ML20138C965

Forwards Application for Amend to License NPF-3,revising Tech Specs Re Water Source for Auxiliary Feedwater Pumps, Safety Grade Flow Indication for Flow Verification & Bases

ML20138C965
Person / Time
Site:	Davis Besse
Issue date:	08/29/1985
From:	Williams J TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20138C971	List: ML20138C965 ML20138C973 ML20138C980
References
1180, TAC-55782, NUDOCS 8510230117
Download: ML20138C965 (2)

Text

I MREDO

%mm EDISON JOE WILUAMS. JR.

Senor vce prenomrt-f* oar (419)249 2300 Docket No. 50-346 14,m 24e se2a License No. NPF-3 Serial No. 1180 August 29, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Stolz:

Under separate cover, we are transmitting three (3) original and forty (40) conformed copies of an application for Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No. 1.-

This application requests that the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications, Appendix A, be revised to reflect the changes attached. The proposed changes involve Section 3.7.1.2, 4.7.1.2 and Bases.

The attachment identifies the changes, safety evaluation and significant hazard consideration. This amendment request is a revision to a previous submittal dated August 27, 1984 (Serial No. 1074). That request identified for the auxiliary feedwater (AFW) system flow verification surveillance testing, locked valve position verification and established communication when testing is performed in Modes 1, 2 or 3. This-submittal results from an NRC letter dated May 9, 1985 (Log No. 1742) requesting a revised application. This application identifies the water source for the AFW pumps, safety grade flow indication used for flow verification and a bases change.

In the review process it was identified that there was an inconsistency with the 18 months surveillance test mode requirements for receipt of an auxiliary feedwater actuation test signal. The steam supply in the steam generator is inadequate to perform the test and the auxiliary boiler steau cannot be auto initiated by the steam and feed rupture control system.

The performance of this test requires the plant to be in Mode 3 with main 8510230117 850829 PDR ADOCK 05000346-p PENT -

THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43G52 0 0,

I l-

-Dockst No. 50-346 License No. NPF-3

' Serial No. 1180 August 29, 1985 Page 2 steam available at >800 psia. The test is presently performed during startup testing in Mode 3. Also, identified is a typographical error in B3/4 7.1.3 Condensate Storage Facilities. The first-line contains the extra words "and to" at the end of the sentence and, therefore, should be deleted.

4 Toledo Edison requests this amendment request be granted by December 1985.

l This is a revision to a previous submittal, therefore, no fee is incurred.

^

Very truly yours, W Je} y JW: GAB:HA f Attachment i

! cc: DB-1 NRC Resident Inspector

! State of Ohio '

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