Letter Sequence Approval |
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TAC:ME0763, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 (Approved, Closed) |
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MONTHYEARRC-09-0012, License Amendment Request LAR 08-01332, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR 262009-03-0202 March 2009 License Amendment Request LAR 08-01332, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR 26 Project stage: Request ML0912106662009-06-0909 June 2009 Issuance of Amendment Regarding Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR 26. Project stage: Approval ML0921702752009-08-21021 August 2009 Request for Additional Information for Second 10-Year Interval Inservice Inspection Program Plan Relief Request 2-ISI-19 Revision 1 Project stage: RAI ML0928707662009-09-17017 September 2009 Response to NRC Request for Additional Information for Third 10-Year Interval Inservice Inspection Program Plan, Relief Request 2-ISI-19, Revision 1 Project stage: Response to RAI ML0928602592010-02-0202 February 2010 Relief, Alternative to Nozzle to Vessel Weld and Inner Radius Examinations Project stage: Other ML1005506452010-02-25025 February 2010 Safety Evaluation for Relief Request 2-ISI-19, Revision 1, for the Third 10-year Inservice Inspection Interval Project stage: Approval ML13308A3892013-11-0404 November 2013 E-mail from R.Guzman to B.Shingleton Request for Additional Information - LAR to Update Pressure Temperature Limit Curves (TACs ME0763/64/65) Project stage: RAI 2009-09-17
[Table View] |
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Category:Letter
MONTHYEARML24038A0322024-02-0707 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 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 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 ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 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 ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23137A1782023-05-22022 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 ML1021600202010-10-0404 October 2010 Issuance of Amendment Regarding Alternative Source Term Implementation ML1001103772010-03-22022 March 2010 Issuance of Amendment Regarding: Use of Optimized Zirlo Fuel Rod Cladding 2023-05-22
[Table view] Category:Safety Evaluation
MONTHYEARML23250A3112023-09-20020 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 ML15176A3152015-08-12012 August 2015 Alternative Request Regarding Snubbers ML15063A3552015-04-13013 April 2015 Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6 2023-09-20
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 9, 2009 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
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1, ISSUANCE OF AMENDMENT REGARDING ADOPTION OF TSTF-511, REV. 0, "ELIMINATE WORKING HOUR RESTRICTIONS FROM TS 5.2.2 TO SUPPORT COMPLIANCE WITH 10 CFR 26 (TAC NO: ME0763)
Dear Mr. Archie:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 181 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No.1, in response to your letter dated March 2, 2009 (Agencywide Document and Management System (ADAMS) Accession No. ML090650476).
The amendment deletes those portions of the renewed operating license Appendix A Technical Specifications (TS) that have been superseded by Title 10 to the Code of Federal Regulations (10 CFR), Part 26, Subpart I. This change is consistent with NRC approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The availability of this TS improvement was announced in the Federal Register on December 30, 2008, (73 FR 79923) as part of the consolidated line item improvement process. 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,
()
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. 181to 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.181 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 March 2, 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 paragraphs 2.C.(2) of Renewed Facility Operating License 1\10. NPF-12 is hereby amended to read as follows: 2.C(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 181, 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 by October 1, 2009. FOR THE NUCLEAR REGULATORY COMMISSION Melanie C. Wong, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Attachments:
Changes to the Technical Specifications Date of Issuance:
June 9, 2009 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 Page 3 License Page 3 TS 6-1a 6-1a 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; . 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; 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 . 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 PQwer Level is authQrized tQ operate the facility at reactor core power levels nQt in excess Qf 2900 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to this renewed license. The preoccupation tests, startup tests and Qther items identified in Attachment 1 tQ this renewed license shall be completed as specified.
Attachment 1 is hereby incorporated into this renewed license. Technical Specifications and Environmental ProtectiQn Plan The technical contained in Appendix A, as revised thrQugh Amendment No,;: 181 and the EnvirQnmental PrQtectiQn Plan contained in Appendix S, are hereby incorporated in the renewed license. South Carolina Electric & Gas Company shall Qperate the facility in accQrdance with the Technical SpecificatiQns and the Environmental PrQtection Plan. Renewed Facility Operating License No. NPF-12 Amendment No. 181 ADMINISTRATIVE
- b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1,2, 3 or 4, at least one Licensed Senior Reactor Operator shall be in the Control Room. c. A health physics technician#
shall be on site when fuel is in the reactor. d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
- e. Deleted. # The healt h physics technician composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
SUMMER -UNIT 1 6-1a Amendment No. 18,51,79, 181 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 181T0 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 application dated March 2, 2009, to the U.S. Nuclear Regulatory Commission (NRC, the Commission) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090650476), South Carolina Electric and Gas Company (SCE&G, the licensee) requested changes to the Appendix A Technical Specifications (TSs) for the Virgil C. Summer Nuclear Station (VCSNS), Unit NO.1. The proposed changes would delete paragraph e of VCSNS TS 6.2.2, "Unit Staff." The licensee stated that the application is consistent with NRC approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The availability of this TS improvement was announced in the Federal Register on December 30, 2008 (73 FR 79923) as part of the consolidated line item improvement process (CLlIP).
