NUREG/CR-4077, Recommends Board & Industry Notification of Westinghouse Owners Group Ack of Possible Failure of Secondary O-ring Seal Matl Used in Reactor Coolant Pump Seal Assemblies. NUREG/CR-4077 Re Aecl Seal Test Program Encl

Recommends Board & Industry Notification of Westinghouse Owners Group Ack of Possible Failure of Secondary O-ring Seal Matl Used in Reactor Coolant Pump Seal Assemblies. NUREG/CR-4077 Re Aecl Seal Test Program Encl

ML20132D078
Person / Time
Site:	Diablo Canyon
Issue date:	05/24/1985
From:	Knight J Office of Nuclear Reactor Regulation
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML16341D295	List: NUREG/CR-4077, Recommends Board & Industry Notification of Westinghouse Owners Group Ack of Possible Failure of Secondary O-ring Seal Matl Used in Reactor Coolant Pump Seal Assemblies. NUREG/CR-4077 Re Aecl Seal Test Program Encl
References
RTR-NUREG-CR-4077, TASK-A-44, TASK-OR NUDOCS 8506110613
Download: ML20132D078 (2)

Text

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MEMORANDUM FOR: Hugh L. Thompson, Director Division of Licensing FROM: James P. Knight, Acting Director Division of Engineering

SUBJECT:

BOARD NOTIFICATION REGARDING REPORT ON REACTOR COOLANT PUMP SHAFT SEAL BEHAVIOR DURING STATION BLACK 0UT (APRIL 1985 NUREG/CR-4077)

References:

1) Memo from D. Eisenhut to the Comission dated September 21, 1983, Board Notification Re Westinghouse Reactor Coolant Pump Seals (garding BN-83-139)

2) Memo from'*D. Eisenhut to the Commission dated April 19, 1984, Board Notification Regarding Westinghouse Reactor Coolant Pump Seals (BN-84-076)

3) Memo from D. Eisenhut to the Comrpission dated ,

. June 29, 1984, Board Notification Regarding Westinghouse Reactor Coolant Pump Seals (BN-84-123)

Board Notification BN-84-076 made the boards aware of the reactor coolant pump (RCP) seal test program at Atomic Energy of Canada Limited (AECL) and the preliminary test results which indicated failures of certain secondary seal materials at conditions which could be expected to occur during extended station blackout. Board notifications BN-83-139 regarding results from a Westinghouse test program and BN-84-123 regarding French RCP seal testing, provided information from other sources regarding possible reactor coolant pump seal failures.

The RCP seal test program at AECL is now complete and the final results have been published in NUREG/CR-4077, Reactor Coolant Pump Shaft Seal Behavior During Station Blackout, dated April 1985. The report suggests several failure modes which could result in large leakage through RCP seals during extended station blackout. The report gives detailed information on the test program and the implications of the results, including identification of secondary seals in present use which may be likely to fail in a station blackout.

Contact:

J. Jackson Ext. 27930

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MAY 2 4 1985 Hugh L. Thompson The Westinghouse Owners Group (WOG) has acknowledged the possible failure of a secondary 0-ring seal material (Parker E515-80) used in Westinghouse RCP seal assemblies and has comitted to the replacement of the 0-rings presently used in the RCPs of Westinghouse plants. This commitment is outlined in a letter (0G-142) from J. J. Sheppard, Chaiman of WOG, to Harold Denton dated January 3,1984.

We recomend board notification of this additional informaton as it relates to the previous referenced board notifications and industry wide notification through an IE bulletin or information notices.

arres P. Knight, Acting Director ivision of Engineering

Contact:

J. Jackson Ext. 27930

Enclosures:

1. NUREG/CR-4077

2. WOG Letter OG-142 l

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