ML20210L631

Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2

ML20210L631
Person / Time
Site:	Oyster Creek
Issue date:	08/06/1999
From:	Pastis H NRC (Affiliation Not Assigned)
To:	Roche M GENERAL PUBLIC UTILITIES CORP.
References
GL-92-01, TAC-MA1202, NUDOCS 9908090184
Download: ML20210L631 (5)

Text

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.O E NUCLEAR REGULATORY COMMISSION "f WASHINGTON, D.C. 20566-0001 August 6, 1999 t

Mr. Michael B. Roche Vice President and Director GPU Nuclear, Inc.

Oyster Creek Nuclear Generating Station P.O. Box 388 Forked River, NJ '08731'

SUBJECT:

CLOSURE OF TAC NO. MA1202 - RESPONSE TO THE REQUESTS FOR INFORMATION IN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1,

" REACTOR VESSEL STRUCTURAL INTEGRITY," FOR OYSTER CREEK NUCLEAR GENERATING STATION

Dear Mr. Roche:

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). to 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  !

i (2) to assess the impact of that data on their RPV integrity analyses relative to the l 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 i G and H to Part 50 of Title 10 of the Code of Federal 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 assessments for Oyster Creek Nuclear Generating Station. The staff evaluated your response to GL 92-01, Rev.1, i Supp.1, and provided its conclusions relative to your response on August 6,1996. However, ,

since the time of the staff's closure letter, the Combustion Engineering (CE) Owners Group 1 and the Babcock and Wilcox (B&W) Owners Group have each submitted additional data l regarding the alloying chemistries of beltline welds in CE and B&W fabricated vessels. The <

. additional alloying data were submitted in Topical Reports CE NPSD-1039, Revision 2, CE 3  !

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 ,

mU in Topical Report BWRVlP-46. As a result of the efforts by CE and B&W, the staff determined 4 that additional information was necessary relative to the structural integrity assessments for your plants. On April 29,1998, the staff issued a request for additional information (RAI) in f)s)'

regard to the alloying chemistries of beltline welds, your assessment of surveillance data for g),

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your facility, and pressure-temperature (P T) limits for the Oyster Creek Nuclear Generating ,

Station, 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 surveillance welds relative to I

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ADOCK 05000219 PDR

August 6, 1999 M. Roche 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 the Oyster Creek Nuclear Generating Station on September 10,1998. 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 j information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID l Version 2. l The new database diskettes are posted on the world-wide-web at a location which is linked to I the NRC home page (http //www.nrc. gov /NRR/RVID/index.html). We recommend that you f review this information. If the staff does not receive comments by September 1,1999, we will l assume that the data entered into the RVID are acceptable for your plant. No additional 1 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 staff's efforts in regard to TAC No. MA1202. The staff appreciates your efforts in regard to this matter.

Sincerely, '

Original signed by:

Helen N. Pastis, Sr. Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-219 cc: See next page f

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I DISTRIBUTION: (

Secent Bly ACRS KWichman Alee SBajwa

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PUBLIC SLittle OGC GVissing E. Adensam (E-mail) l PDI-1 r/f AHiser TColburn BElliot M. Oprencek, RGNI l l

DOCUMENT NAME: G:\PDl-1\ Oyster Creek \Ltra1202.wpd To receive a copy of this document, indicate in the box: "C" 'opy without attachment / enclosure "E" - Copy with attachment / enclosure . - No copy 0FFICE PDI-1/PM th l PDI-1/LA sQV l PDI-1/SC j l l NAME HPastis:ltc' b Slittle

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DATE 7699 U V/J99 f/[/99 / /99 0FFICIAL RECORD COPY 090061 1

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l' August 6, 1999

! M. Roche 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 the Oyster Creek Nuclear Generating Station on September 10,1998. 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 Vesse! 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 necessarf with regard to the structuralintegrity 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 staff's efforts in regard to TAC No. MA1202. The staff appreciates your efforts in regard to this matter.

Sincerely, Original signed by:

Helen N. Pastis, Sr. Project Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50 219 cc: See next page DISTRIBUTION:

Docket File ACRS KWichman Alee SBajwa PUBLIC SLittle OGC GVissing E. Adensam (E-mail)

PDI-1 r/f AHiser TColburn BElliot M. Oprencek, RGNI DOCUMENT NAME: G:\PDl-1\ Oyster Creek \Ltra1202.wpd To receive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy wi,th attachment / enclosure "N" - No copy 0FFICE PDI-1/PM t1[r, l PDI-1/LA3QV l PDI-1/SC j l l NAME HPastis:lec' b SL1ttle

• SBa]wa X I' R DATE ffI99 U Y/J99 f/[/99 / /99 OFFICIAL RECORD COPY

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M. Roche 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 structuralintegrity 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 the Oyster Creek Nuclear Generating Station on September 10,1998. 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 databaso 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 structuralintegrity 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 staff's efforts in regard to TAC No. MA1202. The staff appreciates your efforts in regard to this matter.

Sincerely,

)

474 s.&A~

Helen N. Pastis, Sr. Project Manager, Se tion 1

. Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation

. Docket No. 50-219 cc: See next page 1

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M. Roche~

GPU Nuclear, Inc.

cc:

- Mr. David Lewis Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037 Manager Licensing & Vendor Audits GPU Nuclear, Inc.

1 Upper Pond Road Parsippany, NJ 07054 Manager Nuclear Safety & Licensing f

Oyster Creek Nuclear Generating Station Mail Stop OCAB2 P. O. Box 388 Forked River, NJ 08731 i

Regional Administrator, Region i U.S. Nuclear Regulatory Commission -

475 Allendale Road King of Prussia, PA 19406-1415

. Mayor Lacey Township 818 West Lacey Road Forked River, NJ 08731 Residew Inspector c/o U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering ,

CN 415 i Trenton, NJ 08625 '

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