2.0 REGULATORY EVALUATION
The history of NRC regulations pertaining to prevention of worker impairment is summarized in the Federal Register notice containing the final rule that amended 10 CFR Part 26 (73 FR 16966, March 31, 2008). 10 CFR Part 26, Subpart I provides the regulatory requirements for managing worker fatigue at nuclear power plants. The NRC's regulatory requirements related to the content of the TS are contained in 10 CFR Part 50.36. 10 CFR 50.36 requires that the TS include items in the following categories:
(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) Surveillance Requirements; (4) design features; and (5) administrative controls.
The administrative controls are the provisions relating to organization and management, procedures, record keeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
-The NRC's guidance for the format and content of licensee Technical Specifications can be found in NUREG-1431, Revision 3.0, "Standard Technical Specifications Westinghouse Plants," referred to as Standard Technical Specifications (STS). Section 5 of STS contains administrative controls.
Paragraph d of Section 5.2.2 of STS contains requirements for administrative procedures to limit the working hours of personnel who perform safety related functions.
This paragraph represents NRC's guidance on how licensee TS requirements should address work hour controls.
Licensees adhere to the guidance to varying degrees due to minor administrative differences and differences in each licensee's current licensing basis. The inconsistent level of adherence to NRC guidance has lead to inconsistent TS interpretation and implementation.
This has also made it difficult for NRC to enforce the requirements.
The new requirements of 10 CFR Part 26, Subpart I supersede the guidance found in Paragraph d of Section 5.2.2 of all STS. Subpart I distinguishes between work hour controls and fatigue management and strengthens the requirements for both. Subpart I requires nuclear power plant licensees to ensure against worker fatigue adversely affecting public health and safety and the common defense and security by establishing clear and enforceable requirements for the management of worker fatigue. Licensees are required to implement Subpart I by October 1, 2009, as announced in the final rule that revised 10 CFR Part 26 (73 FR 16966, March 31,2008).
TSTF-511 proposed a change to STS that would delete Paragraph d of STS 5.2.2. This change was approved in Federal Register notice on December 30, 2008 (73 FR 79923). 2.1 Adoption of TSTF-511, Revision 0, by VCSNS, Unit NO.1 Proper adoption of TSTF-511 and implementation of 10 CFR Part 26, Subpart I by SCE&G will provide reasonable assurance that SCE&G will maintain limits on the working hours of personnel who perform safety related functions.
SCE&G has committed to remove the plant-specific TS requirements concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.
3.0 TECHNICAL EVALUATION Controls on work hours for personnel at nuclear power plants are necessary to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Work hour controls for VCSNS are currently located in Paragraph e of TS 6.2.2. When implemented, the regulatory requirements of 10 CFR 26, Subpart I replace the plant-specific TS requirements found in paragraph 6.2.2.e of VCSNS TS. The licensee proposed deleting paragraph e of VCSNS TS 6.2.2. The licensee committed to implement the new requirements of 10 CFR Part 26, Subpart I concurrently with the deletion of the TS requirements on work hour controls.
The NRC staff finds that reasonable controls for the implementation and subsequent evaluation of proposed changes pertaining to the above regulatory commitment are best provided by the licensee's administrative processes, including its commitment management program (see Regulatory Issue Summary 2000-017, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff'). The above regulatory commitments do not warrant the creation of regulatory requirements (items requiring prior NRC approval of subsequent changes).
The staff evaluated the licensee's proposed change against the applicable regulatory requirements listed in section 2. The staff also compared the proposed change to the change
-made to STS by TSTF-511.
The staff considered the licensee's commitment to implement 10 CFR Part 26, Subpart I concurrently with the deletion of TS work hour control requirements in its evaluation of the proposed chal1ge. Given the licensee's commitment, there is reasonable assurance that the licensee will comply with the regulations for work hour controls, either through TS requirements or through the requirements of 10 CFR part 26, Subpart I, at all times at VCSNS. Therefore, the licensee will continue to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Therefore, the staff finds the proposed change acceptable. STATE CONSULTATION 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 This amendment changes record keeping, reporting, or administrative procedures.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
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 SCE&G License Amendment Request to adopt TSTF-511, March 2, 2009 Federal Register Notice, Notice of Availability published on December 30, 2008, 73 FR 79923. TSTF-511 Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." Principal contributors:
V. Cusumano, NRR/DIRS M. Hamm, NRR/DIRS Date of Issuance:
June 9, 2009 June 9, 2009 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 ADOPTION OF TSTF-511, REV. 0, "ELIMINATE WORKING HOUR RESTRICTIONS FROM TS 5.2.2 TO SUPPORT COMPLIANCE WITH 10 CFR 26 (TAC NO: ME0763)
Dear Mr. Archie:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment NO.181 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No.1, in response to your letter dated March 2, 2009 (Agencywide Document and Management System (ADAMS) Accession No. ML090650476).
The amendment deletes those portions of the renewed operating license Appendix A Technical Specifications (TS) that have been superseded by Title 10 to the Code of Federal Regulations (10 CFR), Part 26, Subpart I. This change is consistent with NRC approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The availability of this TS improvement was announced in the Federal Register on December 30,2008, (73 FR 79923) as part of the consolidated line item improvement process. 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. 181 to NPF-12 2. Safety Evaluation cc w/enclosures:
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