ML20073R695

Application for Amend to License NPF-3 Revising Tech Spec Section 4.8.1.2,Tables 4.3-11 & 3.6-2 Re Surveillance Requirements for Automatic Load Sequencer & Monthly Testing of Auxiliary Feedwater Sys Logic

ML20073R695
Person / Time
Site:	Davis Besse
Issue date:	05/02/1983
From:	Crouse R TOLEDO EDISON CO.
To:
Shared Package
ML20073R689	List: ML20073R688 ML20073R695 ML20073R705
References
TAC-46677, TAC-51791, TAC-51792, NUDOCS 8305040497
Download: ML20073R695 (3)

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4 APPLICATION FOR AMENDMENT i

TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No. NPF-3, together with the Safety Evaluation for the requested change.

The proposed changes include:

1. Section 4.8.1.2

2. Table 4.3-11

3. Table 3.6-2 By /s/ R. P. Crouse Vice President, Nuclear t

Sworn and subscribed before me this 2nd day of May, 1983. ,

Laurie A. Hinkle, nee (Brudzinski)

Notary Public State of Ohio My Commission Expires May 16, 1986 '

SEAL 8305040497 830502 PDR ADOCK 05000346 P PDR

I Docket No. 50-346 License No. NPF-3 Serial No. 938 May 2, 1983 Attachment I I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications Section 4.8.1.2.

A. Time required to Implement. This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 80-270B).

This revises a previous submittal (July 10, 1980 Serial No.731) to add only the exception of the automatic load sequencer.

C. Safety Evaluation (See attached)

SAFETY EVALUATION This amendment request is to revise Technical Specifications Sections 4.8.1.2.

Surveillance Requirement 4.8.1.2, applicable in modes 5 and 6 presently requires the Emergency Diesel Generator to be demonstrated as OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for 4.8.1.1.2.a.5. The correct exceptions to be referred are 4.8.1.1.2.a.5 and 4.8.1.1.2.a.7. Surveillance Requirement 4.8.1.1.2.a.7 concerns the verification of the operability of the Safety Features Actuation System (SFAS) automatic load sequence timer. This requirement should be exempted in modes 5 and 6 as the SEAS instrumentation Tech Spec's 3/4.3.2, Table 3.3-3, item 4 is only applicable in modes 1, 2, 3 and 4. It is noted that the operability of the SFAS automatic load sequencer is not required in modes 5 and 6 since the reactor coolant system is sufficiently cooled down and depressurized in these modes and automatic sequence loading of the ECCS loads on the diesel generator in these modes is not needed.

Therefore, it is concluded that the proposed change is not an unreviewed safety question.

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