ML20044F613
| ML20044F613 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/19/1993 |
| From: | Fairtile M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9305280315 | |
| Download: ML20044F613 (23) | |
Text
{{#Wiki_filter:W ypucq+k UNITED STATES ., e [4 - {I . J 22f j NUCLEAR REGULATORY COMMISSION I f WASHINGTON D.C. 20555-0001 %.% */ May 19, 1993 Docket No. 50-029 LICENSEE: YANKEE ATOMIC ELECTRIC COMPANY FACILITY: YANKEE NUCLEAR POWER STATION
SUBJECT:
MEETING
SUMMARY
On Tuesday - May 11, 1993, at the NRC headquarters in Rockville, Maryland, the staff met with Yankee Atomic personnel. The licensee requested the meeting in order to update the staff on the status of the Yankee Rowe Decommissioning Program. Currently, the licensee is removing asbestos insulation from components that will be shipped to the low-level waste disposal facility at Barnwell, South Carolina. This facility is managed by Chem-Nuclear Systems, Inc., and this organization is a key contractor in the transport of the components being shipped to Barnwell. Yankee Atomic is also preparing the engineering documents needed to support the program as well as the safety and environmental analyses needed to demonstrate the safety of the program. In addition, Yankee is preparing the Decommissioning Plan, needed under NRC regulations, and stated that it will be submitted to the NRC before October 1, 1993. The NRC staff brought up concerns about morale at the site and how licensee management will maintain a safety perspective among its contract employees. In regard to morale, the licensee said that while problems are unavoidable, they believe that by the nature of the retention program they instituted and the fact that a great deal of meaningful work is underway, morale problems will be minimal. As to the contract employees following proper radiological and industrial safety practices, the licensee stated that they have hired contractors experienced in the nuclear industry and that Yankee will maintain proper management control over the program. The NRC staff was satisfied with the licensee responses. Yankee plans to maintain the site in SAFSTOR, after the early component removal program is completed, until the year 2000; then, the licensee estimates it will take two more years for dismantlement of the remainder of the facility. This schedule is based on licensee estimates of future availability of low-level waste disposal sites. SAFSTOR is defined as placing and maintaining the facility in a condition that allows the nuclear facility to be safely stored and subsequently decontaminated to levels that permit release for unrestricted use. l i 1 9305200315 930519 FDR ADDCK 05000029 r l-y PDR
r i May 19, 1993
- is an attendance list. is a set of handouts, used by the licensee at the meeting.
t-fL A. h aw k ) 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
1 3 Ms. Jane M. Grant Yankee Rowe Docket No. 50-29 cc: Dr. Andrew C. Kadak, President Chairman, Franklin County and Chief Executive Office Commission Yankee Atomic Electric Company 425 Main Street 5B0 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 I Plant Superintendent P. O. Box 83 f 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 i 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 01701-0317
) May 11, 1993 YANKEE ATOMIC ENERGY CO. MEETING - ROCKVILLE, MD. 1. Mort Fairtile NRR/ DORS /0NDD 2. Richard Dudley NRR/ DORS /0NDD 3. Michael Breck NUS 4. Ken Heider YAEC 5. Jane Grant YAEC 6. Russell Mellor YAEC 7. Greg Maret YAEC 8. Patrick Sheldon YAEC 9. David Fauver NRC/NMSS 10. Jack Parrott NRC/NMSS 1 e
' May 19, 1993 , is an attendance list. is a set of handouts, used by the licensee at the meeting. Original signed by: MT' Morton B. Fairtile, Senior Project Manager Non-Power Reactors and Decomissioning Project Directorate i Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
As stated i cc w/ enclosures: j ee next page DISTRIBUTION:[5-11MSUM.MBF] *w/ licensee's handouts
- Docket Files No. 50-029
- PDRs
- 0NDD R/F T. Murley/F. Miraglia J. Partlow R. Wood B. Grimes i
S. Weiss E. Hylton
- M.
Fairtile NRC Attendees Region I E. Jordan ACRS (10)
- J.
