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Category:Code Relief or Alternative
MONTHYEARML23150A0802023-05-30030 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 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) ML21154A2132021-06-0303 June 2021 Enclosure 2 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14162(VEGP 3-ALT-16) 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) 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 2023-05-30
[Table view] Category:Letter
MONTHYEARML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24010A0712024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports and Recordkeeping and Suspicious Activity Reporting) ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public ML24029A0592024-01-30030 January 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report Enclosure 2, GAE-NRCD-RF-LR-000002 P-Attachment, Rev. 0 ML24016A1132024-01-30030 January 2024 Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 IR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23347A2092024-01-17017 January 2024 Voluntary Requests for Data, Information, And/Or Observation ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) 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 ML23335A1222023-12-19019 December 2023 Safety Evaluation Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 (EPID L-2023-LRQ-0002) - Letter ML23353A1702023-12-19019 December 2023 LAR-22-002, TS 3.8.3 Inverters Operating Completion Time Extension Letter ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 ML23339A1812023-12-0707 December 2023 Correction Letter Regarding License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 ML23338A2182023-12-0606 December 2023 Project Manager Reassignment NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23289A1632023-11-28028 November 2023 Letter and Amendment 195 and 192 LAR-23-006R1 TS 3.1.9 More Restrictive Action NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 ML23318A4582023-11-14014 November 2023 Integrated Inspection Report 05200025/2023003 ML23312A3502023-11-14014 November 2023 Integrated Inspection Report 05200026/2023003 ML23306A3552023-11-0808 November 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 052000/262023008 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) IR 05000424/20234022023-11-0606 November 2023 Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402 IR 05000424/20230032023-10-27027 October 2023 Integrated Inspection Report 05000424/2023003 and 05000425/2023003 ML23291A1512023-10-18018 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 0520026/2024401 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 ML23283A0472023-10-0808 October 2023 Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23254A2032023-09-13013 September 2023 Initial Test Program and Operational Programs Inspection Report 05200025/2023013 ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report ML23234A2352023-09-0808 September 2023 Request for Withholding Information from Public Disclosure Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events IR 05000424/20230912023-09-0505 September 2023 Plan Units 1 and 2 - NRC Investigation Report 2-2022-006 and Notice of Violation - NRC Inspection Report 05000424/2023091 and 05000425/2023091 ML23234A3002023-09-0101 September 2023 NRC Integrated Inspection Report 05200026/2023003 ML23243A0092023-08-31031 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 & 4 (Report 05200025 2023005 & 05200026 2023005) NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) ML23243B0252023-08-30030 August 2023 Exam Corporate Notification Letter (210 Day) IR 05000424/20230052023-08-29029 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 & 2 - Report 05000424/2023005 and 05000425/2023005 NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23317A2072023-12-22022 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 ML23335A1232023-12-19019 December 2023 Safety Evaluation Final Integrated Plan 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 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) ML20196L6822020-08-11011 August 2020 Safety Evaluation for Vogtle Electric Generating Plant Units 3 and 4 Amendment 183 and 181 for LAR 20-002 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 ML20132A0782020-08-0404 August 2020 Safety Evaluation for Vogtle Electric Generating Plant Unit 3 (LAR 20-001) ML20178A1322020-07-15015 July 2020 Safety Evaluation Regarding Welded Reinforcement Bar Splices at Vogtle Electric Generating Plant Units 3 and 4 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)) 2023-08-02
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 7, 2013 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. Post Office Box 1295 / Bin 038 Birmingham, AL 35201-1295 VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 -SAFETY EVALUATION OF RELIEF REQUESTVEGP-ISI-ALT-08, VERSION 1.0, REGARDING INSTALLATION OF A MECHANICAL CLAMP ON A CLASS 1 FOURTH 10-YEAR INTERVAL (TAC NO. ME9850) Dear Mr. By letter to the U.S. Nuclear Regulatory Commission (NRC), dated October 25,2012, supplemented by letter dated October 29, 2012, Southern Nuclear Operating Company, (SNC, the licensee) proposed an alternative (VEGP-ISI-AL T-08, Version 1.0) to Appendix IX Section XI of the American Society of Mechanical Engineer's Boiler and Pressure (ASME) Code to allow installation of a mechanical clamp on a non-pressure boundary leak a Class 1 Chemical and Volume Control valve 1-1208-U4-A 11 for the Vogtle Electric Plant, Unit 1 On November 1, 2012, pursuant to Title 10 Code of Federal Regulations, Part Section 50.55a(a)(3)(ii)), the NRC staff verbally authorized the use of the VEGP-ISI-AL T-08, Version 1.0. This safety evaluation documents the technical basis of verbal The NRC staff determines that the proposed alternative provides reasonable assurance structural integrity and leak tightness of the subject components and that complying with specified requirement would result in a hardship or unusual difficulty without a increase in the level