ML17321A967
| ML17321A967 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/15/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0916C, AEP:NRC:916C, NUDOCS 8511250048 | |
| Download: ML17321A967 (6) | |
Text
REGUlATOR)
NFORMATION DISTRIBUTION S
'EM (RIDS)
ACCESSION NBR: 8511250048 DOC ~ DATE: 85/11/15 NOTARIZED; NO DOCKET FACIL!50-316 Donald C,
Cook Nuclear Power Planti Unit'~ Indiana 8
05000316 AUTH'AME AUTHOR AFFILIATION ALEXICH~M~ P.
& Michigan Electric Co.
REC IP ~ NAIVE'ECIPIENT AF F ILIATION DENTON~H ~ R ~
Of fice,, of Nuclear Reactor Regul ationi Director (pre-851125)
SUBJECT:
Notifies that plant-related parameter values in Cycle 6
transient analysis.rept submitted on 851015 reviewed by American Electric Power Svc Corp,Info will be reviewed by plant committees prior to 851231 Tech Spec submittal'ISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE,:
OR Submittal:
General Distribution NOTES:
OL e 12/23/72 05000316 RECIPIENT ID CODE/NAME PHR A PD4 PD 01 INTERNAL: ACRS 09 ELD/HDS3.
EB NRR/DHFT/TSCB NRR/DSRO DIR NRR/ORAS RGN3 COPIES LTTR ENCL 6
1 1
1 1
1 0
1 RECIPIENT ID CODE/NAME ADM/LFMB NRR BNR EB NRR PNR B
EB NRR/DSI/METB
/RRAB G
04 COPIES LTTR'NCL EXTERNAL: 24X LPDR NSIC 03~
05 1
1 1
EG8G BRUSKEgS NRC PDR 02 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 28 ENCL 5,
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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.o. BOX 16631 COLUMBUS, OHIO 43216 November 15, 1985 AEP:NRC:0916C Donald C.
Cook Nuclear Plant Unit No. 2 Docket No."50-316 License. No. DPR-74 D. C.
COOK UNIT 2>>
CYCLE 6, TRANSIENT ANALYSIS REPORT Mr. Harold R. Denton, Director r
Offioe of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
>lashington, D;C. 20555
Dear Mr. Denton:
Please be advised that Mr. R. A. Copeland of Exxon Nuclear Company (ENC)"transmitted to you by separate cover (ENC letter RAC:070:85 dated November 15, 1985) the report titled "Plant Transient Analysis for D. C.
Cook Unit 2 with 10$ Steam Generator Tube Plugging" (XN-NF-85-64).
'I The analyses were performed using, among other codes, the PTSPMR2 code.
The method of application is detailed in ENC report; ~Exxon Nuclear Methodology for PNRs: Analysis of Chapter 15 Events"
[XN-NF-84-73(P)] which was transmitted to"the Commission on August 27, 1985 via ENC.letter RAC:058:85.
In aooordanoe with this methodology, a systematic review of eaoh event described in the Standard Review Plan was performed in order to determine whioh events are most severe in terms of margin to limits.
This review is desoribed in ENC report
>>D. C. Cook Unit 2, Cycle 6 Safety Analysis Report: Disposition of Standard Review Plan Chapter 15 Events" t.XN-NF-85-28(P)3 which was transmitted to, you on',October 15, 1985 via ENC letter, RAC:.069:85.
The values used in the transient analysis which deal direotly with plant-related parameters (e.g., flows, temperatures, eto.) have been reviewed by the American Electric Power Service Corporation (AEPSC) with respect to applioation to.Donald C;. Cook'uclear'Plant, Unit 2; Application to the transient related analysis-;was performed by Exxon"Nuolear Company.
This information will be reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and the Nuclear Safety and Design Review Committee (NSDRC) prior to submittal of the Technical Speoification changes soheduled for; December 31, 1985.
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~'r. Harold R. Denton
~ pw AEP: NRC: 091 6C This dooument has been prepared following Corporate prooedures which inoorporate a reasonable set of oontrols to insure its aoouracy and oompleteness prior to signature by the undersigned.
Very truly yours, M.
. Alex h
Vice Pres ent ad cc:
John E. Dolan W. G.-Smith, Jr. - Bridgman G. Bruohmann "
R. C. Callen R. Gharnoff NRC-Resident Inspector - Bridgman R;--Copeland, ENC - Richland, WA
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