|
---|
Category:Letter
MONTHYEARIR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000395/20240112024-06-26026 June 2024 – Comprehensive Engineering Team Inspection Report 05000395/2024011 ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2262024-03-26026 March 2024 License Amendment Request - Inverter Allowed Outage Time Extension Response to Request for Additional Information ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. ML24067A0232024-03-0707 March 2024 (Vcsns), Unit 1 - Readiness for 95001 Supplemental Inspection; EA-23-093 IR 05000395/20230062024-02-28028 February 2024 Annual Assessment Letter for Virgil C. Summer Nuclear Station - Report 05000395/2023006 IR 05000395/20244032024-02-27027 February 2024 Security Baseline Inspection Report 05000395/2024403 ML24057A1132024-02-22022 February 2024 Special Report 2024-001 Waste Gas System Inoperability ML24051A0112024-02-20020 February 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Proposed Project Location or May Be Affected by Proposed Project for V.C. Summer SLR ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24032A3062024-02-15015 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24040A1802024-02-12012 February 2024 Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000395/20244012024-02-0808 February 2024 Security Baseline Inspection Report 05000395/2024401 ML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report 2024-08-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML23137A1782023-05-22022 May 2023 Correction to Issuance of Amendment to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program 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 ML22341A1972022-12-15015 December 2022 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval ML22244A1722022-09-22022 September 2022 Issuance of Amendment No. 223 to Relocate Main Steam Isolation Valve Isolation Times to the Updated Final Safety Analysis Report ML22242A1632022-08-31031 August 2022 Correction to Issuance of Amendment to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21319A2622021-12-28028 December 2021 Issuance of Amendment No. 220 to Relocate Unit Staff Qualifications from Technical Specification to Quality Assurance Program Description ML21112A1082021-06-30030 June 2021 Issuance of Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML19276D3772019-12-11011 December 2019 Issuance of Amendment Revise Company Name to Dominion Energy South Carolina, Inc. ML19080A1032019-04-30030 April 2019 Issuance of Amendment No. 215 Technical Specification 3.8.2, D.C. Sources - Operating ML19074A2222019-04-10010 April 2019 Issuance of Amendment No. 214 Removes the Expired One-Time Extension to Surveillance Requirement 4.3.3.6 and Removes the Index from Technical Specifications ML19023A4202019-03-0707 March 2019 Issuance of Amendment Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 ML19056A4062018-11-30030 November 2018 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Thermal Mixing Zone Evaluation 2018 Water Quality Monitoring Report 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 ML18260A0272018-09-25025 September 2018 Issuance of Exigent Amendment One Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation ML18141A6682018-06-28028 June 2018 Issuance of Amendment No. 210, Revise Technical Specification 6.8.4.g for Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML18157A2122018-06-0707 June 2018 Correction to Amendment No. 199 to Correct an Administrative Error ML18108A1632018-04-20020 April 2018 Correction to Amendments Nos. 79 and 202, to Correct Typographical Errors ML18033A8442018-02-27027 February 2018 Correction to Amendment No. 170 to Correct a Typographical 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). ML17011A0502017-03-0909 March 2017 Issuance of Amendment to Revise Completion Date of Implementation Milestone 8 of the Cyber Security Plan ML16348A2002017-01-18018 January 2017 Issuance of Amendment to Revise Technical Specification 3.5.4 Limiting Condition for Operation Refueling Water Storage Tank ML16264A4112016-10-26026 October 2016 Issuance of Amendment to Revise Technical Specification 3/4.7.1.2, Emergency Feedwater System ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident ML16104A2952016-05-0606 May 2016 Issuance of Amendment to Adopt TSTF-523, Revision 2 RC-16-0043, License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System.2016-04-0707 April 2016 License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System. ML16063A0902016-03-0909 March 2016 Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2 RC-16-0035, (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B2016-03-0101 March 2016 (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B 