ML20209E523

Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583

ML20209E523
Person / Time
Site:	Waterford
Issue date:	07/09/1999
From:	Chandu Patel NRC (Affiliation Not Assigned)
To:	Dugger C ENTERGY OPERATIONS, INC.
References
GL-92-01, GL-92-1, TAC-MA0583, TAC-MA583, NUDOCS 9907150059
Download: ML20209E523 (3)

Text

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$ - WASHINGioN, D.C. 20066 0001 g(n.. s / July 9, 1999 Mr. Charles M. Dugger -

Vice Presloent Operations Entergy Operations, Inc.

P. O. Box B Killona, LA 70066

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - RESPONSE TO THE

. REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO. MA0583)

Dear Mr. Dugger:

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 generic letter, the staff required addressees of the generic letter 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) tc 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 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 to the structural integrity assessment for Waterford [  ;

' Unit 3. In your August 17,1995, letter you also committed to take additional action to locate "all data relevant to the determination of Reactor Pressure Vessel (RPV) integrity...." You g {

submitted the rest.s of your participation in a Combustion Engineering (CE) Owners Group p activity (which acquired "all relevant data" for CE fabricated vessel materials) in a letter dated February 17,1997. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and Q /

provided its conclusion relative to your response on August 28,1997. The staff has recently

. verified the information that you submitted and determined that it adequately reflects the information contained _in CE Topical Reports CE NPSD-1039, Revision 2 (June 1997), and CE NPSD-1119, Revision 1 (July 1998), for CE fabricated RPV welds.

As a result of the staff's review of your responses to GL 92-01, Revision 1, and GL 92-01, Rev.1, Supp.1, 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 that 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, the staff will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the

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i C. M. Dugger July 9, 1999 structuralintegrity assessments. Future submittals on Pressure-Temperature limits, Pressurized Thermal Shock, or upper shelf energy should reference the must current information.

This closes the staff's efforts in regard to TAC number MA0583. The staff appreciates your efforts in regard to this matter.

Sincerely, ORIGINAL SIGNED BY Chandu P. Patel, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382 cc: See next page DISTRIBUTION:

Docket File PUBLIC K. Brockman,RIV PDIV-1 Reading OGC A. Lee ACRS To receive a copy of this document, indic5fd "C" in the box OFFICE PDIV-1/PM C PDIV 1/@ q y PDIV-1/SC (,

NAME C.PatYsp:db L. Berry ()d ) R.Grammhy DATE 7 / 9 /99 I / b /99 i /9 /99 i i

DOCUMENT NAME: G:\PDIV-1\Waterford\LTR0583.wpd OFFICIAL RECORD COPY 1

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I Waterford Generating Station 3 cc:

I Administrator Regional Administrator, Region IV Louisiana Radiation Protection Division U.S. Nuclear Regulatory Commission P. O. Box 82135 611 Ryan Plaza Drive, Suite 1000 Baton Rouge, LA 70884-2135 Arlington, TX 76011 Vice President Operations Support Parish President Council Entergy Operations, Inc. St. Charles Parish P. O. Box 31995 P. O. Box 302 Jackson, MS 39286 Hahnville, LA 70057 Director Executive Vice-President Nuclear Safety & Regulatory Affairs and Chief Operating Officer Entergy Operations, Inc. Entergy Operations, Inc.

P. O. Box B P. O. Box 31995 Killona, LA 70066 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Chairman P. O. Box 651 Louisiana Public Service Commission Jackson, MS 39205 One American Place, Suite 1630 Baton Rouge, LA 70825-1697 General Manager Plant Operations Entergy Operations, Inc.

P. O. Box B Killona, LA 70066 Licensing Manager Entergy Operations, Inc.

P. O. Box B Killona, LA 70066 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Resident inspector /Waterford NPS Post Office Box 822 Killona, LA 70066 May 1999