Linville, RI p l OGC n V. McCree, ED0 ONDD:FM[fM 0FC: ONDD ONDD:SC OND ! NAME: EHyl MFairtile:1b RDudley SWeiss DATE: (/l /93 5'//g/93 g Q /93 f/g/93
l HANDOUTS FOR MEETING BETWEEN YANKEE ATOMIC ELECTRIC COMPANY AND U. S. NUCLEAR REGULATORY COMMISSION i l STATUS OF YANKEE NUCLEAR POWER STATION j i I E b MAY 11, 1993 ROCKVILLE, MARYLAND
2, f AGENDA FOR MEETING BETWEEN YANKEE ATOMIC ELECTRIC COMPANY AND NUCLEAR REGULATORY COMMISSION MAY 11. 1993 e GENERAL STATUS PLANT ACTIVITIES PUBLIC INFORMATION PROGRAM LICENSING ACTIONS e DECOMMISSIONING PLAN UPDATE GENERAL STATUS ACCIDENT ANALYSES QUALITY ASSURANCE PROGRAM r COST ESTIMATING e COMPONENT REMOVAL ACTIVITIES i STEAM GENERATOR / PRESSURIZER / INTERNALS REMOVAL ACTIVITIES SCHEDULE OF ACTIVITIES PROJECT MANAGEMENT PLAN t
3, GENERAL-STATUS i e PLANT ACTIVITIES COMPONENT REMOVAL ALTERNATIVE USE STUDY STAFFING i UNION NEGOTIATIONS P e PUBLIC INFORMATION PROGRAM e LICENSING ACTIONS PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS PRICE ANDERSON EXCLUSION l TRAINING RULE (10 CFR 50.120) l i i k m-
4' ) DECOMISSIONING PLAN SUBMI1TAL ON SCHEDULE FOR 10/93 DRAFT -{ STATUS e
SUMMARY
/ l e CHOICE OF ALTERNATIVE AND DESCRIPTION OF l ACTIVITIES i DECOMMISSIONING ALTERNATIVE / FACILITY DESCRIPTION / ACTIVITIES AND PLANNING [ ORGANIZATIONAL STRUCTURE / e OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY FACILITY RADIOLOGICAL STATUS j RADIATION PROTECTION PROGRAM / RADI0 ACTIVE WASTE MANAGEMENT / ACCIDENT ANALYSIS e MISCELLANE0US PLAN DESCRIPTIONS FINAL RADIATION SURVEY PLAN / COST ESTIMATE AND FUNDING PLAN / PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS / f QUALITY ASSURANCE PLAN / ACCESS CONTROL PLAN / i
4 a-4 m.. + a 4-a . + -r a+ w-4su. m-m. i f.l RADIOLOGICAL CHARACTERIZATION' ACTIVITIES SCOPING SURVEYS UNDERWAY OBJECTIVE: SUFFICIENT DATA TO ESTIMATE RAD-WASTE VOLUME j & CURIES SURVEYS INSIDE STRUCTURES COMPLETED + CONTACT AND AREA DOSES FOR PIPING,-COMPONENTS, &- STRUCTURES' + LIMITED ISOTOPIC ANALYSES OF PIPE SAMPLES + PAINT AND CONCRETE SAMPLES FROM STRUCTURAL SURFACES SURVEYS OUTSIDE STRUCTURES UNDERWAY 1 I + CORE BORINGS AND OBSERVATION WELLS COMPLETED + SURFACE SAMPLES OF TARMAC AND SOIL UNDERWAY + SURFACE SCANNING l e SURVEY RESULTS-COMPILED IN COMPUTERIZED j DECOMMISSIONING DATABASE 1 ' FACILITATES RADIOLOGICAL DATA STORAGE AND RETRIEVAL l DATABASE INTEGRATED WITH SYSTEMS AND STRUCTURES DATABASE FOR CURIE ESTIMATES l DATABASE WILL BE EXTENDED DURING CHARACTERIZATION AND FINAL SURVEYS j i SITE CHARACTERIZATION INITIATED AFTER SCOPING COMPLETED j e r
~ 6 ACCIDENT ANALYSIS e ACCIDENT ANALYSIS IDENTIFIES YANKEE DECOMMISSIONING LIMITS SPENT FUEL STORAGE LIMIYS INTEGRITY REQUIREMENTS FOR ACTIVITIES IN CONTAINMENT l SYSTEMS AND STRUCTURES REQUIREMENTS DURING DECOMMISSIONING e CRITERIA: RELEASES CANNOT EXCEED EPA-PAG LIMITS AT EXCLUSION AREA BOUNDARY e SYSTEMATIC REVIEW OF EVENTS UNDERWAY NUREG/CR-0130 PUBLIC AND OCCUPATIONAL SAFETY l EVALUATIONS YANKEE EVENT TREE i e RADIOLOGICAL SCOPING SURVEY RESULTS USED IN l ANALYSIS l l l i I l 9 1
