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-24-0276, EN 57402 - Catawba Nuclear Station Interim Part 21 Report2024-10-28028 October 2024 EN 57402 - Catawba Nuclear Station Interim Part 21 Report RA-24-0191, Submittal of Updated Final Safety Analysis Report (Revision 24), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of2024-10-22022 October 2024 Submittal of Updated Final Safety Analysis Report (Revision 24), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of RA-24-0259, Transmittal of Core Operating Limits Reports (COLR) for Oconee Nuclear Station (ONS) Unit 1 Cycle 33 (Revision 2), ONS Unit 2 Cycle 32 (Revision 1 and ONS Unit 3 Cycle 33 (Revisions O and 1)2024-10-16016 October 2024 Transmittal of Core Operating Limits Reports (COLR) for Oconee Nuclear Station (ONS) Unit 1 Cycle 33 (Revision 2), ONS Unit 2 Cycle 32 (Revision 1 and ONS Unit 3 Cycle 33 (Revisions O and 1) RA-24-0254, Resubmittal of Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components2024-10-14014 October 2024 Resubmittal of Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components RA-24-0247, Core Operating Limits Report (COLR) for Unit 1 Cycle 29 Reload Core2024-10-0707 October 2024 Core Operating Limits Report (COLR) for Unit 1 Cycle 29 Reload Core RA-24-0258, Reply to a Notice of Violation; EA-24-0492024-10-0707 October 2024 Reply to a Notice of Violation; EA-24-049 RA-24-0244, Snubber Program Plan Revision, AD-EG-ONS-1618, Oconee Nuclear Station Snubber Program Plan2024-09-30030 September 2024 Snubber Program Plan Revision, AD-EG-ONS-1618, Oconee Nuclear Station Snubber Program Plan RA-24-0229, Transmittal of Refuel 32 (O3R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2024-09-23023 September 2024 Transmittal of Refuel 32 (O3R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-24-0217, End of Cycle 25 (H1 R25) Inservice Inspection Program Owners Activity Report2024-09-0909 September 2024 End of Cycle 25 (H1 R25) Inservice Inspection Program Owners Activity Report RA-24-0180, Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change2024-08-29029 August 2024 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change RA-24-0193, Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-08-28028 August 2024 Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-24-0185, Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-16182024-08-28028 August 2024 Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-1618 RA-24-0215, Registration for Use of General License Spent Fuel Cask Numbers 177 and 1782024-08-15015 August 2024 Registration for Use of General License Spent Fuel Cask Numbers 177 and 178 RA-24-0208, Refuel 26 (C2R26) Inservice Inspection (ISI) Report2024-08-12012 August 2024 Refuel 26 (C2R26) Inservice Inspection (ISI) Report RA-24-0209, Regulatory Conference, Additional Supporting Information2024-08-0606 August 2024 Regulatory Conference, Additional Supporting Information RA-24-0203, Regulatory Conference Supporting Information2024-07-31031 July 2024 Regulatory Conference Supporting Information RA-24-0197, Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition2024-07-31031 July 2024 Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition RA-24-0092, Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis2024-07-29029 July 2024 Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis RA-24-0165, Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations2024-07-26026 July 2024 Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations RA-24-0178, Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks2024-07-10010 July 2024 Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks RA-24-0172, Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2024-07-0808 July 2024 Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-24-0137, Relief Requests for Inservice Testing Plan – Fifth Interval2024-07-0101 July 2024 Relief Requests for Inservice Testing Plan – Fifth Interval RA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld2024-06-28028 June 2024 Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld RA-24-0166, Revision to Emergency Plan Implementing Procedure2024-06-27027 June 2024 Revision to Emergency Plan Implementing Procedure RA-24-0163, Registration for Use of General License Spent Fuel Casks2024-06-19019 June 2024 Registration for Use of General License Spent Fuel Casks RA-24-0164, Inservicee Inspection Program Owners Activity Report Refueling Outage 252024-06-19019 June 2024 Inservicee Inspection Program Owners Activity Report Refueling Outage 25 RA-23-0245, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2024-06-18018 June 2024 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-24-0154, Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-06-0707 June 2024 Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-24-0136, Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 52024-05-24024 May 2024 Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 5 RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable RA-24-0152, Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2024-05-22022 May 2024 Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-24-0132, Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Steam Generator Tube Inspection Report2024-05-14014 May 2024 Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Steam Generator Tube Inspection Report RA-24-0110, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical.2024-05-0909 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical. RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 20232024-04-29029 April 2024 Duke Energy - Annual Radioactive Effluent Release Report - 2023 RA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-24-0096, Instrumentation and Control Safety Systems NRC Review of Framatome TXS-Compact Topical Report2024-04-24024 April 2024 Instrumentation and Control Safety Systems NRC Review of Framatome TXS-Compact Topical Report RA-24-0031, Annual Radiological Environmental Operating Report - 20232024-04-23023 April 2024 Annual Radiological Environmental Operating Report - 2023 RA-24-0103, Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval2024-04-19019 April 2024 Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval RA-24-0094, Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Traini2024-04-17017 April 2024 Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Training RA-24-0117, Cycle 26 Core Operating Limits Report, Revision O2024-04-16016 April 2024 Cycle 26 Core Operating Limits Report, Revision O RA-24-0101, (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2024-04-16016 April 2024 (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-24-0099, Reactor and Senior Reactor Operator Initial Examination Outlines2024-04-10010 April 2024 Reactor and Senior Reactor Operator Initial Examination Outlines RA-24-0106, Annual Environmental (Non-Radiological) Operating Report2024-04-0909 April 2024 Annual Environmental (Non-Radiological) Operating Report RA-24-0097, Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-04-0303 April 2024 Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations RA-24-0085, Onsite Property Insurance Coverage2024-04-0101 April 2024 Onsite Property Insurance Coverage RA-24-0086, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-04-0101 April 2024 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-24-0080, Duke Energy Progress, LLC - Request for Review of Master Curve Methodology to Determine the Fracture Toughness-based Reference Temperature Topical Reports2024-03-28028 March 2024 Duke Energy Progress, LLC - Request for Review of Master Curve Methodology to Determine the Fracture Toughness-based Reference Temperature Topical Reports RA-24-0073, Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2024-03-21021 March 2024 Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-24-0082, Core Operating Limits Report (COLR) for Unit 2 Cycle 27 Reload Core2024-03-21021 March 2024 Core Operating Limits Report (COLR) for Unit 2 Cycle 27 Reload Core 2024-09-09
[Table view] Category:Request for Code Relief or Alternative
MONTHYEARRA-24-0193, Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-08-28028 August 2024 Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-24-0137, Relief Requests for Inservice Testing Plan – Fifth Interval2024-07-0101 July 2024 Relief Requests for Inservice Testing Plan – Fifth Interval ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 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) 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 2024-08-28
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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 a nd 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 a nd 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, USN RC Senior Resident Inspector -CNS P.Boguszewski, USNRC Senior Resident Inspector-HNP C.Safouri USNRC Senior Resident Inspector-MNS J.Nadel, USN RC Senior Resident Inspector -ONS J.Zeiler, USN RC Senior Resident Inspector -RNP L.Haeg, USNRC NRR Project Manager for BNP and RNP M.Mahoney, USN RC 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
Plant/Unit(s) ISI ASMECode Section XI Interval Start Interval Edition/Addenda Date Interval End Date1
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)
Electric PlantH.B. Robinson Steam 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.