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MONTHYEARML0609304392006-04-19019 April 2006
Virgil C.Summer - Request for Additional Information Regarding Loss of Coolant Accident Analysis
Project stage: RAI
ML0627002792006-09-0707 September 2006
V.C. Summer, Tech Spec Pages for Amendment 176 Regarding Best Estimate Loss-of-Coolant Accident Analyses Methodology
Project stage: Other
ML0622705522006-09-0707 September 2006
V.C. Summer, License Amendment 176 Regarding Best Estimate Loss-of-Coolant Accident Analyses Methodology
Project stage: Approval
2006-04-19
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Category:Technical Specifications
MONTHYEARML23317A2242023-11-0909 November 2023
(Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension
ML23072A0892023-05-0101 May 2023
(Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements
ML23012A0152023-02-21021 February 2023
Issuance of Amendment No. 224 to Change Nozzle Blockage Testing Requirement for Reactor Building Spray System
ML22269A4342022-09-26026 September 2022
VC Summer Correction Letter to Amendment 166 - Enclosure -
ML22269A4372022-09-26026 September 2022
Correction to Issuance of Amendment Related to Surveillance Requirement 4.0.5, Associated Basis, and Bases 3/4.4.2, 3/4.4.6, and 3/4.4.10
ML22115A1042022-04-22022 April 2022
License Amendment Request- Technical Specifications Nozzle Blockage Testing Requirement Change for Reactors Building Spray System
ML21319A2622021-12-28028 December 2021
Issuance of Amendment No. 220 to Relocate Unit Staff Qualifications from Technical Specification to Quality Assurance Program Description
ML21280A3282021-10-0707 October 2021
Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
ML20156A3032020-06-0404 June 2020
License Amendment Request Update of Analytical Method to the Core Operating Limits Report with the Full Spectrum Loss of Coolant Accident Approach
ML18253A1152018-10-0505 October 2018
Issuance of Amendment No. 212 Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit
ML18092B5102018-03-29029 March 2018
(VCSNS) - Administrative License Amendment Request to Correct the Typographical Error in TS Table 6.2-1 Minimum Shift Crew
RC-17-0175, Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error2018-01-31031 January 2018
Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error
ML17206A4122017-10-0404 October 2017
Issuance of Amendment TSTF-411, Revision 1, Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P-A).
ML16104A2952016-05-0606 May 2016
Issuance of Amendment to Adopt TSTF-523, Revision 2
ML16063A0902016-03-0909 March 2016
Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2
ML15208A0292015-10-15015 October 2015
Issuance of Amendment
ML15170A0872015-08-18018 August 2015
Issuance of Amendment to Revise the Radiation Emergency Plan
ML15063A3552015-04-13013 April 2015
Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6
ML14287A2892015-02-11011 February 2015
Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c)
ML14122A3092014-05-29029 May 2014
Issuance of Amendment 198 Regarding the Cyber Security Plan Implementation Schedule Milestone 8
ML14030A3742014-03-11011 March 2014
Issuance of Amendment for Technical Specification Change Related to Control Room Emergency Filtration System
ML13354B6432014-02-0606 February 2014
Issuance of Amendment for the Technical Specification Change Related to Snubber Surveillance Requirements
ML13326A2042014-02-0505 February 2014
Issuance of Amendment Extending Integrated Leak Rate Test Interval
RC-13-0034, License Amendment Request - LAR (11-02281) Technical Specification Change to Add an Exception to Specification 3.0.4 in Technical Specification 3/4.7.6 Control Room Emergency Filtration System (CREFS)2013-04-0303 April 2013
License Amendment Request - LAR (11-02281) Technical Specification Change to Add an Exception to Specification 3.0.4 in Technical Specification 3/4.7.6 Control Room Emergency Filtration System (CREFS)
RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement..2013-04-0202 April 2013
License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement..
ML12146A0172012-05-30030 May 2012
Issuance of Amendment on Beacon Core Monitoring and Operations Support System
RC-11-0063, License Amendment Request - LAR 11-01774, Application to Eliminate License Condition 2.G.1 Requiring Reporting of Violations of Section 2.C of the Operating License Using the Consolidated Line Item Improvement Process (CLIIP)2011-08-23023 August 2011
License Amendment Request - LAR 11-01774, Application to Eliminate License Condition 2.G.1 Requiring Reporting of Violations of Section 2.C of the Operating License Using the Consolidated Line Item Improvement Process (CLIIP)
RC-11-0104, License Amendment Request - LAR (10-03107) Proposed Change in Administrative Controls Section to Allow the Use of Westinghouse WCAP-12472-P-A, Addendum 1-A2011-08-11011 August 2011
License Amendment Request - LAR (10-03107) Proposed Change in Administrative Controls Section to Allow the Use of Westinghouse WCAP-12472-P-A, Addendum 1-A
RC-11-0062, V. C. Summer, License Amendment Request - LAR 04-02961, License Amendment Request for Slave Relay Surveillance Testing2011-04-18018 April 2011
V. C. Summer, License Amendment Request - LAR 04-02961, License Amendment Request for Slave Relay Surveillance Testing
RC-11-0006, License Amendment Request - LAR-10-03108, Proposed Change to Relocate Administrative Control Requirements Related to Quality Assurance and Submittal of Quality Assurance Program Description (QAPD)2011-03-18018 March 2011
License Amendment Request - LAR-10-03108, Proposed Change to Relocate Administrative Control Requirements Related to Quality Assurance and Submittal of Quality Assurance Program Description (QAPD)
RC-10-0092, License Amendment Request (LAR 10-02033), Changes to Emergency Diesel Generator Surveillance Test Requirements2010-11-11011 November 2010
License Amendment Request (LAR 10-02033), Changes to Emergency Diesel Generator Surveillance Test Requirements
ML1001103772010-03-22022 March 2010
Issuance of Amendment Regarding: Use of Optimized Zirlo Fuel Rod Cladding
RC-08-0007, License Amendment Request - LAR 03-01931-20, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-01-17017 January 2008
License Amendment Request - LAR 03-01931-20, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
ML0713705092007-05-15015 May 2007
Technical Specifications, Issuance of Amendment Regarding Steam Generator Tube Integrity
RC-06-0199, License Amendment Request - LAR 05-3262, Changes to Emergency Diesel Generator Specification2006-11-21021 November 2006
License Amendment Request - LAR 05-3262, Changes to Emergency Diesel Generator Specification
ML0630700682006-11-0202 November 2006
Technical Specifications Pages Re Alternate AC Power Supply
ML0630000262006-10-24024 October 2006
Technical Specifications, Implementing Approved Changes in Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times.
