ML20209E555
| ML20209E555 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/08/1999 |
| From: | Nolan M NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0524, TAC-MA524, NUDOCS 9907150071 | |
| Download: ML20209E555 (3) | |
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k UNITED STATES 9
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j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20566-0001
- .***p July 8, 1999 I
Mr. C. Randy Hutchinson Vice President, Operations ANO
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Entergy Operations, Inc.
1448 S. R. 333 i
Russellville, AR 72801 i
SUBJECT:
COMPLETION OF LICENSING ACTION FOR CLOSURE OF GENERIC LETTER 92 01, REVISION 1, SUPPLEMENT 1 " REACTOR VESSEL STRUCTURAL INTEGRITY," REQUEST FOR ADDITIONAL INFORMATION FOR ARKANSAS NUCLEAR ONE, UNIT 2 (TAC NO. MA0524)
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 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 Reaulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to 10 CFR Part 50.
j 17 On August 11,1995 (OCAN089505), and November 13,1995 (OCAN119502), you submitted your initial responses to GL 92-01, Rev.1, Supp.1, and provided the requested information f
relative to the structural integrity assessment for the Arkar sas Nuclear One, Unit 2 (ANO-2).
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The staff evaluated your responses to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on October 16,1997. However, since the time of the aaff's closure letter, the Combustion Engineering (CE) Owners Group and the Babcock anc '.".'ilcox (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 i
fabricated RPV welds, and BAW-2325, Revision 1, for B&W fabricated RPV welds. In addition, Chicago Bridge and iron BWR data were submitted in Topica! Report BWRVIP-46.
On August 13,1998, the staff issued a request for additional information (RAI) regarding upper / intermediate shell circumferential weld 8-203 (heat number 10137), and the revised reactor vessel fluence determination. In general, with respect to the contents of the RAI, the staff requested that you provide (1) fluence at expiration of license (EOL), (2) ARTuor at M L (3) Margin term, and (4) RTpTs at EOL for weld 8-203; and details on the revised reactor vessel fluence determination (e.g., excore ratios and adjustments to the calculated fluence).
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C. R. Hutchinson 2
July 8, 1999 You provided your response to the staff's RAI for ANO-2 on November 2,1998 (2CAN119803).
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 limiting material for ANO-2 is a plate. The revised chemistry values for the limiting plate resulted in a 4 *F increase in the chemistry factor. This slight increase did not warrant a revision to the pressure and temperature limits. It should also be noted that the methodology for the fluence determination
. that was included in the June 18,1997 (2CAN069709), submittal, and supplemented in the November 2,1998, submittal did not justify the proposed reduction in fluence for ANO-2.
Therefore, the current accepted fluence values are from your letter dated June 18,1991 (2CAN069109), from J. W. Yelverton (Entergy Operations, Inc.), to the USNRC Document Control Desk. The revised fluence should be calculated when the next surveillance capsule is removed and analyzed. This closes the staff's efforts in regard to TAC number MA0524. The staff appreciates your efforts in regard to this matter.
- 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, 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 pressure and temperature limits, pressurized thermal shock, or upper shelf energy should reference the most current information.
- If you hr.ve any questions regarding this matter, please contact me at (301) 415-1320.
Sincerely, ORIGINAL SIGNED BY M. Christopher Nolan, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368 DISTRIBUTION Docket File S.Richards cc: See next page PUBLIC N.Hilton PDIV-1 RF K.Brockman,RIV A. Lee ACRS OGC 4
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Arkansas Nuclear One cc:
Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
1 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, Rackville Nuclear Licensing Framatont Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 -
Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 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