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| | issue date = 10/06/2015 | | | issue date = 10/06/2015 |
| | title = Issuance of Amendment No. 150 Regarding Note for Reactor Coolant System Surveillance Requirements | | | title = Issuance of Amendment No. 150 Regarding Note for Reactor Coolant System Surveillance Requirements |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Curtland D A | | | addressee name = Curtland D |
| | addressee affiliation = NextEra Energy Seabrook, LLC | | | addressee affiliation = NextEra Energy Seabrook, LLC |
| | docket = 05000443 | | | docket = 05000443 |
| | license number = NPF-086 | | | license number = NPF-086 |
| | contact person = Lamb J G, NRR/DORL/LPLI-2, 415-3100 | | | contact person = Lamb J, NRR/DORL/LPLI-2, 415-3100 |
| | case reference number = TAC MF6478 | | | case reference number = TAC MF6478 |
| | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications | | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications |
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| ==1.0 BACKGROUND== | | ==1.0 BACKGROUND== |
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| RELATED TO AMENDMENT NO. 150 TO FACILITY OPERATING LICENSE NO. NPF-86 NEXTERA ENERGY SEABROOK, LLC, ET AL. SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443 By letter dated June 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14177 A503), as supplemented by letter dated December 11, 2014 (ADAMS Accession No. ML 14349A646), NextEra Energy Seabrook, LLC (NextEra, or the licensee) requested changes to the Technical Specifications (TSs) for Seabrook Station, Unit No. 1 (Seabrook). | | RELATED TO AMENDMENT NO. 150 TO FACILITY OPERATING LICENSE NO. NPF-86 NEXTERA ENERGY SEABROOK, LLC, ET AL. SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443 By letter dated June 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14177A503), as supplemented by letter dated December 11, 2014 (ADAMS Accession No. ML14349A646), NextEra Energy Seabrook, LLC (NextEra, or the licensee) requested changes to the Technical Specifications (TSs) for Seabrook Station, Unit No. 1 (Seabrook). |
| Specifically, the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation,'' | | Specifically, the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation,'' |
| dated February 21, 2013 (ADAMS Accession No. ML 13053A075). | | dated February 21, 2013 (ADAMS Accession No. ML13053A075). |
| By letter dated February 6, 2015 (ADAMS Accession No. ML 14345A288), the NRC issued Amendment No. 144 to Facility Operating License No. NPF-86 for Seabrook, which modified Seabrook's TSs by revising the surveillance requirements (SRs) related to gas accumulation for the emergency core cooling system (ECCS). Amendment No. 144 also added new SRs related to gas accumulation for the residual heat removal (RHR) and containment spray (CS) systems. In its letter dated June 24, 2014, the licensee requested a note be added to TS page 3/4 4-5, Reactor Coolant System (RCS), Reactor Coolant Loops and Coolant Circulation, Hot Shutdown, Surveillance Requirements (SRs). In its subsequent letter dated December 11, 2014, however, the licensee inadvertently left off the note on TS page 3/4 4-5. Therefore, Amendment No. 144 does not have the note on TS page 3/4 4-5. | | By letter dated February 6, 2015 (ADAMS Accession No. ML14345A288), the NRC issued Amendment No. 144 to Facility Operating License No. NPF-86 for Seabrook, which modified Seabrook's TSs by revising the surveillance requirements (SRs) related to gas accumulation for the emergency core cooling system (ECCS). Amendment No. 144 also added new SRs related to gas accumulation for the residual heat removal (RHR) and containment spray (CS) systems. In its letter dated June 24, 2014, the licensee requested a note be added to TS page 3/4 4-5, Reactor Coolant System (RCS), Reactor Coolant Loops and Coolant Circulation, Hot Shutdown, Surveillance Requirements (SRs). In its subsequent letter dated December 11, 2014, however, the licensee inadvertently left off the note on TS page 3/4 4-5. Therefore, Amendment No. 144 does not have the note on TS page 3/4 4-5. |
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| ==2.0 INTRODUCTION== | | ==2.0 INTRODUCTION== |
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| By letter dated July 13, 2015 (ADAMS Accession No. ML 15198A027), the licensee requested that the note in NRC-approved TSTF-523 be added to TS page 3/4 4-5. Enclosure 2 | | By letter dated July 13, 2015 (ADAMS Accession No. ML15198A027), the licensee requested that the note in NRC-approved TSTF-523 be added to TS page 3/4 4-5. Enclosure 2 |
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| ==3.0 REGULATORY EVALUATION== | | ==3.0 REGULATORY EVALUATION== |
Letter Sequence Approval |
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TAC:MF6478, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) |
