Letter Sequence Request |
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EPID:L-2023-LLR-0018, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI (Open) |
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Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-24-0015, Submittal of 2023 Sea Turtle Annual Report2024-01-10010 January 2024 Submittal of 2023 Sea Turtle Annual Report RA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024 Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval RA-24-0006, 10 CFR 50.54(q) Evaluation2024-01-0404 January 2024 10 CFR 50.54(q) Evaluation RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0320, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2023-12-14014 December 2023 Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023 Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency RA-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report RA-23-0304, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)2023-11-14014 November 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0) RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0275, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-10-12012 October 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0268, Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan2023-09-29029 September 2023 Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan RA-23-0234, Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS)2023-09-28028 September 2023 Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS) RA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2023-09-21021 September 2023 Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0228, Registration for Use of General License Spent Fuel Cask Number 1752023-09-14014 September 2023 Registration for Use of General License Spent Fuel Cask Number 175 RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0215, Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks2023-08-28028 August 2023 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks RA-23-0223, Registration for Use of General License Spent Fuel Cask Numbers 173 and 1742023-08-23023 August 2023 Registration for Use of General License Spent Fuel Cask Numbers 173 and 174 RA-23-0222, On-Shift Staffing Analysis (Ossa), Revision 12023-08-23023 August 2023 On-Shift Staffing Analysis (Ossa), Revision 1 RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0199, Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2023-08-18018 August 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-23-0211, Reply to a Notice of Violation (NOV) 05000270/2023010-022023-08-17017 August 2023 Reply to a Notice of Violation (NOV) 05000270/2023010-02 RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0195, Notice of Intentions Regarding Apparent Violation Response; (EA-23-060)2023-07-20020 July 2023 Notice of Intentions Regarding Apparent Violation Response; (EA-23-060) RA-23-0186, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)2023-07-18018 July 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3) RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0184, Registration for Use of General License Spent Fuel Cask Numbers 171 and 1722023-07-10010 July 2023 Registration for Use of General License Spent Fuel Cask Numbers 171 and 172 RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record RA-23-0045, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 262023-06-28028 June 2023 Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26 RA-23-0146, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-06-20020 June 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications RA-23-0145, Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks2023-06-15015 June 2023 Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0139, Registration for Use of General License Spent Fuel Casks2023-06-0606 June 2023 Registration for Use of General License Spent Fuel Casks RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations 2024-02-05
[Table view] Category:Request for Code Relief or Alternative
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 RA-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record RA-23-0018, Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 12023-05-0404 May 2023 Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1 RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0174, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems.2022-07-27027 July 2022 Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. ML22019A1352022-01-21021 January 2022 Proposed Alternative to Implement ASME Code Case OMN-24 RA-20-0329, Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers2021-09-0707 September 2021 Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers RA-21-0169, Relief Requests for Inservice Testing Plan - Sixth Interval2021-07-29029 July 2021 Relief Requests for Inservice Testing Plan - Sixth Interval RA-21-0152, Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)2021-07-0101 July 2021 Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv) RA-21-0100, Proposed Alternative to Use ASME Code Case N-885 for Catawba Nuclear Station Unit 22021-06-0808 June 2021 Proposed Alternative to Use ASME Code Case N-885 for Catawba Nuclear Station Unit 2 RA-19-0418, Proposed Alternative for Inservice Inspection of Containment Post-Tensioning System Components2021-05-0606 May 2021 Proposed Alternative for Inservice Inspection of Containment Post-Tensioning System Components RA-21-0095, Relief Requests for Inservice Testing Program Plan - Sixth Ten-Year Interval2021-03-29029 March 2021 Relief Requests for Inservice Testing Program Plan - Sixth Ten-Year Interval RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-20-0328, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals2021-01-19019 January 2021 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals RA-19-0352, Duke Energy Carolinas, LLC - Relief Request for Alternative for Reactor Vessel Closure Stud Examinations2020-12-0101 December 2020 Duke Energy Carolinas, LLC - Relief Request for Alternative for Reactor Vessel Closure Stud Examinations 2024-01-10
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Text
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( ~ DUKE Nldearfi'eglllalolyAf~ P:alcy&
Eil~Mi:y~iess ENERGY@ l)JJre Enelgy 13.225 tta,en; FenyRd., tl>G011E fu!l"..mille, 1\C 20076 643-951-1329 i<e\iJI,. sM,;e-e11£NYCOm Serial: RA-23-0001 10 CFR 50.55a February 2, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325, 50-324 / Renewed License Nos. DPR-71 And DPR-62 Catawba Nuclear Station, Unit Nos. 1 and 2 Docket Nos. 50-413, 50-414 / Renewed License Nos. NPF-35 and NPF-52 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63 McGuire Nuclear Station, Unit Nos. 1 and 2 Docket Nos. 50-369, 50-370 / Renewed License Nos. NPF-9 and NPF-17 Oconee Nuclear Station, Unit Nos. 1, 2, and 3 Docket Nos. 50-269, 50-270, and 50-287 / Renewed License Nos. DPR-38, DPR-47, and DPR-55 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23
SUBJECT:
Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code,Section XI
REFERENCES:
- 1. NRC Regulatory Issue Summary 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI, dated July 28, 2004.
