDE 0F RADIOLOGICAL CONTAMINATION FOR DETAILED PLANNING e
- 1994 FOCUS:
SAMPLE SOIL AND GROUNDWATER IN-AREAS IDENTIFIED DURING SCOPING SURVEYS GROUNDWATER MODEL DATA COLLECTION SURVEY STRUCTURES'AND COMPONENTS TO SUPPORT DETAILED PLANNING b
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REMOVE POTENTIALLY CONTAMINATED' ASBESTOS-FROM-RADIATION CONTROL AREA SUPER-COMPACT ASBESTOS _FOLLOWED BY.
DISPOSAL (IF BARNWELL AVAILABLE)
STORAGE ON SITE (IF BARNWELL NOT AVAILABLE)
CDMEORENT REMOYAL e
SELECTED SYSTEMS NOT REQUIRED TO SUPPORT PLANT OPERATIONS OR DECOM4ISSIONING REMOVAL ACTIVITIES SIMILAR TO NORMAL PLANT MODIFICATION ACTIVITIES e
REMOVED MATERIALS WILL BE PROCESSED AT RECLAMATION FACILITY FOLLOWED BY.
DISPOSAL AT BARNWELL (IF AVAILABLE)
STORAGE IN ON SITE WAREHOUSE IF BARNWELL NOT AVAILABLE SIMILAR ENGINEERING, PLANNING, AND EXECUTION AS CURRENT: ACTIVITIES
- 10. CFR.50.59 REVIEW, INCLUDING DECOMISSIONING CRITERIA PROCEDURALIZED DESIGN CONTROLS EXPERIENCED IMPLEMENTATION TEAM q
MAIN C0_0LANT PUMP _ REMOVAL f
e REMOVAL SIMILAR TO ROUTINE PLANT OUTAGE MAINTENANCE ACTIVITY e
DISPOSAL IN BARNWELL
-CURRENTLY. SCHEDULED BEFORE 3/15/94 REACTOR INTERNALS EFFORT HAS PRIORITY SIMILAR ENGINEERING, PLANNING, AND EXECUTION.AS CURRENT ACTIVITIES 10 CFR 50.59 REVIEW, INCLUDING DECOMMISSIONING CRITERIA
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PROCEDURALIZED DESIGN CONTROLS EXPERIENCED IMPLEMENTATION TEAM
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s ACTIVITIES ARE LEGITIMATEzDEC0191ISSIONING EXPENSES l
e CONSISTENT WITH DEFINITION OF DECOMMISSIONING REMOVE (AS A FACILITY) SAFELY FROM SERVICE REDUCE RESIDUAL RADI0 ACTIVITY TO A LEVEL THAT PERMITS RELEASE OF THE PROPERTY FOR UNRESTRICTED USE AND TERMINATION OF LICENSE ACTIVITIES ARE REQUIRED T0 DEC0 MISSION YNPS COMPONENTS ARE RADI0 LOGICALLY CONTAMINATED AND MUST BE REMOVED SURVEYS'ARE NEEDED TO CONTINUE ASSESSMENT OF RADIOLOGICAL CONTAMINATION
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ACTIVITIES 1DO NOT FORECLOSE THE RELEASE.0F THE SITE FOR POSSIBLE-UNRESTRICTED USE
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ACTIVITIESEDO NOT REDUCE VALUE OF DECOPBIISSIONINGLTRUST-BELOW AM0_UNT NEERED TO PLACE-FACILITY-IN SAFE STORAGE-COST OF PLANNED ACTIVITIES IS LESS THAN 1994 FUND-COLLECTION.
COST-OF PLANNED ACTIVITIES: ABOUT-$7 MILLION VERY SMALL FRACTION OF TRUST FUND
- e COST TO RETURN TO SAFE STORAGE IS SMALL PREMATURE TERMINATION COULD-REQUIRE RETURN OF UNPROCESSED COMPONENTS AND STORAGE AT YANKEE COST EXPOSURE LOW PRIMARILY SHIPPING, HANDLING, AND STORAGE
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NO SIGNIFICANT CHANGES TO THE FACILITY THAT MUST BE REVERSED l
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D WITHDEAWALS DO NOT INHIBIT ABILITY TO FUND TRUST COST OF ACTIVITIES IS SMALL FRACTION OF OVERALL TRUST FUND VALUE e
ACTIVITIES REDUCE DECOMMISSIONING COSTS e
COST EXPOSURE FROM PREMATURE TERMINATION IS MINOR e
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E ENCLOSURE 2 December 21, 1993 YANKEE ATOMIC ENERGY CO. MEETING - ROCKVILLE, MD.
1 NAME ORGANIZATION 1
1.
Mort Fairtile NRR/0NDD 2.
Richard Dudley NRR/0NDD 3.
Russ Mellor Yankee Atomic 4.
Ken Heider Yankee Atomic 5.
Seymour Weiss NRR/0NDD 6.
Bill McDowell NRC/0lG 7.
Kathy Black NRC/0lG 8.
Stewart Brown NRC/NMSS 9.
John Austin NRC/NMSS/LLDR
- 10. Larry Bell NRC/NMSS/LLDR
- 11. Anthony Markley NRC/NRR/ DORS /0NDD
- 12. Mitzi Young (Part-time)
NRC/0GC i
i l
i