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 ML14010A1822014-02-28028 February 2014 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-510 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 ML12292A0562012-12-21021 December 2012 Issuance of Amendment Regarding Deviation of Scope of the Cyber Security Plan Implementation and Facility Operating Condition 2.E ML12270A3012012-10-12012 October 2012 Issuance of Amendment ML12184A1352012-07-0909 July 2012 Issuance of Amendment ML12146A0172012-05-30030 May 2012 Issuance of Amendment on Beacon Core Monitoring and Operations Support System ML12121A0342012-05-0101 May 2012 Issuance of Amendment Extending Integrated Leak Rate Test ML11346A0062012-03-20020 March 2012 Issuance of Amendment Regarding Quality Assurance Program ML12047A1922012-03-0606 March 2012 Issuance of Amendment No. 187 Regarding Surveillance Frequency of Solids State Protection Westinghouse Type AR Relays 18 Months ML11326A2502012-02-22022 February 2012 Issuance of Amendment Regarding Reactor Coolant System Leakage Detection Systems ML11201A3122011-08-24024 August 2011 Issuance of Amendment 184 Regarding Cyber Security Plan 2024-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations 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 ML23062A7292023-03-31031 March 2023 Deferral of Pressurizer and Steam Generator Weld Examinations ML23012A0152023-02-21021 February 2023 Issuance of Amendment No. 224 to Change Nozzle Blockage Testing Requirement for Reactor Building Spray System ML22341A1972022-12-15015 December 2022 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval ML22244A1722022-09-22022 September 2022 Issuance of Amendment No. 223 to Relocate Main Steam Isolation Valve Isolation Times to the Updated Final Safety Analysis Report ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21319A2622021-12-28028 December 2021 Issuance of Amendment No. 220 to Relocate Unit Staff Qualifications from Technical Specification to Quality Assurance Program Description ML21188A3322021-08-10010 August 2021 Correction to Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML21173A1632021-08-0606 August 2021 Authorization and Safety Evaluation for Alternative Request No. RR-4-25 ML21112A1082021-06-30030 June 2021 Issuance of Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML20248H3782020-12-0202 December 2020 Alternative Requests RR 4-19 and RR-4-21 Related to the In-Service Testing Program (Epids L-2020-LLR-0077 and L-2020-LLR-0078) ML19361A0702020-01-24024 January 2020 Relief Request Regarding Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography (RR-4-20) ML19276D3772019-12-11011 December 2019 Issuance of Amendment Revise Company Name to Dominion Energy South Carolina, Inc. ML19242E0272019-09-0606 September 2019 Relief Request (RR-4-22) for Use of ASME Code Case N-513-4 ML19140A4732019-06-0404 June 2019 Relief Request (RR-4-23) to Utilize Code Case N-513-4 ML19080A1032019-04-30030 April 2019 Issuance of Amendment No. 215 Technical Specification 3.8.2, D.C. Sources - Operating ML19074A2222019-04-10010 April 2019 Issuance of Amendment No. 214 Removes the Expired One-Time Extension to Surveillance Requirement 4.3.3.6 and Removes the Index from Technical Specifications ML19023A4202019-03-0707 March 2019 Issuance of Amendment Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 ML19035A2992019-02-26026 February 2019 Relief Request (RR-4-18) for Use of NRC Generic Letter 90-05 ML19030B8272019-02-13013 February 2019 Relief Request (RR-4-17) for Use of ASME Code Case N-513-3 ML19003A1882019-01-18018 January 2019 Relief Request (RR-4-16) for Use of ASME Code Case N-513-4 and NRC Generic Letter 90-05 ML18345A0602018-12-17017 December 2018 Relief Request Regarding Use of a Performance Based Testing Frequency for Pressure Isolation Valves (RR-4-14) ML18296A1112018-11-0808 November 2018 Relief Request (RR-4-15) for Use of ASME Code Case N-513-4 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 ML18260A0272018-09-25025 September 2018 Issuance of Exigent Amendment One Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation ML18255A2562018-09-24024 September 2018 Correction to the Safety Evaluation and the Orders Approving Indirect Transfer of Licenses ML18129A0762018-08-30030 August 2018 Transmittal Letter and Safety Evaluation Related to the Orders Approving Indirect Transfer of Licenses for Units 1, 2, 3 and the Independent Spent Fuel Storage Installation ML18186A5882018-07-19019 July 2018 Relief Request (RR-4-13) for Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds. ML18141A6682018-06-28028 June 2018 Issuance of Amendment No. 210, Revise Technical Specification 6.8.4.g for Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change 