ML17320B087
| ML17320B087 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/01/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0860N, AEP:NRC:860N, NUDOCS 8406050315 | |
| Download: ML17320B087 (6) | |
Text
REGULATORY FORMATION DISTRIBUTION SY EM (RIDS)
ACCESSION NBR:8006050315 DOC ~ DATE: 84/06/01 NOTARIZED:
NO DOCKET FACIL:50-316 Donald C,
Cook Nuclear Power-Pl ant~ Unit 2~ Indiana 8
05000316 AUTH BYNAME AUTHOR AFFILIATION ALEXICHgM.PE Indiana 8 Michigan Electric Co, RECIP ~ NAME RECIPIENT AFFILIATION DENTONiH ~ RE Office of Nuclear Reactor Regulationr Director
SUBJECT:
Advises that PTS"PHR2 code mods~benchmarking documents 8
methodology L applications documentation for Nestinghouse P~'IR will be submi,tted to provide acceptable plant:-transient
- analyses, DISTRIBUTION CODE:
A001S COPIES RECEIVED:LTR ENCL SIZE TITLE:
OR Submittal:
General Distribution NOTES:
RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: ELD/HDS3 NRR/DL DIR NRR/
I/METB 04 COPIES LTTR ENCL 7
7 1
0 1
1 1
1 1
RECIPIENT ID CODE/NAME NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGN3 COPIES LTTR ENCL 1
0 1
1 EXTERNAL+
6 1
1 1
1 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 25 ENCL 23
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INDIANA& MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 June 1,'984 AEP:NRC:0860N 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 Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In order to provide acceptable plant transient analyses for Unit 2, using the PTS-PWR2 code developed by Exxon Nuclear
- Company, we will be providing the following:
1)
PTS-PWR2 code modifications 2)
Benchmarking documents a)
Prairie Island tube rupture event b)
LOFT tests c)
RELAP5 analysis of coastdown of Primary Pumps 3)
Methodology and applications documentation for Westinghouse PWR's Pursuant to our discussions with your staff, AEP commits to providing the above information on or before September 1,
1984.
The plant specific analyses using the PTS-PWR2 code will be provided within 90 days after our receipt of NRC written acceptance of the PTS-PWR2 code for D.C. Cook application.
Exxon Nuclear Company has assured us that this can be achieved in accordance with the above schedule.
Also, please note that Mr. R.A. Copeland of Exxon Nuclear Company transmitted to Mr. J.
Guttmann of Reactor Systems Branch (NRC) on March 26, 1984 responses to the preliminary set of questions from Argonne National Laboratory on the PTS-PWR2 code (ENC Letter No. RAC:026:84).
Specifically inoluded are responses to:
- 1) forty-three of the forty-nine September 30 questions on PTS-PWR2 code,
- 2) all of the March 6 Prairie Island benchmark questions and 3) the three questions of November 22 concerning PTS-PWR2 code.
840b0503i5 840b0i PDR ADQCK 05000Dib PDR
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Hr. Harold R. Denton AEP: NRC:0860N 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 under signed.
Very truly yours, Alex ch qg /p ice Pr ident cc:
John E. Dolan H.G. Smith, Jr. - Bridgman R.C. Callen G. Charnoff E.R.
- Swanson, NRC Resident Inspector - Bridgman G.F. Owsley - Exxon Nuclear Company
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