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Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 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 SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements ML22287A1572022-12-0505 December 2022 Issuance of Amendment No. 171 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22230C9242022-09-30030 September 2022 Issuance of Amendment No. 170 Revision of 120-Volt AC Vital Instrument Panel Requirements ML21008A0142021-02-25025 February 2021 Issuance of Amendment No. 168 Revise Technical Specification Table 3.3.4 to Change Time Delay Setpoints for Degraded Voltage Relays ML20293A1572020-12-28028 December 2020 Issuance of Amendment No. 167 Reactor Trip System Instrumentation Technical Specification Changes to Implement WCAP-14333 and WCAP-15376 ML20298A2532020-11-24024 November 2020 Issuance of Amendment No. 166 Revise Technical Specification 3/4.8.1, A.C. Sources Operating ML20318A0032020-11-24024 November 2020 Issuance of Revised Page for Renewed Facility Operating License Atomic Safety and Licensing Board Decisions LBP-20-09 and LBP-20-12 ML20070Q0712020-03-27027 March 2020 Issuance of Amendment No. 165 Emergency Core Cooling System Accumulator Technical Specification Changes ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements ML19224A5632019-11-18018 November 2019 Issuance of Amendment No. 162 Revisions to Technical Specifications Associated with Movable Control Rods ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19129A2432019-05-10010 May 2019 Correction to Amendment No. 160 Regarding Measurement and Assessment Frequency for Technical Specification 6.7.6 L, Control Room Envelope Habitability Program ML19065A2152019-03-29029 March 2019 Issuance of Amendment No. 160 Measurement and Assessment Frequency for Technical Specification 6.7.6.l, Control Room Envelope Habitability Program ML18355A4912019-03-12012 March 2019 Renewed Facility Operating License ML18204A2912019-03-11011 March 2019 Issuance of Amendment No. 159 Methodology for Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction ML18247A5382018-11-27027 November 2018 Issuance of Amendment No. 158 Removing Requirement to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications ML18199A6092018-08-0707 August 2018 Issuance of Amendment No. 157 Changes to the Technical Specifications Requirements for DC Batteries (CAC No. MG0046; EPID L-2017-LLA-0289) ML17102A8892017-04-13013 April 2017 Issuance of Amendment Licensing Basis Change for Service Water Cooling Tower ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) SBK-L-16082, Supplement to License Amendment Request 16-01 Request to Extend Containment Leakage Test Frequency2016-05-31031 May 2016 Supplement to License Amendment Request 16-01 Request to Extend Containment Leakage Test Frequency ML16068A1302016-02-27027 February 2016 License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors 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 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 ML15002A2512015-03-31031 March 2015 Unit No.1 - Issuance of Amendment Regarding License Amendment Request 14-06, Application Regarding the Removal of the Cold Leg Injection Permissive from Technical Specifications 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 ML13213A1432014-03-0505 March 2014 Issuance of Amendment Regarding the Use of Optimized Zirlo Fuel Rod Cladding Material ML13107A0162013-10-25025 October 2013 Issuance of Amendment Regarding the License Amendment Request 13-02, Application to Revise Technical Specifications to Adopt TSTSF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.. ML13204A3792013-07-26026 July 2013 Correction to Issuance of Amendment 137 Regarding the Administrative Changes and Corrections to the Technical Specifications ML13074A7602013-06-17017 June 2013 Issuance of Amendment Regarding the Administrative Changes and Corrections to the Technical Specifications ML13114A3172013-04-25025 April 2013 Correction to Issuance of Amendment 136 Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System 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 ML1208205102013-04-15015 April 2013 Issuance of Amendment Revision to the Applicability of the Reactor Coolant System Pressure-Temperature Limits and the Cold Overpressure Protection Setpoints ML13028A1462013-04-0404 April 2013 Issuance of Amendment Regarding the Extension of the Inspection Interval for the Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process ML12332A3012013-01-31031 January 2013 Issuance of Amendment Emergency Plan ML12237A0942012-11-0202 November 2012 Issuance of Amendment Cyber Security Program ML12178A5372012-09-10010 September 2012 Issuance of Amendment Permanent Application of Steam Generator Tube Alternate Repair Criteria, H* ML1200302712012-02-23023 February 2012 Issuance of Amendment Regarding the Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation ML1120700482011-08-23023 August 2011 Issuance of Amendment Approval of Cyber Security Plan ML1112503882011-08-22022 August 2011 Issuance of Amendment 126 Remove Technical Specification 3.4.10, Structural Integrity ML1108401882011-04-29029 April 2011 Issuance of Amendment Relocation of Technical Specification Requirements Related to Electrical Equipment Protective Devices ML1021702782010-09-0202 September 2010 Issuance of Amendment Operations Manager Qualification Requirements 2023-12-22
[Table view] Category:Safety Evaluation
