ML20216B848
| ML20216B848 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/14/1998 |
| From: | Wang A NRC (Affiliation Not Assigned) |
| To: | Olivier L BOSTON EDISON CO. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1206, NUDOCS 9805180477 | |
| Download: ML20216B848 (6) | |
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UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION 9'f WASHINGTON, D.c. 2006H001
.....p liay 14, 1998 Mr. Leon J. Olivier Vice President - Nuclear / Station Director Boston Edison Company Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road Plymouth, MA 02360
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT PILGRIM NUCLEAR POWER STATION (TAC NO. MA1206)
Dear Mr. Olivier:
Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural integrity" was issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structuralintegrity of their RPVs and to assess the impact of those data on their RPVintegrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Reaulations (10 CFR Part 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits.
After reviewing your response, the NRC issued a letter dated December 10,1996, acknowledging receipt of your response and noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups' programs relative to your plant. We further indicated that a plant-specific TAC Number may be opened to review this material. Following issuance of these letters, the BWR Vessel and Intemals Project (BWRVIP) submitted the report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)." This report included bounding assessments of new data from 1) the Combustion Engineering Owners Group (CEOG) database released in July 1997 which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are documented in NRC Inspection Report 99901300/97-01 dated January 28,1998;
- 3) FTl's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September 20,1996; and 4) Chicago Bridge and Iron quality assurance records. New data for one vessel fabricated by Hitachi was also included in the BWRVIP report.
The staff is requesting that you re-evaluate the RPV weld chemistry values that you have previously submitted as part of your licensing basis in light of the information presented in the CEOG, FTl and BWRVIP reports. The staff expects that you will assess this new information to determine whether any values of RPV weld chemistry need to be revised for your facility.
Therefore, in order to provide a complete response to items 2,3 and 4 of the GL, the NRC requests that you provide a response to the enclosed request for additional information within 90 days of receipt of this letter, if a question does not apply to your situation, please indicate this in your RAI response along with your technical basis and, per GL 92-01, Rev.1, Supp.1, provide a certification that previously submitted evaluations remain valid.
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L. Olivier 2
The information provided will be used in updating the Reactor Vessel Integrity Database (RVID).
l Also, please note that RPV integrity analyses utilizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If additionallicense amendments or assessments are necessary, the enclosed requests that you provide a schedule for such submittals.
If you should have any questions regarding this request, please contact me at (301)415-1445.
Sincerely, Original signed by l
Alan B. Wang, Project Manager 1
l Project Directorate 1-3 l
Division of Reactor Projects - t/11 l-Office of Nuclear Reactor Regulation j
Docket No. 50-293 i
Enclosure:
Request for Additional Information cc w/ encl: See next page Distrioutiorr l
, Docket File
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OGC ACRS C. Cowgill, RI DOCUMENT NAME: G:\\ PILGRIM \\RPV.RAI
, To rescive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with l. att!chment/ enclosure "N" = No copy l
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05r4-/98 OFFICIAL RECORD COPY l
T Mr. Lcen J. OliviIr Boston Edison Company Pilgrim Nuclear Power Station cc:
Mr. Ron Ledgett Ms. Nancy Desmond Executive Vice President Manager, Reg. Affairs Dept.
800 Boyleston Street Pilgrim Nuclear Power Station Boston, MA 02199 RFD #1 Rocky Hill Road Plymouth, MA 02360 Resident inspector U. S. Nuclear Regulatory Commission Mr. David F. Tarantino Pilgrim Nuclear Power Station Nuclear Information Manager Post Office Box 867 Pilgrim Nuclear Power Station Plymouth, MA 02360 RFD #1, Rocky Hill Road Chairman, Board of Selectmen 11 Lincoln Street Ms. Kathleen M. O'Toole Plymouth, MA 02360 Secretary of Public Safety l
Executive Office of Public Safety Chairman, Duxbury Board of Selectmen One Ashburton Place Town Hall Boston, MA 02108 878 Tremont Street Duxbury, MA 02332 Mr. Peter LaPorte, Director Attn: James Muckerheide Office of the Commissioner Massachusetts Emergency Management l
Massachusetts Department of Agency Environmental Protection 400 Worcester Road One Winte.- Street P.O. Box 1496 Boston, MA 02108 Framingham, MA 01701-0317 l
Office of the Attomey General Chairman, Citizens Urging One Ashburton Place Responsible Energy 20th Floor P.O. Box 2621 Boston, MA 02108 Duxbury, MA 02331 l
i Mr. Robert M. Hallisey, Director Citizens at Risk Radiation Control Program P.O. Box 3803 Massachusetts Department of Plymouth, MA 02361 Public Health 305 South Street W.S. Stowe, Esquire Boston, MA 02130 Boston Edison Company 800 Boyleston St.,36th Floor Regional Administrator, Region l Boston, MA 02199 U. S. Nuclear Regulatory Commission 475 Allendale Road Chairman King of Prussia, PA 19406 Nuclear Matters Committee Town Hall Ms. Jane Fleming 11 Lincoln Street i
8 Oceanwood Drive Plymouth, MA 02360 Duxbury, MA 0233 Mr. William D. Meinert Mr. Jeffery Keene Nuclear Engineer Licensing Division Manager Massachusetts Municipal Wholesale Boston Edison Company Electric Company 600 Rocky Hill Road P.O. Box 426 Plymouth, MA 02360-5599 Ludlow, MA 01056-0426 l
a REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY PILGRIM NUCLEAR POWER STATION Section 1.0: Assessment of Best-Estimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2-6
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Reactor Pressure Vessel Integrity issues (BWRVIP-46)".
Based on this information, in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
1.
An evaluation of the bounding assessment in the reference above and its applicability to the determination of the best-estimate chemistry for all of your RPV beltline welds. Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table 1 for each RPV beltline weld material. If the limiting material for your vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 j
for the limiting material also.
With respect to your response to this question, the staff notes that some issues regarding the evaluation of the data were discussed in a public meeting between the staff, NEl, and industry representatives on November 12,1997. A summary of this meeting is documented in a meeting summary dated November 19,1997, " Meeting Summary for November 12,1997 Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement i Responses"(Reference 1). The information in Reference 1 may be useful in helping you to prepare your response.
In addition to the issues discussed in the referenced meeting, you should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. This is an important l
consideration when a mean-of-the-means or coil-weighted average approach is determined to be i
the appropriate method for determining the best-estimate chemistry. If a weld (or welds) were fabricated as weld qualification specimens by the same manufacturer, within a short time span, using similar welding input parameters, and using the same coil (or coils in the case of tandem arc welds) of weld consumables, it may be appropriate to consider all chemistry samples from that weld (or welds) as samples from "one weld" for the purposes of best-estimate chemistry l
determination. ifinformation is not available to confirm the aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, the best-estimate chemistry l
should be evaluated both by assuming the data came from "one weld" and by assuming that the data came from an appropriate number of " multiple welds". A justification should then be l
provided for which assumption was chosen when the best-estimate chemistry was determined.
Section 2.0: P-T Limit Evaluation 2.
If the limiting material for your plant changes or if the adjusted reference temperature for the limiting materialincreases as a result of the above evaluations, provide the revised RT,, value for the limiting material. In addition, if the adjusted RT, value increased, n
provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.
l t
Enclosure
l l
Reference 1.
Memorandum dated November 19,1997, from Keith R. Wichman to Edmund J. Sullivan,
" Meeting Summary for Novernber 12,1997 Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, l
Supplement 1 Responses."
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