ML17326B149
| ML17326B149 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/20/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:086OR, AEP:NRC:86OR, NUDOCS 8408240121 | |
| Download: ML17326B149 (6) | |
Text
REGULATO r
INFORMATION DISTRIBUTION SYSTEM (RIDS)
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ACCESSION NBR ~ 8408240 1 2 1 DOC s DATE ~ 84/08/20 NOTARI'ZED ~
NO, DOCKET ¹ FACIL:50-316 Donald C.
Cook Nuclear Power Planti Unit 2i Indiana L
05000316 AUTH BYNAME AUTHOR AFFILIATION ALEXICHiM,P, Indiana L Michigan Electric Co.
REC IP ~ NAME RECIPIENT AFFILIATION DENTONiH Ri Office of Nuclear Reactor Regulationi Director
SUBJECT:
Notifies of plans to submit listed documents re PTSPNR2 code 8
ENC transient analysis methodology by 840831<pe 840601 ltr,App C for four loop methodology will be initiated following NRC comments re throe-loop methodologyg DISTRIBUTION CODE ~
A00 1D COPIES RECEI VED LTR ENCL SIZE ~
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Distribution NOTES:
. OL: 12/23/72 05000316 RECIPIENT ID CODE/NAME NRR ORBl BC 01 INTERNAl: ADM LFMB NRR/DE/MTEB NRR/DL/ORAB NRR/DS1/RAB RGN3 COPIES LTTR ENCL RECIPIENT ID CODE/NAME ELD/HDS3 NRR/DL D IR ETB R
G F ILE 04 COPIES LTTR ENCL EXTERNAL: ACRS NRC PDR NT'IS 09 02 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 26 ENCL
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 August 20, 1984 AEP:NRC:0860R Donald C.
Cook Nuclear Plant Unit No.
2 Docket No. 50-316
-License No. DPR-74 PLANT TRANSIENT ANALYSES Mr. Harold R. Denton, Director Office of Nuolear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
As mentioned in our letter, AEP:NRC:0860N dated June 1,
- 1984, Exxon Nuclear Company (ENC) will be transmitting to you by August 31, 1984 the following documents that will enable the NRC staff to review the PTSPWR2 code and ENC transient analysis methodology:
1.
PTSPWR2 Code Modification Report 2.
PTSPWR2 Code Benchmarking Report 3.
Generic methodology and applications document The third report describes the Exxon Nuclear Company generic methodology for the analysis of events for PWR safety analysis which was developed in accordance with the guidelines of the Standard Review Plan and Regulatory Guide 1.70.
As per discussions with your staff, it will contain Appendix B (Event Specific Analytical Methodology for Westinghouse three-loop design).
Once comments from the NRC staff are received on the three-loop methodology, ENC will initiate preparation of Appendix C for four-loop methodology.
The four-loop methodology is expected to be similar to the three-loop methodology.
The plant specific analyses using the PTSPWR2 code will be provided within 90 days after our receipt of NRC written acceptance of the PTSPWR2 code for D.C.
Cook 2 application.
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Hr. Harold R. Denton AEP:NRC:0860R 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.P. Ale ich gl4 lM'l Vice President g]
MPA/bgs cc: John E. Dolan M.G. Smith, Jr. - Bridgman R.C. Callen G. Charnoff E.R.
- Swanson, NRC Resident Inspector - Bridgman
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