ML18081B251

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Forwards Safety Evaluation Re Override of Containment Purge Isolation.Mods Are Acceptable W/Three Exceptions:Licensee Should Provide spring-loaded Covers Over Buttons,Provide for Sys Level Annunciation & Upgrade Radiation Monitors
ML18081B251
Person / Time
Site: Salem  
Issue date: 01/30/1980
From: Lainas G
Office of Nuclear Reactor Regulation
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML18081B250 List:
References
NUDOCS 8003270092
Download: ML18081B251 (2)


Text

I I

I i UNITEDSTAiES e

NU~AR REGULATORY COMMISSION WASHINGTON, D. C. 20555 JAN 3 0 1980.

MEMORANDUM FOR:

A. Schwencer, Chief FROM:

Operating Reactors Branch #1 Division of Operating Reactors G. Lainas, Chief Plant Systems Branch Division of Operating Reactors

SUBJECT:

SALEM UNITS 1 & 2 - OVERRIDE OF CONTAINMENT PURGE ISOLATION (TAC8993)

Pursuant to TAC 8993, we are providing the enclosed safety evaluation report on this subject.

Our review has concluded that, with three exceptions, the modifications made at the plants have brought the designs into conformance with our cri"teria.

The exceptions are that the licensee should be required to:

1.

Provide spring loaded covers over the existing safety related push buttons that are*mounted on the control roo~ panels within 30 days,

2.

Provide for system level annunciation of the bypassed status of containment ventilation isolation within 90 days, and

3.

Provide a C011iTlitment to upgrade the radiation monitors which initiate containment purge isolation to safety-grade status when and if Revision 1 to Regulatory Guide 1.141 is approved by the Commission, These matters have been discussed with the licensee and he has comnitted to these changes. if they are made official requirements of the Commission.

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i

t JAN :; 0 1980 With this SER we consider the electrical aspects of this TAC to be complete. Operation on an interim basis is acceptable because the schedule requested in item (1) above represents the minimum practical time to procure and install these passive devices, and the schedule requested in item (2) is the minimum practicable time for the design and installation of the required change to the non-safety indication systems, and (3) past operating experience has not indicated any problems with the present radiation monitors that would lead the staff to believe they will fail to perform this safety function until monitors with qualification documentation are installed.

Contact:

R. Scholl, X27162

Enclosure:

Safety Evaluation Report cc w/enclosure:

D. Eisenhut W. Gammi 11 E. Reeves

c. Trammell G. Lainas D. Tandi E. Adensam V. Panciera P. Shemanski R. Scholl PSB Section A J. Zwolinski

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~

ainas, Chief Plant Systems Branch Division of Operating Reactors