ML20091Q702
| ML20091Q702 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/31/1992 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9202050087 | |
| Download: ML20091Q702 (2) | |
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Southom Nuclear Oper:tino Company e
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Post Ofrc3 Box 1295.
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Southern Nudear Operating Company
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Vsce Presdent doe South &tn cloclic Jystem Faty Project-January 31, 1992 Dncket.Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN:: Document-Contral Desk l-Washington, DC 20555 b
Joseph M. Farley Nuclear Plant
- Request for Cxtension for Response.to Generic Issue 70
" Power-0perated Relief Valve and Bleck Valve Reliability" Der Generic letter 90-06 Gentlemer,:
- 0n' June 1", 2 00-the NRC issued Generic Letter (G.L.) 90-06, " Resolution of Generic _Issus 70, ' Power-Operated Relief Valve and Block Valve Reliability,'
and Generic-Issue 94, ' Additional Low-Temperature Overpressure Protection for Light-Water. Reactors.'" Alabama Power Company submitted ar. initial response to C.L. 90-06 by_ letter dated December ~ 14, 1990, in this letter Alabama Power
. Company cosnitted to submit a response to Generic Isst.e 70' relating to the power-operated relief valve- (PORV) technical specification by October 1991.
4 This (ate = was selected.to. allow time to develop a plant-specific probabilistic risk. analysis (PRA) model and conduct analyses with one and two PORV's inoperable. The intention of this approach was to justify lon9er allowed p
outate times than those specified in G,L. 90-06, Alabama Power Company notified the NRC by letter dated September 30,-1991 that the efforts-associated with developing the PRA models, which are being coordinated with the efforts! required by G.L. 88-20, " Individual Plant Examination (IPE) for Severe-Accident Vulnerabilities,"'are not progressing as-originally predicted. Therefore, a commitment was made fo.' a January 31, 1992
- submi tt-1, date~. As an interim compensatory measure, in September 1991 Alabama Power 1 Company met the intent of the generic letter by implementing asT,inistrative requirements which comply with the limiting conditions for y
operation as specified in Enclosure'A,. Attachment A-1 of G.L. 90-06.
The PRA model has not yet been completed, and as such, the necessary basis for
.an-FNP-specific allowed outage time for PORV's and block valves will not be 1/1 eailable to permit a January 31, 1992 submittal, lherefore, Southern Nuclear Operating Company will provide 'a response to Generic Issur 70 upon completion ofithe=PRA analysis which is tentatively scheduled for September 1992.
The administrative requirements described above will remain in effect until the results:of the'PRA are available and a response is submitted.
9202050087 920131 PDR' ADOCK 05000349
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U. S.. Nuclear Regulatory Commission.
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-If there.are questions, please advise.
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Respect'.ully, SOUTHERN NUCLEAR OPERATING COMPANY
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