ML083150421
| ML083150421 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/14/2008 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Rencheck M Indiana Michigan Power Co |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC MD9935 | |
| Download: ML083150421 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 14, 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 2 -ACCEPTANCE REVIEW RE:
AMENDMENT REQUEST FOR SUBMITTAL OF INSERVICE INSPECTION (lSI)
INFORMATION AND ANALYSES (TAC NO. MD9935)
Dear Mr. Rencheck:
By letter dated October 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082980354), Indiana Michigan Power Company (I&M) submitted a license amendment request for Unit 2 of the Donald C. Cook Nuclear Plant. The proposed amendment will add a license condition to comply with a requirement specified in the U.S.
Nuclear Regulatory Commission (NRC) safety evaluation associated with approval of topical report WCAP-16168-NP-A, Revision 2, "Risk-Informed Extension of the Reactor Vessel In Service Inspection Interval."
The license condition requires I&M to provide the NRC with the information and analysis requested in Section (e) of the final Section 50.61a of Title 10 of the Code of Federal Regulations (10 CFR) - or the proposed 10 CFR 50.61a, given in 72 FR 56275, prior to issuance of the final 10 CFR 50.61a - following completion of each American Society of Mechanical Engineers (ASME) Code,Section XI, Category B-A and B-D reactor vessel weld inspection, and that this information be submitted within 1 year of the inspection. The license condition provides assurance that I&M will submit the defined information and analyses to the NRC every time a specific lSI is performed.
The purpose of this letter is to provide the results of the NRC staff's 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, 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
M. Rencheck
-2 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 regarding this review, please contact me at (301) 415-3049.
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-316 cc: Distribution via ListServ
November 14, 2008 M. Rencheck
-2 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 regarding this review, please contact me at (301) 415-3049.
Sincerely, lRAI Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-316 cc: Distribution via ListServ DISTRIBUTION:
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