ML17326A955

Application to Amend Tech Specs Re Fire Protection,Fire Detection Instrumentation,Fire Suppression Sys & Fire Rated Assemblies

ML17326A955
Person / Time
Site:	Cook
Issue date:	08/02/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17326A956	List: ML17326A955 ML17326A957
References
AEP:NRC:0660D, AEP:NRC:660D, NUDOCS 8208090056
Download: ML17326A955 (8)

Text

REGULATOR NFORMAT ION DISTRIBUTION i'EM (RIDS)

AOGESSION NBR:8208090056 DOC.DATE: 82/08/02 NOTARIZED: NO DOCKET FACIL:50-31'5 Donald 50-3i6 Donald C< Cook Cook Nuclear Power Pl anti Unit ii Nuclear Power Planti -Uni,t 2i Indiana Indiana 8 8

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AUTH, NAME AUTHOR AFFILIATION HUNTERgR ~ ST Indiana 8 Michigan Electric Co ~

GREC IP, NAME RECIPIENT AFFILIATION DENTONtH ~ RE 0 f f i ce of Nuc l ear Reac tor Regul.a t i one D i rector

SUBJECT:

Application,to amend Tech Specs re fire -protectionifire detection instrumentationifire sepression sys 8 fire rated assemblies, DI'STRIBUTION CODE: A001S COPIES RECEIVED:LTR, -ENCL I SIZE' WA/f NOTES: ~/~

TITLE: General Distribution for after REC IP IEN 7 ~COPIES Issuance'of .Operating License RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ORB g1 BC 01 7 7 I

INTERNAL: ELD/HDS3 1 0 NRR/DHFS DEPY08 1 NRR/DL DIR 1 B 1 NRR/DS I/RAB 1 1 EG F 04 ,1 RGN3 1 1 EXTERNAL+ 'ACRS 09 10 10 LPDR 03 2 2 NRC PDR 02 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 27

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INDIANA 5 MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOW1 lN G GREEN STATlON NE'W YORK, N. Y. 10004 August 2, 1982 AEP:NRC:0660D Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 TECHNICAL SPECIFICATION CHANGE REQUEST FIRE PROTECTION Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ref: 1) AEP Letter AEP:NRC:0660 dated March 1, 1982

Dear Mr. Denton:

This letter and its Attachments request a change to our current Technical Specifications in the area of Fire Protection, including Fire Detection Instrumentation, Fire Suppression Systems and Fire Rated Assemblies (formerly Penetration Fire Barriers) .

Specifically, this change request applies to the following Technical Specifications:

Unit l Unit 2 Title 3/4.3.3.7 3/4.3.3.8 Fire Detection Instrumentation 3/4.7.9.1 3/4.7.9.1 Fire Suppression Water, System 3/4.7.9.2 3/4.7.9.2 Spray and/or Sprinkler Systems 3/4.7.9.3 3/4.7.9.3 Low Pressure CO Systems 3/4.7.9.4 3/4.7.9.4 Halon System 3/4.7.9.5 3/4.7.9.5 Fire Stations Wl -zi I

Hose C'yQ, 0 3/4.7.10 3/4.7.10 Rite Rated Assemblies V Y.

8208090056 820802 PDR ADOCK 05000315 4 P PDR

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.Mr. Harold R. Dento AEP:NRC:0660D Attachment 1 to this letter presents the proposed changes to the above listed Unit 1 Technical Specifications and Attachment 2 presents the Unit 2 changes; both Attachments indicate by vertical bars in the right margin the changes from the current Unit 1 and Unit 2 Technical Specifications.

Technical Specification 3/4.7.10 is being changed pursuant to our commitment in Reference 1. In the course of processing this Technical Specification change it was decided to revise all of the current Unit 1 and Unit 2 Technical Specifications relating to Fire Protection since we believe that they are unduly restrictive to plant operations and impose unnecessary hardships in meeting the present ACTION statements. Accordingly, we have reviewed the current Donald C.

Cook Technical Specifications for Units 1 and 2 using as guidance the most recent NRC proposed Standard Technical Specifications for Westin'ghouse Pressurized Water Reactors (NUREG-0452, Rev. 4) .

Approval of the proposed Technical Specifications changes will impose requirements in the area of plant Fire Protection which reflect current NRC positions on these topics, and will update the Donald C.

Cook Technical Specifications beyond requirements which date back to the 1977-1978 time-frame. In addition, approval of these proposed revisions should remove unduly restrictive ACTION statements which are not imposed on current Westinghouse plants. We also believe that approval of these changes will clarify the requirements for the operating personnel of the Plant.

These proposed changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee at their next meeting.

Pursuant to 10 CFR 170.22, this application for the attached Technical Specification revisions is deemed to be a Class III amendment in that a single safety issue (fire protection) is involved which has a clearly identified NRC position regarding acceptability (NUREG-0452, Rev. 4) . A Class I Amendment Duplicate Fee also applies. Therefore a check for $ 4,400 accompanies this request for Technical Specifications change.

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, Mr. Harold R. Dent .3 This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, R. S. Hunter RSH/os Vice President cc: John E. Dolan Columbus M. P. Alexich R. W. Jurgensen W. G. Smith, Jr.. Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant Bridgman

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