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). ML17089A6172017-08-0101 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17011A0502017-03-0909 March 2017 Issuance of Amendment to Revise Completion Date of Implementation Milestone 8 of the Cyber Security Plan ML17031A0152017-02-0909 February 2017 Relief from the Requirements of the ASME Code Regarding Service Water System Piping ML16348A2002017-01-18018 January 2017 Issuance of Amendment to Revise Technical Specification 3.5.4 Limiting Condition for Operation Refueling Water Storage Tank ML16264A4112016-10-26026 October 2016 Issuance of Amendment to Revise Technical Specification 3/4.7.1.2, Emergency Feedwater System ML16161A0452016-07-0101 July 2016 Relief from the Requirements of the ASME Code ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident ML16104A2952016-05-0606 May 2016 Issuance of Amendment to Adopt TSTF-523, Revision 2 ML16124A8972016-05-0606 May 2016 Relief from the Requirements of the ASME Code ML16063A0902016-03-0909 March 2016 Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2 ML15208A0292015-10-15015 October 2015 Issuance of Amendment ML15222A5422015-09-0101 September 2015 Alternative Request Regarding Root Mean Square Depth Sizing Requirements ML15170A0872015-08-18018 August 2015 Issuance of Amendment to Revise the Radiation Emergency Plan 2024-08-05
[Table view] Category:Technical Specifications
MONTHYEARML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML23317A2242023-11-0909 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 2024-08-05
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 M:'lrch 22, 2010 Mr. Jeffrey B. Archie Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, SC 29065 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1, ISSUANCE OF AMENDMENT REGARDING:
USE OF OPTIMIZED ZIRLO FUEL ROD CLADDING (TAC NO: ME1489)
Dear Mr. Archie:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 182 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No.1, in response to your letter dated June 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091620072).
The amendment changes Technical Specification (TS) 5.3.1, "Fuel Assemblies," to add Optimized ZIRLOŽ as an acceptable fuel rod cladding material and adds a Westinghouse topical report to the analytical methods identified in TS 6.9.1.11.
The NRC staff authorized the exemption by letter dated March 9, 2010, and published it in the Federal Register on March 15,2010 (75 FR 12312). A copy of the related Safety Evaluation is enclosed.
Notice of Issuance will be included in the Commission's next Biweekly Federal Register notice. Sincerely, ..
VRobert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosures:
- 1. Amendment No. 182 to NPF-12 2. Safety Evaluation cc w/enclosures:
Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 182 Renewed License No. NPF-12 The U.S. Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by South Carolina Electric & Gas Company (the licensee), dated June 9, 2009, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
- 2. Accordingly, the license is amended by changes to the Appendix A Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-12 is hereby amended to read as follows: Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 182, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. This amendment is effective as of its date of issuance and shall be implemented within sixty (60) days. EOR THE NUCLEAR REGULATORY COMMISSION oria Kulesa, Chief 0" Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Attachments:
Changes to the Technical Specifications Date of Issuance:
March 22, 2010 ATTACHMENT TO LICENSE AMENDMENT NO. TO RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Pages Insert Pages License License 3 3 TS TS 5-6 5-6 6-16 6-16 6-16a 6-16a 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 7D 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; SCE&G, 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 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. 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: Maximum Power Level SCE&13 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. Technical Specifications and Environmental Protection Plan The technical SpAr.ifications contained in AppendiX A, as revised through Amendment No.;: 1B2and the Environmental Protection Planoontained 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 Amendmen t No. 1 82 DESIGN
5.3 REACTOR
FUEL 5.3.1 The core shall contain 157 fuel assemblies. Each fuel assembly shall consist of . 264 Zircaloy-4, ZIRLOŽ, or Optimized ZIRLOŽ clad fuel rods with an initial composition of uranium dioxide with a maximum nominal enrichment of 4.95 weight percent U*235 as fuel material.
