ML20135G350

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Summarizes 850320 Meeting W/Westinghouse & PG&E Re Proposed Removal of Auto Closure Interlock on RHR Drop Line. Westinghouse Currently Performing PRA Study to Demonstrate That Overall Safety Will Be Improved by Removing Interlock
ML20135G350
Person / Time
Issue date: 04/18/1985
From: Jensen W
Office of Nuclear Reactor Regulation
To: Sheron B
Office of Nuclear Reactor Regulation
Shared Package
ML20132C684 List:
References
NUDOCS 8509180453
Download: ML20135G350 (1)


Text

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Brian W. Sheron, Chief Reactor Systems Branch DSI -

ROM: Walton L. Jensen, Section A Reactor Systems Branch, DSI *

SUBJECT:

AUTO CLOSURE INTERLOCK MEETING MINUTES On March 20, 1985, representatives from the Reactor Systems Branch met with Westinghouse and Pacific Gas and Electric to discuss proposed removal of the auto-c.losure interlock on the Residual Heat Removal drop line that is required by Branch Position RSB 5-1. PG&E requested that auto-closure be removed to prevent inadvertent loss of RHR suction and possible pump damage. The staff

, had transmitted a letter to PG&E requesting additional evaluation dated January 23, 1985.

Westinghouse is currently performing a PRA study by which they expect to demonstrate overall safety will be improved by removing the interlock. The request for interlock removal including the PRA study is expected to be sub-mitted in August or September 1985. PG&E requests staff approval by January 1986 for implementation in the mid 1986 Diablo Canyon Unit I refueling outage..

The licensee currently favors replacing the interlock with a system of lights and alarms for one or more drop 1.ine valve left open at high pressure. One staff member suggested that a mechanism be evaluated by which both valves would be closed by operator action to close either.

. Original signed by s Walton L. Jensen, Section A Reactor Systems Branch Division of Systems Integration cc: RSB S/L Cistribution E. Lant: 45B R/F T Dur.r.i ng 059 S/F: Br. Misc.

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