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MONTHYEARML0205606262002-02-14014 February 2002 Issuance of Amendment, Increases Allowable Operational Leakage Rate for Reactor Coolant System Pressure Isolation Valves (TAC Mb 2238) Project stage: Approval 2002-02-14
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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] |
Text
Mr. Stephen A. Byrne February 14, 2002 Senior Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - INCREASED ALLOWABLE OPERATIONAL LEAKAGE RATE FOR REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES (TAC NO. MB2238)
Dear Mr. Byrne:
The Nuclear Regulatory Commission has issued the enclosed Amendment No.154 to Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1.
The amendment changes the Technical Specifications (TS) in response to your application dated June 19, 2001.
This amendment revises V. C. Summer TS 3.4.6.2f by increasing the allowable operational leakage rate for 23 of the 35 reactor coolant system pressure isolation valves listed in TS Table 3.4-1. This change implements a size-dependent allowable leakage rate of 0.5 gallon per minute per nominal inch of valve diameter, up to a maximum of 5 gallons per minute per valve.
Additionally, the word above from ACTION c. of Limiting Condition for Operation (LCO) 3.4.6.2 is removed. This is an editorial change necessitated by the shifting of the specific pressure isolation valve allowable leakage limits from LCO 3.4.6.2.f to Table 3.4-1, which is on a separate page.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's Bi-weekly Federal Register notice. This completes the staff's efforts on TAC No.
MB2238.
Sincerely,
/RA/
Ramin Assa, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosures:
- 1. Amendment No. 154 to NPF-12
- 2. Safety Evaluation cc w/encls: See next page February 14, 2002 Mr. Stephen A. Byrne
Senior Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - INCREASED ALLOWABLE OPERATIONAL LEAKAGE RATE FOR REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES (TAC NO. MB2238)
Dear Mr. Byrne:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 154 to Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1.
The amendment changes the Technical Specifications (TS) in response to your application dated June 19, 2001.
This amendment revises V. C. Summer TS 3.4.6.2f by increasing the allowable operational leakage rate for 23 of the 35 reactor coolant system pressure isolation valves listed in TS Table 3.4-1. This change implements a size-dependent allowable leakage rate of 0.5 gallon per minute per nominal inch of valve diameter, up to a maximum of 5 gallons per minute per valve.
Additionally, the word above from ACTION c. of Limiting Condition for Operation (LCO) 3.4.6.2 is removed. This is an editorial change necessitated by the shifting of the specific presssure isolation valve allowable leakage limits from LCO 3.4.6.2.f to Table 3.4-1, which is on a separate page.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's Bi-weekly Federal Register notice. This completes the staff's efforts on TAC No.
MB2238.
Sincerely,
/RA/
Ramin Assa, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosures:
- 1. Amendment No. 154 to NPF-12
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC RLaufer (hard copy) RidsAcrsAcnwMailCenter PDII-1 Rdg EDunnington(hard copy) GHill (4) RidsRgn2MailCenter RidsNrrDlpmLpdii RidsOgcRp WBeckner FILENAME - G:\PDII-1\SUMMER\RAMIN\MB2238-AMD.WPD OFFICE PM:PDII/S1 LA:PDII/S2 SC(A):PDII/S1 OGC EMEB NAME RAssa EDunnington RLaufer SUtal DTerao DATE 1/30/02 1/29/02 2/13/02 2/8/02 2/13/02 OFFICIAL RECORD COPY
SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. NPF-12
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by South Carolina Electric & Gas Company (the licensee), dated June 19, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 154, 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.
- 3. This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 14, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 154 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 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 3/4 4-19 3/4 4-19 3/4 4-21 3/4 4-21 B 3/4 4-4 B 3/4 4-4 B 3/4 4-5 B 3/4 4-5 B 3/4 4-6 B 3/4 4-6
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 154TO 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
In a submittal dated June 19, 2001, South Carolina Electric & Gas Company (the licensee) proposed changes to the technical specifications (TS) for the Virgil C. Summer Nuclear Station, Unit 1 (Summer). The licensees proposal would increase the allowable operational leakage rate for 23 of the 35 Reactor Coolant System (RCS) pressure isolation valves (PIVs) listed in TS Table 3.4-1. Currently, the allowable leakage rate for PIVs of all sizes is 1 gallon per minute (gpm). The proposed TS changes would implement a size-dependent allowable leakage rate of 0.5 gpm per nominal inch of valve diameter, up to a maximum of 5 gpm per valve.
2.0 BACKGROUND
PIVs are those valves in the primary RCS that isolate the boundary between the high pressure primary coolant system and connected low pressure piping systems. Leakage rate limits for PIVs were originally implemented by the NRC in response to concerns regarding the inter-system loss-of-coolant accident (LOCA), which was identified in the Reactor Safety Study of 1975, WASH-1400. An intersystem LOCA event involves the failure of two in-series PIVs, which would subject a low pressure system outside of containment to full primary coolant system pressure. The low pressure system would consequently rupture, resulting in a LOCA that would bypass containment, thereby jeopardizing the ability for long-term reactor core cooling.
