ML20203L750

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Forwards Insp Rept 50-344/86-32 on 860804-14.Potential Generic Question on RHR Pump Runout for Westinghouse Reactors During Recirculation Phase Identified
ML20203L750
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 08/25/1986
From: Kirsch D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20203L752 List:
References
NUDOCS 8608290153
Download: ML20203L750 (1)


See also: IR 05000344/1986032

Text

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AUG 251986

MEMORANDUM TO: E. L. Jordan, Director

Division of Emergency Preparedness and Engineering Response

FROM: Dennis F.- Kirsch, Director

Division of Reactor Safety and Projects

SUBJECT: POTENTIALLY GENERIC QUESTION ON RESIDUAL HEAT REMOVAL (RHR)

PUMP RUNOUT FOR WESTINGHOUSE REACTORS DURING RECIRCULATION

PHASE

Inspection Report 86-32 for the Trojan Nuclear Power Plant identified a

finding that with a single failure of.a RHR pump during the recirculation

phase af ter a Loss of Coolant Accident (LOCA), there was a potential for RHR

pump cavitation (See Enclosure for details). As the report indicates the

question of generic applicability was-asked of Westinghouse by the Trojan

licensee and there was indication that similar problems occurred or were

possible at other facilities. The ' result of a loss of all RHR flow (a single

failure and the other train failure due to cavitation or runout) is obviously

significant as it would result in the loss of all recirculation flow

following a LOCA. Actions taken by the Trojan licensee are specified in the

Enclosure. Inspection of the other, similarly designed Westinghouse plants

in the region (Diablo Canyon) concluded that because of procedural

differences that Diablo Canyon was not susceptible to the problem.

Contact for the Trojan licensee is Gary Zimmerman, telephone number: (503)

226-8119, address: Portland General Electric Company, 121 S. W. Salmon

Street, Portland, Ores,on 97204.

CrWe q.,M b'y

D. F. Drs.h

Dennis F. Kirsch, Director

Division of Reactor Safety and

Projects

Contact: M. Mendonca

Enclosure: Excerpt from Report Number 50-344/86-32

cc w/ enclosure:

T. Novak

J. Partlow

T. Chan

J. Dyer

A. Howell

A. Chaffee

D. Pereira

bec w/ enclosure: RSB/ Document Control Desk (RIDS); Project Inspector;

Resident Inspector; G. Cook; B. Faulkenberry; J. Martin

Region V

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