of quality and safety. Accordingly, the NRC staff concludes that licensee has adequately addressed all of the regulatory requirements set forth 10 CFR 50.55a(a)(3)(ii), and is in compliance with requirements of the ASME Code, Section for which relief was not requested. Therefore, in accordance with 10 CFR 50.55a(a)(3)(ii) NRC authorizes use of the licensee's proposed alternative, VEGP-ISI-AL T-08, Version 1.0, VEGP-1 until the 1 R 18 refueling outage in the spring of C. Pierce -All other requirements in ASME Code,Section XI, and 10 CFR 50.55a for which relief was not specifically requested and approved in this RR remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. Sincerely, Robert Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-424 Enclosure: Safety Evaluation cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUESTVEGP-ISI-ALT-08, VERSION 1.0, REGARDING INSTALLATION OF A MECHANICAL CLAMP ON A CLASS 1 VALVE -FOURTH 10-YEAR INTERVAL SOUTHERN NUCLEAR OPERATING COMPANY, INC. VOGTLE ELECTRIC GENERATING PLANT. UNIT 1 DOCKET NO. 50-424 1.0 INTRODUCTION By letter dated October 25,2012 (Agencywide Documents Access and Management System (ADAMS Accession No. ML 12299A244), as supplemented by letter dated October 29,2012 (ADAMS Accession No. ML 12305A421), Southern Nuclear Operating Company, Inc., the licensee, proposed an alternative (VEGP-ISI-ALT-08, Version 1.0) to Appendix IX of Section XI of the American Society of Mechanical Engineer's Boiler and Pressure Vessel (ASME) Code to allow installation of a mechanical clamp on a non-pressure boundary leak from a Class 1 Chemical and Volume Control valve 1-1208-U4-A 11. The licensee proposes this alternative during the current 2012 operating cycle at the Vogtle Electric Generating Plant, Unit 1 (VEGP-1 ). The licensee states that the mechanical clamp will only be in place until the 1 R18 outage in the spring of 2014 or until an outage of sufficient duration to allow VEGP-1 to either a permanent repair to the affected valve or replace the valve. The licensee also information on the hardship involved with performing a plant shutdown and cooldown to Mode which the licensee assessed as an option. Therefore the licensee requested authorization their proposed alternative under the requirements of Title 10 of the Code of Regulations, Part 50 (10 CFR 50) On November 1, 2012, pursuant to 10 CFR 50.55a(a)(3)(ii)), the NRC staff verbally the use of the Alternative VEGP-ISI-AL T-08, Version 1.0 (ADAMS Accession ML 12307 A411). This safety evaluation documents the technical basis of the 2.0 REGULATORY EVALUATION In this relief request the licensee requests authorization of an alternative to the requirements ASME Code,Section XI, Appendix IX pursuant to 10 CFR 50.55a(a)(3)(ii).
-Section 50.55a(g)(4) of 10 CFR, states that ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that lSI of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a{b) twelve months prior to the start of the 120-month interval, subject to the conditions listed therein. Section 50.55a(a){3) states, in part, that alternatives to the requirements of paragraph (g) of 10 CFR 50.55a may be used, when authorized by the NRC, if the licensee demonstrates (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Based on the above analYSiS, the staff finds that regulatory authority to authorize an alternative to the ASME Code requirement, as requested by the licensee, exists. 3.0 TECHNICAL EVALUATION 3.1 Applicable Code Edition and Addenda The applicable ASME Code,Section XI of record for the third 10-year lSI interval at VEGP-1 is the 2001 Edition through 2003 Addenda. 3.2 Reason for Request On October 7,2012, while performing the VEGP-1 Class 1 leakage test during start-up from the 1 R 17 refueling outage, a steam leak was observed on the Kerotest valve 1-1208-U4-A 11 on the 2-inch pressurizer auxiliary spray line. The steam leak emanated from a pinhole on the seal weld between the threaded connection joining the valve body and bonnet. Because the leakage was occurring at the seal weld, it was determined that the leakage was operational leakage and not reactor coolant pressure boundary leakage. SNC realized that actions would need to be taken to address the leakage. In order to stop steam from escaping through the pinhole in the seal weld a mechanical clamp with sealant was installed on October 13, 2012. Subsequently, steam leakage was re-identified on October 22, 2012. Discussions with the vendor determined that the most likely cause of the recurrence of the leakage was that the sealant had been injected at a temperature lower than that required to ensure proper curing of the material. Replacement of the clamp with a similar clamp and reinjection of the sealant is desired to prevent leakage until a permanent solution can be implemented. 3.3 Licensee's Proposed Alternative Section XI, Appendix IX provides rules for the installation of mechanical clamps on Class 2 and 3 pressure boundary leakage. The licensee proposed to use the rules of Appendix IX as guidance for installation of a mechanical clamp on the Class 1 non-pressure boundary leakage. The replacement clamp is the same design as the original clamp except with a relocated sealant injection port. The clamp and the sealant will encapSUlate the leak and will replace the seal
