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Category:Technical Specifications
MONTHYEARML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML20293A1572020-12-28028 December 2020 Issuance of Amendment No. 167 Reactor Trip System Instrumentation Technical Specification Changes to Implement WCAP-14333 and WCAP-15376 ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements SBK-L-19104, License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements2019-10-0303 October 2019 License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements ML18228A7372018-08-31031 August 2018 Correction Letter for Amendment No. 157 Changes to the Technical Specifications Requirements for DC Batteries (CAC No. MG0046; EPID L-2017-LLA-0289) L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications 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 ML15231A1442015-10-0606 October 2015 Issuance of Amendment No. 150 Regarding Note for Reactor Coolant System Surveillance Requirements SBK-L-15183, LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days2015-09-25025 September 2015 LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days ML15096A1312015-07-17017 July 2015 Issuance of Amendment Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations ML15118A6322015-05-18018 May 2015 Issuance of Amendment Regarding License Amendment Request Regarding New Fuel Valut ML15082A2332015-04-24024 April 2015 Issuance of Amendment Regarding Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement ML15058A7062015-04-22022 April 2015 Issuance of Amendment No. 146 Regarding the Cyber Security Plan Implementation Schedule ML14345A2882015-02-0606 February 2015 Issuance of Amendment Regarding Technical Specifications Task Force Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation Using the Consolidated Line Item Improvement Process ML14363A2752015-02-0404 February 2015 Non-Proprietary SE for Issuance of Amendment Regarding License Amendment Request Regarding Fixed Incore Detector System Analysis ML14184A7952014-09-0303 September 2014 Issuance of Amendment Regarding License Amendment Request Regarding Fuel Storage Changes ML13212A0692014-07-24024 July 2014 Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML14029A4452014-03-0606 March 2014 Issuance of Amendment Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive SBK-L-13121, License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology2013-09-10010 September 2013 License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology ML1130000632013-04-23023 April 2013 Issuance of Amendment Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System SBK-L-13061, Response to December 2012 Request for Additional Information Regarding License Amendment Request 11-04, Changes to Technical Specifications for New and Spent Fuel Storage2013-03-27027 March 2013 Response to December 2012 Request for Additional Information Regarding License Amendment Request 11-04, Changes to Technical Specifications for New and Spent Fuel Storage SBK-L-13030, LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-03-27027 March 2013 LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process SBK-L-12266, Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2013-01-31031 January 2013 Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2012-12-20020 December 2012 License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process SBK-L-11130, License Amendment Request 11-03, Regarding Containment Spray Nozzles Surveillance Requirement2011-07-14014 July 2011 License Amendment Request 11-03, Regarding Containment Spray Nozzles Surveillance Requirement SBK-L-09196, License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program and TS 6.8.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria2009-09-18018 September 2009 License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program and TS 6.8.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria ML0819102622008-07-30030 July 2008 Technical Specifications, Issuance of Amendment Nuclear Instrumentation Surveillance Requirements ML0812000612008-04-29029 April 2008 Tec Specs to Amendment 118, License No. NPF-086, for Seabrook, Unit 1 ML0804606942008-03-27027 March 2008 Tech Spec Pages for Amendment 117 Setpoint Change for Reactor Trip System Interlock P-9 SBK-L-07142, Correction to License Amendment Request (LAR) 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-10-15015 October 2007 Correction to License Amendment Request (LAR) 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0723901902007-08-23023 August 2007 Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity. SBK-L-07112, License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process.2007-07-17017 July 2007 License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process. ML0708802862007-03-28028 March 2007 Technical Specifications, Issuance of Amendment Regarding TSTF -449 Steam Generator Tube Integrity TAC No. MD0696 ML0704704742007-02-0909 February 2007 Technical Specifications, Issuance of