ML13267A037
| ML13267A037 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/25/2013 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Meyer L Point Beach |
| Beltz T | |
| References | |
| TAC MF2372, TAC MF2373 | |
| Download: ML13267A037 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 25, 2013 Mr. Larry Meyer Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -ACCEPTANCE OF LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO TRANSITION TO NFPA 805, "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS" (TAC NOS. MF2372 AND MF2373)
Dear Mr. Meyer:
By letter dated June 26,_ 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. IVIL131820453), NextEra Energy Point Beach, LLC (NextEra) submitted a license amendment request for the Point Beach Nuclear Plant, Units 1 and 2 (Point Beach). The proposed amendment request would transition the fire protection licensing basis at Point Beach to Title 10 of the Code of Federal Regulations (10 CFR), Section 50,48(c), National Fire Protection Association Standard NFPA 805. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (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 (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.
In an e-mail datedSeptember9.2013(ADAMSAccessionNo.ML13256A197), the NRC staff informed NextEra that supplemental information was required to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and protection of public health and safety and the environment. In response to the NRC staff's request, NextEra provided supplemental information in a letter dated September 16,2013 (ADAMS Accession No. ML13259A273).
The NRC staff has reviewed your application and supplemental information, and concluded that there is now technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment. Given the lesser scope and depth of the acceptance review as
L. Meyer
- 2 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.
If you have any questions, please contact me at (301) 415-3049, or via e-mail at Terry.Beltz@nrc.gov.
Terry A. Beltz, Senior Project 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
L. Meyer
- 2 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 staffs detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-3049, or via e-mail at Terry.Beltz@nrc.gov.
Sincerely, IRA!
Terry A. Beltz, Senior Project 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 DISTRIBUTION:
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