ML20134B315

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Safety Evaluation Supporting Amends 188 & 171 to Licenses DPR-70 & DPR-75,respectively
ML20134B315
Person / Time
Site: Salem  
Issue date: 01/23/1997
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20134B306 List:
References
NUDOCS 9701300030
Download: ML20134B315 (3)


Text

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WASHINGTON, D.C. 30666-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REL8JED TO AMENDMENT NOS. 188 AND 171 TO FACILITY OPERATING LICENSE N05. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COtiPANY PHILADELPHIA ELECTRIC COMPANY 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

1.0 INTRODUCTION

By letter dated October 24, 1996, supplemented December 23, 4i96, the Public 4

Service Electric & Gas Company (the lic.ensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit Nos.1 and 2, Technical Specifications (TSs). The requested changes would revise TS 3/4.7.1.2,

" Auxiliary Feedwater System," by changing the 18-month surveillances performed on the system's pumps and valves because testing of the turbine driven Auxiliary Feedwater (AFW) pump can only be performed in higher modes when sufficient secondary steam pressure exists. The December 23, 1996, letter proposed changes to TS 3/4.3.2 to provide consistency with those proposed in the October 24, 1996, letter and therefore did not change the initial proposed no significant hazards consideration determination and was within the scope of the initial Federal Reaister notice.

2.0 EVALUATION TS 4.7.1.7.c.2 is performed to verify that the AFW pumps start autocatically upon receipt of an actuation signal. The motor-driven pumps can be tested in the shutdown condition. However, since steam is needed to drive the ?.urbine driven AFW pump (TDAFWP), it cannot be tested until the necessary secondary steam pressure is available, which occurs in Mode 3.

TS 4.0.4 prohibits entry into an OPERATIONAL MODE without having performed the required surveillances.

Thus, the licensee proposed a change to TS 4.7.1.2.c.2 which states that the provisions of TS 4.0.4 are not applicable to the TDAFWP provided that the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the secondary steam pressure is greater than 680 pounds per square inch (psig). This is consistent with the changes approved by the staff in Amendment 165 for Unit I and Amendment 146 for Unit 2, dated April 17, 1995.

Since the exception to TS 4.0.4 is necessary to accommodate testing of the TDAFWP and the proposed change is consistent with previously approved amendments, the staff finds this change acceptable.

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1 The licensee proposed to delete "during shutdown" from TS 4.7.1.2.c.

As explained above, the TDAFWP cannot be tested during shutdown. Therefore, the l

staff finds the change acceptable.

The licensee also proposed a change to TS 4.7.1.2.c.2 which allows the automatic start to be initiated by either an actual or a simulated signal, rather than just a simulated signal.

(The licensee changed the original wording of " test" signal to " simulated" signal for consistency with NUREG-1431, " Standard Technical Specifications - Westinghouse Plants," Revision 1, dated April 7, 1995.) The staff concludes that for the purposes of this surveillance, it makes no difference if the automatic start is initiated by an actual or a simulated signal; therefore, the staff finds this change acceptable.

The licensee proposed a change to TS 4.7.1.2.c.1 from "each automatic valve in the motor driven pump flow path" to "each auxiliary feedwater automatic valve i

that is not locked, sealed, or otherwise secured in position". The change expands the scope of the surveillance to include the TDAFWP start-stop valves.

The staff concludes that this change is more conservative (an additional valve is included in the surveillance), that the wording is consistent with NUREG-1431, and it is therefore acceptable.

F By letter dated December 23, 1996, the licensee proposed a change to TS 4.3.2.1.3.

This change provides consistency with the change in TS 4.7.1.2.c.2 and, therefore, it is acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendments.

The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendments change surveillance requirements. The NRC staff has determined that the amendments involve no 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 public comment on such finding (61 FR 58905). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 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 the amendments.

5.0 CONCLUE10N The Commission has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such

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, 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 Contributor:

L. 01shan l

Date: January 23, 1997 4