ML13007A057
| ML13007A057 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  (NPF-086) |
| Issue date: | 01/18/2013 |
| From: | John Lamb Plant Licensing Branch 1 |
| To: | Walsh K NextEra Energy Seabrook |
| Lamb J NRR/DORL/LPL1-2 301-415-3100 | |
| References | |
| TAC MF0464 | |
| Download: ML13007A057 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 18, 2013 Mr. Kevin Walsh Site Vice President c/o Michael O'Keefe Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO.1 - ACCEPTANCE LETTER REGARDING LICENSE AMENDMENT REQUEST 12-06, EXTEND THE INSPECTION INTERVAL FOR THE REACTOR COOLANT PUMP FLYWHEELS USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MF0464)
Dear Mr. Walsh:
By letter dated December 20, 2012 (Agencywide Documents Access and Management System Accession No. ML12359A016), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 12-06 for Seabrook Station, Unit 1 (Seabrook). The proposed change is to the Seabrook Technical Specification (TS) TS 6.7.6.m, "Reactor Coolant Pump Flywheel Inspection Program." The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years. The changes are consistent with Industryrrechnical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)." The availability of this TS improvement was announced in the Federal Register on October 22, 2003, as part of the consolidated line item improvement process.
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 Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, 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.
K. Walsh
~ 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 NRC staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-3100.
J n G. Lamb, Senior Project Manager ant Licensing Branch 1~2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443 cc: Distribution via Listserv
ML13007A057 OFFICE LPL 1-2/PM LPL3-1/LAit LPL1-2/LA LPL1-2/BC LPL 1-2/PM NAME JLamb ELee ABaxter MKhanna JLamb DATE 01/09/13 01/09/13 01/14/13 01/17/13 01/18/13