ML19319B514

Forwards Revision of 780518 Attachment 1 to Amend OL for Removal of Burnable Poison Rod & Orifice Rod Assemblies & Revised Pages.No Fee Required as This Document Constitutes Revision to Util 780518 Request

ML19319B514
Person / Time
Site:	Davis Besse
Issue date:	05/26/1978
From:	Roe L TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19319B515	List: ML19319B514 ML19319B519
References
NUDOCS 8001230634
Download: ML19319B514 (3)

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'NRC DISTRIBUTION son PART 50 DOCKET MATERIAL TO: FRCM: cATscpoccuutNT Mr. John F. Stolz Toledo Edison 05/26/79 Toledo, Ohio 43652 cATE RECEIVED Lowell E. Roo 05/3n/7A ELarTu m CNoTonizEO PACP INPUT Po AM NUMSER CP copies MECElv53 (en: GIN AL NcLAsslPt E O Ccon j g f(,,, y,qp c:scarpTicN ENetesu mE Forwarding revision to Applicant's ltr dtd 05/18/78 entitled: " Davis-Besse Nuc Pwr:

Station Unit No 1 Attachment 1 to Amend Operating License For Removal of the Burnable Poison Rod Assemblies and Orifice Rod Assemblies"...w/att Revision Instructions...

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Foc* ties Cowesopment Operating License No. NPF-3 "" 5 258-52'2 Serial No. 439 day 26, 1978 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Light Water Reactors 3 ranch No. 1 Division of Project :ianagement United States Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Stol :

As a result of wear observed on the Davis-Besse Nuclear Fower Station Unit No. I holddown latch assemblies for the orifice rod assemblies (0RA's), we have decided to remove the ORA's. The one enclosure, " Davis-Besse Nuclear Power Station Unit No. 1 Attachment 1 To Amend Operating License For Removal Of The Burnable Poison Rod Assemblies And Grifice Rod Assemblies", is a revision to the enclosure to our letter dated

tay 18, 1978 concerning the removal of the burrable poison rod assemblies (BPRA's). The second enclosure, " Revision Instructions", identifies those new or revised pages which are to be added to revise the study.

This revised document addresses the technical apecification changes, the pertinent safety analyses which have been performed, and the testing whica will be performed as a result of the cemoval of the 3PRA's and the O RA' s .

The technical specification changes identified in the attached document are being requested on an emergency basis because the technical speci-fications are needed by June 9, 1978.

As part of the testing, we will remeasure the reactor coolant system flow rate and supply information on flow data and total pressure drops, as required in Davis-Besse Unit 1 Operating License NPF-3, Condition 2.C. (3) (e), as given in Amendment 7. This information will revise the information previously given you in our letter to Mr. John F. Stolz dated April 24, 1978.

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THE TCLECO ECISCN CCMPANY EDISCN PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43552

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A separate letter giving the qualification of modified orifice rod assemblies to hold down the neutron sources will be submitted to you later.

As noted on the proposed change to the Table 3.2-1 the Reactor Coolant Flow Rates include the flow rate measuring uncertainties which are addressed in our letter to you dated !1ay 26, 1978 (Serial Number 436).

In that this document constitutes a revision to our request dated May 18, 1978, we consider the fee requirement of 10CFR Part 170 to have been satisfied by the remittance transmitted with that submittal.

Yours very truly, Enclosure db c/5 I

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