Limited substitutions of Zircaloy-4, ZIRLOŽ, or Optimized ZIRLOŽ and/or stainless steel filler rods for fuel rods, if justified by a cycle specific reload analysis using an NRC-approved methodology, may be used. Fuel assembly configurations shall be limited to those designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or cycle-specific reload analyses to comply with all fuel safety design bases. Reload fuel shall contain sufficient integral fuel burnable absorbers such that the requirements of Specifications 5.6.1.1 a.2 and 5.6.1.2.b are met. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core locations.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 fUll length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing. 5.4 REACTOR COOLANT DESIGN PRESSURE AND 5.4.1 The reactor coolant system is designed and shall be maintained: In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, For a pressure of 2485 psig, and c. For a temperature of 650°F, except for the pressurizer which is 5.4.2 The total water and steam volume of the reactor coolant system is 9914 +/- 100 cubic feet at an indicated T avg of 587.4°F. 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1. SUMMER .* UNIT 5-6 Amendment No. 182 ADMINISTRATIVE 6.9.1.9 Not used. 6.9.1.10 Not used. CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following: Moderator Temperature Coefficient BOL and EOL Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, Control Rod Insertion Limits for Specification 3/4.1.3.6, Axial Flux Difference Limits, target band, and APLN°for Specification 3/4.2.1, Heat Flux Hot Channel Factor, F;TP, K(z), W(z), APL NO, W(Z)BL, and Fa(z) manufacturing/measurement uncertainties for Specification 3/4.2.2, Nuclear Enthalpy Rise Hot Channel Factor, FfJP, Power Factor Multiplier, PF<1H' and measurement uncertainties limits for Specification 3/4.2.3. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: WCAP-9272-P-A, 'WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary). (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 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor.) WCAP-10216-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 (Fa Methodology for W(z) surveillance requirements).)
SUMMER -UNIT 6-16 Amendment No.. 182 ADMINISTRATIVE CORE OPERATING LIMITS REPORT (Continued) 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, Analysis Work Plans Using Final Best Estimate Methodology" dated 6/13/1996. (Methodology for Specification 3.2.2 -Heat Flux Hot Channel Factor.) 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, RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor, and Quadrant Power Tilt Ratio.) 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.) WCAP-12610-P-A, VANTAGE
+ Fuel Assembly Reference Core Report," April 1995 r1J..
WCAP-12610-P-A
& CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO T ," July 2006 (W Proprietary). (Methodology for Specification 3.2.2 -Heat Flux Hot Channel Factor.) The core operating limits shall be determined so that all applicable limits (e.g., fuel 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 6-16a Amendment No. J UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 182 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated June 9, 2009 (Reference 1), South Carolina Electric and Gas Company (SCE&G), the licensee, submitted a license amendment request (LAR) for Technical Specification (TS) revisions for the Virgil C. Summer Nuclear Station, Unit 1 (VCSNS). The proposed change to TS 5.3.1, "Fuel Assemblies," will add Optimized ZIRLOŽ as an acceptable fuel rod cladding material.
SCE&G also requested an exemption from the requirements of Title 10 of the Code of Federal RegUlations (10 CFR), Section 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," and Appendix K to 10 CFR 50, "ECCS Evaluation Models," to allow the use of fuel rods clad with Optimized ZIRLO alloy for future reload applications.
The U.S. Nuclear Regulatory Commission (NRC) staff authorized the exemption by letter dated March 9, 2010, and published it in the Federal Register on March 15,2010 (75 FR 12312). The Optimized ZIRLO cladding, manufactured by Westinghouse Electric Company, is a newer version of the ZIRLO material and was approved as described in Addendum 1A of topical report WCAP-12610-P-A and CENPD-404-P-A, entitled "Optimized ZIRLO," for Westinghouse and Combustion Engineering (CE) fuel designs (Reference 3). The fuel rod burnup limits were approved to a peak rod average of 62,000 mega-watt days per metric ton uranium (MWD/MTU) for Westinghouse fuel and 60,000 MWD/MTU for CE fuel. However, the staff requires that licensees using the Optimized ZIRLO comply with the conditions and limitations listed in the safety evaluation (SE) dated June 10, 2005 (Reference 2).
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.90, "Application for Amendment of License or Construction Permit," allow a licensee to amend or change the original license applications.
10 CFR 50.92, "Issuance of Amendment," specifies that the staff will be guided by the considerations which govern the
-2 issuance of initial licenses to the extent applicable and appropriate in determining whether an amendment will be issued to the applicant.
