ML081560332
| ML081560332 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/31/2008 |
| From: | Beltz T NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Rencheck M Indiana Michigan Power Co |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC MD5297 | |
| Download: ML081560332 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 31 ' 2008 Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1) - REQUEST FOR ADDITIONAL INFORMATION, SECOND ROUND, REGARDING RE-ANALYSIS OF SMALL-BREAK LOSS-OF-COOLANT ACCIDENT (TAC NO. MD5297)
Dear Mr. Rencheck:
In a letter dated March 29,2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML071000431), Indiana Michigan Power Company (/&M) provided a re-analysis of the small-break loss-of-coolant accident for DCCNP-1. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information transmitted by that letter and issued a Request for Additional Information (RAI) on August 10, 2007 (ADAMS Accession No. ML072050570). I&M responded by letter dated February 29, 2008 (ADAMS Accession No. ML080740053).
The NRC staff reviewed the February 29, 2008, response, and generated an additional question which was discussed during a telephone conference with your staff on October 9, 2008. As a result of that discussion and subsequent internal deliberation, the NRC staff developed the enclosed second-round RAI. The details of RAJ were mutually agreed upon during a telephone conversation with Michael Scarpello of your staff on October 23, 2008.
Please respond within 60 days of the date of this letter. Feel free to contact me if you need further clarification of this RAI.
Sincerely,
~'-----
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
As stated cc: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION, SECOND ROUND DONALD C. COOK NUCLEAR PLANT, UNIT 1 RE-ANALYSIS OF SMALL-BREAK LOSS-OF-COOLANT ACCIDENT (SBLOCA)
(1)
Please provide an explanation, with appropriate supporting information, to understand the non-physical core mixture level behavior exhibited by the two-phase mixture level plots for the evaluated break spectrum contained in the small-break loss-of-coolant accident evaluation model re-analysis applicable to the Donald C. Cook Nuclear Plant, Unit 1.
October 31, 2008 Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUB~IECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1) - REQUEST FOR ADDITIONAL INFORMATION, SECOND ROUND, REGARDING RE-ANALYSIS OF SMALL-BREAK LOSS-OF-COOLANT ACCIDENT (TAC NO. MD5297)
Dear Mr. Rencheck:
In a letter dated March 29, 2007, Indiana Michigan Power Company (I&M) provided a re-analysis of the small-break loss-of-coolant accident for DCCNP-1. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information transmitted by that letter and issued a Request for Additional Information (RAI) on August 10, 2007 (Accession No. ML072050570). I&M responded by letter dated February 29, 2008.
The NRC staff reviewed the February 29,2008, response, and generated an additional question which was discussed during a telephone conference with your staff on October 9, 2008. As a result of that discussion and subsequent internal deliberation, the NRC staff developed the enclosed second-round RAI. The details of the RAI were mutually agreed upon during a telephone conversation with Michael Scarpello of your staff on October 23, 2008.
Please respond within 60 days of the date of this letter. Feel free to contact me if you need further clarification of this RAI.
Sincerely, lRAI Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
As stated cc: Distribution via ListServ DISTRIBUTION:
PUBLIC RidsOgcRp Resource RidsNrrDorlLpl3-1 Resource RidsAcrsAcnw_MailCTR Resource LPL3-1R/F RidsNrrDorlDpr Resource RidsNrrLATHarris Resource RidsNrrPMTBeltz Resource RidsNrrDssSnpb (AMendiola)
RidsRgn3MailCenter Resource RidsNrrDssSnpb (LWard)
ACCESSION NUMBER ML081560332 OFFICE LPL3-1:PM LPL3-1'PM LPL3-1:LA SNPB SNPB:BC LPL3-1:BC.
NAME TBeltz 7Ifi)
PTam\\()r1 ITHarri~..::b1If" LWard
~Mendiola LJames~,\\
DATE 10130108 10TJ (108 10/~'1/08 10/27/08 10/28/08 10/~ \\108
-J