ML20127B965

Forwards Request for Addl Info Re Draft Ser.Expedited Response Requested Re Internally Generated Missile Protection & Quality of Instrumentation Indicating LOCA to Reactor Coolant Pumps

ML20127B965
Person / Time
Site:	Beaver Valley, 05000000
Issue date:	08/07/1984
From:	Parr O Office of Nuclear Reactor Regulation
To:	Knighton G Office of Nuclear Reactor Regulation
Shared Package
ML20126J910	List: ML20126J908 ML20126J981 ML20127B938 ML20127B965 ML20127C169 ML20127C196 ML20127C243 ML20127C248 ML20127C259 ML20127C298
References
FOIA-84-926 NUDOCS 8408220120
Download: ML20127B965 (2)

Text

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WASHINGTON, D. C. 20555

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ggg 7 1934 MEMORANDUM FOR: G. Knighton, Chief Licensing Branch #3, DL FROM: 0. D. Parr, Chief Auxiliary Systems Branch, DSI

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR BEAVER VALLEY POWER STATION, UNIT 2 - AUXILIARY SYSTEMS BRANCH In the process of re-reviewing and updating the Auxiliary Systems Branch draft safety evaluation report (DSER) for Beaver Valley Power Station, Unit 2, to reflect the applicant's responses to the previously identified open items, we have identified two additional items that need to be addressed by the applicant. These concerns are identified in the enclosure. Please expedite the applicant's response in order to permit their resolution prior to submittal of our final SER input.

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. D. arr,' Chief Auxiliary Systems Branch Division of Systems Integration

Enclosure:

As stated cc: R. Bernero l

L. Rubenstein T. Novak J. Wenniel J. N. Wilson M. Licitra M. Ley R. Anand

Contact:

R. Anand, D \ -

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c0 REQUEST FOR ADDITIONAL INFORMATION BEAVER VALLEY POWER STATION, UNIT 2 AUXILIARY SYSTEMS BRANCH l

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1. In regard to internally generated missile protection inside and outside of containment (i.e., SRP Section 3.5.1.1 and 3.5.1.2), we are unable l

to confirm that you have properly assumed a single active failure concurrent with postulated internally generated missiles. Verify that redundant safety-related trains are protected from damage which may result from the impact of missiles generated fron nonsafety-related sources consistent with the guidelines of Position C.2 of Regulatory Guide 1.29,

2. Verify that the instrumentation provided for indication of los.; of component cooling water to the reactor coolant pumps is safety grade (in accordance with IEEE 279) as identified in Part 4d. of the Review Frocedures of SRP Section 9.2.2.

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