ML18005A013

Forwards Post-Accident Core Damage Assessment Methodology, Per NUREG-0737,Item II.B.3 Requirement.Procedure Will Be Implemented as Part of Emergency Plan Procedures within 90 Days of NRC Approval

ML18005A013
Person / Time
Site:	Cook
Issue date:	08/31/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17326B153	List: ML17326B152 ML18005A013
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM AEP:NRC:0678J, AEP:NRC:678J, NUDOCS 8409050255
Download: ML18005A013 (4)

Text

REGULAA~TINFORMATION DISTRIBUTION TEM (RIDS)

I ACCESSION NBR48409050255 DDCBDATE: Sll/08/31 NOTARIZEDj NO DOCKET FACIL:50 315 Donald C, Cook Nuclear Power Planti Un) t 50 316 Donald C ~ Cook Nuclear Power Planti Unit 2i Indiana li .

Indiana 8 8

05000315 05000316 AUTH, NAME,, AUTHOR AFFILIATION ALEXICHiM,P, Indiana 8 Michigan Electric Co, RECIP 0 NAME 'ECIPIENT AFFILIATION DENTONiH.RB Office of Nuclear Reactor Regulationi Director

SUBJECT:

= Forwards "Post Accident Core Damage Assessment Methodo'logyi" per NUREG 0737i Item II '.3 requirement, Procedure will be implemented as part of emergency plan procedures within 90 days of NRC approual-, /1

.~~ ) V+

lL DISTRIBUTION CODE: A0400:COP ES REC IV D:LTR t. E'NCLl SIZE:

TITLE:. OR Submittal: TMI Action Plan Rgmt NUREG 0737 8 NUREG~0660 NOTES 05000315 OL 0 10/25/70 05000316 OL:12/23/72 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01 7 7 INTERNAL: ADM/LFMB 1 0 ELD/HDS3. 1 0 IE/DEPER DIR 33 IE/DEPER/EPB 3 3' IE/DEP ER/IRB 1 1 NRR PAULSONiN ~ 1 NRR/DHFS DEPY29 1 1 NRR/DL D IR 10 1 1 NRR/DL/ORAB 18 3 3 NRR/DS I/ADRS 27 1 1 NRR EB 1 1 NRR/DSI/ASB 1 1-

/DS RA 1 1 NRR/DST DIR 30 1 1 REG 1 1 RGN3 1 RGN2/DRSS/EPRPB 1 1 EXTERNAL; ACRS 3Q 10 10 LPDR 03 2 2' NRC PDR 02 1 1 NSIC 05 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED; 'TTR 03 ENCL '1

If

<< I iif 4

<< I i Il II

<<<<W'P f,jj <<l ij IW<< 4<<g<< ~ W W" ~

(

" <<ff i i W

( y j~ W WW<< ~ tx

'W 1Q j F7

, IWVWW j 4,

<<i i i<<

C <<T I! n q<<i 'i I I

t. W Y' j )

w<< ~ gg I

'i

<<<< I i 0 h

'4 j~

il g

X r.

W II i

• W

INDIANA 8 N I CH IGAN ELECTRIC CON PAN Y P.O. BOX I6631 COLUMBUS, OHIO 432I6 August 31, l984 AEP:NRC:0678J Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG-0737, Item II.B.3 CORE DAMAGE ASSESSMENT PROCEDURE Mr. Harold R. Denton Off1ce of Nuclear Reactor Regulat1on U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

In our August 2, 1984 letter to you we committed to provide the NRC a core damage est1mate procedure as required under Criterion 2 of NUREG-0737, Item II.B.3 for the Donald C. Cook Nuclear Plant Units 1 and

2. 0 Attached for your review and approval is a plant specific procedure dated August, 1980 based on revision 1 to the Westinghouse Owners Group "Accident Core Damage Assessment Methodology~. It is anticipated that this procedure will be implemented as part of the D. C. Cook's plant emergency plan procedures within 90 days of the NRC's approval.

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, M. . Ale ich Vice President ~(ply" cm Attachment cc: John E. Dolan W. G. Smith, Jr. - Br1dgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Br idgman 8409050255 840831 05000315

'F' ADOCK

,PDR PDR

1 v 1I e

'{ l>f a.. \ 'i.

4 >

4 I'

f