ML113560409

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Acceptance Letter Regarding License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure-Temperature Limits and the Cold Overpressure Protection Setpoints
ML113560409
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 12/28/2011
From: John Lamb
Plant Licensing Branch 1
To: Freeman P, O'Keefe M
NextEra Energy Seabrook
Lamb, JG, NRR/CLPM/LPD III-1, 415-1446
References
TAC ME7645
Download: ML113560409 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 28,2011 Mr. Paul Freeman Site Vice President clo 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 11-06, APPLICATION TO REVISE THE APPLICABILITY OF THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS AND THE COLD OVERPRESSURE PROTECTION SETPOINTS (TAC NO. ME7645)

Dear Mr. Freeman:

By letter dated November 17, 2011 (Agencywide Documents Access and Management System Accession No. ML11329A017), NextEra Energy Seabrook, LLC submitted a license amendment request for Seabrook Station.

The proposed amendment would revise the applicability of the figures in the Technical Specifications (TSs) for the reactor coolant system pressure-temperature limits and the cold overpressure protection setpoints. The proposed change revises the applicability of the figures from 20 effective full power years (EFPY) to 23.7 EFPY.

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 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.

P. Freeman

- 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, please contact me at (301) 415-3100.

G. Lamb, Senior Project Manager t Licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-443 cc: Distribution via Listserv

ML113560409 OFFICE LPL 1-2/PM LPL1-2/LA LPL1-2/BC LPL 1-2/PM NAME JLamb ABaxter (SUttle for)

HChernoff JLamb DATE 12/27111 12/28/11 12/28/11 12/28/11