ML17284A864

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Advises That as Result of Review of Responses to GL 92-01, Rev 1,Suppl 1 & Suppol 1 Rai,Nrc Revised Info in Rvid & Releasing Info as Rvid Version 2.NRC Efforts in Regard to TAC MA1213 Closed
ML17284A864
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 07/13/1999
From: Jack Cushing
NRC (Affiliation Not Assigned)
To: Parrish J
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
GL-92-01, TAC-MA1213, NUDOCS 9908170026
Download: ML17284A864 (10)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ouly 13,;3999 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)

Richland, WA 99352-0968

SUBJECT:

CLOSURE OF TAC NO. MA1213-RESPONSE TO THE REQUESTS FOR ADDITIONALINFORMATIONJ'g, Qgf+@Q~g ER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR'MCSKSTAOCTURALINTEGRITY,"FOR THE WASHINGTON PUBLIC POWER SIJP[P )YSTEM NUCLEAR PROJECT NO. 2 (WNP-2)

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Dear Mr. Parrish:

On May 19, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01; Rev. 1, Supp. 1), "Reactor Vessel Structural Integrity,"

to holders of nuclear operating licenses.'n issuing the GL the staff required addressees of the GL to:

(1) identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative.to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code ofFederal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code ofFederal Regulations (Appendices G and H to 10 CFR Part 50).

On August 16, 1995, you submitted your initial response to GL 92-01, Rev. 1, Supp. 1. and provided the requested information relative to the structural integrity assessment for WNP-2.

The staff evaluated your response to GL 92-01, Rev. 1, Supp. 1, and provided its conclusion relative to your response on August 22, 1996.

However, since the time of the staffs closure letter, the Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B&W)

Owners Group have each submitted additional data regarding the alloying-chemistries of beltline welds in CE and B8W fabricated vessels.

The additional alloying data were submitted in Topical Reports CE NPSD-1039, Revision 2, CE NPSD-1119, Revision 1, for CE fabricated RPV welds, and BAW-2325, Revision 1, for B&Wfabricated RPV welds.

In addition, Chicago Bridge and Iron (CB8 I) BWR data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that additional information was necessary relative to the structural integrity assessments for your plant. On May 14, 1998, the staff issued a request for additional information (RAI) in regard to the alloying chemistries of beltline welds, your assessment of surveillance data for your facility, pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments (only applicable to PWRs) for WNP-2.

In general, with respect to the contents of the RAI, the staff requested that you reassess the "P~

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'J. Parrish alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report, and provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60, 10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for your plant.

You provided your response to the staff's RAI for WNP-2 on August 12, 1998. As a result of the staffs review of your responses to GL 92-01, Revision 1, GL 92-01, Rev. 1, Supp. 1, and the

Supp, 1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID)and is releasing it as RVIDVersion 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/index.html ). We recommend that you

. review this information. Ifthe staff does not receive comments by September 1, 1999, we will assume that the data entered into the RVID are acceptable for your plant.

No additional information is necessary with regard to the structural integrity assessments.

Future submittals on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information.

This closes the staffs efforts in regard to TAC No. MA1213. The staff appreciates your efforts in regard to this matter.

Sincerely, Jack Gushing, Project Manager, Section 2 Project Directorate IV 8 Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation cc: See next page

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Nude& Project No. 2 CC:

Mr. Greg O. Smith (Mail Drop 927M)

Vice President, Generation Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352-0968 Mr. Albert E. Mouncer (Mail Drop 1396)

Chief Counsel Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352-0968 I

Ms. Deborah J. Ross, Chairman Energy Facility Site Evaluation Council P. O. Box 43172 Olympia, Washington 98504-3172 Mr. D. W. Coleman (Mail Drop PE20)

Regulatory Affairs Manager Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352-0968 Mr. Paul Inserra (Mail Drop PE20)

Manager, Licensing Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 8 Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman

.Benton County Board of Commissioners P.O. Box 69 Prosser, Washington 99350-0190 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 69 Richland, Washington 99352-0968 Mr. Rodney L. Webring (Mail Drop PE08)

Vice President, Operations Support/PIO Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 Perry D. Robinson, Esq.

Winston 8 Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Mr. Bob Nichols Executive Policy Division Office of the Governor P.O. Box 43113 Olympia, Washington 98504-3113

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iJ.-parrish alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report, and provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60, 10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for your plant.

You provided your response to the staffs RAI for WNP-2 on August 12, 1998. As a result of the staffs review of your responses to GL 92-01, Revision 1, GL 92-01, Rev. 1, Supp. 1, and the Supp.

1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID)and is releasing it as RVIDVersion 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/index.html ). We recommend that you review this information. Ifthe staff does not receive comments by September 1, 1999, we will assume that the data entered into the RVID are acceptable for your plant.

No additional information is necessary with regard to the structural integrity assessments.

Future submittals on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information.

This closes the staffs efforts in regard to TAC No. MA1213. The staff appreciates your efforts in regard to this matter.

Sincerely,

/s/

Jack Gushing, Project Manager, Section 2 Project Directorate IV 8 Decomissioning Division,of Licensing Project Management Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION Docket File PUBLIC PDIV-2 Reading S Richards(clo)

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