ML20209G287

Forwards AEOD/E511, Closure of ECCS Min Flow Valves, Engineering Evaluation Rept.Recommends IE Issue Info Notice to Remind Licensees of Importance of Min Flow Bypass Capability as Essential Pump Protection Feature

ML20209G287
Person / Time
Site:	Peach Bottom, 05000000
Issue date:	08/09/1985
From:	Leeds E NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Seyfrit K NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20209G223	List: ML20209G218 ML20209G287 ML20209G305
References
AEOD-E511, NUDOCS 8509190206
Download: ML20209G287 (2)

Text

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PDR F ROAB CF R0AB SF Eleeds SRubin KSeyfrit TIppolito August 9, 1985 CHeltemes-I MEMORANDUM FOR: Karl V. Seyfrit,-Chief AE0D/E511 Reactor Operations Analysis Branch Office for Analysis and Evaluation

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of Operational Data  ;

[ THRU: Stuart D. Rubin, Chief

-Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data

-FROM: Eric J. Leeds, Reactor Systems Engineer Recctor Systems Section 1 Reactor Operations-Analysis Branch Office for Analysis and Evaluation of Operational Data 4

SUBJECT:

CLOSURE OF EMERGENCY CORE COOLING SYSTEM MINIMUM FLOW VALVES j The enclosed Engineering Evaluation -is forwarded for your information and consideration. The report. concludes that not all, licensees may recognize the importance of minimum flow valves.to Emergency Core Cooling System pump-i operability. It is recommended that AE00 suggest that the Office of-Inspection and Enforcement consider issuing an Information Notice to remind licensees of the importance'of minimum flow bypass capability as an essential pump protecticn feature and the dependency of ECCS pump operability on minimum

. flow' valve operability. .It is als: suggested that the information notice l emphasize that licensees review the control logic of the ECCS minimum flow

', valves to ensure that it is' adequate to satisfy containment isolation requirements, where' applicable.

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.i B509190206 850815 '. I PDR ADOCK 05000278-)

, S PDR R Eric J. Leeds, Reactor Systems Engineer Reactor Systems Section 1

Reactor Operations Analysis Branch Office for Analysis'and Evaluati e 1

of Operational Data l

Enclosure:

1 As stated  :

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