MONTHYEARML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code ML22287A1572022-12-0505 December 2022 Issuance of Amendment No. 171 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22262A3142022-10-0404 October 2022 Relief Requests 3IR-18 and 3IR-19, Relief from the Requirements of the ASME Code ML22230C9242022-09-30030 September 2022 Issuance of Amendment No. 170 Revision of 120-Volt AC Vital Instrument Panel Requirements ML21008A0142021-02-25025 February 2021 Issuance of Amendment No. 168 Revise Technical Specification Table 3.3.4 to Change Time Delay Setpoints for Degraded Voltage Relays ML20293A1572020-12-28028 December 2020 Issuance of Amendment No. 167 Reactor Trip System Instrumentation Technical Specification Changes to Implement WCAP-14333 and WCAP-15376 ML20298A2532020-11-24024 November 2020 Issuance of Amendment No. 166 Revise Technical Specification 3/4.8.1, A.C. Sources Operating ML20070Q0712020-03-27027 March 2020 Issuance of Amendment No. 165 Emergency Core Cooling System Accumulator Technical Specification Changes ML20076D2812020-03-17017 March 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML20073E4342020-03-17017 March 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19340A1282019-12-13013 December 2019 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements ML19224A5632019-11-18018 November 2019 Issuance of Amendment No. 162 Revisions to Technical Specifications Associated with Movable Control Rods ML19249B1012019-09-30030 September 2019 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code; Relief Request RA-19-001 ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19065A2152019-03-29029 March 2019 Issuance of Amendment No. 160 Measurement and Assessment Frequency for Technical Specification 6.7.6.l, Control Room Envelope Habitability Program ML18204A2912019-03-11011 March 2019 Issuance of Amendment No. 159 Methodology for Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction ML18247A5382018-11-27027 November 2018 Issuance of Amendment No. 158 Removing Requirement to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications ML18199A6092018-08-0707 August 2018 Issuance of Amendment No. 157 Changes to the Technical Specifications Requirements for DC Batteries (CAC No. MG0046; EPID L-2017-LLA-0289) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17102A8892017-04-13013 April 2017 Issuance of Amendment Licensing Basis Change for Service Water Cooling Tower ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17080A0382017-03-27027 March 2017 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML17046A4432017-03-15015 March 2017 Issuance of Amendment Extension of Containment Leakage Rate Test Frequency ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16321A4182016-12-0101 December 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 (CAC Nos. MF0836 and MF0837) 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 ML15096A1432015-07-28028 July 2015 Exemption from Specific Requirements of 10 CFR Part 50, Appendix G, and 10 CFR 50.60 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 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 ML15002A2512015-03-31031 March 2015 Unit No.1 - Issuance of Amendment Regarding License Amendment Request 14-06, Application Regarding the Removal of the Cold Leg Injection Permissive from Technical Specifications 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 ML14071A4102014-04-10010 April 2014 Request for Relief RA-14-001 from American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection Piping (TAC No. Mfxxxx) ML14029A4452014-03-0606 March 2014 Issuance of Amendment Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive ML13213A1432014-03-0505 March 2014 Issuance of Amendment Regarding the Use of Optimized Zirlo Fuel Rod Cladding Material ML13247A7772014-02-0909 February 2014 Request for Relief to Use an Alternative to the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML13107A0162013-10-25025 October 2013 Issuance of Amendment Regarding the License Amendment Request 13-02, Application to Revise Technical Specifications to Adopt TSTSF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.. ML13074A7602013-06-17017 June 2013 Issuance of Amendment Regarding the Administrative Changes and Corrections to the Technical Specifications ML13050A1382013-06-13013 June 2013 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 2023-03-23
[Table view] Category:Technical Specifications
MONTHYEARSBK-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 SBK-L-05260, License Amendment Request 05-11, Changes to Technical Specification 3.8.3.1, Onsite Power Distribution, for Vital Inverter Allowed Outage Time.2005-12-0606 December 2005 License Amendment Request 05-11, Changes to Technical Specification 3.8.3.1, Onsite Power Distribution, for Vital Inverter Allowed Outage Time. SBK-L-05197, License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval.2005-09-29029 September 2005 License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval. 2022-03-07
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Dean Curtland, Site Vice President c/o Mr. Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 0387 4 October 6, 2015
SUBJECT:
SEABROOK STATION, UNIT NO. 1 -ISSUANCE OF AMENDMENT REGARDING NOTE FOR REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (TAC NO. MF6478)
Dear Mr. Curtland:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 150 to Facility Operating License No. NPF-86 for the Seabrook Station, Unit No. 1 (Seabrook).
