ML17321A399
| ML17321A399 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/25/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0860W, AEP:NRC:860W, NUDOCS 8501300239 | |
| Download: ML17321A399 (6) | |
Text
REGULATO INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR: 8501300239 DOC ~ DATE: 85/01/25 NOTARIZED:
NO DOCKET' FACIL;50-316 Donald CD Cook Nuclear Power Plant~ Unit 2i Indiana L
05000316 AUTH'AME'UTHOR AFF II IATION ALEXICH,M,P~
Indiana 8 Michigan Electr ic Co.
RECIP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationi Director
SUBJECT:
Confirms under standing that reanalyses" for Cycle 5 not required~as PTSPNR?
code 8 analysis methodology still being reviewed, Evaluation by Exxon Nuclear Co concluded that mods would have no significant effect on Cycle 5 analysis, DISTRIBUTION CODE; A001D COPIES RECEIVED:LTR ENCL SIZE; TITLE:
OR Submittal:
General Distribution NOTES: OL:12/23/72 05000316 RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: ACRS 09 ELD/HDS3 NRR/DL D IR NRR/DL/TSRG NRR/DSI/RAB RGN3 COPIES LTTR EN<'L RECIPIENT ID CODE/NAME ADM/LFMB NRR/DE/MTEB NRR/DI /ORAB ETB REG 00 COPIES LTTR ENCL EXTERNAL: LPDR NSIC 03.
05 NRC PDR'2" TOTAL NUMBER OF COPIES REQUIRED:
LTTR 26 ENCL
l 4
I 1
INDIANA 8 MICHIG AN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 January 25 1985 AEP:NRC:
0860>1 Donald C.
Cook Nuclear Plant Unit No.
2 Docket No. 50-316 License No. DPR-74 UNIT 2, CY(LE 5 TRANSIENT ANALYSES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commiss1on
)lashington, D. C.
20555
Dear Mr. Denton:
In accordance w1th the Unit 2, Cycle 5 Safety Evaluation Report, Indiana 4
Michigan Electric Company was to have reanalyzed transient analyses for Cycle 5=-
with the approved PTSP>lR2 code.
Pursuant to discussions with your staff in this matter, we understand that these reanalyses for Cycle 5 will not be required since the PTSPMR2 code and the analysis methodology are still under NRC staff review and for the reasons cited in your Safety Evaluation Report (Attachment to Amendment No 64 dated June 18, 1984) regarding margin of conservatism in predicting the minimum DNBR.
In addition, Exxon Nuclear Company has evaluated the recent modifications that have been made to the PTSP>lR2 oode in connection with the NRC's rev1ew of the oode and has concluded that these code modifications would not significantly affect the outcome of the Cycle 5 safety analysis.
Th1s document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to s1gnature by the undersigned.
Very truly yours, M
. Ale ich Vice President
/tm
$501300239 850125 PDR ADOCK 05000316 P
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Harold R. Denton Page 2
January
>~,
1985 oo: John E. Dolan W.
G. Smith, Jr. - Bridgman R.
C. Callen G. Bruohmann G. Charnoff NRC Resident Inspector - Bridgman
~
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