ML19319C110

Notifies That Tech Specs Table 3.3-11 Should Be Changed to Reflect Replacement of Steam Generator Level Switches W/Steam Generator Level Transmitters in Steam & Feedwater Rupture Control Sys.Safety Evaluation & Tech Specs Encl

ML19319C110
Person / Time
Site:	Davis Besse
Issue date:	06/24/1977
From:	Roe L TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19319C111	List: ML19319C110 ML19319C118
References
308, NUDOCS 8001310473
Download: ML19319C110 (3)

Text

_

TOLEDO

- EDISON Docket No.58-346 0

,f '

s .e .... .. c ... .o r ...

June 24, 1977 m S'25$-52'2 m &' :Sb M da b Serial No. 308 f\9I try

!Q 6

.:> . weg Irw Director of Nuclear Reactor Regulation -+

Attention: Mr. John F. Stolz, Chief 4((6l ObM El; Lightwater Reactors Branch No. 1 .

T l' C/

Division of Project Management 'C United States Nuclear Regulatory Commission Washington, D.C, 20535 s.

v... ./

Dear Mr. Stolz:

The Davis-Besse Nuclear Power Station Unit 1 Technical Specifications need to be changed to reflect the replacement of the steam generator level switches with the steam generator level trancmitters in the Steam and Feedwater Rupture Control System. The requested changes have been made to the attached Technical Specification pages 3/4 3-25, 3/4 3-26, 3/4 3-28 and 3/4 3-30 which are a part of the Safety Evaluation. As noted in the attached Safety Evaluation the design of the steam generator level transmitters has been reviewed and accepted by your staff.

The installation of the level transmitters is listed in the Operating License as a constraint to operation in Mode 2. However, these Technical Specification changes are required prior to operation in Mode 3 since the level switches being replaced a e not presently functional. Therefsre, this change is requested on an emergency basis to allow us to proceed to Mode 3 as presently scheduled.

Yours very truly, g / /

wwA d: /e g

Enclosure:

Safety Evaluatica for requested change to the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications including Technical Specification Pages 3/4 3-25, 3/4 3-26, 3/4 3-28 and 3/4 3-30 mj e/3 THE TCLEDO ECiSON COMPANY ECISCN PLAZA 3CO MACISCN AVENUE TCLECO. CHIO 43652

$ 001310473

DB 1 Safety Evaluation For Requested Change to the Davis-Besse Nuclear Power Station Unit No. 1 Technical Specifications (Appendix A to Operating License No. NPF-3)

The Davis-Besse Nuclecr Power Station Unit No. 1 Technical Specifications should be changed as follows:

Table 3.3-11 on Pages 3/4 3-25 and 3/4 3-26 should be changed to show the new level switch numbers. Table 3.3-12 on Page 3/4 3-23 should be changed to show that the Allowable Value for Functional Unit 2 is greater than or equal to (29 20 inches H,0 for the Channel Functional Test and greater than or equal to G3) 18.87 inches H3 0 for the Channel Calibration.

Also Table 4.3-11 on Page 3/4 3-30 should be changed to show a Channel Calibration f requency for Item lb to be once every 18 months (R) instead of once every 92 days (Q). See the attached Technical Specification Pages for these requested changes.

These Technical Specification changes are required to refirmt the steam generator startup range level transmitters which have been installed o replace the level switches for the Steam and Feedwater Rupture Control System (SFRCS) to comply with IEEE 279-1971. Until the transmitters were installed the level switches were to be calibrated once every 92 days. The description and analysis of the SFRCS in Section 7.4 of the FSAR was modified in Revision 23 in November, 1976 to reflect the installation of the level transmitters. Supplement No. I to the NRC Safety Evaluation Report on Davis-Besse Nuclear Power Station Unit No. 1 dated April, 1977, stated in Section 7.4.1 (4) that the design of the SFRCS incorporating these level transmitters satisfies the commission's requirements a d ia acceptable. Also the NRC has required as a license condition that these level ransmitters be installed prior to operating in Mode 2 (startup). Hence the design change has already been reviewed by the NRC and all that remains are the changes to the Technical Specifi-cations to reflect the proper Allowable Values and Surveillance Requirements.

I 1

c'O . 7___ pgy