ML091120534
| ML091120534 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/28/2009 |
| From: | Boska J Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC ME0788 | |
| Download: ML091120534 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 2009 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO.2 - ACCEPTANCE OF REQUESTED LICENSING ACTION FOR REVIEW RE: REACTOR VESSEL HEATUP AND COOLDOWN CURVES (TAC NO. ME0788)
Dear Sir or Madam:
By SECY-09-0027 Entergy'S Petition for Interlocutory Review of Licensing Board'S 12/18/08 Memo & O|letter dated March 5, 2009]], Agencywide Documents Access and Management System (ADAMS) Accession No. ML090760649, Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted a license amendment request for Indian Point Nuclear Generating Unit NO.2. The proposed amendment would revise the reactor vessel heatup and cooldown curves in the Technical Specifications (TSs). The purpose of this letter is to provide the results of the 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), an amendment to the license (including the TSs) 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 reviewed your application and initially concluded that supplemental information was needed to enable the NRC staff to proceed with its detailed technical review. By letter dated April 17, 2009, Entergy provided the supplemental information. The NRC staff has reviewed the supplemental information and concluded that it does provide technical information in sufficient detail to enable the NRC 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 NRC staff to complete its technical review, you will be advised by separate correspondence.
- 2 Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely,
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/ 40hn P. Boska, Senior Project Manager Jlant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247 cc: Distribution via Listserv
- 2 Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely, Ira!
John P. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247 cc: Distribution via Listserv DISTRIBUTION:
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