ML20002D129

Application to Amend License NPF-3,changing Tech Specs to Permit Deautomation of Valve Shifts Caused by Incident Level 5 of Safety Features Actuation Sys

ML20002D129
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
ML20002D130	List: ML20002D129 ML20002D134
References
678, TAC-43253, NUDOCS 8101190503
Download: ML20002D129 (3)

Text

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Docket No. 50-346 .

TOLEDO License No. NPF-3 EDISON Serial No. 678 - -* f' RicHAAO P Cnoust vu nneen January 15, 1981 wa-M191259 5221 Director of Nuclear Reactor Regulation Attention: Darrell G. Eisenhut, Director Division of Licensing United States Nuclear hegulatory Commission Washington, D.C. 20555

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 acti,n 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 modifi-cation retains the SFAS Incident Level 5 to provide a permissive function for control rocra 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 manually initiate long-term post-LOCA recirculation core cooling.

Only the major revisions from Attachment B of the January 5, 1981, , OC)/

submittal are provided. All previous references to six feet will now read eight feet. b Attachment C: This provides, in verbal form, a description of how the electrical modification propored in our submittal of January 9, j/ /

1981, functions.

THE TOLECO EDISON COMPANY EDISON PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43552 b 10 310() )4

Docket No. 50-346 License No. NPF-3 Serial No. 678 January 15, 1981-All control room personnel will be trained in the procedural revisions prior to their standing watches after system modification. Additionally, the prime responsibility for ensuring 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 i 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, g

. a W- JW RPC:TJM:aa ec: DB-1 NRC Resident Inspector i

e p.,v.-

Dockat No. 50-346 License No. NPF-3 Serial No. 678 January 15, 1981 Attachment A APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT 1 Enclosed are forty (40) copies 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 deautomate the valve shif ts caused by Incident Level 5 of the Safety Features Actuation System.

The proposed Technical Specific ~ations 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 and B3/4-12.

By "

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

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