ML20058D076
| ML20058D076 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/23/1993 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9312030047 | |
| Download: ML20058D076 (2) | |
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Southem Nactear Operating Company
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Post Omce Box 1295 i
. Bemingham. Alabama 05201 i
Telephone (205) 66B-5131 L
Southem Nudear Operating Company l
i o.ve uor y ve. Prescent Farley Pro 3ect the Southern elecinC system November 23, 1993' Docket No. : 50-364 i
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U.S. Nuclear Regulatory Commission
.l ATTN: Document Control Desk j
Washington, D.C. 20555 Joseph M. Far'cy Nuclear Plant - Unit 2 Interim Pluceine Criteria Analysis Repo_r1 j
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Gentlemen:
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By letter dated October 20,1993, the NRC issued Amendment No 94 for Unit 2 of the Joseph M. Farley Nuclear Plant concerning steam generator tube interim plugging criteria.
The Safety Evaluation for the amendment required that the following data be submitted j
either prior to restart or shonly after completion of the outage:
i Requirement Results i
i Repon probability of tube burst, consistent 6.1 x 10-5 u_ sing a 60%,
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with the requirements of WCAP-12871, probability ofdetection and j
Revision 2.
including all bobbin -
indications leftin service.
Repon primary-to-seccndary leakage 0.270 gpm using'a 60%
during a postulated main steam line break probability ofdetection and calculated as described in draft NUREG-including allbobbin 1477.
indications left in service.
-l Repon any unexpected inspection findings' No unexpected mspection j
relative to the assumed characteristics of findings relative to the j
flaws at the tube suppon plate, i.e., -
3ssumed characteristics of j
detectable circumferential indications or tlaws at the tube support detectable indications cutside the tube -
plate.
suppon plate thickness.
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o U. S. Nuclear Regulatory Commission Page 2 On November 18,1993, a conference call was held between the NRC Staff and the Farley Licensing Staff to discuss the results of the Farley Unit 2 steam generator inspections.
The two primary points of dbcucion, unusual inner diameter phase angle indications and previous voltage undercalls, will be further discussed in the assessment of the interim plugging criteria methodology required by the Safety Evaluation. The further assessment of the interim plugging criteria methodology will be forwarded after the completion of the outage.
If there are any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COh.PANY
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Dave Morey l
f REM: IPCU2C9 Doc l
i cc-Mr. S.D. Ebneter l
Mr. T. A. Reed Mr. B.L. Siegel j
l Mr. T.M. Ross i
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