7. OA PROGRAM ASSURES OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY e BASED ON REQUIREMENTS OF 10 CFR 50 APPENDIX B e MAINTAIN PLANT CONFIGURATION TO PREVENT AND TO MITIGATE CONSEQUENCES OF FUEL HANDLING ACCIDENTS e ASSURE COMPLIANCE WITH APPLICABLE LICENSE AND TECHNICAL SPECIFICATIONS e ASSURE COMPLIANCE WITH SEVERAL DECOMMISSIONING PROGRAMS RADIATION PROTECTION RADI0 ACTIVE WASTE HANDLING AND SHIPPING (INCLUDING PROCESS CONTROL) RADI0 ACTIVE EFFLUENT CONTROL RADIOLOGICAL ENVIRONMENTAL MONITORING SECURITY FIRE PROTECTION EMERGENCY PREPAREDNESS TRAINING 1 ~ l
B, - UPDATED COST ESTIMATE' BASED ON 1992 FERC SUBMITTAL e SITE SPECIFIC ESTIMATE USING CURRENT DECOMMISSIONING SAFSTOR SCENARIO-i e BASED ON " BOTTOM-UP" ANALYSIS OF PLANT SYSTEMS, STRUCTURES, AND COMPONENTS j e BASIS OF 1992 FERC SUBMITTAL AND DECOMMISSIONING FUND COLLECTION NEXT COST ESTIMATE UPDATE PLANNED AFTER NRC i e APPROVAL OF PLAN I t INCORPORATE ANY REVISIONS TO DECOMMISSIONING PLAN RESULTING FROM NRC REVIEW SUBMIT TO FERC, PER 1992 AGREEMENT. ) FERC APPROVED ESTIMATE WILL BE INCORPORATED INTO l APPROVED DECOMMISSIONING PLAN l t i
O. COMPONENT' REMOVAL PROJECT STATUS i e STEAM GENERATOR AND PRESSURIZER REMOVAL-e REACTOR VESSEL INTERNALS REMOVAL 1 e OTHER PLANT MODIFICATIONS j POLAR CRANE UPGRADES AUXILIARY CRANE INSTALLATION i e SCHEDULE
SUMMARY
o CONTRACTOR STATUS e PROJECT MANAGEMENT PLAN e i I l i
10 - STEAM GENERATOR / PRESSURIZER REMOVAL l s' INITIAL DRAFT OF ENGINEERING DESIGN CNANGE PACKAGE j i 1 e LIFTING FIXTURE AND TRUNNION DESIGN ONGOING i i e LIFTING AND RIGGING STUDY UNDERWAY i e REMOVAL AND PACKAGING PROCEDURES UNDER DEVELOPMENT j l e SAFETY EVALUATION SCOPING ONGOING l RADIOLOGICAL CONSEQUENCES OF SG DROP COMPLETED YAEC WILL PRECLUDE BREACH OF SG PRESSURE BOUNDARY DURING REMOVAL + IMPACT LIMITER WILL BE USED j + DETAILED PROCEDURAL CONTROLS WILL BE USED- + POLAR CRANE UPGRADES / TESTING + RIGGING / HEAVY LIFT SPECIALIST INVOLVED j i .l i i i i l l
// - P STEAM GENERATOR / PRESSURIZER REMOVAL (CONT.) e 10 CFR PART 71 SAR UNDER REVIEW BY NRC e TRANSPORTATION ISSUES ROAD TRANSIT TO H00 SAC TUNNEL i TRANSFER TO RAIL ON NEW SIDING RAIL ROUTE BEING FINALIZED k TRANSFER TO ROAD HAULER AT CHEM FUCLEAR (CNSI) SITE DISPOSAL AT BARNWELL r i 6 h ~.e-
12 REACTOR VESSEL INTERNAI% REMOVAL e SEGMENTATION TOOLING DESIGN ONGOING - PCI e SEGMENTATION / PACKAGING PLAN UNDER DEVELOPMENT - YAEC/PCI/CNSI/WMG e PLANT MODS TO SUPPORT SEGMENTATION MISC EQUIPMENT REMOVAL FROM' CAVITY - RACKS, ETC. CASK LINER LAY DOWN PADS WILL BE INSTALLED REFUELING ERIDGE AND MANIPULATOR WILL BE' REMOVED. ELECTRICAL MODS TO PROVIDE POWER TO CONTAINMENT l LOOP PIPING WILL BE CAPPED 1 CAVITY LEAKAGE CONTROL MEASURES WILL BE IMPLEMENTED-l l' e [' ,' i. ^
^ 13. POLAR CRANE UPGRADES e ORIGINAL 150 TON CAPACITY WILL BE RESTORED-r NEW HOOKS / LOWER BLOCK ASSEMBLIES NEW WIRE ROPE i LOAD TESTED e COMPREHENSIVE MECHANICAL / ELECTRICAL t INSPECTION COMPLETED GOOD OVERALL CONDITION e r w Y P l.