The licensee requests a license amendment to add Optimized ZIRLOŽ as an acceptable fuel rod cladding material in the TS. The NRC staff review of the requested amendment verifies that Optimized ZIRLOŽ fuel rod cladding material is applicable to the licensee and its implementation is done in accordance with established conditions and limitations.
3.0 TECHNICAL
EVALUATION
3.1 Conditions
and Limitations On June 1 0, 2005 (Reference
- 2) the NRC staff issued a safety evaluation (the SE) for Addendum 1 to topical report WCAP-12610-P-A and CENPD-404-P-A for Optimized ZIRLOŽ. In the SE, the staff concluded that: Based upon demonstrated material performance in addendum 1 and in response to RAls ... and the irradiated database, the NRC staff has approved Optimized ZIRLOŽ for full batch implementation.
And in the SE conclusion the staff stated: The !\IRC staff reviewed the effects of Optimized ZIRLOŽ using the appropriate fuel design requirements of [Standard Review Plan] SRP 4.2 and 10 CFR Part 50, Appendix A, General Design Criteria and found that the TR provided reasonable assurance that under both normal and accident conditions, Westinghouse and CE fuel assembly designs implementing Optimized ZIRLOŽ fuel cladding would be able to safely operate and comply with NRC regulations.
The NRC staff SE also stated that licensees referencing Addendum 1 to the topical report to implement Optimized ZIRLOŽ must ensure compliance with ten issues as specified in the SE. SCE&G has documented its compliance with these ten conditions and limitations in its LAR (Reference
- 1) and has committed to ensuring compliance with them for future fuel reloads. With the exception of SE Conditions 6 and 7, the NRC staff has reviewed SCE&G's response to each of the ten SE conditions and limitations and finds each to be acceptable.
SE Conditions 6 and 7 relate to validating in-reactor performance and fuel performance models based on Lead Test Assembly (L TA) data ahead of batch application.
SCE&G noted that Westinghouse has provided four references related to test data and models (references 4, 5, 6 and 7) and has provided the following statement in response to Condition 6: LTA measured data and favorable results from visual examinations of once and twice-burned L TAs confirm, for at least two cycles of operation, that the current fuel performance models are applicable for Optimized ZIRLOTM fuel rods. Westinghouse will continue to provide additional data from the Optimized ZIRLOTM L TA programs to the NRC after new data for higher burnup/fluence become available.
SCE&G will confirm that as higher burnups/fJuences are achieved for Optimized ZIRLOTM clad fuel rods that the requirements of this condition will be met as it applies to VCSNS.
-3 In response to Condition 7, SCE&G stated that the data from two cycles of operation had been evaluated and that the updated creep model had been used to predict the growth and creep in fuel rod performance.
The licensee provided the favorable results to the staff. SCE&G will continue to confirm the model adequacy as higher burnups and fluences are achieved for Optimized ZIRLOŽ fuel rods. Based upon the information provided, the NRC staff finds that SCE&G's response, as discussed above, meets the requirements of SE Conditions 6 and 7 and is acceptable for the VCSNS. Therefore, the staff concludes that the Optimized ZIRLO fuel design is acceptable for use in the VCSNS to a peak rod average burnup limit of 62 GWD/MTU. 3.2 TS Revisions 3.2.1 TS Section 5.3.1 Fuel Assemblies The licensee proposes to add Optimized ZIRLOŽ in TS 5.3.1 as an acceptable fuel rod cladding material.
The new sentences are stated as follows: "... Each fuel assembly shall consist of 264 Zircaloy-4, ZIRLOŽ, or Optimized ZIRLOŽ clad fuel rods ... Limited substitutions of Zircaloy-4, ZIRLOŽ, or Optimized ZIRLOŽ and lor ..." In Reference 2, the NRC staff approved Optimized ZIRLOŽ fuel cladding based on (1) similarities with standard ZIRLOŽ, (2) demonstrated material performance, and (3) a commitment to provide irradiated data and validate fuel performance models ahead of burnups achieved in batch application.
