ML20209G283

Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant

ML20209G283
Person / Time
Site:	Hope Creek
Issue date:	07/14/1999
From:	Richard Ennis NRC (Affiliation Not Assigned)
To:	Keiser H Public Service Enterprise Group
References
GL-92-01, GL-92-1, TAC-MA1194, NUDOCS 9907190114
Download: ML20209G283 (4)

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NUCLEAR REGULATORY COMMISSION WAf,HINGTON, D.C. 20555-4001

\*****/ July 14, 1999 Mr. Harold W. Keiser Chief Nuclear Officer & President -

Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

CLOSURE OF TAC NO. MA1194 - RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR HOPE CREEK GENERATING STATION

Dear Mr. Keiser:

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. In 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 of Federal 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 of FederalRegulations (Appendices G and H to 10 CFR Part 50). I On August 14,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1 and provided the requested information relative to the RPV structural integrity assessment for Hope Creek Generating Station (HCGS). The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 2,1996. However, since the time of the staff's 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 B&W fabricated vessels. The additional 3 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&W fabricated RPV welds. In addition, Chicago Bridge and Iron (CB&l) 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 RPV structural integrity assessment for HCGS. On May 4,1998, 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, and pressure-temperature (P-T) limits. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the beltline welds and RPV g

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I 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 j

on the structural integrity assessment 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 HCGS on July 27,1998. As a result of the staff's 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 RVID Version 2.

The new database diskettes are posted on the world-wide-web at a ' aation which is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). Vve recommend that you review this information. If the 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 RPV structural integrity assessment. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.

This closes the staff's efforts in regard to TAC No. MA1194. Tne staff appreciates your efforts in regard to this matter.

Sincerely, Richard B. Ennis, Project Manager, Section 2 i Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354 cc: See next page l

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9 H. Keiser 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 assessment 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 HCGS on July 27,1998. As a result of the staff's review of your responses to GL 92-01, Revision 1; GL 92-01, Rev.1, Supp.1; and the Supp.1 RAl, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 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. If the 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 RPV structural integrity assessment. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.

This closes the staf's efforts in regard to TAC No. MA1194. The staff appreciates your efforts in regard to this matter.

Sincerely, ORIGINAL SIGNED BY:

Richard B. Ennis, Project Manager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354 cc: See next page DISTRIBUTION Docket File JClifford ADLee OGC PUBLIC TClark GVissing ACRS PDI-2 Reading REnnis GMeyer, RGN-1 OFFICE PDI-2/PM PDI-2/LA PDl-2/SC NAME REnnis:b TClar' k lb bihob DATE 7/l1/99 h/ /99 1/l4 /99 OFFICIAL RECORD COPY DOCUMENT NAME: G:\PDI-2\ Hope Creek \ltra1194.wpd

I Hope Creek Generating Station ec:

'Jeffrie J. Keenan, Esquire Manager - Joint Generation Nuclear Business Unit - N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg Harbor Twp., NJ 08234-4130 Hope Creek Resident inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 0509 Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department c/o Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 General Manager - Hope Creek Operations Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President '

P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Director - Licensing Regulation & Fuels Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 l

P.O. Box 236 '

Hancocks Bridge, NJ 08038 Regional Administrator, Region I  !

U.S. Nuclear Regulatory Commission )

475 Allendale Road King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy  ;

CN 415 '

Trenton, NJ 08625-0415

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