ML20198T476
| ML20198T476 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/10/1997 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20198T480 | List: |
| References | |
| GL-95-05, GL-95-5, NUDOCS 9711170007 | |
| Download: ML20198T476 (3) | |
Text
DavoMorey Southern Nucleat y
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E0. Box 1295 Birmirgham. Al*bama 35'01 Tel 205 932.5131 SOUTHERN COMPANY November 10, 1997 Eurgy ro Serve %r%W" Docket Nos.: 50-348-50-364 U.S. Nuclear Regulatory Commission ATTN: - Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Regvest for information Regarding Steam Generators Ladies and Gentleme...
By letter dated March 7,1997, Southern Nuclear (SNC) forwarded the Farley Unit 2 ninety day report for voltage-based alternate repair criteria. Included in the March 7 submittal was a summary of small probe (0.640 inch diameter) qualification tests conducted on Farley Unit 2.
The NRC Staff was requested to approve the use of the small bobbin probe based on the test results as required by Generic Letter 95-05.
Several issues / requests have recently arisen as a result of this submittal.
First, the Farley Unit 21996 Alternate Repair Criteria 90 Day Report, SG-97-03-0001, was marked as " WESTINGHOUSE PROPRIETARY CLASS 3." This resulted in the document not being placed in the public document room. As discussed in Westinghouse WCAP-7211, Revision 2, Energy Systems Business Unit Procedures for the Protection of Westinghouse Information and Westinghouse Management of our Obligation to Protect Customer (Other Party) Furnished Proprietary Information, Westinghouse Proprietary Class 3 is actually non-4 proprietary. The information is available for general distribution. Consequently, this information may be t.eated as non-proprietary. Additionally, the Farley Unit i 1997 Alternate Repair Criteria 90 Day Report, SG-97-08-004, with the same markings should also be treated as non-proprietary.
\\gl Second, a copy of reference 11.8 of the Farley Unit 21996 Alternate Repair Criteria 90 Day Report was requested by the NRC Staff. A copy of the reference is provided in Enclosure 1.
The reference, Farley Unit-2 Small Bobbin Probe (0.640") Qualification Test Report, SG 01-002, documents the testing conducted on Farley Unit 2 to qualify the small bobbin probe for use in the alternate repair criteria. As stated in the report, qualification of the probe should be considered generic in nature and applicable to other plants with 7/8 inch diameter steam 9711170007 971110
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U.S. Nuclear Regulatory Commission Page 2 generator tubes. The qualifict. tion program was previously attempted at both D. C. Cook Unit I ano Farley Unit 1. As briefly discussed in Enclosure 1, the D. C. Cook test had only twelve RPC confirmed indications and, as a result, did not have an adequate sample size. While the Farley Unit I test had an adequate test sample size, the evaluated data points were all less than the 2 volt repair limit. Consequently the results are distorted without data points above the repair limit. The Parley Unit 2 test is the first to have an adequate sample size with an adequate flaw distribution.
Third, the request for use of the small probe was submitted in conjunctic vith the Farley Urtit 2 ninety day report and was docketed only on Unit 2. A question has arisen as to whether the request is only for use on Unit 2 or intended for use on both units. The small bobbin probe will be used on both Farley units when approved by the NRC Staff.
If you have any questic+ please advise.
Respectfully submitted, l' 'l 2hr Dave hforey REhi/cht: CLASS 3. DOC Enclosure cc:
hir. L A. Reyes, Region 11 Administrator hir. J.1. Zimmerman, NRR Project hianager hir. T. hl. Ross, Plant Sr. Resident inspector
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ENCLOSURE Farley Unit-2 Small Bobbin Probe (0.640") Qualification Test Report SG-97-01-002 i