ML20137C004

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Discusses Four Areas of ACRS Interest Resulting from Review of ACRS Rept.No Opponent Connection Found Between Four Areas & Schedule for Sser 1
ML20137C004
Person / Time
Site: Beaver Valley
Issue date: 01/09/1986
From: Carey J
DUQUESNE LIGHT CO.
To: Rubenstein L
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-03, REF-GTECI-A-47, REF-GTECI-SG, REF-GTECI-SY, RTR-NUREG-0844, RTR-NUREG-844, TASK-A-03, TASK-A-3, TASK-A-47, TASK-OR 2NRC-6-003, 2NRC-6-3, TAC-62883, NUDOCS 8601160158
Download: ML20137C004 (2)


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Pittsburgh, PA 15205 January 9, 1986 United States Nuclear Regulatory Commission A

Washington, DC 20555 ATTENTION: Mr. Lester S. Rubenstein PWR Project Directorate No. 2 Office of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 ACRS Report Gentlemen:

Duquesne Light Company (DLC) has reviewed the ACRS report as requested in Mr. Knighton's letter dated Novenber 22, 1985, and has identified four areas of ACRS interest.

1.

The ACRS wishes to be kept infonned regarding resolution of open issues.

Although their report does not specifically identify what infonnation the ACRS is seeking in that regard, we assune it is a standard request which the staff understands and deals with routinely through such actions as providing SER suppl enents.

Therefore, unless the staff perceives a need for DLC to deal directly with the ACRS on this request, we believe no DLC action is necessary, 2.

The conmittee reconmends that DLC evaluate the seismic capability of the decay heat renoval systen.

It appears the conmittee is not aware that the BVPS-2 decay heat renoval systen is designed as a seismic Category I systen.

The staff should refer then to the appropriate SER sections which document the acceptability of this system.

3.

The report indicates the capability of stean lines to acconinodate the consequential effects of overfilling the stean generators fran any cause, such as instrument f ailures, tube ruptures, etc.,

has not been fully addressed.

Whil e it is not apparent what other causes the ACRS had in mind, the resolution of USI A-3 and A-47 are intended to deal with the instrunent f ailure and tube rupture scenarios.

NUREG 0844, "NRC Integrated Progran for Reso-lution of Unresolved Safety Issue A-3 (Stean Generator Tube Rupture)," indicates that resolution will be obtained as part of an on-going generic progran involving USI A-47.

Since resolution of USI A-47 has not been reached, the ACRS conclusion that the gC*\\

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i Unit:d States Nuclear R:gulatory Commission Mr. Lester S. Rubenstein ACRS Report Page 2 staff will fail to address all pertinent aspects of this matter would seen prer.atur e.

DLC believes that duplication of staff efforts in this regard is unnecessary.

4.

The ACRS wishes to be briefed "before impl enentation" of an alternate pipe rupture progran for non-primary systens.

To the best of our knowledge, the pre-implenentation briefings occurred prior to the BVPS-2 ACRS subconmittee meeting and resulted in a f avorable reaction fran ACRS with no restrictions on implenenta-tion. We understood that the ACRS wished to periodically monitor the activity as it was perfonned, however.

DLC is Pchently implenenting the progran and will assist the staff in any further presentations as requested.

We see no apparent connection between these four areas and a schedule for SER Supplenent No.1 DUQUESNE LIGHT COMPANY l

By J. V.tGerey Vice Pfesident GLB/wjs cc: Mr. G. W. Knighton Mr. B. K. Singh, Project Manager Mr. G. Walton, NRC Resident Inspector