ML17319B483

Application for Amend to Licenses DPR-58 & DPR-74,proposing Tech Spec Changes Re Radiation Monitoring Sys Upgrade Including Implementation of post-TMI Requirements Per NUREG-0578 & NUREG-0737.Description of Changes Encl

ML17319B483
Person / Time
Site:	Cook
Issue date:	08/20/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17319B484	List: ML17319B483 ML17319B485
References
RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737 AEP:NRC:0717, AEP:NRC:717, NUDOCS 8208260276
Download: ML17319B483 (9)

Text

REGULATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR:8208260276 DOC ~ DATE: 82/08/20 NOTARIZED; NO ,

DOCKET ¹ FACIL:50 315 Donald C. Cook Nuclear Power Planti Unit 1i Indiana 8 05000315 50-316 Donald CD Cook Nuclear Power Planti Unit 2i Indiana R 05000316 AUTH'AME AUTHOR AFFILIATION HUNTERiRRSS Indiana L Michigan Electr ic Co, RHC I P NAME RECIPIENT AFFILIATION DENTONiH,RE Office of Nuclear Reactor Regulationi Director

SUBJECT:

Application for amend to Licenses DPR 58 8 DPR 74iproposing Tech Spec changes re radiation monitoring sys upgrade including implementation of post-TMI requirements per NUREG-0578 8 NUREG"0737 'escription of changes encls DISTR I BUT I N CODE: A006S COPIES RECEIVED:LTR I. ENCL 1 SIEE:

TI'TLE: Response to NUREG '"0737/NUREG-0660 'TMI Action Plan Rgmts (OL's)

NOTES:

RECIPIENT ~COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ORB ¹1 BC 01 7 7 INTERNAL: ELD/HDS3 1 0 IE/DEP D IR 33 1 1 IE/DEP EPOS 1 1 IE/DEP/EPLB 3 3 NRR/DE D IR 21 1 1 NRR/DE/ADCSE '22 1 1 NRR/DE/ADMQE 23 1 1 NRR/DHFS D IR 28 1 1 NRR/DHFS/DEPY29 1 1 NRR/DL DIR )4 1 1 NRR/DL/ADL 16 1 1 NRR/DL/ADOR 15 1 1 NRR/DL/ADSA 17 1 1 NRR/DL/DRAB 18 :3 3 NRR/DSI DIR 24 1 1 NRR/DS I /ADDP S25 1 1 NRR/DS I/ADRP 26 1 1 NRR/DS I/ADRS 27 1 1 NRR/DS I/AEB 1 1 NRR/DS I/ETSB 1 1 NRR/DSI/RAB 1 1 NRR/DST DIR 30 1 1 ADGP '31 1 1 NRR/DST/ADT 32 1 1 REG F ILE 04 1 1 RGN3 1 1 EXTERNAL: ACRS 34 10 10 FEMA~REP .OIV 1 1 INPOiJ ~ STARNES 1 1 LPDR 03 2 2 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: L'TTR 54 ENCL 53

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0 INDIANA 5 MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLlNG GREEN STATION NEW YORK, N. Y. 10004 August 20, 1982 AEP:NRC:0717 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 SPECIFICATIONS CHANGES REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dear Mr. Denton'.

This letter and its attachments request changes in the Appendix "A" Technical Specifications for the Donald C. Cook Nuclear Plant Unit Nos, 1 and 2. Attachment 1 describes the changes.

Attachment 2 contains the revised Technical Specification (T/S) pages.

All changes have been indicated by a vertical line on the right hand side of the page.

These proposed T/S changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) as required by our T/S. These changes will also be reviewed by the (NSDRC) Nuclear Safety Design Review Committee at their next regularly scheduled meeting to be held on August 24, 1982.

The payment for .these changes will be made as part of the fee to be levied for the issuance of the NUREG-0737 Technical Specifications covered by other NRC reviews.

Since these changes are required for restart following our current Unit 1 outage, we request that they be processed expeditiously.

8208260276 820820 PDR ADOCK 05000315 l P PDR

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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, S, Hunter

/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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'ATTACHMENT 1 TO AEP:NRC:0717 Descri tion of 'Technical S ecification (T/S) Chan es Unit 1; Page 3/4 3-19; Table 3.3-3 Unit 1; Pages 3/4 3-35,36,37; Table 3.3-6 Unit 1; Page 3/4-3-38; Table 4.3-3 Unit 1; Page 3/4 4-14; Section 3.4.6.1 Unit 1; Page 3/4 9-10; Section 4.9.9 Unit 2; Page 3/4 3-18; Table 3.3-3 Unit 2; Pages 3/4 3-34,35,36; Table 3.3-6 Unit 2; Page 3/4 3-37; Table 4,.3-3 Unit 2; Page 3/4 4-14; Section 3.4.6.1'/4 Unit 2; Page 9-9 ; Section 4.9.9 The new radiation monitors are part of an overall Plant Radiation Monitoring System (RMS) upgrade package which includes implementation of post-TMI requirements as stated in NUREG-0578 and 0737. Only those Technical Specifications applicable to equipment which is being replaced and which was previously used to satisfy them are being changed. The new RMS is designed to minimize equipment failures of the type experienced with the original equipment. We believe that these modifications will result in an overall improvement in plant safety.

It is our desire to complete the first phase of the RMS upgrade work during this year's refueling outages. In particular, we intend to have the equipment operational in Unit 1 in time to meet the operability dates stated in our letters of December 23, 1981 (AEP:NRC:0652) and May 14, 1982 (AEP:NRC:0678) for these post-TMI items.

The new lower containment monitors which initiate closure of the purge isolation valves, are of a redundant design with each monitor train oriented to a corresponding Class 1E electrical train. These monitors, ERS-1300 and ERS-1400, each consists of particulate, gaseous and iodine detecting capability. They will replace the old Rll/R12 monitors. The containment monitors will each initiate closure of a set of Containment Ventilation Isolation (CVI) valves (7 of 14 isolation valves per Unit) as was discussed in our letter AEP:NRC:0723 dated July 21, 1982.

The modification in the upper containment volume involves replacing the single upper containment radiation area monitor (R2) with two, independent, redundant, train-oriented detector/indicator/alarm area monitor sets, each of which is capable of automatically isolating seven containment purge and exhaust valves. That, is, the train A device will be capable of isolating the seven inboard purge and exhaust valves and the train B device will be capable'of isolating the seven outboard valves. This modification fulfills the commitment in our letter of March 25, 1980 (AEP:NRC;02951) .

DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 ATTACHNENT 2 TO AEP: NRC: 0717 TECHNICAL SPECIFICATIONS CHANGES