ML20082V311

Safety Evaluation Supporting Amends 166 & 148 to Licenses DPR-70 & DPR-75,respectively

ML20082V311
Person / Time
Site:	Salem
Issue date:	05/03/1995
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082V309	List: ML20082V307 ML20082V311
References
NUDOCS 9505090174
Download: ML20082V311 (2)

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UNITED STATES

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j WASHINGTON, D.C. 30806 4001 j

NUCLEAR REGULATORY COMMISSION L

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,% ******,4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ~

l RELATED TO AMEN 0 MENT N05. 166 Als 148 TO FACILITY OPERATING i

LICENSE NOS. DPR-70 Als DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY i

PHILADELPHIA ELECTRIC COMPANY l

DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 i

1.0 INTRODUCTION

By letter dated August 19, 1994, as supplemented March 15, 1995, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to the Sales Nuclear Generating Station, Unit Nos. I and 2, Technical

j Specifications (TS). The requested changes would add a new action statement to TS 3.1.3.2.1, " Position Indication Systems - Operating".. The March 15, 1995, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.

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2.0 EVALUATION i

The analog rod position indication system is designed so that removal of one Dixon module or removal of one power supply fuse results in the loss of more -

i than one analog position indication. During certain planned activities, it is i

sometimes required to remove one Dixon module or one power supply fuse. This renders two analog position indications inoperable for approximately 30 seconds, a condition for which no action statement is provided in TS 3.1.3.2.1.

Therefore, entry into TS 3.0.3 is required. TS 3.0.3 in this instance requires that within I hour, action shall be initiated to place the unit in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

In addition, since this is a condition prohibited by the TSs, a Licensee Event Report (LER) must be submitted in accordance with 10 CFR 50.73(a)(2)(i)(B).

j The proposed change specifies an action statement that has the same effect as TS 3.0.3 and is comparable with the action statement in Section 3.1.8 of NUREG-1431, Standard Technical Specifications Westinghouse Plants, which is for a digital rod position indication system. However, by specifying an action statement, entry into 3.0.3 is no longer required and the need to submit an unnecessary LER is eliminated.

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In its August 19, 1994, letter, the licensee stated that the proposed change l

was more conservative that NUREG-1431. After discussions with the staff, the i

licensee agreed that this was not so and in its letter of March 15, 1995, withdrew that statement.

i Therefore, since the proposed change is consistent with the current TS l

and eliminates an, unnecessary LER, the staff finds it acceptable, j

3.0 STATE CONSULTATION

i In accordance with the Commission's regulations, the New Jersey State official i

was notified of the proposed issuance of the amendments.

The State official had no coments.

4.0 ENVIRONMENTAL CONSIDERATION

i The amendments change a requirement with respect to installation or use of a i

facility component located within the restricted area as defined in 10 CFR j

Part 20.

The NRC staff has determined that the amendments involve no t

significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no l

public comment on such finding (59 FR 51626). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR j

51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of

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the amendments.

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5.0 CONCLUSION

I The Commission has concluded, based on the considerations discussed above, i

that:

(1) there is reasonable assurance that the health and safety of the i

public will not be endangered by operation in the proposed manner, (2) such i

activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors:

J. Luehman L. Olshan Date: May 3, 1995

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