ML20209H525
| ML20209H525 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/15/1999 |
| From: | Nick Hilton NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0523, TAC-MA523, NUDOCS 9907200243 | |
| Download: ML20209H525 (3) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30806 0001 July 15,1999
.g Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.
1448 S.R. 333 I
Russellville, AR 72801 -
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SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 1 - RESPONSE TO THE REQUEST FOR
. ADDITIONAL INFORMATION ON GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO.
MA0523)
Dear Mr. Hutchinson:
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) 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 11,1995, 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 Arkansas 4
Nuclear One, Unit 1 (ANO-1). The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 27,1996. However, since the
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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, and 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 8,1998, the staff issued a request for additional information (RAI) regarding the alloying chemistries of beltline welds, and your assessment of surveillance data for your facility, including pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) 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 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 9907200243 990715 PDR ADOCK 05000313
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b C. R. Hutchinson July 15,1999 10 CFR 50.60,10 CFR 50.61, and Appradices 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 ANO-1 on July 1,19C3. with correcM,
submitted March 11,1999. As a result of the staff's review of your responses to GL 9k s*
Revision 1, GL 92-01, Rev.1, Supp.1, and the Supplement 1 RAI, the statt hac iv/ied one information in the Reactor Vessel Integrity Database (RVID) and is releasing li as L'VID Version 2.
The new database diskettes are posted on the World Wide Web at a location that is linked to the NRC home page (http1/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, or upper-shelf energy should reference the most current information.
This closes the staff's efforts regarding TAC number MA0523. The staff appreciates your efforts in regard to this matter.
Sincerely, ORIGINAL SIGNED BY Nicholas D. Hilton, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313 cc: See next page DISTRIBUTION:
Docket File PUBLIC PD#1V-1 Reading A.D. Lee G. Vissing OGC ACRS K. Brockman, RIV To receive a copy of this document, indicate "C" in the box OFFICE PDIV-1/PM C
PDIV-1/Lp n N PDIV-1/SC C
NAME NHilton:g LBerry h RGramm b DATE
- 7 / /1e/99
/$ /99 1/ d/99 DOCUMENT NAME: G:\\PDIV-1\\ANO1\\LTR0523.wpd OFFICIAL RECORD COPY
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Arkansas Nuclear One cc:
Executive Vice President Vice President. Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 4
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 May 1999
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