ML20002E130

Revision to 810105 Application to Amend License NPF-3, Changing Tech Specs Sections 3,4 & 6 to Support de-automation of Incident Level 5 of Safety Features Actuation Sys

ML20002E130
Person / Time
Site:	Davis Besse
Issue date:	01/15/1981
From:	Crouse R TOLEDO EDISON CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML20002E131	List: ML20002E130 ML20002E135
References
678, NUDOCS 8101260487
Download: ML20002E130 (3)

Text

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e Dock No. 50-346 gg L uense No. NPr-3 A caac P Caomss Serial No. 678 s(e %ssect January 15, 1981 Zm, y h

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Director of Nuclear Reactor Regulation d'

2l3 qs Attention: Darrell G. Eisenhut, Director I;d N

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Washington, D.C.

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Dear Mr. Eisenhut:

On January 5, 1981, Toledo Edison submitted (letter Serial No. 675) a package to support de-automation of Incident Level 5 of the Safety Features Actuation System (SFAS) at the Davis-Besse Nuclear Power Station, Unit 1, (DB-1).

Also on that day, members of my staff met with you and your staff in Bethesda, Maryland, to discuss this proposal for manual action to provide appropriate long-term post-loss of coolant accident (LOCA) core cooling.

Several discussions have transpired since that time with your staff. As a result, we have altered the proposed modification compared to the one presented on January 5, 1981. Toledo Edison's letter of January 9,1981, (Serial No. 676) transmitted the electrical drawings describing the current proposed electrical changes. Specifically, the proposed modification re-tains the SFAS Incident Level 5 to provide a permissive function for control room operator action. This letter transmits the following:

Attachment A: Three (3) original and forty (40) conformed copies of an application for an Amendment to the Davis-Besse Facility Operating License No. NPF-3.

This attachment supersedes in total Attachment A of Toledo Edison's January 5, 1981, submittal. This Attachment A identifies the specific pro-posed changes to the technical specifications, the safety evalu-ation supporting analysis and the schedule to implement the pro-posed amendment.

Attachment B: This provides the draft proposed modifications to the emergency operating procedures and the system operating pro-cedures that are to be made reflecting the actions required to

.nanually initiate long-term post-LOCA recirculatic'n core cooling.

Only the major revisions from Attachment B of the January 5, 1981, submittal are provided. All previous references to six feet will now read eight feet.

Attachment C: This provides, in verbal form, a description of how the electrical modification proposed in our submittal of January 9, 1981, functions.

THE TOLEDO ED! SON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652

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0 Docket No. 50-346 License No. NPF-3 Serial No. 678 January 15, 19J1 All control room personnel will ' e trained in the procedural revisions pricJ to their standing watcher af ter system modification. Additionally, the prime responsibility for e 4uring the manual shifting will be assigned to a dedicated licensed operator. This person is planned to be the same operator currently stationed for reactor coolant pump termination upon injection mode initiation.

This physical modification requires testing to verify its completion. As a result, this modification is to be completed during an outage period.

This will be done the first outage of duration greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in operational Mode 4 after NRC approval.

Very truly yours, RB W

~sc RPC:TJM:aa cc: DB-1 NRC Resident Inspector i

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DJckst Ns. 50-346 License No. NPF-3 Serial No. 678 January 15, 1981 Attachment A APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 DAVIS-BESSE NUCLEAR POWER STATION UNIT I Enclosed are forty (40) copiec of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No.

NPF-3, together with the supporting Safety Evaluation and Analysis for the requested change. This requested change. deals with the proposal to de-automate the valve shifts caused by Incident Level 5 of the Safety Features Actuation System.

The proposed Technical Specifications changes include pages:

3/4 1-17, 3/4 3-13, 3/4 3-48, 3/.4 3-50, 3/4 5-3, 3/4 5-6 3/4 5-7, 3/4 6-11 at.d B3/4-12.

7 By Director, Nuclear Services 3

For R. P. Crouse Vice President, Nuclear Sworn and subscribed before me this 15th day of January, 1981.

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