NOC-AE-03001560, Revised Response to Request for Additional Information Regarding Request for Alternatives RR-ENG-2-35

Revised Response to Request for Additional Information Regarding Request for Alternatives RR-ENG-2-35

ML031920097
Person / Time
Site:	South Texas
Issue date:	07/01/2003
From:	Thomas S South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-03001560, RR-ENG-2-35
Download: ML031920097 (2)

Text

Nuclear Operating Company

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South Tets f! Ekdrin Gewrt Stao PO Bar 28.9 bdmh. Texs 77483A A A July 1, 2003 NOC-AE-03001560 10CFR50.55a U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Unit I Docket No. STN 50-498 Revised Response to Request for Additional Information Regarding Request for Alternatives RR-ENG-2-35

References:

1. Letter, S. E. Thomas to NRC Document Control Desk, "Request for Alternatives to ASME Section XI Requirements Associated with Mechanical Processing of Thermally Cut Surfaces (Relief Request RR-ENG-2-35)," dated June 13, 2003 (NOC-AE-03001551)

2. Letter, S. E. Thomas to NRC Document Control Desk, "Response to Request for Additional Information Regarding Request for Alternatives RR-ENG-2-35," dated June 26, 2003 (NOC-AE-03001558)

The NRC informally requested additional information regarding the request for alternatives submitted in Reference 1 and the response to that information request was provided in Reference 2. As a result of further telephone discussions with the NRC, STP Nuclear Operating Company (STPNOC) is hereby revising our response to question 5 as follows:

5. Will any Examination be done on this item on an ongoing basis? (Every outage or every other outage, etc.)

Response

The original J-groove weld of the two repaired BMI penetrations has been re-classified under ASME Section XI Code inservice inspection (ISI) requirements as a Class 1, Table IWB-2500-1, Examination Category B-N-2, Item B13.60 weld. This weld is an interior attachment to the reactor vessel beyond the core belt region. Accessible interior attachment welds are subject to a VT-3 visual examination of the exposed weld surface under the STPNOC ISI program for the second interval. The VT-3 visual examination of this weld is intended to detect the presence of cracking, corrosion, erosion, or other structural degradation.

N 317 STI: 31623459

NOC-AE-03001560 Page 2 of 2 ISI examinations of reactor vessel interior attachment welds below the core belt region will be performed in conjunction with the examinations of the vessel shell and bottom head welds when the internals and core barrel are removed. The next ISI VT-3 visual examination of the repaired BMI J-groove welds will be augmented with an enhanced visual examination of the boat sample cavities.

If there are any questions regarding this revised response, please contact Mr. Michael Lashley at 361-972-7523 or me at 361-972-7162.

Steven E. Thomas Manager, Plant Design Engineering jtc cc:

(paper copy) (electronic copy)

Ellis W. Merschoff A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 L. D. Blaylock Arlington, Texas 76011-8064 City Public Service U. S. Nuclear Regulatory Commission Mohan C. Thadani Attention: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike R. L. Balcom Rockville, MD 20852 Texas Genco, LP Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Department of Health 1100 West 49th Street C. A. Johnson Austin,TX 78756-3189 AEP Texas Central Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MNI 16 Wadsworth, TX 77483 C. M; Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704