ML091170096

E-mail Transmitting Acceptance Review of License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology

ML091170096
Person / Time
Site:	Cook
Issue date:	04/27/2009
From:	Beltz T Plant Licensing Branch III
To:	Scarpello M - No Known Affiliation
beltz T, NRR/DORL/LPL3-1, 301-415-3049
References
TAC ME1017
Download: ML091170096 (2)

Text

Accession No. ML091170096 From:

Terry Beltz Sent:

Monday, April 27, 2009 9:08 AM To:

mkscarpello@aep.com Cc:

'jazwolinski@aep.com'; 'pgschoepf@aep.com'; Marshall David; Karl Feintuch

Subject:

Donald C. Cook Nuclear Plant, Unit 2 (CNP-2) - Acceptance Review Results of LAR re: Large Break LOCA Analysis Methodology (TAC No. ME1017)

Dear Mr. Scarpello:

By letter dated March 19, 2009, Indiana Michigan Power Company (the licensee) submitted a license amendment request for the Donald C. Cook Nuclear Plant, Unit 2 (CNP-2). The proposed amendment would modify Technical Specification (TS) 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," TS 3.5.2, "ECCS -

Operating," and TS 5.6.5, "Core Operating Limits Report (COLR)." The licensee is also requesting approval to adopt a new large break loss-of-coolant accident analysis for CNP-2.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR 50.90), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.

This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-3049.

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 (BB882299B277DB4C9C9A613B507A6F60088FDDB215)

Subject:

Donald C. Cook Nuclear Plant, Unit 2 (CNP-2) - Acceptance Review Results of LAR re: Large Break LOCA Analysis Methodology (TAC No. ME1017)

Sent Date: 4/9/2009 2:30:50 PM Received Date: 4/27/2009 9:07:00 AM From: Terry Beltz Created By: Terry.Beltz@nrc.gov Recipients:

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

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

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

Tracking Status: None Marshall.David@nrc.gov (Marshall David)

Tracking Status: None Karl.Feintuch@nrc.gov (Karl Feintuch)

Tracking Status: None Post Office:

HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 14315 4/9/2009 Options Expiration Date:

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