Letter Sequence Acceptance Review |
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MONTHYEARML14239A5892014-08-21021 August 2014
NRR E-mail Capture - Acceptance Review for TACs MF4576 & MF4577 - Seabrook Unit 1 - Exemption Request and Technical Specification Change
Project stage: Acceptance Review
ML14232A6222014-09-0909 September 2014
Acceptance of Requested Licensing Amendment Request and Exemption Regarding Revised Reactor Coolant System Pressure-Temperature Limits
Project stage: Acceptance Review
ML14363A3672015-01-0909 January 2015
Request for Additional Information Regarding the License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Tempt Requirements
Project stage: RAI
SBK-L-15040, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-03-0909 March 2015
Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Response to RAI
ML15084A3752015-04-0303 April 2015
Request for Withholding Information from Public Disclosure Regarding License Amendment Request 14-04 for Seabrook Station, Unit 1 (TAC Nos. MF4576 and MF4577)
Project stage: Withholding Request Acceptance
ML15128A1482015-06-0505 June 2015
Request for Withholding Information from Public Disclosure Regarding License Amendment Request 14-04 for Seabrook Station, Unit 1
Project stage: Withholding Request Acceptance
SBK-L-15129, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-06-24024 June 2015
Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Response to RAI
SBK-L-15132, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-07-0909 July 2015
Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Response to RAI
SBK-L-15151, Supplemental Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-07-20020 July 2015
Supplemental Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Supplement
ML15096A1682015-07-27027 July 2015
Memorandum to File from John Lamb, DORL, NRR No Significant Hazards Consideration Analysis and Categorical Exclusion Related to Proposed Exemption
Project stage: Other
ML15205A3332015-07-28028 July 2015
Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Request for Exemption from Table 1 of 10 CFR Part 50, Appendix G NextEra Energy Seabrook, LLC Seabrook Station, Unit 1 Docket No. 50-443
Project stage: Approval
ML15092A5192015-07-28028 July 2015
Exemption
Project stage: Other
ML15096A1432015-07-28028 July 2015
Exemption from Specific Requirements of 10 CFR Part 50, Appendix G, and 10 CFR 50.60
Project stage: Approval
NRC-2015-0184, Exemption2015-07-28028 July 2015
Exemption
Project stage: Other
SBK-L-15172, Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-09-0808 September 2015
Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Supplement
ML15096A2552015-11-0202 November 2015
Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years
Project stage: Approval
2015-06-24
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Category:Acceptance Review Letter
MONTHYEARML23117A3652023-05-0404 May 2023
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves
ML23109A1862023-04-19019 April 2023
and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1
ML22341A0012022-12-0606 December 2022
Acceptance of Requested Licensing Action Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
ML22116A2442022-04-26026 April 2022
Acceptance of Requested Licensing Action Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage
ML21278A3092021-10-0606 October 2021
Acceptance of Requested Licensing Action Regarding Amendment to Revise 120-Volt AC Vital Instrument Panel Technical Specification Requirements
ML20063J9792020-02-28028 February 2020
Acceptance of Requested Licensing Action Amendment Request to Revise Degraded Voltage Time Delay Setpoint
ML16158A0182016-06-10010 June 2016
Acceptance of Requested Licensing Action Request to Extend Containment Leakage Test Frequency
ML15195A0692015-07-27027 July 2015
Acceptance of Proposed Licensing Amendment Request Regarding the Addition of a Note to Technical Specification Surveillance Requirement 4.4.1.3.4
ML14245A2042014-09-0909 September 2014
Acceptance of Proposed Licensing Amendment Request Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations
ML14245A1892014-09-0909 September 2014
Acceptance of Proposed Licensing Amendment Request Regarding the Increase to the Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement
ML14232A6222014-09-0909 September 2014
Acceptance of Requested Licensing Amendment Request and Exemption Regarding Revised Reactor Coolant System Pressure-Temperature Limits
ML14198A4202014-08-0808 August 2014
Acceptance of Requested Licensing Amendment Request Regarding Cyber Security Plan Implementation Schedule (Tac No. MF4447)
ML14085A3622014-04-0101 April 2014
Acceptance Letter Regarding Request for Relief 3IR-6 from American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection Piping
ML13262A3742013-11-22022 November 2013
Acceptance Letter Regarding License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology
ML13098A1152013-04-11011 April 2013
Acceptance Letter Regarding License Amendment Request 13-02, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.
ML13066A1582013-03-20020 March 2013
Acceptance Letter Regarding License Amendment Request 13-01, Application for Administrative Change and Corrections to the Technical Specifications
ML12178A6282012-06-29029 June 2012
Acceptance Letter Regarding License Amendment Request 12-03, Proposed Change to Cyber Security Plan Implementation Schedule Milestone 6
ML1135604092011-12-28028 December 2011
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
ML1125004162011-09-0707 September 2011
E-mail, Miller to O'Keefe, Seabrook Relief Requests 2IR-17, 2IR-18, 2IR-19, and 2IR-20 Acceptance Review
ML1121502302011-08-0303 August 2011
E-mail, Miller to O'Keefe, Seabrook LAR 11-03 Acceptance Review
ML1113804712011-05-18018 May 2011
E-mail, Miller to O'Keefe, Seabrook LAR 11-01 Acceptance Review
ML1106700172011-03-0808 March 2011
E-mail, Miller to O'Keefe, Seabrook LAR 10-06 Acceptance Review
ML1021403082010-08-0202 August 2010
E-mail, Miller, to O'Keefe, Seabrook, Acceptance Review LAR 10-03 Containment Protective Devices
ML1016605532010-06-15015 June 2010
E-mail, Miller, to O'Keefe, Seabrook Acceptance Review LAR 10-02 Ceeacs LCO
ML1012702572010-05-0707 May 2010
E-mail, Miller, to O'Keefe, Seabrook, Acceptance Review, ASME Code Alternative, Alternate Depth Sizing Qualification
ML0829400702008-10-20020 October 2008
E-mail, Acceptance Review for Relief Requests MD9781 and MD9783.
2023-05-04
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 9, 2014 Mr. Dean Curtland, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING AMENDMENT R~UEST AND EXEMPTION REGARDING REVISED 1
REACTOR COOL NT SYSTEM PRESSURE-TEMPERATURE LIMITS
{TAC NO. MF457 AND MF4577)
Dear Mr. Curtland:
By letter dated July 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14216A404) NextEra Energy Seabrook, LLC (NextEra or the licensee) requested a license amendment request to revise the Seabrook Station Technical Specification (TS) and an exemption from the requirements of Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, Appendix G. The proposed change is a request to revise the reactor coolant system (RCS) pressure-temperature limits applicable for 55 effective full-power years, provide new overpressure protection setpoints, and lowering the RCS temperature at which the TS is applicable.
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 following the email sent on August 21, 2014 (ADAMS Acces~ion No. ML14239A589). The acceptance review was i 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 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 concluded that it does 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
D. Curtland 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) 415-3100 or via e-mail at John .Lamb@ nrc.gov.
Jo G. Lamb, Senior Project Manager PI t Licensing Branch 1-2 Di ision of Operating Reactor LicensinQ Office of Nuclear Reactor Regulation 1 Docket No. 50-443 cc: Distribution via Listserv
ML14232A622 *via e-mail OFFICE LPL 1-2/PM LPL 1-2/PM LPL 1-2/LA* LPL 1-2/BC LPL 1-2/PM NAME Tlamb Jlamb ABaxter RSchaaf Jlamb DATE 8/19/14 8/19/14 08/29/14 9/09/14 9/09/14
