ML101970089
| ML101970089 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/21/2010 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Meyer L Point Beach |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC ME4006, TAC ME4007 | |
| Download: ML101970089 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2010 Mr. Larry Meyer Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516 SUB..IECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ACCEPTANCE REVIEW RE: LICENSE AMENDMENT REQUEST FOR REVISION TO THE REACTOR VESSEL HEAD DROP METHODOLOGY (TAC NOS. ME4006 AND ME4007)
Dear Mr. Meyer:
In an application dated June 1, 2010, as supplemented by letter dated July 9, 2010, NextEra Energy Point Beach, LLC (NextEra, the licensee) submitted a license amendment request to revise the current license basis regarding a postulated reactor vessel head drop event to conform to the U.S. Nuclear Regulatory Commission (NRC)-endorsed guidance of Nuclear Energy Institute 08-05, "Industry Initiative on Control of Heavy Loads," Revision a (ADAMS Accession No. ML082410532). The purpose of this letter is to provide the results of the !\\IRC 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 (10 CFR), 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 supplement, and concluded that they provide technical information in sufficient detail to enable the NRC staff to complete 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
L. Meyer
- 2 If you have any questions regarding this matter, I may be reached at (301) 415-2048.
- ~J/ _
~~f;~:ect Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: Distribution via ListServ
ML101970089 JFFICE LPL3-1/PM LPL3-1/LA LP3-1/BC
\\lAME rTBeltz fHarris RPascarelli JATE Kl7/16/10 07/16/10 107/21/10