ML20079D971
| ML20079D971 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/30/1991 |
| From: | Woodard J ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-OR GL-90-06, NUDOCS 9110040264 | |
| Download: ML20079D971 (2) | |
Text
.n - _ . . ,- ~ . . . . ~ . . .
I d-W1
.. 40 invenetA Cener Pwkway Post Offer Box 1295
. B.mnyat Abhwns 3s201
. it?cohone ?OS SOMO% -
r-u J[D. Woodard -/ b M}DMl! N Cf uce ree+ Neem ray m"' ***"" "'" "
Septatber 30, 1991
-Docket Nos. 50-348 50-364 U. S Nuclear Regulatory Commission ATTN: Document Cont rol Desk
~ Washington, DC 20555 Joseph H. Farley Nuclear Plant Request for Extension for Response to Generic Issue 70
" Power-Operated . Relief Valve and Block Valve Reliability" i:
Der Geaeric Letter 90-06 Gentlemen:
On June-25, 1990 the'NRC issued Generic tetter (G.L.) 90-06: Resolution of
. Generic Issue 70, " Power-0perated Relief Valve and Block Valve Reliability," and Generic Issue 94, " Additional Low-Temperature
- Overpressure Protection for Light-Water Reactors." Alabama Power Company
-submitted a response to C.L. 90-06 by letter dated December 14, 1990, in this: letter a commi.tment was made to submit a proposed change to the power-operated relief valve (PORV) technical specification or a
, justification for the current technical ' specification by October 1991.
N This date was selected to' allow time'to develop a plant-specific probabilistic- risk analysis-(PRA) model and cenduct- analysis-with one and two PORV's inoperable. Alabama Power Company wished to coordinate this effort with that required by G.L. 88-20, " Individual Plant Examination (IPE). for Severe Accident Vulnerabilities "
Alabama Power. Company is'. presently performing the PRA analysis-in an effort to quantify the risk associated with operation with one or both PORV's.
L inor 'rable. ' The. intention of this analysis .is'in justify longer allowed
, : outs i times than those specified in G.L. 90-06. However, the PRA model is L not yet complete,- and as such, the necessary technicalLbasis will not be available inLtime to. permit an October 1991 submittal. Based upon the
~
L .
current schedule, the' PRA model will be complete' by the end of 1991.
Therefore, Alabama Power Company will provide a response to Generic 1ssue -
70 by January 31, 1992.
I L. . Alabama Power Company recognizca the'NRC's' assertion that the technical "
specifications should provide assurance of a PORV's ability to perform pressure control functions as wsll as to close and not contribute to-the severity of an. accident as-occurred at THI-2.. Therefore, as-an interim compensatory measure, Alabama Power Company-has-implemented administrative requirements which comply with the limiting conditions of operation as
'specified in Enclosure A, Attachment- A-1 of G.L. 90-06.
9110040264 DR 910930 ADOCK 05000340 f
~ PDR J l 0 m am_ . _ _ _ . _ . _ . _ _ .__ _ __. _ _ __ _ _ _ _
a4 ,, j U. S. Nuclear Regulatory Commission Page 2 These provisions will remain in effect until the results of the PRA are available and a final response to G.L. 90-06 is submitted.
If.there are any questions, please advise.
Respectfully, ALADAMA POWER COMPANY t0. jb )k ANW:
J. D. Woodard /*~
J0W/BHW: map 0775 cc: Mr.- S. D. Ebneter Hr. S. T. Iloffman SWORN TO AND SUBSCRIBED BEFORE ME Mr. G. F. Maxwell Tills 30 S DAY OF 3._,c W , 1991
, Ya e/o !?u ")lr')e:lMc0?
otary P My Comission Expires: /s/es/jp i
L L
i I
i l
l I
f l~
. - - - - - - _ _ _ _ _ _ - - -- - .__ . - . . . ,-- .