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Category:Code Relief or Alternative
MONTHYEARML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24079A0062024-04-10010 April 2024 – Proposed Alternative to the Requirements of ASME Code of Operation and Maintenance of Nuclear Power Plants for Pressure Isolation Valve Testing Frequency ML23150A0802023-05-30030 May 2023 Acceptance Review - Vogtle Units 1 and 2 - Proposed LAR and Relief Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23095A2962023-04-14014 April 2023 Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (Vegp 3&4-Isi1- Alt-17) ML22259A1822022-09-22022 September 2022 Request for Proposed Inservice Testing Alternative ALT-VR-01 ML22118A0762022-05-13013 May 2022 Cover Letter for Vogtle Electric Generating Plant, Units 3 and 4 Request for Alternative Requirements for Inservice Test Interval Code Edition (VEGP 3&4-IST-ALT-01R2) ML22021A0012022-01-24024 January 2022 Relief Request for Proposed Alternative Requirements for the Repair of Reactor Vessel Head Penetrations for the Fourth 10-Year Inservice Inspection Interval, VEGP-ISI-ALT-04-05, Version 1.0 ND-21-0392, Enclosure 3 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14163 (VEGP 3-ALT-16)2021-06-0303 June 2021 Enclosure 3 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14163 (VEGP 3-ALT-16) ML21154A2132021-06-0303 June 2021 Enclosure 2 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14162(VEGP 3-ALT-16) ML21154A2122021-06-0303 June 2021 Enclosure 1 - Vogtle Electric Generating Plant (VEGP) Unit 3 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1): Alternative Requirements for ASME Section III Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16) ML21040A1652021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2): Alternative Requirements for ASME Section XI Examination Coverage of Weldolet Branch Connection Welds ML20352A1552021-01-11011 January 2021 Proposed Relief Request for Alternative VEGP-ISI-ALT-04-04 to the Requirements of the ASME Code ML20307A1412020-11-12012 November 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal NL-20-1262, Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion2020-10-30030 October 2020 Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion ML20216A3992020-08-0606 August 2020 Relief Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20143A2332020-06-0303 June 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19)) ML20132A1532020-05-14014 May 2020 ASME Code Alternative - May 14, 2020 Presubmittal Technical Exchange for Preservice Inspection (PSI) Alternative ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ND-20-0083, Revision to Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01R1)2020-02-0606 February 2020 Revision to Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01R1) ND-19-1294, Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01)2019-10-31031 October 2019 Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01) ML18320A0192018-11-30030 November 2018 Relief Request Regarding Examination Coverage for Certain ASME Code Class 2 Category Welds (VEGP-ISI-RR-05) ML18296A7172018-10-31031 October 2018 Relief Request Regarding Examination Coverage for Certain Pressurizer and Steam Generator Welds (VEGP-ISI-RR-03) ND-18-1158, Revision to Request for Alternative: Alternative Requirements for Preservice Examination Volumetric Surface Configuration Requirements (VEGP 3&4-PSI/ISI-ALT-10R1)2018-08-30030 August 2018 Revision to Request for Alternative: Alternative Requirements for Preservice Examination Volumetric Surface Configuration Requirements (VEGP 3&4-PSI/ISI-ALT-10R1) NL-18-0428, Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-12018-04-0909 April 2018 Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-1 ML18054A0652018-03-0505 March 2018 Cover Letter - Vogtle Electric Generating Plant - Request for Alternative (ALT-9) ML17171A1022017-06-27027 June 2017 Inservice Inspection Alternative Regarding Category B-N-2 and B-N-3 Welds (VEGP ISI ALT 13) ML17061A2022017-03-17017 March 2017 Request for Alternative RR-PR-03 Regarding Nuclear Service Cooling Water Pump Instrument Accuracy ML17037D0502017-02-17017 February 2017 and 2; Request to Use Asme Code Case OMN-18 as an Alternative to Inservice Testing Requirements (CAC Nos. MF8188 and MF8189) NL-17-0101, Proposed Alternative VEGP-ISI-AL