ML17320B025

Forwards Exxon Nuclear Co 840416 Explanation of Statements Re Rod Bow.Cycle 4 SER Indicated That Evaluation of Rod Bow & Rod Power Should Be Made If Peaking Factor Limits Need to Be Adjusted

ML17320B025
Person / Time
Site:	Cook
Issue date:	05/04/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0860E, AEP:NRC:860E, NUDOCS 8405080149
Download: ML17320B025 (4)

Text

REGULATOR'iONFDRMATION DISTRISUTION SA~(EM (RIDS)

ACCESSION NBR:8405080149 DOC ~ DATE: 84/05/04 NOTARIZED; NO DOCKET FACIL:50 316 Donald C ~

Cook Nuclear Power Pl anti Unit 2i 'Indiana 8

05000316 AUTH BYNAME AUTHOR AFFILIATION ALEXICHRM ~ PE Indiana 8 MiChigan EleCtriC CO ~

RECIP ~ NAllE 'ECIPIENT AFFILIATION DENTONiH ~ RE Office of Nuclear Reactor Regulation.

Director

SUBJECT:

Forwards Exxon Nuclear Co 840416 explanation of statements re rod bow.C'ycle 4

SER indicated that evaluation of rod bow 8 rod power should be made to if peaking factor limits need be adjusted.

I DISTRIBUTION COOK'001S COPIES RECEIVED LTR ENCL S1ZE; TITLE:

OR Submittal:

General Distribution NOTES'ECIPIENT ID CODE/NAME NRR ORB1 BC, 01 INTERNAL: ELD/HDS3

'RR/DL DTR METB G '4 COPIES LTTR ENCL-7 7

1 0

1 1

1 1

1 1

RECIPIENT ID CODE/NAME NRR/DE/MTEB NRR/DL/ORAB NRR/DSI/RAB RGN3 COP IE5 LTTR ENCL 1

1 1

0 1

1 1

1 EXTERNAL: ACRS NRC PDR NTIS 09 02 6

1 1

1 1

LPDr>>

NSIC 03 05 1

1 1

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 25 ENCL 23

4 II I

Y f fl

~

K li C

II c

J f 'l 1

g II p

ll h

II

INDIANA8 NICHIGAN ELECTRIC CONPANY P.O, BOX 16631 COLUMBUS, OHIO 43216 Nay 4, 1984 AEP:NRC:0860E Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 CYCLE 5 SAFETY ANALYSIS REPORT Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

The Cycle 4 Safety Evaluation Repor t (SER) indicated that an evaluation of rod bow and rod power should be made to determine if DNBR or peaking factor 11mits need to be ad)usted to account for fuel rod bowing.

During the course of our review of the Cycle 5 Safety Analysis Report (SAR), Exxon Nuclear Company (ENC) was asked to further explain the statements with respect to rod bow.

We mentioned to Mr. D. Wigginton on April 6, 1984 that we would be clarifying the SAR statements on rod bow after receiving confirmation from ENC.

We are attach1ng a copy of a letter on the subject from ENC for this purpose.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness pr1or to signature by the undersigned.

Very truly yours,

.P. Al ieh PP iQ'I'ice President 4zV Attachment bus cc:

John E. Dolan W.G. Smith, Jr. - Bridgman R.C. Callen G. Charnoff E.R.

Swanson, NRC Resident Inspector - Br1dgman 8405080149 840504 PDR ADOCK 05000316 PDR

E)f(ON NUCLEAR COMPANY,Inc.

600 -108th Avenue N.E., C-00777, Bellevue, Washington 98009, Telephone (206) 453-4300 April 16, 1984 ENC-AEP/0343 5)~

Mr.

Ge ge John, Sr. Engineer

'PPR

~ ~ 1984.

Nuc 1 ar Mater ia 1 s

& Fuel Management Indiana

& Michigan Electric Company c/o American Electric Power Service Corp.

One Riverside Plaza

Columbus, OH 43215

Subject:

Supplemental Information to D.

C.

Cook 2, Cycle 5 Safety Analysis Report Regarding Effect of Rod Bow on DNB Margins Ref:

1)

XN-NF-83-85, Supp.

1, Rev.

1, "D. C.

Cook Unit 2, Cycle 5 Safety Analysis Report," March 15, 1984 2)

XN-NF-75-32(P)(A), Supps.

1, 2, 3 & 4, "Computational Procedure for Evaluating Fuel Rod Bowing," October 1983 3)

XN-NF-82-32(P), Rev. 2, "Plant Transient Analysis for the Donald C.

Cook Unit 2 Reactor at 3425 MWt:

Operation with 5% Steam Generator Tube Plugging," February 1984 Exxon Nuclear has reanalyzed the effect. of rod bow on DNB margin during the D. C. Cook Unit 2, Cycle 5.

The effects were analyzed in accordance with the NRC Staff SER and Exxon Nuclear methodology (Reference 2).

The results of the analysis show that no fuel assembly is expected to experience DNBR.less than that reported (Reference

3) during Cycle 5.

The analysis showed that the reduction in fuel assembly power due to burnup more than compensates for the effects of rod bow to EOC5

~

Very trul

yours, H.

G.

Shaw Contract Administrator tlm ij

~

c:

M. P. Alexich J.

M. Cleveland W. L. Zimmermann AFFILIATEOF EXXON CORPORATION