ML17320B004

Forwards Response to Second Set of Questions from BNL Re Cycle 5 Sar,Exxon Nuclear Repts XN-NF-83-85 & XN-NF-83-85, Suppl 1,Rev 1

ML17320B004
Person / Time
Site:	Cook
Issue date:	04/19/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0860D, AEP:NRC:860D, NUDOCS 8404240174
Download: ML17320B004 (7)

Text

pp DISTRIBUTION CODE:

IE26S COPIES RECEIyED:LTR ENCL SIZE;.

TITLE: Start-Up Report/ Refueling Report (50 Dkt)

NOTES:

t REGULATORY NFORMATION DISTRIBUTION SYSTEM

('RIDS)

ACCESSION NBR:8400200170 DOC ~ DATE: 84/00/19 NOTARIZED:

NO DOCKET

, FACIL:50-316 Donald C ~

Cook Nuclear Power Plant~ Unit 2< Indiana 8

05000316 AUTH,NAME AUTHOR AFFILIATION ALEXICH~M~ P, Indiana L Michigan Electric Co ~

REC IP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationg Director

SUBJECT:

For wards response to second set of questions from BNL re C)'cle 5 SARgExxon Nu'clear Repts XN NF"83"85 8

XN NF-83-85'u

'1 igRev 1.

RECIPIENT Id CODE/NAME NRR ORB1 BC 04 COPIES LTTR ENCL 3

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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 1663'I COLUMBUS, OHIO 43216 April 19, 1984 AEP:NRC:0860D Donald C. Cook Nuclear Plant Unit No.

2 Docket No. 50-316 License No. DPR-74 Cycle 5 Reload Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

By this letter we transmit responses to the second set of verbal questions received from Brookhaven National Laboratory (BNL) regarding the Cycle 5 Safety Analysis Report (Exxon Nuclear Co. Report No. XN-NF-83-85 and XN-NP-83-85, Supp.

1, Rev.

1) that was submitted to the NRC in support of the Cycle 5 reload application.

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

Very truly yours, M.P. Alexich Vice President uIi5'i MPA/bjs cc: John E. Dolan W.G. Smith, Jr.

Bridgman R.C. Callen G. Charnoff E.R. Swanson, NRC Resident Inspector Bridgman eiaeaOO174 BOO419 PDR ADOCK 05000316 P

PDR

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Mz. Harold R. Denton +

AEP:NRC: 0860D Attachment Question fl Is the 2X penalty on DNBR to account for the hydraulically different fuel assemblies in the core taken into account?

Answer fl The 2X penalty on DNBR has been taken into account in the Cycle 5 transient analyses.

Documentation regarding this is a letter from Exxon Nuclear Co. and is attached herewith.

Question f2 What is the value of F used in the transient analyses 7

Answer f2 F

used in the transient analyses is 2.47 as reported in Table 3.1 of XN-NF-82-32(P).

Question f3 It was reported that the ENC reload fuel will have less available thermal margin but the F<

limit for ENC fuel is higher than'the Westinghouse fuel.

Shyf Answer f3 The Westinghouse Fz H and F

limits for Cycle 4 were reduced (from their Cycle 3 values) slightly to allow for an increase in core power.

This was done because a new plant specific LOCA analysis was not warranted for the Westinghouse fuel.

The Exxon values re'present new plant specific analysis for Cycles 4 and 5.

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E)$(ON NUCLEAR COIVIPANY,Inc.

I:N" 1UIJII) AVBnrre N,l: (: 0077'". RI)llr.'Vuc. Waah'rrgtcr) 98009, Te!ephor Ie (206) 453-4:I00 April 12, 1984 ENC-AEP/0341

'.Ir, George

John, Sr. Engineer

. Indi arlp 6 Hichi)1an El'cctric Company c/o

@<ver ican Flnctric PowIl< Service Corp.

One Riverside Plash.

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Cook LInit 'eactor at 3425 Iml.: Opec'ation with 5'l SL<<am Cencrator Tub>> Plugging," i~larch i984 I

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