T-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 Inservice Inspection Examinations Schedule2017-01-26026 January 2017 Proposed Alternative VEGP-ISI-AL T-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 Inservice Inspection Examinations Schedule ML17006A1092017-01-26026 January 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads Inflange Inspection ML16326A0442016-12-0808 December 2016 Alternative for Pump and Valve Inservice Testing Program ML16264A3212016-10-14014 October 2016 Alternatives for Pumps and Valves Inservice Testing Program ML14030A5702014-03-20020 March 2014 Request for Alternatives VEGP-ISI-ALT-06 ML13123A1602013-05-0707 May 2013 (VEGP) - Safety Evaluation of Relief Request VEGP-ISI-ALT-09, Version 2.0, Regarding Leakage Tests for Reactor Coolant Pressure Boundary Components ML13032A1062013-02-0707 February 2013 Safety Evaluation of Relief Request VEGP-ISI-ALT-08, Version 1, Regarding Installation of a Mechanical Clamp on a Class 1 Valve - Fourth 10-Year Interval ML1009001292010-06-11011 June 2010 Relief Requests VEGP-ISI-ALT-04 (Units 1 and 2) and VEGP-ISI-RR-01 (Unit 2) Inservice Inspection Alternatives for Third and Subsequent Inservice Inspection Intervals (TAC Nos. ME2226, ME2227, and ME1134) ML1012000882010-04-30030 April 2010 Acceptance of Vogtle Relief Request (VEGP-ISI-ALT-03) Dated April 7, 2010 NL-09-1410, VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)2009-09-0909 September 2009 VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii) ML0731004352007-11-15015 November 2007 Third 10-Year Interval, Inservice Program Relief Request RR-V-1 (Tac Nos. MD5409 and MD5410) ML0627703592006-09-29029 September 2006 Evaluation of Relief Request ISI-GEN-ALT-06-02 NL-06-1713, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays2006-08-10010 August 2006 Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays ML0510301992005-04-25025 April 2005 RR, ISI Program Intervals for Alternative Alignment of Iwe/Iwl Inspection Program (Tac No. MC4870, MC4871, MC4872, MC4873, MC4874, MC4875) ML0332800372003-11-21021 November 2003 Safety Evaluation Re. Request to Use ASME Code Case N-661 ML0225904572002-09-16016 September 2002 Code Relief, Relief Request for the Second Ten-Year Interval Inservice Testing Program 2024-07-19
[Table view] Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24243A0932024-08-30030 August 2024 Non-concurrence Text No Annotations ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) ML24030A9092024-04-10010 April 2024 Issuance of Amendment Nos. 224 and 207, Regarding Revision to Technical Specification 3.4.14 (Reactor Coolant System) Pressure Isolation Valve Leakage Surveillance Requirement 3.4.14.1 ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23243B0492023-12-19019 December 2023 VEGP Units 3 and 4, Safety Evaluation, LAR-22-002, TS 3.8.3 Inverters Operating, Completion Time Extension - Enclosure 3 ML23335A1232023-12-19019 December 2023 Safety Evaluation Final Integrated Plan ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 ML23326A1362023-11-28028 November 2023 Safety Evaluation for Amendment 195 & 192 for TS 3.1.9 More Restrictive Action ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23093A0282023-08-0101 August 2023 Issuance of Amendments Nos. 220 and 203, Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23159A1022023-07-31031 July 2023 Safety Evaluation - Vogtle Electric Generating Plant, Unit 3 Amendment No. 192 (LAR 23-001) ML23158A0182023-07-31031 July 2023 Issuance of Amendments Nos. 219 and 202, Regarding Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML23158A2062023-07-19019 July 2023 LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Safety Evaluation ML23115A1492023-06-15015 June 2023 Issuance of Amendments No. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology ML23109A0702023-05-0404 May 2023 Enclosure - Safety Evaluation for VEGP3&4 ISI1-ALT-18 ML23072A2742023-05-0101 May 2023 Enclosure 3 - LAR 22-005 Safety Evaluation ML23095A2962023-04-14014 April 2023 Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (Vegp 3&4-Isi1- Alt-17) ML23095A2972023-04-14014 April 2023 Enclosure - VEGP 3&4-ISI1-ALT-17 Safety Evaluation ML23037A0912023-02-0808 February 2023 Safety Evaluation - Vogtle Unit 3 Amendment No. 190, Tech Spec Exceptions for In-Containment Refueling Water Storage Tank Operability Prior to Initial Criticality (Exigent Circumstances) ML23013A2202023-01-13013 January 2023 Safety Evaluation for License Amendment No. 189 Tech Spec Limiting Conditions for Operability Reqs for Auto Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ML22284A1332022-11-22022 November 2022 LAR-22-003 U4 Electrical ITAAC Consolidation Amendment Safety Evaluation ML22286A1252022-11-16016 November 2022 Issuance of Amendments Nos. 217 & 200 Regarding Revision to Technical Specifications to Adopt TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes ML22259A1822022-09-22022 September 2022 Request for Proposed Inservice Testing Alternative ALT-VR-01 ML22249A0922022-09-14014 September 2022 Enclosure - Safety Evaluation the Requirements of the ASME Code for Main Turbine System Valve Testing, VEGP 3&4-IST-ALT-02 ML22116A0842022-07-0505 July 2022 Issuance of Amendment Nos. 215 and 198, Regarding Revision to Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs) ML22118A0772022-05-13013 May 2022 Safety Evaluation Regarding Request for Alternative Requirements for Inservice Test Interval Code Edition (VEGP 3&4-IST-ALT-01R2) ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21314A1502021-12-0707 December 2021 Issuance of Amendment Nos. 210 and 193, Regarding Revision to Technical Specification 3.3.5, 4.16 (Kilovolt) Kv (Engineered Safety Feature) Esf Bus Loss of Power (LOP) Instrumentation (EPID L 2021-LLA-0054 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21237A2402021-10-15015 October 2021 Safety Evaluation for Amendment No. LAR-21-001: Clarification of ITAAC Regarding Invessel Components ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21217A0282021-09-17017 September 2021 Safety Evaluation for Vogtle Electric Generating Plant Units 3 and 4 Regarding Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21068A0822021-07-30030 July 2021 Issuance of Amendment Nos. 206 and 189, Regarding a License Amendment Request for a Risk-Informed Resolution to GSI-191 ML20268A0702021-07-30030 July 2021 Safety Evaluation - Vogtle GSI-191 LAR ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality ML21090A2472021-04-0909 April 2021 Safety Evaluation by the Office of Nuclear Reactor Regulation Regarding Proposed ASME Code Alternative Requirements for ASME Section XI Examination Coverage of Weldolet Branch Connections ML20352A1552021-01-11011 January 2021 Proposed Relief Request for Alternative VEGP-ISI-ALT-04-04 to the Requirements of the ASME Code ML20314A0162020-12-0707 December 2020 Safety Evaluation Vacuum Relief Valve Technical Specification Changes (LAR 20-005) ML20307A1412020-11-12012 November 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal ML20269A4002020-10-27027 October 2020 Interim Staff Evaluation for Vogtle Electric Generating Plant, Units 3 and 4 Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 ML20247J4642020-10-14014 October 2020 Safety Evaluation Report for Vogtle Electric Generating Plant for Amendments 185/183 (LAR 20-004) ML20237F4952020-09-24024 September 2020 Safety Evaluation for Vogtle Electric Generating Plant Units 3 and 4 Amendment Nos. 184/182 (LAR 20-003) 2024-08-30
[Table view] |
Text
November 15, 2007 Mr. Tom E. Tynan Vice President - Vogtle Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, THIRD 10-YEAR INTERVAL INSERVICE PROGRAM RELIEF REQUEST RR-V-1 (TAC NOS. MD5409 AND MD5410)
Dear Mr.Tynan:
By letter dated April 16, 2007, as supplemented by letter dated September 20, 2007, Southern Nuclear Operating Company, Inc. (the licensee), submitted Relief Request RR-V-1 for Vogtle Electric Generating Plant, Units 1 and 2. The relief request proposed an alternative to the requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a (10 CFR 50.55a), concerning a requirement in the American Society of Mechanical Engineers, Operation and Maintenance of Nuclear Power Plants Code (ASME OM Code). The proposed alternative involves the elimination of the ASME OM Code required 5-minute test interval between successive setpoint tests for liquid service pressure relief valves.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensees analysis in support of its relief request. The NRC staff has concluded that the elimination of the 5-minute test interval required by the ASME OM Code would provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the elimination of the 5-minute test interval for liquid service pressure relief valves.
