ML17321A341

Summarizes 841113 Meeting Re 840828 Application for Amend to License DPR-74,changing Tech Specs to Permit Total Power Peak Limit of 2.04 & Corresponding Limit of 1.49.Status of Evaluation of Impact of Potential Delays Provided

ML17321A341
Person / Time
Site:	Cook
Issue date:	12/07/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0860V, AEP:NRC:860V, NUDOCS 8412120440
Download: ML17321A341 (22)

Text

REGULATORY FORMATION DISTRIBUTION SY EM (RIDS)

ACCESSION NBR:8412120440 DOC ~ DATE: 84/12'/07 NOTARIZED'O DOCKET FACIL:50 316 Donald C ~ Cook, Nuclear Power Planti Unit'~ Indiana L 05000316 AUTH, NAME, . AUTHOR AFFILIATION ALEXICHpM~ Pf Indiana 8 Michigan Electric Co, RECIP ~ NAME'ECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationi Director

SUBJECT:

Summarizes 841113 meeting re 840828 application for amend to License DPR-74~changing Tech Specs to permit total power peak limit of 2.04 & corresponding limit of 1.49,Status of evaluation of impact of potentia'l delays pro'vided.

DISTRIBUTION CODE: A001D" COPIES RECEIVED:LTR ENCL: 'SIZE:

TITLE: OR $ ubmittal: Gener al Distribution NOTES'L: 05000316 12/23/72 REC IP IENT COPIES REC IP I, ENT COPIES ID CODE/NAME LTTR ENCI ID LTTR ENCL NRR" OR81 BC Ol 7 7 CODE/NAME'DM/LFMB INTERNAL; ACRS 09 6 6 1 0 ELD/HDS3- 0 NRR/DE'/MTEB 1 .-1 NRR/DL DIR 1 1 NRR/DL/ORAB 1 0 N TB 1 1 NRR/DS I/RAB 1 EG FIL 04 1 1 RGN3 1 1 EXTERNAL+ LPDR 03 1 1 NRC PDR 02 1 NSIC 05 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 23

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p't t t INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 December 7, 1984 AEP:NRC:0860V Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 N

UNIT 2 TECHNICAL SPECIFICATION CHANGES (F AH) FOR CYCLE 5 AND ADMINISTRATIVE LIMITS IMPOSED DURING ANALYSIS Mr. Harold R. Denton, Director Office of Nuclear Regulator Regulation U.S. Nuclear Regulatory Comm1ssion Washington, D.C. 20555

Dear Mr. Denton:

An application for amendment to the Donald C. Cook Unit 2 technical Specifications wIIich would permit a total power peak limit (F )of 2.04 and a corresponding F <H 11mit of 1.49 was submitted 1n letter AEP:IIRC:0860J dated August 28, 1984. Th1s submission was supported by an analysis performed by our fuel vendor, Exxon Nuclear Company. Subsequently, a meeting was held in Bethesda on November 13, 1984 to discuss questions raised by your staff regarding this submission and to elaborate on conservative measures AEP has taken pending final resolution of the questions. This letter 1s to summarize this presentation and also to provide the current status of our analys1s and our evaluation of the impact of potential delays 1n resolving the staff's questions. Members of your staff present at the meeting concurred with the action we'e taken and our planning for the immediate future.

Your staff asked us to provide justification that the analysis performed cons1dered a range of power d1str1bution shapes and peaking factors that would represent power distr ibut1ons that may occur over the core life t1me. Prior to this submittal Exxon Nuclear Company supported this requirement by referencing a generic Nestinghouse methodology. During the November 13, 1984 meeting a new approach to developing an Exxon methodology in the near term, was presented.

This methodology will limit the peaks in the top of the core by placing 11mits on axial offset. The limit on axial offset may be relaxed by tightening the l1mit on F < H. Power distributions which the operating restrictions permit will be reviewed to select those which most closely approach the LOCA acceptance criteria for LOCA analys1s. It is our intention that the methodology of this approach and Cook specific analys1s be submitted to your staff for review in January 1985. A status report and prel1minary discussion of results has been planned for December 13, 1984.

8412120440 841207 PDR ADOCK 05000316 P PDR

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Mr. Harold R. Dento AEP:NRC:0860V In order to assure marg1n to 10 CFR 50.46 limits while the near term Exxon methodology is being developed, we have imposed a new administrative K(Z) curve. This K(Z) 1s based on preliminary calculations performed by Exxon Nuclear Company. The calculation was performed by utilizing a heatup code with an axial profile peaked in a conservative manner at the top of the core. It was coupled with results from blowdown and reflood analyses which were computed with a chopped cosine power distribution. Our vendor's belief that the calculation is conservative is based on the natur e of the power distribution assumed in the heatup calculation. It is anticipated that complete LOCA calculations with physically achievable power distributions will meet the acceptance criteria of 10 CFR 50.46. The large break LOCA segment of this administrative K(Z) curve and the old K(Z) curve are shown in Figure 1 of the attachment. The administrative K(Z) curve has been reviewed by PNSRC and NSDRC.

We have conducteg studies comparing the current and anticipated power d1stribution with FA limits and F limits obtained from the administrative K(Z) curve. This comparison indicates that we can operQe the plant at full H

power until approximately March or April 1985 with an FA limit of 1.415. The results of this work were presented at the November 13 meeting, copies of the transparencies from this presentation are attached as requested.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insur e 1ts accuracy and completeness prior to s1gnature by the unders1gned.

t Very truly yours,

\

M. P. Al ich OAQ Vice Freeidect tm Attachment cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman

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TRANSPARENCIES PRESENTED BY AEPSC ON NOVEMBER 13, 1980 CCMPARING CURRENT AND ANTICIPATED POWER DISTRIBUTIONS WITH F AH AND Fq LIMITS FOR DONALD C. COOK NUCLEAR PLANT UNIT 2.

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'"'c AMERICAN ELECTRIC POWER SERVICE CORPORATION Wag SvSTS DATEs October 29, 1984 SU8JECTs Unit 2 K(Z) Curve FROMs J.M. Cleveland TOs W.G. Smith, Jr.

On August 28, 1984 a new Unit 2 LOCA analysis was submitted to the NRC.

This analysis supports an F> of 1.55 (1.49 measured). The NRC r eviewer of this submission does not consider it appropriate for the submission to reference the Westinghouse K(Z) analysis described in WCAP 8356. Therefore, Exxon is performing calculations with the Exxon LOCA model to develop a K(Z) curve which will potentially become a supplement to the August 28, 1984 submission.

.Preliminary. calculations performed by ~xan phow,that the. Exxon madel can'.

'uppo'rt'. a r'evfsed'K(Z) c'uive. lour"'th'ah the current"K(Z) c'use 'bised oh"QCAP'""'""

8356. In orgier to prevent exceeding Appendix K peak clad temperature limits, we 'requested Exxon to develop an interim conservative K(Z) curve. This interim K(Z) is attached, We request this curve to be applied on an administrative basis. Doing so is expected to ensure continued compliance with Appendix K while further analysis continues.

Data sets for the detector code have been prepared which include the new K(Z) curve. These data sets are:

Source Library: SRC . LIB02. S418010 Member for burnups 4000-5000 MWD/MT: E254500A Member for burnups 5000>>6000 MWD/MT: E255500A Clevela d J.G. Fe stein, Conc ence M.P. lexich, Approval cc: V. Vanderburg/G. John A. Blind/R. Hennen NMFM f84-0559 IH T RA SYSTEM

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