ML0627002792006-09-0707 September 2006
V.C. Summer, Tech Spec Pages for Amendment 176 Regarding Best Estimate Loss-of-Coolant Accident Analyses Methodology
RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity2006-05-24024 May 2006
License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
ML0614204982006-05-0404 May 2006
Technical Specifications, Administrative Controls
ML0535300472005-12-13013 December 2005
Enclosure, Amd MC7375, Reactor Coolant System Pressure-Temperature Limits
ML0522402792005-08-10010 August 2005
Operating License, License Amendment Request- LAR 04-0440, Emergency Feedwater System Pump Testing Criteria
RC-05-0090, License Amendment Request Re Reactor Coolant System - Heatup/Cooldown Curves2005-06-22022 June 2005
License Amendment Request Re Reactor Coolant System - Heatup/Cooldown Curves
ML0513902262005-05-0909 May 2005
Enclosure, Amd MC3308, Extending the Inspection Interval for Reactor Coolant Pump Flywheels
RC-05-0041, License Amendment Request (LAR 03-1931-24) Adoption of TS Task Force (TSTF) Traveler-287, Revision 5, Ventilation System Envelope Allowed Outage Time2005-03-0909 March 2005
License Amendment Request (LAR 03-1931-24) Adoption of TS Task Force (TSTF) Traveler-287, Revision 5, Ventilation System Envelope Allowed Outage Time
ML0410404932004-04-0505 April 2004
Technical Specifications, Revision to Allowed Outage Time for Engineered Safety Features Actuation System Instrumentation
ML0334503692003-12-15015 December 2003
Tech Spec Pages for Amendment 165 One-Time Extension of Steam Generator Inspection Interval
ML0330400312003-10-29029 October 2003
Technical Specification Pages for Virgil C. Summer Nuclear Station, Unit 1, Amendment No. 165
ML0327513912003-09-26026 September 2003
Technical Specification for Virgil C. Summer Nuclear Station, Unit 1 - Issuance of Amendment 164, Revising the Action Statement and Surveillance Requirement for the Emergency Diesel Generators
RC-03-0176, Revision to License Amendment Request - LAR 02-2767 Steam Generators - One Time Exclusion on Inspection Frequency2003-08-20020 August 2003
Revision to License Amendment Request - LAR 02-2767 Steam Generators - One Time Exclusion on Inspection Frequency
2023-05-01
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Text
(3) SCE&G, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as amended through Amendment No. 33; (4) SCE&G, pursuant to the Act and 10 CFR Parts 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 neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) SCE&G, pursuant to the Act and 10 CFR Parts 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 of components; and (6) SCE&G, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as my be produced by the operation of the facility.
C. This renewed 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; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level SCE&G is authorized to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to this renewed license.
The preoccupation tests, startup tests and other items identified in Attachment 1 to this renewed license shall be completed as specified.
Attachment 1 is hereby incorporated into this renewed license.
(2) Technical Specifications and Environmental Protection Plan The technical Specifications contained in Appendix A, as revised through Amendment No.176, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed Facility Operating License No. NPF-12
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
(Methodology for Specifications 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Rod Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor.)
- b. WCAP-1 0216-P-A, Rev. 1A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fa SURVEILLANCE TECHNICAL SPECIFICATION," February 1994 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (Fo Methodology for W(z) surveillance requirements).)
- c. WCAP-12945-P-A, Volume 1 (Revision 2) through Volumes 2 through 5 (Revision 1) "Code Qualification Document for Best Estimate LOCA Analysis,"
March 1998 (Westinghouse Proprietary).
Liparulo, N. (W) to NRC Document Control Desk, NSD-NRC-96-4746, "Re-Analysis Work Plans Using Final Best Estimate Methodology" dated 6/13/1996.
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
- d. WCAP-12472-P-A, "BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM," August 1994, (W Proprietary).
(Methodology for Specifications 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 -
RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor, and 3.2.4 -
Quadrant Power Tilt Ratio.)
- e. WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement,"
March 1997, (Westinghouse Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SUMMER - UNIT 1 6-16a Amendment No. 88, 121, 433,-4 42, 4-&-., 176