-weld's function. In lieu of the Appendix IX, Article IX-6000 required ongoing volumetric examination to monitor adjacent piping throughout the operating cycle the licensee proposed ongoing remote video camera observations and VT-2 examinations for leakage. 3.4 NRC Staff's Evaluation The staff evaluated the technical aspects of proposed Alternative VEGP-ISI-AL T -08, Version 1.0 against the criteria contained in 10 CFR 50.55a(3)(ii), the existence of a hardship or unusual difficulty without a compensating increase in quality or safety. The staff finds the first criterion, hardship or unusual difficulty, to be met if the licensee can demonstrate the requirement would necessitate things such as a need to enter multiple Technical Specification action statements, radiation ALARA concerns, hardware changes, or creating significant hazards to plant equipment or personnel, etc. The staff finds that the second criterion can be met if the proposed alternative provides reasonable assurance of structural integrity and leak tightness of the subject components. Without the proposed alternative, the licensee stated that in order to stop the leakage they would need to return the plant to Mode 5. The licensee stated the activities associated with the shutdown and startup processes would cause an additional estimated radiation dose of approximately 400-500 mREM. The licensee also cited the inherent risk associated with a shutdown transient and the extra cycles of thermal and pressure stresses for plant components. The unit startup and shutdown activities also present otherwise unnecessary challenges to personnel safety_ The staff finds the radiological dose and risk associated with these startup and shutdown evolutions, to be significantly larger than that expected to be associated with the installation of the mechanical clamping device to resolve the non-pressure boundary leakage concern associated with valve 1-1208-U4-A 11. Therefore the staff finds the licensee has identified sufficient hardship under 10 CFR 50.55a(a)(3)(ii). The licensee proposed to install a mechanical clamp at the degraded body to bonnet seal weld on valve 1-1208-U4-A11 to encapsulate the steam leak. The mechanical clamp is designed using Appendix IX of the ASIVIE Code,Section XI, as guidance with two exceptions, use of the device on a Class 1 valve under Article IX-1000(c)(1) and monitoring requirements under Article IX-6000(a). The staff reviewed the licensee's Minor Design Change 439341 and its associated worksheets, and found the licensee's design meets the requirements of Appendix IX in that all of the calculated stresses were below the code allowable stresses. The licensee had a piping analysis done to demonstrate that the piping system would continue to operate safely with the additional weight of a clamp on Valve 1-1208-U4-A 11. The licensee performed calculation X4CPS0351 which concluded the new loading conditions are still acceptable and there is adequate inherent reserve margin to accommodate the increased loads from the clamp. Therefore, the staff finds the licensee's design will provide reasonable assurance of structural integrity. To support the leakage integrity of the degraded seal weld, the licensee proposed to inject a sealant into the mechanical clamp enclosure to minimize the leakage. The licensee stated that the sealant is approved for use on a Class 1 system. The staff finds that the use of a sealant that has low concentration of halogens along with the temporary nature of the application will limit the potential for stress corrosion cracking of the stainless steel piping and valve, and is therefore acceptable in this time limited application.
-The licensee proposed not to perform ultrasonic examination of the clamp area in accordance with Article IX-6000(a). In this specific case, the NRC staff finds this deviation acceptable based on the configuration of the valve and the clamp installation. Due to the temporary nature of this application and its conservative design, the staff finds the required ultrasonic examination is not necessary as any potential degradation mechanism should not affect the structural integrity of the system and clamping device. In addition, the licensee has committed to perform visual monitoring of the valve and the temporary clamp for leakage on a daily basis for seven days. If after the initial seven days no leakage is observed, a monitoring schedule of weekly remote observations along with monthly VT-2 visual examinations will be implemented to ensure the structural and leakage integrity of the temporary repair. On the basis of the above evaluation, the NRC staff finds that the proposed alternative provide reasonable assurance that the structural integrity and leakage integrity of the seal weld on valve 1-1208-U4-A 11 will be maintained until the next refueling Therefore, given the hardship presented by the licensee, the temporary nature of the proposed alternative, and the staffs review of the design of the mechanical clamping device, the NRC staff concludes that the licensee has provided sufficient technical basis to find that compliance with the limitation of Appendix IX Article XI-1000(c)(1) and required exams of Article IX-6000(a) would cause an unnecessary hardship without a compensating increase in the level of quality and safety 4.0 CONCLUSIONS As set forth above, the NRC staff determines that the proposed alternative provides reasonable assurance of structural integrity and leak tightness of the subject components and that complying with the specified requirement would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR SO.SSa(a)(3)(ii), and is in compliance with requirements of the ASME Code,Section XI for which relief was not requested. Therefore, in accordance with 10 CFR SO.SSa(a)(3)(ii) the NRC authorizes use of the licensee's proposed alternative, VEGP-ISI-AL 08, Version 1.0, at Vogtle Electric Generating Plant, Unit 1, until the 1 R 18 refueling outage in the spring of 2014. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. Principal Contributor: Keith M. Hoffman Date: February 7,2013 C. Pierce -2 All other requirements in ASME Code,Section XI, and 10 CFR 50.55a for which relief was not specifically requested and approved in this RR remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. Sincerely, IRA! Robert Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-424 Enclosure: Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-1 R/F RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsNrrDeEpnb (TLupold) RidsNrrLASFigueroa Resource RidsRgn2MailCenterResource RidsNrrPMVogtle Resource RidsNrrDirsStsb Resource RidsAcrsAcnw_MailCTR Resource, VMcree, RA R-II KHoffman, NRR ADAMS Accession No ML 13032A 106
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