In accordance with 10 CFR 50.55a, Codes and Standards, paragraph (g)(4)(iv), and the guidance provided in the referenced document, Duke Energy Carolinas, LLC and Duke Energy Progress, LLC (hereafter referred to collectively as Duke Energy) request U.S Nuclear Regulatory Commission (NRC) approval to use a specific provision of a later edition of the American Society of Mechanical (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the units identified above. Specifically, Duke Energy is seeking approval to use Paragraph IWA-6230 of the 2019 edition of the ASME Code,Section XI which provides 120 days to submit inservice inspection (ISI) summary reports to the NRC. The request is provided as the Attachment to this submittal.
RA-23-0001 Page 2 Duke Energy requests approval of this request by May 1, 2023 to support post-outage work for the Spring, 2023 plant outages. There are no regulatory commitments in this letter.
If you have additional questions, please contact Ryan Treadway, Director - Nuclear Fleet Licensing, at (980) 373-5873.
Kevin Ellis General Manager, Nuclear Regulatory Affairs, Policy & Emergency Preparedness
Attachment:
Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv) cc:
L. Dudes, Regional Administrator USNRC Region II G. Smith, USN RC Senior Resident Inspector - BNP D. Rivard, USNRC Senior Resident Inspector- CNS P. Boguszewski, USNRC Senior Resident Inspector- HNP C. Safouri USNRC Senior Resident Inspector- MNS J. Nadel, USNRC Senior Resident Inspector - ONS J. Zeiler, USNRC Senior Resident Inspector- RNP L. Haeg, USNRC NRR Project Manager for BNP and RNP M. Mahoney, USNRC NRR Project Manager for HNP J. Klos, USNRC NRR Project Manager for MNS S. Williams, USNRC NRR Project Manager for CNS and ONS
RA-23-0001 Attachment Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Page 1 1.0 ASME CODE COMPONENTS AFFECTED:
All pressure-retaining components described in the ASME Boiler and Pressure Vessel Code,Section XI, 2019 Edition, Article IWA-6230, Owners Activity Report, paragraph (b).
2.0 APPLICABLE CODE EDITION AND ADDENDA:
The applicable Edition and Addenda of the ASME Code,Section XI is identified in Table 1.
Table 1 ISI ASME Section XI Interval Start Plant/Unit(s) Code Interval End Date1 Interval Edition/Addenda Date Brunswick Steam Electric 2007 Edition, Through 2008 Plant Units 1 and 2 Fifth Addendum 05/11/2018 05/10/2028 Catawba Nuclear Station 2007 Edition, Through 2008 12/06/2024 (Unit 1)
Units 1 and 2 Fourth Addendum 08/19/2015 02/24/2026 (Unit 2)
H.B. Robinson Steam Electric Plant Unit 2 Sixth 2017 Edition 02/20/2023 02/19/2033 2007 Edition, Through 2008 McGuire Nuclear Unit 1 Fifth Addendum 12/01/2021 11/30/2031 2007 Edition, Through 2008 McGuire Nuclear Unit 2 Fourth Addendum 07/15/2014 02/29/2024 Oconee Nuclear Station 2007 Edition, Through 2008 Units 1, 2, and 3 Fifth Addendum 07/15/2014 07/15/2024 Shearon Harris Nuclear 2007 Edition, Through 2008 Power Plant Unit 1 Fourth Addendum 09/09/2017 09/08/2027 Note 1: Date listed is the planned interval end date. In accordance with IWA-2430(c)(1), this end date may be extended or shortened as necessary.
3.0 PROPOSED SUBSEQUENT CODE EDITION AND ADDENDA:
Duke Energy proposes to utilize portions of the ASME Section XI, 2019 Edition in lieu of the 2007 Edition up to and including the 2008 Addenda and 2017 Edition. Specifically, Duke Energy proposes to utilize IWA-6230(b) which provides an extension of the 90 calendar-day submittal requirement of the Owners Activity Report to 120 calendar-days following completion of a refueling outage.
Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Page 2 4.0 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. "
10 CFR 50.55a(b)(2) incorporates by reference Section XI, Division 1, of the ASME B&PV Code 2019 Edition as approved in Reference 2. Duke Energy is requesting use of IWA-6230(b) of the 2019 Edition of ASME Section XI to utilize an extension of the 90 calendar-day submittal requirement of the Owners Activity Report to 120 calendar-days. There are no related requirements or applicable conditions associated with this subparagraph, IWA-6230(b).
5.0 DURATION OF PROPOSED ALTERNATIVE:
This alternative is proposed for the remainder of the current inservice inspection intervals listed in Table 1.
6.0 PRECEDENTS
None.
7.0 REFERENCES
- 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," dated July 28, 2004.
- 2. Federal Register, 87 FR 65128, dated October 27, 2022.