ML19270F997

Summary of 790223 Meeting W/Westinghouse & Duquesne Light Re Steamline Break Protection Sys.W/Supporting Documentation

ML19270F997
Person / Time
Site:	Beaver Valley
Issue date:	03/12/1979
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-11010, NUDOCS 7904090331
Download: ML19270F997 (9)

Text

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NRC PUBUC DOCUMENT ROOM

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UNITED STATES y**

y NUCLEAR REGULATORY COMMISSION

{& mj WASHINGTON, D. C. 20555 c

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March 12,1979 Docket No. 50-334 LICENSEE: Duquesne Light Company FACILITY:

Beaver Valley Power Station, Unit No. 1

SUBJECT:

MEETING

SUMMARY

- STEAMLIIM BREAK PROTECTION SYSTEM The licensee and Westinghouse met with the staff on February 23, 1979 to discuss the proposed steamline break protection system at the Beaver Valley Power Station (BVPS), Unit No. 1.

An attendance list is attached as Enclosure 1.

The licensee presented their proposed steamline break protection system as a comparison to their current system by use of the five viewgraphs in Enclosure 2.

The systems were discussed in relation to their logic and function of steam line break location and mode of operation.

Distinctions were made on those systems and components that will not change from the current to proposed operation and to signals in the current system (coincidence Lo-Lo Tavg) which were given no credit in the safety analyses.

During the course of the meeting, questions were developed and provided to the licensee.

They are included in Enclosure 3.

The licensee was requested to respond expiditiously but no later than 30 days.

In addition, the licensee will provide 10 sets of full (or larger size) logic diagrams of the material originally submitted on October 27, 1978.

Dave Wigginton, roject Manag'r Operating Reactors Branch #1 Division of Operating Reactors

Enclosures:

1.

Attendance List 2.

Viewgraphs 3.

Questions 7304090 331

Meeting Sumary for

-2_

March 12,1979 Beaver Valley Docket File NRC PDR Local PDR ORB 1 Reading NRR Reading H. Denton E. Case V. Stello D. Eisenhut B. Grimes D. Davis D. Ziemann P. Check G. Lainas A. Schwencer R. Reid T. Ippolito V. Noonan J. McGough Project Manager OELD OI&E(3)

ACRS (16)

C. Parrish NRC Participants TERA J. R. Buchanan Licensee

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a ENCLOSURE NO. 1 ATTENDANCE LIST MEETING WITH DUQUESNE LIGHT COMPANY FEBRUARY 23, 1979 DUQUESNE LIGHT COMPANY J. J. Carey D. H. Williams WESTINGH0llSE D. Gregg D. Wood EG&G J. H. Cooper NRC - STAFF D. Wigginton H. Li J. T. Beard J. F. Burdoin F. Orr T. Marsh

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ENCLOSURE NO. 3 QUESTIONS:

STEAMLINE BREAK PROTECTION SYSTEM 1.

Please ensure that your Technical Specifications (proposed or existing) provide positive assur'nce that your new system cannot be enabled until the RCS is bora d to a cold shutdown condition.

2.

Provide justification that Safety Injection is not required for all steam line breaks when the " Low Steamline Pressure" portion of the system is disabled (i.e., during heatup and cooldowns).

3.

Show the minimum possible pressurizer level and RCS temperature during a steamline break during heatup/cooldowns (pick worst case initial conditions).

Compare this value to the value with the existing system.

(Scoping calculations are o.k.)

4.

Is the existing system used in the mitigation for the feedwater break accident, or any of the plant transients?

5.

Will the new system get activated during a feedwater accident, or a plant transient? Will you have to take credit for its activation?

6.

Indicate where the instrument channel descriptions are available to NRC.

7.

What specific separation criteria were applied to the sensors, cabling, instruments, and logic for the existing steamline break protection system.

If, as we understand, the same criteria are to be applied for the proposed new system, explain why the criteria are still appropriate and acceptable.

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