ML20099G919
| ML20099G919 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/12/1992 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-20, NUDOCS 9208180023 | |
| Download: ML20099G919 (1) | |
Text
Souther. Nuciew OpsranN Compa,y s
Por) Mce Boa 1295 Le Arc %v. /Cacama 35?01
'r le:ephow 205 808 5006 u
O i
J. D. Woodard EINh$
Aug" 12, 1992 v*
Docket Nos. 50-348 g-50-364 1
U. S. Nuclear Regulatery Commission ATTN: Cocument Controi Derk M
Washington, D.C.
20555 pg -
Joseph M. Farley Nuclear Plant Potification of IPE Submittal Extensio2 Gentlemen:
In a letter dated October 26, 1989, Alabama Power Company indicated that g
the results of tha Indi.
Pl>:.6 Examination (IPE) for Farley Nuclear Plant would be <
NRC in September 1C92.
This submittal date was based or estimates for the conduct of tne IPE contained in (
38-20 using common resources for Farley y*4 Nuclear Plant
.#ie uectric Generating Plant. The actual effort to pmvitie IPE anaiyses consistent with the requirements of Generic Letter 88-20 and NUREG-1335 has prove.1 to be significantly greater than that estimated in Generic letter 88-20.
At this t;me it is evident that subM. nth i additional effort will be necessary to ensure that the model res? st.t.J iy reflects the design and operation of Farley Nuclear Plant, in acadon, with one vendor providing technical support for the probabilistic risk assessment (PRA) for both Farley Nuclear Pla;t and Vogt 3 Electric Generating Plant, conflicts have developed in the use of common resources which has resulted in delays.
Therefore, SNC is extending its submittal date for the results of the Farley IC to June 30, 1993.
As most recently stated in a letter dahd JanJary 31, 4992, a final respense to Generic Letter 90-06, " Resolution of Generic Issue 70, ' Power-Operated Relief Valve and Block Valve Reliability,' and Generic Issue 94,
' Additional low-Temperature Overpressure Protection for Light-Water Reactors'" would be provided upon completion of the PRA nalysis.
The PRA model would be used to evaluate the allowed outage times for power-operated relief valves, However, in light of the delay of the nRA effort, a proposed te).nical specification change, which is casistent with the guidance provided in G.L. 90-06, will be submitted by October 30, 1992.
If you havc any questions regarding this request, please advise.
Respectf?lly submitted, khd)rk 9208180023 m e12 DR ADOcK ObOO O
D} Woodatd JDW/DEMc: map wp.shrd i
cc: Mr. S. D. Ebneter
.Q; i
C Mr. S. T. Hoffman Mr. G. F. Maxwe
-