ML20237B451
| ML20237B451 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/06/1998 |
| From: | Alexander J BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BECO-2.98.107, GL-92-01, GL-92-1, TAC-MA1206, NUDOCS 9808180282 | |
| Download: ML20237B451 (4) | |
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Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360-5599 August 6, 1998 BECo Ltr. 2.98.107 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Docket No. 50-293 License No. DPR-35 i
Response to a Reauest for AdditionalInformation Reaardina Reactor Pressure Vessel Intearity at Pilarim Nuclear Power Station (TAC NO. MA1206)
Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Sup.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 to 1
identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to
' the requirements of Section 50.60 of Title 10 of the Code of Federal Regulations (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.
Boston Edison Company (BECo) responded to GL 92-01, Rev.1, Sup.1, for Pilgrim by letters dated August 17,1995, (BECo letter 2.95.082) and November 11,1995, (BECo letter 2.95.119). After reviewing our response, the NRC issued a letter dated December 10,1996, acknowledging receipt of Pilgrim's response and noted additional RPV information may l
become available as a result of owners group efforts and requested the NRC be provided with the results of the owners groups' programs relative to Pilgrim.
l By letter dated May 14,1998, the NRC requested Pilgrim to provide additional (updated)
{j data concerning GL 92-01, Rev.1, Sup.1, based on recent data developed by the Combustion Engineering (CE) Owners' Group. CE fabricated Pilgrim's reactor vessel. The l-RAI also stated that the NRC recently received the BWRVIP report, " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)". Based on BWRVIP-46, CEOG information, and in accordance with the provisions of Generic Letter g
92-01, Rev.1, Sup.1, we provide the following responses to the RAl:
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Provide 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-Tlimits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.
Pilarim Response to No.1 The data requested is attached to this submittal as Table 1. This information supplements or supersedes previous information provided in earlier BECo submittals on GL92-01, Rev.1, Sup.1.
The new data is consistent with the Combustion Engineering Owners' Group (CEOG) CE NPSD-1039 and the BWRVIP-46 documents referenced in your letter. The chemistry values differ from those previously provided based on the new information supplied in the CEOG document. In previous responses to GL 92-01, we provided preliminary results and stated that this inforrnation was conditional upon completion of the BWRVIP-46 assessment and the final draft of CE NPSD-1039. We also stated that we did not have information on weld deposit data for weld 1-338 A, B, C filler Heat 27204/12008 (Tandem Arc), Wire Type B-4 (Mod, Flux Lot 3774) and, therefore, used the " Upper Bound" Chemistry Factor (CF) of 272 ( which corresponds to a 0.35 Wt.% Cu and 1.0 Wt. % Ni) as the worst case " limiting" weld chemistry in accordance with Reg. Guide 1.99 Rev. 2, guidance. Since that time, the CEOG has completed CE NPSD-1039, and "Best Estimate" values of 0.22 Wt. % Cu and 1.0 Wt. % Ni have been established for this weld. The CEOG document also provided new information on the "Best Estimate" chemistry for all beltline welds, and this updated information is listed in attached Table 1. The calculations supporting the values reported in Table 1 are provided on the table.
NRC Reauest No. 2 If the limiting material for your plant changes or if the adjusted refersnce temperature (ART) for the limiting materialincreases as a result of the above evaluations, provide the revised RTna value for the limiting material. In addition, if the adjusted RT,,a value increased, provide a schedule for revising the P-Tlimits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.
Pilarim Response to No. 2 The new lower reference temperature values were determined in accordance with Reg.
Guide 1.99, Rev. 2, as were the previously provided values. The new values described in Section 1.0 would result in a reduction in a chemistry factor below the value used in our analysis, and reduce the adjusted reference temperature. However, since we used the worst case chemistry factor in developing the values provided in our earlier report and the current P-T curves, there is no effect on the existing Technical Specification P-T curves and,
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therefore, no need to revise them.
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Ccmmitment3 This response contains no commitments. The revised data does not require the revision of our. Technical Specification " Pressure-Temperature (P-T) Curves."
Should you require further information on this issue, please contact P.M.Kahler at (508)830-7939.
h r' exander egulatory Affairs Gr,oup Manager id: 298107
Attachment:
Table 1, " Calculation for Adjusted Reference Temperature" cc:
Mr. Alan B. Wang, Project Manager U.S. Nuclear Regulatory Commission Project Directorate 1-3 Region l Office Of Nuclear Reactor Regulation 475 Allendale Road Mail Stop: OWFN 14820 King of Prussia, PA 19406 1 White Flint North 11555 Rockville Pike Senior Resident inspector Rockville, MD 20852 Pilgrim Nuclear Power Station I
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