This amendment consists of changes to the facility technical specifications (TSs) in response to your application dated July 13, 2015. The amendment adds a note to the Seabrook TS Surveillance Requirements (SRs) 4.4.1.3, "Reactor Coolant System, Reactor Coolant Loops and Coolant Circulation, Hot Shutdown." By letter dated February 6, 2015, the NRC issued Amendment No. 144 that modified Seabrook's TSs to address NRC Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems." The changes were consistent with the NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation," for plant-specific adoption using the Consolidated Line Item Improvement Process. The Federal Register notice published on January 15, 2014 (79 FR 2700), announced the availability of this TS improvement.
In a submittal dated June 24, 2014, the licensee requested to have the note added to Seabrook TS SRs 4.4.1.3. In a later submittal dated December 11, 2014, the licensee inadvertently left out the note on the TS page. On February 6, 2015, the NRC approved the licensee's request, in Amendment No. 144 to the operating license. Amendment No. 144 inadvertently omitted the note; however, the omitted note was due to the licensee's letter dated December 11, 2014. The current amendment corrects the inadvertent omission of the note.
D. Curtland A copy of the related safety evaluation is also enclosed.
Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-443
Enclosures:
- 1. Amendment No. 150 to NPF-86 2. Safety Evaluation cc w/enclosures:
Distribution via Listserv . Lamb, Senior Project Manager Licensing Branch 1-2 ion of Operating Reactor Licensing e of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NEXTERA ENERGY SEABROOK, LLC, ET AL.* DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. NPF-86 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment filed by NextEra Energy Seabrook, LLC, et al., (the licensee) dated July 13, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- NextEra Energy Seabrook, LLC is authorized to act as agent for the: Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, and Taunton Municipal Light Plant and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
Enclosure 1 2. Accordingly, the license is amended by changes to paragraphs 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 151), and the Environmental Protection Plan contained in Appendix B are incorporated into the Facility License No. NPF-86. NextEra Energy Seabrook, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days. FOR THE NUCLEAR REGULATORY COMMISSION Douglas A. Broaddus, Chief Plant Licensing Branch 1-2
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
October 6 , 2015 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 150 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following page of Facility Operating License No. NPF-86 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. Remove 3 Insert 3 Replace the following page of Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the area of change. Remove 3/4 4-5 Insert 3/4 4-5 (4) NextEra Energy Seabrook, LLC, pursuant to the Act and 1 O CFR 30, 40, and 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) NextEra 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) NextEra Energy Seabrook, LLC, pursuant to the Act and 1 O 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 1 O 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:
- Implemented (1) Maximum Power Level NextEra 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. 150*, and the Environmental Protection Plan contained in Appendix Bare incorporated into the Facility License No. NPF-86. NextEra 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 1 O CFR 50. 75 with respect to the interest in Seabrook Station FPL Energy Seabrook, LLC**, acquires on such dates(s).
- On April 16, 2009, the name "FPL Energy Seabrook, LLC" was changed to "NextEra Energy Seabrook, LLC". AMENDMENT NO. 150 (4) NextEra Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 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) NextEra 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) NextEra 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:
- Implemented (1) Maximum Power Level NextEra 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. 151 *,and the Environmental Protection Plan contained in Appendix B are incorporated into the Facility License No. NPF-86. NextEra 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).