Amendment Mode Change Limitations ML0629902612006-10-17017 October 2006 Tech Spec Pages for Amendment 113 Removal of License Condition 2.G ML0627501812006-09-29029 September 2006 Technical Specifications, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet SBK-L-06157, Response to Request for Additional Information Regarding License Amendment Request 05-08 Limited Inspection of the Steam Generator Tube Portion within the Tubesheet.2006-08-0808 August 2006 Response to Request for Additional Information Regarding License Amendment Request 05-08 Limited Inspection of the Steam Generator Tube Portion within the Tubesheet. SBK-L-06059, License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.2006-08-0707 August 2006 License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes. ML0616402492006-06-12012 June 2006 Technical Specification - Correction of Amendment No. 108, Six-Month Extension for the Containment Integrated Leakage Rate Test Interval ML0616402512006-06-0909 June 2006 Tech Spec Page for Emergency Amendment 111 Allowed Outage Time Extension from 7 Days to 14 Days for Enclosure Air Handling Fan SBK-L-06127, Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change2006-06-0707 June 2006 Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change ML0614402592006-05-22022 May 2006 Tech Spec Pages for Amendment 110 Regarding Measurement Uncertainty Recapture Power Uprate ML0612802822006-05-0505 May 2006 Technical Specification Pages Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports - Technical Specifications Index, 6.0 Administrative Controls SBK-L-06065, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.2006-04-28028 April 2006 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process. ML0610203542006-04-13013 April 2006 Tech Spec Pages for Correction of Amendment No. 107, Regarding Removal of Requirement to Perform End-of-Life Moderator Temperature Coefficient Measurement (Tac No. MC6566) ML0608601162006-03-24024 March 2006 Technical Specification Page, Revises to Permit a one-time, 6-month, Addition to the currently-approved 5-year Extension to the 10-year Test Interval for the Containment Integrated Leak Rate Test L-2006-042, 30-day Response to NRC Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 20062006-02-17017 February 2006 30-day Response to NRC Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 2006 ML0600904762006-01-0606 January 2006 Tech Spec Page for Amendment 106 Extension of Containment Air Lock Interlock Surveillance Requirement Interval 2024-05-07
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.(4) F P Energy Seabrook, LLC,_pursuant to the Act and 10QCF 0.,40 nd 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein; and (7) DELETED C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject.to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level FPL Energy Seabrook, LLC, is authorized to operate the facility at reactor core power levels not in excess of 3648 megawatts thermal (100% of rated power).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 117*, and the Environmental Protection Plan contained in Appendix B are, incorporated into the Facility License No. NPF-86.
FPL Energy Seabrook, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) License Transfer to FPL Energy Seabrook, LLC
- a. On the closing date(s) of the transfer of any ownership interests in Seabrook Station covered by the Order approving the transfer, FPL Energy Seabrook, LLC, shall obtain from each respective transferring owner all of the accumulated decommissioning trust funds for the facility, and ensure the deposit of such funds and additional funds, if necessary, into a decommissioning trust or trusts for Seabrook Station established by FPL Energy Seabrook, LLC, such that the amount of such funds deposited meets or exceeds the amount required under 10 CFR 50.75 with respect to the interest in Seabrook Station FPL Energy Seabrook, LLC, acquires on such dates(s).
- Implemented AMENDMENT NO. 117
TABLE 2.2-1 (continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) z TRIP SETPOINT ALLOWABLE VAL!.IE
- 18. Reactor Trip System Interlocks
- a. Intermediate Range N.A. N.A. N.A. Ž1 x 10-10 amp x 10-11 amp
___6 Neutron Flux, P-6
- b. Low Power Reactor Trips Block, P-7
- 1) P-10 input N.A. N.A. N.A. *10% of RTP* *12.1% of RTP*
- 2) P-13 input N.A. N.A. N.A. *10% RTP* Turbine *12.3% of RTP* Turbine Impulse Pressure Impulse Pressure Equivalent Equivalent
- c. Power Range Neutron N.A. N.A. N.A. *50% of RTP* *52.1% of RTP*
Flux, P-8
- d. Power Range Neutron N.A. N.A. N.A. *45% of RTP* <45.3% of RTP*
Flux, P-9 I
- e. Power Range Neutron N.A. N.A. N.A. >_10% of'RTP* >7.9% of RTP*
Flux, P-10
- f. Turbine Impulse Chamber N.A. N.A. N.A. <10% RTP* Turbine *12.3% RTP* Turb ne Pressure, P-13 Impulse Pressure Impulse Pressure Equivalent Equivalent
- 19. Reactor Trip Breakers N.A. N.A. N.A. N.A. N.A.
- 20. Automatic Trip and Interlock N.A. N.A. N.A. N.A. N.A.
I Logic
- RTP = RATED THERMAL POWER SEABROOK - UNIT 1 2-6 Amendment No. 117