14. AUXILIARY CRANES e NEW 5. TON JIB CRANE WILL BE INSTALLED OVER EQUIPMENT HATCH FOR HISCELLANE0US MATERIAL HANDLING e NEW GANTRY CRANE WILL BE INSTALLED OVER i REFUELING CAVITY TO SUPPORT INTERNALS SEGMENTATION i I P l i I 2
if, i SCHEDULE SU N RY t h e DESIGN CHANGE' PACKAGES APPROVED BY PORC STEAM GENERATORS / PRESSURIZER REMOVAL - 7/13/93 l REACTOR VESSEL INTERNALS SEGMENTATION - 7/15/93 e SITE ACTIVITIES REMOVE INSULATION FROM SG/PZR - IN PROCESS l i REFURBISH / LOAD TEST POLAR CRANE - 7/28/93 REMOVE, PREPARE, SHIP SG/PZR - 9/18/93 - 4/30/94 FLOOD REFUELING CAVITY - 8/25/93 DELIVER SEGMENTING TOOLING-TO YNPS - 8/23/93 BEGIN SEGMENTATION - 9/23/93 i CASK SHIPPING - 10/14/93 - 2/17/94 -l ? I i
COMPONEST REMOVAL PROGRAM 1993 1994 J.. l ren l ns., l A pr l ns.r l Jim l Jia l A.. I see I os l N.- I rw J.. l rb l nr.r l A pr l nr.r l J.m 1 Jun PLANNING & ENGINEERING tw m;$im e nse e m m ysa %;rese g y % @ a$n g gf g f d ASBESTOS REMOVAL Id#sWawheM1 CUT #4 SG MC LINES SUPPORT SYSTEM & STRUCTURE CHANGES li2nnMMMwWe#EW@tt3Medt LOAF 1 YE ST F'OL.AR CnANE SAR Development LDMMMn9HsttB%2M%M#n4%Mt SunsMTSIR P#tcAW HOVE VO NFIC SAR Remove SG & PZR
- ,. Jf***3E%L SG & PZR REMOVAL ntuovAt ntuovAt Prep SG & PZR for Shipment It#s*MMMM@25R4thWMWWI l
Ship SG & PZR LAMAMMMENRFM13 tat f f SHIPMENT f 2 SitW'9ENT TO 9ARNWELL TO BAFINWEtt Tooling Design, Fabrication,-Test. BEGIN SEGMENTING and Delivery IW M t F M W 9 M M Me 3 % M e Pi R M I RPV INTERNALS Segment internais L REMOVAL
- g*
- m e m* m m Ni 03RnwEtt l
CLOSURE c^* ' Load and Sh. Casks - ip LM4mwmimiMrmlasi g s 4 lF,H10.5 m
17,. 1 CONTRACTOR STATUS INTERNALS-SEGMENTATION TOOLING AND SUPPORT - PCI INTERNALS CNARACTERIZATION - CNSI/WMG 4 e SG/ PRESSURIZER PACKAGING AND TRANSPORTATION - 1 CNSI/LOCKWOOD BROS./ RAIL Co. e ASBESTOS-ASATEMENT - PERFORMANCE ABATEMEN e RADIATION PROTECTION SUPPORT SERVICES - P,ARTLETT a NUCLEAR /NUMANCO 1 e CONSTRUCTION SUPPORT SERVICES - SWEC l f 'l -f 1 a 1 f
- i i -
18,, l PROJECT MANAGEMENT PLAN e
SUMMARY
DOCUMENT PROJECT OVERVIEW SCHEDULE
SUMMARY
COST CONTROL PROGRAM ORGANIZATION AND RESPONSIBILITIES IMPLEMENTATION GUIDELINES i LICENSING REQUIREMENTS i CONTRACTORS l HEALTH AND SAFETY PROGRAM SITE ACCESS REQUIREMENTS RADIATION PROTECTION PROGRAM QUALITY ASSURANCE PROGRAM t 6 i 'l l
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