4.4.1.3.2 The required steam generator(s) shall be determined OPERABLE by verifying secondary-side water level to be greater than or equal to 14% in accordance with the Surveillance Frequency Control Program. 4.4.1.3.3 At least one reactor coolant or RHR loop shall be verified in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program. 4.4.1.3.4 Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.*
- Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4. SEABROOK -UNIT 1 3/4 4-5 Amendment No. 141, 144, 150 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BYTHE OFFICE OF NUCLEAR REACTOR REGULATION
1.0 BACKGROUND
RELATED TO AMENDMENT NO. 150 TO FACILITY OPERATING LICENSE NO. NPF-86 NEXTERA ENERGY SEABROOK, LLC, ET AL. SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443 By letter dated June 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14177A503), as supplemented by letter dated December 11, 2014 (ADAMS Accession No. ML14349A646), NextEra Energy Seabrook, LLC (NextEra, or the licensee) requested changes to the Technical Specifications (TSs) for Seabrook Station, Unit No. 1 (Seabrook).
Specifically, the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation,
dated February 21, 2013 (ADAMS Accession No. ML13053A075).
By letter dated February 6, 2015 (ADAMS Accession No. ML14345A288), the NRC issued Amendment No. 144 to Facility Operating License No. NPF-86 for Seabrook, which modified Seabrook's TSs by revising the surveillance requirements (SRs) related to gas accumulation for the emergency core cooling system (ECCS). Amendment No. 144 also added new SRs related to gas accumulation for the residual heat removal (RHR) and containment spray (CS) systems. In its letter dated June 24, 2014, the licensee requested a note be added to TS page 3/4 4-5, Reactor Coolant System (RCS), Reactor Coolant Loops and Coolant Circulation, Hot Shutdown, Surveillance Requirements (SRs). In its subsequent letter dated December 11, 2014, however, the licensee inadvertently left off the note on TS page 3/4 4-5. Therefore, Amendment No. 144 does not have the note on TS page 3/4 4-5.
2.0 INTRODUCTION
By letter dated July 13, 2015 (ADAMS Accession No. ML15198A027), the licensee requested that the note in NRC-approved TSTF-523 be added to TS page 3/4 4-5. Enclosure 2
3.0 REGULATORY EVALUATION
3.1 Gas Accumulation Background Gas accumulation in reactor systems can result in water hammer, pump cavitation, and pumping of non-condensible gas into the reactor vessel. These effects may result in the subject system being unable to perform its specified safety function.
The NRC issued Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," in January 2008 to address the issue of gas accumulation in ECCS, AHR, and CS systems (ADAMS Accession No. ML072910759).
The industry and NRC staff agreed that a change to the STS and plant-specific TS would be necessary to address some of the issues discussed in GL 2008-01. TSTF-523 contains changes to the TS SRs and TS Bases to address some of the concerns in GL 2008-01. The licensee proposed amending the Seabrook TSs using a plant-specific adoption of the TSTF-523 changes. 3.2 Technical Specification Changes Changes were proposed for Seabrook TS SR 4.4.1.3, "Reactor Coolant Loops and Coolant Circulation
-Hot Shutdown," to add the note in TSTF-523, which states, "Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4." 3.3 Regulatory Review The regulations in Appendix A to Title 1 O of the Code of Federal Regulations (1 O CFR) Part 50 or similar plant-specific principal design criteria provide design requirements.
Appendix B to 10 CFR Part 50, the TSs, and the licensee quality assurance programs, provide operating requirements.
The regulatory requirements of 1 O CFR Part 50, Appendix A that are applicable to gas management in the subject systems include: General Design Criteria (GDC) 1, 34, 35, 36, 37, 38, 39, and 40. GDC 1 requires that the subject systems be designed, fabricated, erected, and tested to quality standards.
GDC 34 requires an AHR system designed to maintain specified acceptable fuel design limits and to meet design conditions that are not exceeded if a single failure occurs and specified electrical power systems fail. GDC 35, 36, and 37 require an ECCS design that meets performance, inspection, and testing requirements.
Additionally, the regulations in 1 O CFR 50.46 provide specified ECCS performance criteria.
GDC 38, 39, and 40 require a containment heat removal system design that meets performance, inspection, and testing requirements.
Appendix B to 1 O CFR Part 50 provides quality assurance criteria that apply to gas management in the subject systems. Criteria Ill and V require measures to ensure that applicable regulatory requirements and the design basis, as defined in 1 O CFR 50.2, "Definitions," and as specified in the license application, are correctly translated into controlled specifications, drawings, procedures, and instructions.
