GO2-98-145, Submits Response to 980514 RAI Re Reactor Pressure Vessel Integrity
| ML20237B487 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/12/1998 |
| From: | Coleman D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GO2-98-145, NUDOCS 9808180330 | |
| Download: ML20237B487 (3) | |
Text
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WAS111NGTON PUBLIC POWER SUPPLY SYSTEM l
P.O. Box 968
- Rkhland, Washington 99352-0968 l
August 12,1998 GO2-98-145 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION l
REGARDING REACTOR ?RESSURE VESSEL INTEGRITY
References:
1)
Letter dated May 14, 1998, C Poslusny (NRC) to JV Parrish (SS),
" Request for Additional Information Regarding Reactor Vessel Integrity for the Washingten Nuclear Project No. 2 (WNP-2)"
2)
Letter GO2-97-077, dated April 24, 1997, JV Parrish (SS) to NRC, "WNP-2, Operating License NPF-21, Submittal of WNP-2 RPV Surveillance Materials Testing and Analysis Report" This letter provides the Supply System response to the requested information in Reference 1 above.
Request 1:
l Based on information in BWRVIP-46, Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity Issues, and in accordance with the provisions of Generic Ixtter 92-l 01, Revision 1, Supplement 1, the NRC is requesting a reevaluation of the bounding assessment in BWRVIP-46 and its applicability to the determination of the best-estimate i
chemistry for all of your RPV beltline welds. Based upon this reevaluation, supply the i
information necessary to completely fill out the data requested in Table 1 for each RPV d
l beltline weld material. If the limiting material in your vessel's PT limits evaluation is not a ry weld, include the information requested in Table 1 for the limiting material also.
O 9808190330 900812 fDR ADOCK 05000397 I
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l RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY Page 2
Response
Tables 8.1 and 8.2 of Reference 2 contain previously identified changes to WNP-2 reactor vessel beltline material adjusted reference temperatures (ART). The Attachment provides the additional requested information and identifies the limiting weld wire and base material for the WNP-2 reactor vessel. The calculations used to develop the ART for the weld materials were performed utilizing the tables contained in Regulatory Guide 1.99, Rev. 2 and the new fluence determined during surveillance capsule testing. The chemistry rest.ts used in the evaluation were those identified on the Chicago Bridge and Iron (CB&I) material test reports. The weld chemistries for both single and tandem arc welding are incorporated in the table for the beltline region. The WNP-2 filler materials (wire) were compared to the BWRVIP-46 document. The filler materials for both tandem and single arc welds show a copper variation of s 0.01 % when compared to the summaries contained in the BWRVIP-46 document. Since the deviation is less than 0.05%, no adjustments from the BWRVIP-46 document were used in evaluating irradiation effects for the WNP-2 beltline welds.
Reauest 2:
If the limiting material for your plant changes, or if the adjusted reference temperature for the limiting material increases as a result of the above evaluations, provide the revised RTwor value for the limiting material. In addition, if the adjusted RT or value increased provide a N
schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.
Resnonse:
Limiting material for WNP-2 did not change and the adjusted reference temperature did not change as a result of the evaluation per BWRVIP-46. The changes to the P-T curves to reflect the previously identified decrease in ART will be provided to the staff by April 24,1999 as identified in Reference 2.
Respectfully, dro DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachment cc:
EW Merschoff-NRC RIV PD Robinson - Winston & Strawn DF Kirsch - NRC RIV, WCFO NRC Sr. Resident Inspector - 927N C Poslusny, Jr. - NRR DL Williams - BPA - 1399
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