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Category:Codes and Standards
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. 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 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 NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal 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 NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection 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 NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding 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) 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) NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 2024-01-30
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Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 tel April 12, 2023 Docket Nos.: 50-321 50-348 50-424 NL-23-0019 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Southern Nuclear Operating Company Hatch Nuclear Plant Units 1&2 Farley Nuclear Plant Units 1&2 Vogtle Electric Generating Plant Units 1&2 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code,Section XI Ladies and Gentlemen:
In accordance with 10 CFR 50.55a, Codes and standards, paragraph (g)(4)(iv) and the guidance provided in Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI, Southern Nuclear Operating Company (SNC) hereby requests NRC approval to use a specific provision of a later edition of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel (B&PV) Code,Section XI, incorporated in 10 CFR 50.55a(a)(1)(ii),
for Edwin I. Hatch Nuclear Plant (HNP) Units 1 and 2; Joseph M. Farley Nuclear Plant (FNP)
Units 1 and 2; and Vogtle Electric Generating Plant (VEGP) Units 1 and 2. Specifically, SNC requests approval to use IWA-6211(a) through IWA-6211(e) (Owners Responsibilities),
IWA-6220 (Owners Repair/Replacement Certification Record), IWA-6230 (Owners Activity Report), and Mandatory Appendix II (Owners Record and Report) of the 2019 Edition of the ASME B&PV Code,Section XI for post outage reporting requirements.
The enclosure to this letter provides the request to use portions of a later edition of the ASME B&PV Code,Section XI.
SNC requests approval of this request by August 12, 2023 to allow for additional time to submit the Owners Activity Report (OAR) following SNCs Fall 2023 outages.
This letter contains no regulatory commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
U. S. Nuclear Regulatory Commission NL-23-0019 Page 2 of 2 Respectfully submitted, R. Keith Brown Director, Regulatory Affairs Southern Nuclear Operating Company RKB/agq/cbg
Enclosure:
Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv), GEN-ISI-ALT-2023-01 cc: Regional Administrator, Region ll NRR Project Manager - Hatch 1&2, Farley 1&2, and Vogtle 1&2 Senior Resident Inspector - Hatch 1&2, Farley 1&2, and Vogtle 1&2 Director, Alabama Office of Radiation Control State of Georgia Environmental Protection Division R-Type: CGA02.001
Southern Nuclear Operating Company Hatch Nuclear Plant Units 1&2 Farley Nuclear Plant Units 1&2 Vogtle Electric Generating Plant Units 1&2 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code,Section XI Enclosure to NL-23-0019 Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv), GEN-ISI-ALT-2023-01
Enclosure to NL-23-0019 Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv),
GEN-ISI-ALT-2023-01 In accordance with 10 CFR 50.55a, Codes and standards, paragraph (g)(4)(iv) and the guidance provided in Reference 1, Southern Nuclear Operating Company (SNC) requests Nuclear Regulatory Commission (NRC) approval to use specific provisions of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
Code,Section XI, for Farley Nuclear Plant Units 1 and 2, Hatch Nuclear Plant Units 1 and 2, and Vogtle Electric Generating Plant Units 1 and 2. Specifically, SNC requests approval to use IWA-6211(a) through IWA-6211(e) (Owners Responsibilities), IWA-6220 (Owners Repair/Replacement Certification Record), IWA-6230 (Owners Activity Report), and Mandatory Appendix II (Owners Record and Report) of the 2019 Edition of the ASME B&PV Code,Section XI for post outage reporting requirements.
- 1. Component(s) Affected:
All Class 1, 2, 3, MC, and CC items.
- 2. Requested Date for Approval:
Approval is requested by August 12, 2023 to allow for additional time to submit the Owners Activity Report (OAR) following SNCs Fall 2023 outages.
3. Applicable Code Edition and Addenda
ISI INTERVAL INTERVAL PLANT EDITION INTERVAL START SCHEDULED END Farley Nuclear Plant, 5 2007 Edition, through 12/01/2017 11/30/2027 Units 1 and 2 2008 Addenda Hatch Nuclear Plant, 5 2007 Edition, through 01/01/2016 12/31/2025 Units 1 and 2 2008 Addenda Vogtle Electric 4 2007 Edition, through 05/31/2017 5/30/2027 Generating Plant, 2008 Addenda Units 1 and 2
- 4. Proposed Subsequent Code Edition and Addenda (or Portion):
All SNC plants listed above comply with the requirements of IWA-6000, Records and Reports. However, SNC implements Code Case N-532-5, Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission. N-532-5 allows for the use of an Owners Activity Report, Form OAR-1, in lieu of the Inservice Inspection Summary Report. These requirements are based on the ASME Section XI Code of Record which, at present, is the 2007 Edition through the 2008 Addenda.
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Enclosure to NL-23-0019 Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv),
GEN-ISI-ALT-2023-01 Pursuant to 10 CFR 50.55a(g)(4)(iv), SNC requests permission to use IWA-6211(a) through IWA-6211(e) (Owners Responsibilities), IWA-6220 ("Owners Repair/Replacement Certification Record"), IWA-6230 ("Owners Activity Report"), and Mandatory Appendix II
("Owners Record and Report") of the 2019 Edition of the ASME B&PV Code,Section XI for post outage reporting requirements. The 2019 Edition of the ASME B&PV Code incorporates the alternate repair/replacement activity documentation and Inservice Inspection summary report preparation and submission requirements of Code Case N-532-5 and extends the submittal time of the OAR-1 outage summary report from 90 days to 120 days.
- 5. Related Requirements:
10 CFR 50.55a(g)(4)(iv) states:
Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.
Section IWA-6211(a) through IWA-6211(e), IWA-6220, IWA-6230, and Mandatory Appendix II of the 2019 Edition of ASME Section XI include all related requirements in this request.
- 6. Duration of Proposed Request:
The duration of this request will continue for each sites Inservice Inspection interval as provided in Section 3.
- 7.
References:
- 1. NRC Regulatory Issue Summary 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM and Section XI, dated July 28, 2004.
- 2. Federal Register, 87 FR 65128, dated October 27, 2022.
- 8. Precedent:
None cited.
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