ML18101A660

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Supplemental SE Supporting Util Deviation from Reg Guide 1.97,Rev 2 Re Plant Er Capability
ML18101A660
Person / Time
Site: Salem  
Issue date: 04/25/1995
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18101A659 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9504280305
Download: ML18101A660 (2)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTO!'<I, D.C. 20555--0001 CONFORMANCE TO REGULATORY GUIDE 1.97 PUBLIC SERVICE ELECTRIC AND GAS COMPANY S~LEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311

1.0 INTRODUCTION

On June 17, 1985, we issued a Safety Evaluation regarding Public Service Electric and Gas Company's conformance to Regulatory Guide (R.G.) 1.97, Revision 2, for the Salem Nuclear Generating Station, Units 1 and 2.

The staff accepted the licensee's deviations from the guidance in R.G. 1.97.

In a submittal dated June 27, 1994, the licensee documented additional deviations concerning the instrumentation that monitors containment isolation valve position.

2.0 EVALUATION R.G. 1.97 recommends Category 1 position indication instrumentation for containment isolation valves.

The licensee's position indication instrumentation for containment isolation valves meets these recommendations except as described below.

Four air-operated containment isolation valves have position indication instrumentation that is not qualified for a harsh environment.

However, since the Emergency Operating Procedures direct the operator to verify the position of these valves prior to their exposure to a harsh environment, we find this qualification acceptable.

Ten other air-operated containment isolation valves have qualified flow instrumentation in lieu of valve position instrumentation.

Flow indication is an acceptable alternative method for determining valve position.

Eight motor-operated containment isolation valves are administratively controlled and locked in position by removal of the power supply.

Manual containment isolation valves are also administratively controlled and locked in position. Therefore, since the operator is aware of the position of these valves and the valves cannot change position, position indication is not necessary.

9504280305 950425 PDR ADOCK 05000272 P

PDR

3.0 CONCLUSION

Based on our review of the submittal, we have concluded that the licensee has provided adequate justification for deviations from to R.G. 1.97, Revision 2, for the instrumentation that monitors containment isolation valve position at the Salem Nuclear Generating Station, Units I and 2 and is, therefore, acceptable.

Principal Contributor:

B. Marcus Date:

April 25, 1995