ML17328A561

Application for Amend to License DPR-74,revising Tech Specs by Implementing Core Operating Limits Rept in Accordance W/ Generic Ltr 88-16, Removal of Cycle-Specific Parameter Limits from Tech Specs.

ML17328A561
Person / Time
Site:	Cook
Issue date:	02/06/1990
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17328A562	List: ML17328A561 ML17328A563
References
AEP:NRC:1077A, GL-88-16, NUDOCS 9002140162
Download: ML17328A561 (7)

Text

ACCELERATED DI~ UTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9002140162 DOC.DATE: 90/02/06 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Contrql Desk)

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SUBJECT:

Application for amend to License DPR-74,implementing core operating limits rept,per Generic Ltr 88-16.

DISTRIBUTION CODE: AOOID TITLE:

NOTES:

OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL l SIZE: ~ F RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 1'

PD3-1 LA 1 1 PD3-1 PD 1 GIITTER,J. 5 5 INTERNAL: NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSBll 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 /&PM 1 0 OGC/HDS1 1 0 REG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WARM CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19

1 Indiana Michigan Company

'ower P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1077A GL 88-16 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 IMPLEMENTATION OF CORE OPERATING LIMITS REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 IN ACCORDANCE WITH GENERIC LETTER 88-16 U.S. Nuclear Regulatory Commission ATTN: Document Control Deck Washington, D.C. 20555 Attn: T. E. Murley February 6, 1990

Dear Mr. Murley:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for Donald C.

Cook Nuclear Plant Unit 2. In this request, we propose to revise the T/Ss by implementing a Core Operating Limits Report (COLR) in accordance with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications."

Our reasons for the proposed changes, as well as our analysis concerning significant hazards considerations, are contained in Attachment 1 to this letter. Attachment 2 contains the proposed revised T/S pages, and Attachment 3 is a sample COLR document.

Our intent is to begin using the COLR document at the start of Cycle 8, when the approved Westinghouse methodologies used to calculate the COLR parameters become applicable. The analyses of record for Unit 2, which are applicable in Cycle 7, were performed by Advanced Nuclear Fuels Corporation. In Cycles 8 and 9, we propose to operate Unit 2 based upon analyses performed by Westinghouse.

Nature of the Pro osed Chan es The proposed T/S changes are purely administrative in that we are removing certain limits from the T/Ss and placing them in a COLR document in accordance with Generic Letter 88-16. The values of r 9002iqOi62 900206 PDR ADGCK 0500031 I DC

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Dr. T. E. Murley 2 AEP:NRC:1077A the COLR parameters may change from cycle to cycle, and will do so in accordance with approved methodologies. The proposed T/S changes include the following parameters:

o moderator temperature coefficient (MTC) o MTC 300 ppm MTC surveillance acceptance criterion o all rods out position, and control rod insertion limits o axial flux difference allowable deviation and target band, o F , K(Z), and N

o F >H, and F

>H slope.

The value of all of these parameters will be different in Cycle 8 from their Cycle 7 values due to the Westinghouse analyses.

Relationshi to the Unit 2 C cle 8 Submittal In parallel with this submittal,- we are submitting our proposed T/S changes for the Unit 2 Cycle 8 reload. Our identifier for the reload submittal is AEP:NRC:1071E. Due to the interrelationships between the COLR and reload submittals, it is important that we your response to this COLR submittal as soon as possible.

If the staff

'eceive cannot approve this COLR submittal, it will be necessary to propose additional T/S changes for Cycle 8 that would have been submitted in the COLR document.

Please advise us before March 31, 1990 of your intentions regarding this COLR submittal so that we can take appropriate action to ensure approval of our Cycle 8 reload submittal.

Certain T/S pages in this COLR submittal are also impacted by the Unit 2 Cycle 8 submittal.

We believe that the proposed changes will not result in (1) significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety Design Review Committee.

IE Dr. T. E. Murley 3 AEP:NRC:1077A In compliance with the requirements of 10 CFR 50.91(b)(10), copies of this letter and its attachments have been sent to Mr. R. C.

Callen of the Michigan Public Service Commission and to the Michigan Department of Public Health.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M. . Alexich Vice President Attachments cc: D. H. Williams, Jr.

A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B. Davis - Region III NRC Resident Inspector NFEM Section Chief