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Revision as of 20:08, 21 April 2019

Acceptance Letter Regarding License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology
ML13262A374
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 11/22/2013
From: Lamb J G
Plant Licensing Branch 1
To: Ossing M, Walsh K
NextEra Energy Seabrook
Lamb J G
References
LAR 13-05, TAC MF2751
Download: ML13262A374 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 0387 4 November 22, 2013

SUBJECT:

SEABROOK STATION, UNIT NO.1 -ACCEPTANCE LETTER REGARDING LICENSE AMENDMENT REQUEST 13-05, "FIXED INCORE DETECTOR SYSTEM ANALYSIS METHODOLOGY" (TAC NO. MF2751)

Dear Mr. Walsh:

By letter dated September 10, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13260A 159), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-05 for Seabrook Station, Unit No. 1 (Seabrook).

The proposed change is to the Seabrook Technical Specification (TS). Specifically, the proposed amendment would revise TS 6.8.1.6.b, "Core Operating Limits Report," by adding Areva Licensing Report ANP-3243P, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis Supplement to YAEC-1855PA," which supplements and modifies the previously approved methodology in YAEC-18855PA, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis," October 1992. The proposed change also modifies the surveillance requirements associated with the heat flux hot channel factor and nuclear enthalpy rise hot channel factor to include revised uncertainty values when measurement is obtained using the fixed incore detector system. 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.

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 (1 0 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 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.

Docket No. 50-443 cc: Distribution via Listserv Sincerely, . Lamb, Senior Project Manager t Licensing Branch 1-2 1 ision of Operating Reactor Licensing ice of Nuclear Reactor Regulation K. Walsh 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.

Docket No. 50-443 cc: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLI-2 RIF Sincerely, Ira/ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorllpl1-2 Resource RidsNrrDoriDpr Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrLAABaxter Resource RidsNrrPMSeabrook Resource RidsRgn1 MaiiCenter Resource ADAMS Accession No: ML 13262A374 OFFICE LPL 1-2/PM LPL 1-2/LA* LPL 1-2/PM NAME Jlamb ABaxter Jlamb DATE 11/22/13 09/23/13 11/22/13 OFFICIAL RECORD COPY