Based on the NRC staff's prior approval of Optimized ZIRLOŽ fuel rod cladding, and the licensee's current and future compliance with the SE conditions and limitations, the staff concludes that this revision is acceptable for the VCSNS. 3.2.2 TS Section 6.9.1.11 Core Operating Limits Report (COLR) SCE&G proposes to add the approved Westinghouse topical reports, WCAP-12610-P-A, "VANTAGE+
Fuel Assembly Reference Core Report," and Addendum 1-A to WCAP-12610-P-A and CENPD-404-P-A, "Optimized ZIRLO," to the list of references to be used in generating the Core Operating Limits Report (COLR). Based on the NRC staff's approval of those reports, the staff concludes that this revision is acceptable for the VCSNS. Based on the NRC staff's evaluation of SCE&G's license amendment request for TS revisions the staff concludes that the Optimized ZIRLOŽ fuel design is acceptable to a peak rod average burnup limit of 62 GWD/MTU and that the TS revisions are acceptable for the VCSNS.
4.0 STATE
In accordance with the Commission's regulations, the State of South Carolina State official was notified of the proposed issuance of the amendment.
The State official had no comments. ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 Commission previously issued a proposed finding in the Federal Register (74 FR 64746) that the amendment involves no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. 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) 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. REFERENCES Letter from SCE&G to NRC, "License Amendment Request For Use of Optimized ZirloŽ Fuel Rod Cladding," June 9, 2009, Agencywide Documents Access and Management System (ADAMS) Accession No. ML091620072. Letter from H. N. Berkow, NRC, to J. A. Gresham, Westinghouse Electric Company, "Final Safety Evaluation for Addendum 1 to Topical Report WCAP-12610-P-A and CEI\IPD-404-P-A, "Optimized ZIRLOŽII June 10,2005. ADAMS Accession No. ML051670403. WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOŽ,
July 2006, ADAMS Accession No. ML062080576. Letter from Westinghouse to NRC, "SER Compliance with WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A 'Optimized ZIRLOŽ, (Proprietary)" L TR-NRC-07-1, January 4, 2007, ADAMS Accession No. ML070100389.
7 -5Letter from Westinghouse to NRC, uSER Compliance with WCAP-1261 O-P-A & CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOŽ'(Proprietary)
L TR-NRC-07-58, November 2007, ADAMS Accession No. ML073130562. Letter from Westinghouse to NRC, uSER Compliance with WCAP-12610-P-A
& CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOŽ, (Non-Proprietary)" L TR-NRC-07-58, Rev. 1, February 2008, ADAMS Accession No. IVIL080390452.
Letter from Westinghouse to U.S. Nuclear Regulatory Commission, uSER Compliance of WCAP-12610-P-A
& CENPD-404-P-A Addendum 1-A "Optimized ZIRLOŽ (Proprietary/Non-Proprietary)," L TR-NRC-08-60, December 30,2008, ADAMS Accession No. ML090080380.
Principal contributor:
S. Wu, SNPB/DSS Date of Issuance:
March 22, 2010 Mr. Jeffrey B. Archie Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, SC 29065 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1, ISSUANCE OF AMENDMENT REGARDING:
USE OF OPTIMIZED ZIRLO FUEL ROD CLADDING (TAC NO: ME1489)
Dear Mr. Archie:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 182 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No.1, in response to your letter dated June 9,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091620072).
The amendment changes Technical Specification (TS) 5.3.1, "Fuel Assemblies," to add Optimized ZIRLOŽ as an acceptable fuel rod cladding material and adds a Westinghouse topical report to the analytical methods identified in TS 6.9.1.11.
The NRC staff authorized the exemption by letter dated March 9, 2010, and published it in the Federal Register on March 15,2010 (75 FR 12312). A copy of the related Safety Evaluation is enclosed.
Notice of Issuance will be included in the Commission's next Biweekly Federal Register notice. Sincerely, IRA! Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosures:
- 1. Amendment No. 182 to NPF-12 2. Safety Evaluation cc w/enclosures:
Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsNrrDssSnpb Resource RidsNrrPMSummer Resource RidsNrrLASRohrer Resource RidsOgcRp Resource RidsRgn2MailCenter Resource SWu, NRR Amendment No' ML 100110377 NRR-058 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA OGC NRR/LPL2-1/BC NAME RMartin SRohrer LSubin GKulesa (JStanq for) DATE 03/22/10 03/22/10 02/23/10 03/22/10 OFFICIAL RECORD COPY