Sincerely,
/RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosure:
Safety Evaluation cc w/encl: See next page
November 15, 2007 Mr. Tom E. Tynan Vice President - Vogtle Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, THIRD 10-YEAR INTERVAL INSERVICE PROGRAM RELIEF REQUEST RR-V-1 (TAC NOS. MD5409 AND MD5410)
Dear Mr.Tynan:
By letter dated April 16, 2007, as supplemented by letter dated September 20, 2007, Southern Nuclear Operating Company, Inc. (the licensee), submitted Relief Request RR-V-1 for Vogtle Electric Generating Plant, Units 1 and 2. The relief request proposed an alternative to the requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a (10 CFR 50.55a), concerning a requirement in the American Society of Mechanical Engineers, Operation and Maintenance of Nuclear Power Plants Code (ASME OM Code). The proposed alternative involves the elimination of the ASME OM Code required 5-minute test interval between successive setpoint tests for liquid service pressure relief valves.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensees analysis in support of its relief request. The NRC staff has concluded that the elimination of the 5-minute test interval required by the ASME OM Code would provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the elimination of the 5-minute test interval for liquid service pressure relief valves.
Sincerely,
/RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosure:
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ADAMS ACCESSION NO.: ML073100435 *memo transmitting SE dated.
NRR/DCI/CPTB/B OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA C OGC NRR/LPL2-1/BC NAME SLingam MO=Brien JMcHale KSexton EMarinos DATE 11/5/07 11/5/07 11/1/07* 11/13/07 11/15/07 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE THIRD 10-YEAR INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST NO. RR-V-1 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425 INTRODUCTION By letter dated April 16, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML071080463), as supplemented by letter dated September 20, 2007 (ADAMS Accession No. ML072640100), Southern Nuclear Operating Company. Inc. (the licensee), submitted Relief Request RR-V-1 for Vogtle Electric Generating Plant (VEGP), Units 1 and 2. The relief request proposed an alternative to the requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a (10 CFR 50.55a), concerning a requirement in the American Society of Mechanical Engineers, Operation and Maintenance of Nuclear Power Plants Code (ASME OM Code). The proposed alternative involves the elimination of the ASME OM Code required 5-minute test interval between successive setpoint tests for liquid service pressure relief valves.
REGULATORY EVALUATION Section 50.55a requires that inservice testing (IST) of certain ASME Boiler and Pressure Vessel Code (ASME Code) Class 1, 2, and 3 pumps and valves be performed in accordance with the ASME OM Code and applicable addenda, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Nuclear Regulatory Commission (NRC) pursuant to paragraphs (a)(3)(i),
(a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for its facility. Section 50.55a allows the NRC to authorize alternatives and to grant relief from ASME OM Code requirements upon making the necessary findings.
NRC guidance contained in Generic Letter (GL) 89-04, Guidance on Developing Acceptable Inservice Testing Programs, provides alternatives to the Code requirements that are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, Revision 1.
