ML20079D971

Requests Extension to Respond to Generic Ltr 90-06, Resolution of Generic Issue 70, PORV & Block Valve Reliability & Generic Issue 94, Addl Low Temp Overpressure Protection for LWRs Until 920131

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" Der Geaeric Letter 90-06 i:

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 L

available inLtime to. permit an October 1991 submittal.

Based upon the 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

. Alabama Power Company recognizca the'NRC's' assertion that the technical L.

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 910930 DR 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 S

Tills 30 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~

.