The Summer TS 3.4.6.2 provides requirements for the maximum allowable leakage for PIVs, including the limiting condition for operation, action requirements and surveillance requirements. TS 3.4.6.2.f limits leakage to 1 gpm for all PIVs in Table 3.4.1. In early 1980, NRC revised the PIV leakage requirement from a single amount of 1 gpm to 0.5 gpm per nominal inch of valve size to a maximum of 5 gpm at an RCS pressure. This change tightened the leakage requirement for smaller valves and relaxed it for larger ones. This revised leakage requirement was incorporated into NUREG-1431, Standard Technical Specifications for Westinghouse Plants, in September of 1992, and is also consistent with leakage limits specified in the 1995 edition of ASME Code,Section XI, which is the latest edition incorporated by reference in Paragraph (b) of 10 CFR 50.55a.
2.1 Description of Proposed TS Changes The licensee has proposed to modify Limiting Condition for Operation (LCO) 3.4.6.2.f and Table 3.4-1 of the Summer TS to reflect the proposed allowable leakage rate of 0.5 gpm per inch of valve diameter (up to a maximum of 5 gpm per valve) rather than the current 1 gpm allowable leakage rate for all valve sizes. There are 35 PIVs listed in Table 3.4-1; implementation of this proposed TS change would cause 12 PIVs to remain at the current 1 gpm allowable leakage rate, 11 PIVs to be allowed a leakage rate of 3 gpm, and 12 PIVs to be allowed a leakage rate of 5 gpm. Both current and proposed requirements prescribe that PIV leakage rate testing shall be performed at an RCS pressure within a 40 psi band centered upon the nominal RCS operating pressure of 2235 psig.
Additionally, the licensee has proposed to delete the word above from ACTION c. of LCO 3.4.6.2. This is an editorial change necessitated by the shifting of the specific PIV allowable leakage limits from LCO 3.4.6.2.f to Table 3.4-1, which is on a separate page.
3.0 EVALUATION The basis for PIV leakage rate testing is to provide assurance that excessive valve degradation has not occurred and that a potential PIV failure is not imminent. As explained above, the use of a 1 gpm acceptance criterion for the testing of PIVs of all sizes is no longer regarded as the recommended method for providing such assurance. For instance, a single allowable leakage rate for all valve sizes does not recognize that a 1 gpm leakage rate provides a more significant indication of degradation for a 2-inch valve than for a 10-inch valve. Thus, the current 1 gpm leakage rate limit for all PIVs may result in an increased frequency of maintenance on larger PIVs.
A potential concern related to increasing PIV allowable leakage rates is that the low pressure systems isolated by the PIVs may not have sufficient pressure relief capacity to cope with the increased leakage. Inleakage exceeding the pressure relief capacity of a low pressure system would lead to its overpressurization and rupture. The licensee has stated in its submittal that the low pressure systems affected by the proposed TS changes have pressure relief capacities that are greater than their proposed allowed inleakage rates. Though increased allowable leakage rates are being proposed for PIVs of larger sizes, those piping lines with larger PIVs have also been designed with an increased pressure relief capacity. Therefore, the staff finds that the proposed increase in PIV allowable leakage rates will not challenge the pressure relief capacities of the connected low pressure systems.
The staff also reviewed the proposed TS changes against the recommendations contained in NUREG-1431 and inservice testing requirements of ASME Code Section XI regarding PIVs, and finds that the changes are consistent with standard TS for Westinghouse plants and the leakage requirements specified in ASME Code,Section XI.
Based upon the above evaluation, the NRC staff has concluded that the licensees proposed TS changes: (1) would satisfy the basis for PIV allowable leakage requirements; (2) would not challenge the pressure relief capacities of connected low pressure systems; and (3) are consistent with standard TS for Westinghouse Plants, NUREG-1431, and the leakage requirements specified in ASME Code Section XI. Therefore, the staff finds the proposed changes to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of South Carolina official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 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 has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 41626). 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.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Y. Huang J. Lehning Date: February 14, 2002
Mr. Stephen A. Byrne VIRGIL C. SUMMER NUCLEAR STATION South Carolina Electric & Gas Company cc:
Mr. R. J. White Ms. Kathryn M. Sutton, Esquire Nuclear Coordinator Winston & Strawn Law Firm S.C. Public Service Authority 1400 L Street, NW c/o Virgil C. Summer Nuclear Station Washington, DC 20005-3502 Post Office Box 88, Mail Code 802 Jenkinsville, South Carolina 29065 Resident Inspector/Summer NPS c/o U.S. Nuclear Regulatory Commission 576 Stairway Road Jenkinsville, South Carolina 29065 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 Mr. Henry Porter, Assistant Director Division of Waste Management Bureau of Land & Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Mr. Gregory H. Halnon, General Manager Nuclear Plant Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 303 Post Office Box 88 Jenkinsville, South Carolina 29065 Mr. Melvin N. Browne, Manager Nuclear Licensing & Operating Experience South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 830 Post Office Box 88 Jenkinsville, South Carolina 29065