Criterion XI requires a test program to ensure that the subject systems will perform satisfactorily in service and requires that test results shall be documented and evaluated to ensure that test requirements have been satisfied.
Criterion XVI requires measures to ensure that conditions adverse to quality such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances, are promptly identified and corrected, and that significant conditions adverse to quality are documented and reported to management.
Criterion XVII requires maintenance of records of activities affecting quality. The NRC's regulatory requirements related to the content of the TSs are contained in 1 O CFR 50.36(c).
Section 50.36 require that the TSs include items in the following categories:
(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCO); (3) SRs; (4) design features; and (5) administrative controls.
SRs are requirements relating to test, calibration, or inspection, to assure that the necessary quality of systems and components is maintained, facility operation will be within safety limits, and the LCOs will be met. Typically, TS Section 5 requires that licensees establish, implement, and maintain written procedures covering the applicable procedures recommended in Appendix A to Regulatory Guide (RG) 1.33, "Quality Assurance Program Requirements (Operation)." Appendix A to RG 1.33 identifies instructions for filling and venting the ECCS and RHR system, as well as for draining and refilling heat exchangers.
Standard TSs and most licensee TSs include SRs to verify that at least some of the subject systems' piping is filled with water. The NRC guidance for the format and content of licensee TSs can be found in NUREG-1431, "Standard Technical Specifications Westinghouse Plants." 4.0 TECHNICAL EVALUATION The NRC staff evaluated the licensee's proposed change against the applicable regulatory guidance in the STS, as modified by TSTF-523.
The proposed change adopted the TS format and content, to the extent practicable, contained in the changes made to NUREG-1431, "Standard Technical Specifications Westinghouse Plants," by TSTF-523.
The Seabrook TS utilizes different numbering, format, and titles than NUREG-1431 on which TSTF-523 was based. The NRC staff found that the format, numbering, and titling of the proposed changes are consistent with guidance in the STS, as modified by TSTF-523, and the differences do not affect the applicability of TSTF-523 to Seabrook.
The NRC staff compared the proposed changes to the existing SRs, as well as the regulatory requirements of 1 O CFR 50.36. The licensee proposed the following TS changes: (1) Add a Note (*) for SR 4.4.1.3.4, which states, "*Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4." SRs are normally performed prior to entering the Applicability.
During a rapid shutdown, there may be insufficient time to verify all susceptible locations in the RHR System before entering the Applicability.
It is safer for the licensee to attend to the rapid shutdown than to perform SR 4.4.1.3.4 immediately upon entering the Applicability.
Therefore, the note provides the licensee time to perform SR 4.4.1.3.4.
The language for the note that states the SR does not have to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering Mode 4 for pressurized water reactors is acceptable, because the note provides a limited time to perform the SR 4.4.1.3.4 after entering the Applicability of the LCO. This is because there may be insufficient time to verify all susceptible locations prior to entering Mode 4 in a rapid shutdown.
However, under the STS usage rules (STS Section 1.4), the requirement to manage gas accumulation is not affected.
Licensees must have confidence that the SR can be met or the LCO must be declared as not met. The NRC staff finds that the proposed note meets the regulatory requirements of 1 O CFR 50.36 because it provides assurance that the necessary quality of systems and components will be maintained and that the LCOs will be met. Therefore, the NRC staff finds the proposed change acceptable.
The regulation at 1 O CFR 50.36(a)(1) states, in part, that, "A summary statement of the bases or reasons for such specifications
... shall also be included in the application, but shall not become part of the technical specifications." The licensee may make changes to the TS Bases without prior NRC staff review and approval in accordance with the TS Bases Control Program described in TS 6.7.6.j. Accordingly, for information purposes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The NRC staff determined that TS Bases changes are consistent with the proposed TS changes and provide the purpose for each requirement in the specification consistent with the Commission's Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors dated July 22, 1993 (58 FR 39132).
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Hampshire and Massachusetts State officials were notified on September 2, 2015, of the proposed issuance of the amendment.
The State officials provided no comments.
6.0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 1 O CFR Part 20 and SRs. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The NRC has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding published on August 4, 2015 (80 FR 46350). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 1 O CFR 51.22(c)(9).
Pursuant to 1 O CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:
J. Lamb Date: October 6, 2015 D. Curtland A copy of the related safety evaluation is also enclosed.
Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-443
Enclosures:
Sincerely, IRA/ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Amendment No. 150 to NPF-86 2. Safety Evaluation cc w/enclosures:
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