ML092310637

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E-mail Transmitting Draft Requests for Additional Information Small Break LOCA Evaluation Model Reanalysis
ML092310637
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 08/19/2009
From: Beltz T
Plant Licensing Branch III
To: Scarpello M
American Electric Power Service Corp, Indiana Michigan Power Co
beltz T, NRR/DORL/LPL3-1, 301-415-3049
References
TAC MC1704
Download: ML092310637 (2)


Text

ADAMS Accession Number: ML092310637 From:

Beltz, Terry Sent:

Wednesday, August 19, 2009 8:09 AM To:

mkscarpello@aep.com Cc:

'pgschoepf@aep.com'; jrwaters@aep.com; jmpetro@aep.com; Ward, Leonard

Subject:

Donald C. Cook Nuclear Plant, Unit 2 - Draft Requests for Additional Information re: Small Break LOCA Evaluation Model Reanalysis (TAC No.

ME1147)

Attachments:

Draft RAIs_Unit 2 SBLOCA Reanalysis (ME1147).doc

Dear Mr. Scarpello:

This e-mail is in reference to Indian Michigan Power Company's (I&M, the licensee) submittal of the small break loss-of-coolant accident (SBLOCA) reanalysis, dated March 30, 2009 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML091100153), for Unit 2 of the Donald C. Cook Nuclear Plant.

The report documents the SBLOCA analyses with two different configurations of the emergency core cooling system (ECCS) cross-tie valves during the injection phase of the transient. One configuration is with the high head safety injection (HHSI) cross-tie valve closed and the residual heat removal (RHR) cross-tie valve(s) open at a core power level of 3304 MWt. The second configuration is with both the HHSI and RHR cross-tie valves open at a core power level of 3600 MWt. The reanalysis was performed using the Westinghouse NOTRUMP SBLOCA Emergency Core Cooling System Evaluation Model (NOTRUMP-EM), with COSI steam condensation model.

The NRC staff in the Nuclear Performance and Code Review Branch (SNPB) of the Office of Nuclear Reactor Regulation (NRR) has reviewed I&M's submittal and developed draft requests for additional information (RAI). The draft RAIs are provided as an attachment to this e-mail.

The NRC staff would like to discuss the draft RAIs with you in a conference call or meeting.

Among other things, the discussion will include how the NRC would formally issue these questions and how the licensee will respond to them.

The sole purpose of this e-mail and its attachment is to prepare you and others for the proposed conference call or meeting. This e-mail and its attachment do not convey a formal NRC staff position, and do not formally request for additional information.

Please don't hesitate to contact me if you have any questions or concerns.

Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov

E-mail Properties Mail Envelope Properties (350107B8B515F94F870C06F3E676E9257061CE0AD6)

Subject:

Donald C. Cook Nuclear Plant, Unit 2 - Draft Requests for Additional Information re: Small Break LOCA Evaluation Model Reanalysis (TAC No. ME1147)

Sent Date: 8/19/2009 8:08:52 AM Received Date: 8/19/2009 8:08:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:

mkscarpello@aep.com (mkscarpello@aep.com)

Tracking Status: None pgschoepf@aep.com ('pgschoepf@aep.com')

Tracking Status: None jrwaters@aep.com (jrwaters@aep.com)

Tracking Status: None jmpetro@aep.com (jmpetro@aep.com)

Tracking Status: None Leonard.Ward@nrc.gov (Ward, Leonard)

Tracking Status: None Post Office:

HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 63541 8/19/2009 Draft RAIs_Unit 2 SBLOCA Reanalysis (ME1147).doc 52754 Options Expiration Date:

Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: