1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks
| ML20210K868 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/29/1999 |
| From: | Vandergrift J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20210K871 | List: |
| References | |
| 1CAN079903, NUDOCS 9908060242 | |
| Download: ML20210K868 (2) | |
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Entergy operations,Inc.
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1448 S.R. 333 RussePv4 AR 72801 Tel 501858 5000 July 29,1999 1CAN079903 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OPI-17 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Addendum to Topical Report BAW-2346P in Support of Proposed Technical Specification Changes Revising Steam Generator Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks Gentlemen:
By letter dated June 1,1999 (ICAN069902), Entergy Operations submitted proposed Arkansas Nuclear One, Unit 1 (ANO-1) technical specification (TS) changes to revise once through steam generator (OTSG) tubing surveillance requirements to provide alternate repair criteria (ARC) for tube end cracks. Much of the basis for the proposed TS changes is contained in topical report BAW-2346P, Alternate Repair Criteria for Tube End Cracking in the Tube-to-Tubesheet Roll Joint of Once Through Steam Generators," Rev. O. This topical report included leak rate values based on worst case bounding main steam line break (MSLB) tube loads for Babcock and Wilcox plants.
The attached non-proprietary addendum to Topical Report BAW-2346P, Rev. O, includes leak rate values based on ANO-1 plant specific MSLB tube loads. These plant-specific leak rates will be utilized during implementation of the ARC for tube end cracks. The data in addendum Tables B-1 and B-2 replace the MSLB portion of Table 7-1 in the topical report.
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The data in addendum Tables B-3 and B-5 replace Table 7-5. Addendum Tables B-4 and B-6 replace Table 7-6.
Addendum Figures B-1 and B-3 replace Figure 7-1, while addendum Figures B-2 and B-4 replace Figure 7-2.
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The information included in the attached addendum does not affect the TS amendment request, no significant hazards consideration or environmental impact evaluation included in 0
the June 1,1999, letter.
0 0600M 9900060242 990729 PDR ADOCK 0500035.3 PDR p
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U. S. NRC l'
July 29,1999 1CAN079903 Page 2 Should you have any questions concerning this submittal, please contact me.
Very truly yours, f
y andergrift irect r, uclear Safety JDV/jj attachment cc:
Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 l
NRC Senict Resident Inspector Arkanses Nuclear One P.O. Box 310 London, AR 72847 Mr. Nick Hilton NRR Project Manager Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, MD 20852 l
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