ML20210E900

Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2

ML20210E900
Person / Time
Site:	River Bend
Issue date:	07/23/1999
From:	Robert Fretz NRC (Affiliation Not Assigned)
To:	Edington R ENTERGY OPERATIONS, INC.
References
GL-92-01, TAC-MA1209, NUDOCS 9907290053
Download: ML20210E900 (4)

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UNITED STATES j

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.....,o July 23, 1999 Mr. Randall K. Edington

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Vice President - Operations Entergy Operations, Inc.

River Bend Station P. O. Box 220 St. Francisville, LA 70775

SUBJECT:

RIVER BEND STATION, UNIT 1 - CLOSURE OF TAC NO. MA1209; RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY"

Dear Mr. Edington:

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 to:

(1) identify, collect, and report any now 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 ar.d H to 10 CFR Part 50.

On August 17,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative the structural integrity assessment for the River Bend Station (RBS). The staff evaluated your response and provided its conclusion relative to your response on July 30,1996. 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 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 boiling water reactor 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 April 24,1998, the staff issued a request for additionalinformation (RAI)in regard to the alloying chemistries of beltline welds, l

your assessment of surveillance data for your facility, pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessment (only applicable to pressurized-water reactors (PWRs) for RBS. In general, with respect to the contents of the RAl, the staff requested that you reassess the 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 I

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b, July 23,1999 R. K. Edington 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 RBS on August 4,1998. As a result of the staff's review of your responses to GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and the Supplement 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 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 structural integrity assessments. Future submittals on P-T limits, PTO (only applicable to PWRs), or upper shelf energy should reference the most current information.

This closes the staff's efforts in regard to TAC number MA1209. The staff appreciates your efforts in regard to this matter.

Sincerely, ORIG. SIGNED BY Robert J. Fretz, Project Manager, Section 1 I

i Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50 458 cc: See next page DISTRIBUTION:

Docket File K.Brockman, RIV OGC PUBLIC ACRS SRichards (cover ltr only)

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l To receive a copy of this document, indicate "C" in the box OFFICE PDIV-1/PM PDIV-1/LQ N PDIV-1/SC (,

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DATE 7 //9 /99 h / \\ >/99 1/ @ /99 DOCUMENT NAME: G:\\PDIV-1\\ Rive rBe nd\\G L9201 -MA1209.wpd OFFICIAL RECORD COPY 4

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T R. K. Edington changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative 'o 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 RBS on August 4,1998. As a result of the staff's review of your responses to GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and the Supplement 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 location which is linked to the NRC home page (http://www.ntc. 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 submittats on P-T limits, PTS (only applicable to PWRs), or upper shelf energy should reference the most current information.

This closes the staff's efforts in regard to TAC number MA1209. The staff appreciates your efforts in regard to this matter.

Sincer k.,

obert J. Fretz, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458 cc: See next page I

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M River Bend Station cc:

Winston & Strawn Executive Vice President and 1400 L Street, N.W.

Chief Operating Officer Washington, DC 20005 3502 Entergy Operations, Inc.

P. O. Box 31995 Manager Licensing Jackson, MS 39286 Entergy Operations, Inc.

River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.

St. Francisville, LA 70775 River Bend Station P. O. Box 220 Senior Resident inspector St. Francisville, LA 70775 P. O. E3x 1050 St. Francisville, LA 70775 Director - Nuclear Safety Entergy Operations, Inc.

President of West Feliciana River Bend Station Police Jury P. O. Box 220 P. O. Box 1921 St. Francisville, LA 70775 St. Francisville, LA 70775 Vice President - Operations Support Regional Administrator, Region IV Entergy Operations, Inc.

U.S. Nuclear Regulatory Commission P. O. Box 31995 611 Ryan Plaza Drive, Suite 1000 Jackson, MS 39286-1995 Arlington, TX 76011 Attorney General Ms. H. Anne Plettinger State of Louisiana 3456 Villa Rose Drive P. O. Box 94095 Baton Rouge, LA 70806 Baton Rouge, LA 70804-9095 Administrator Louisiana Radiation Protection Division P. O. Box 82135 Baton Rouge, LA 70884-2135 Wise, Carter, Ch ld & Caraway P. O. Box 651 Jackson, MS 39205 May 1999 i

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