Enclosure
TECHNICAL EVALUATION By letter dated April 16, 2007, as supplemented by letter dated September 20, 2007, the licensee submitted relief request RR-V-1 for the VEGP, Units 1 and 2. Relief request RR-V-1 requested relief from the ASME OM Code, Appendix I, Section I-8000, requirement for a 5-minute hold time between successive setpoint tests for liquid service pressure relief valves. The Code of record is the 2001 edition with addenda through OMb - 2003. A description of the relief request and the NRC staffs evaluation are as follows.
Code Requirements Appendix I, Section I-8000 of ASME OM Code contains test methods for ASME Code, Class 2 and 3 relief valves in liquid systems. Paragraph I-8130(g) requires a minimum of 5 minutes shall elapse between successive openings.
Licensees Basis for Requesting Relief IST programs require that the testing meets the ASME OM Code of record. Specifically, the Code requires performing a minimum of two consecutive valve actuations to determine the setpoint of the pressure relief valve. Under the ASME OM Code, Appendix I, the minimum elapsed time between valve openings is 5 minutes.
Eliminating this 5-minute hold time will minimize test performance and system outage times, resulting in a more timely return to service.
At VEGP, Units 1 and 2, pressure relief valves in ASME Code, Class 2 and 3 liquid systems are bench tested at ambient conditions using water as the test medium. The setpoint testing is performed in a shop environment with the test medium and valve in thermal equilibrium. There is no thermal source introduced during the test that could result in a thermal imbalance or reduced accuracy of the test. Repeated valve actuations are conducted in a controlled environment under steady-state conditions.
Licensees Proposed Alternative Testing The licensee proposes the elimination of the 5-minute hold time for ASME Code, Class 2 and 3 setpoint tests for liquid service pressure relief valves.
Technical Evaluation The ASME OM Code 5-minute hold time requirement is based on the assumption that the test medium temperature is different from the valve temperature. Setpoint testing with different valve and test medium temperatures would cause the temperature of the valve to change; therefore, the setpoint would be affected. The NRC staff finds that the ASME Code, Class 2 and 3 liquid system pressure relief valves are in thermal equilibrium under the ambient test temperature conditions. Thermal stabilization is achieved with no hold time; consequently, the setpoint is unaffected. Thus, the NRC staff finds that the proposed no hold time between setpoint tests of the ASME Code, Class 2 and 3 system liquid service pressure relief valves provides an adequate method of accurately and repeatedly determining setpoints.
Conclusion The NRC staff concludes that the licensees proposed alternative to the above discussed ASME OM Code testing requirement for ASME Code, Class 2 and 3 liquid service pressure relief valves in RR-V-1 is authorized pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternative testing provides an acceptable level of quality and safety. The elimination of the hold time between consecutive setpoint tests should not impair the valves operational readiness.
Principal Contributor: Michael D. Orenak Date: November 15, 2007
Vogtle Electric Generating Plant, Units 1 & 2 cc:
Mr. Tom E. Tynan Vice President - Vogtle Arthur H. Domby, Esquire Vogtle Electric Generating Plant Troutman Sanders 7821 River Road Nations Bank Plaza Waynesboro, GA 30830 600 Peachtree Street, NE Suite 5200 Mr. N. J. Stringfellow Atlanta, GA 30308-2216 Manager, Licensing Southern Nuclear Operating Company, Resident Inspector Inc. Vogtle Plant P.O. Box 1295 8805 River Road Birmingham, AL 35201-1295 Waynesboro, GA 30830 Mr. Jeffrey T. Gasser Office of the County Commissioner Executive Vice President Burke County Commission Southern Nuclear Operating Company, Waynesboro, GA 30830 Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Mr. Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334 Mr. Harold Reheis, Director Department of Natural Resources 205 Butler Street, SE, Suite 1252 Atlanta, GA 30334 Attorney General Law Department 132 Judicial Building Atlanta, GA 30334 Mr. Laurence Bergen Oglethorpe Power Corporation 2100 East Exchange Place P.O. Box 1349 Tucker, GA 30085-1349