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EPID:L-2023-LLR-0007, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) (Open) |
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Category:Code Relief or Alternative
MONTHYEARML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds ML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 ML23130A3872023-05-18018 May 2023 Request 1-RR-5-15 and 2-RR-5-15 to Use Later Edition of ASME Section XI Code for Performance of Repair/Replacement Activities ML22270A3252022-09-30030 September 2022 (Prairie Island), Unit 2 - Authorization and Safety Evaluation for Alternative Request No. RR-08 ML20276A0032020-10-0202 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML19282A5412019-11-0505 November 2019 Relief from the Requirements of the ASME Code L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 ML19046A1662019-02-25025 February 2019 Relief from the Requirements of the ASME Code ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML16246A2002016-10-0404 October 2016 Request for Relief 1RR-4-11 and 2-RR-4-11 Associated with Certain Inservice Inspection of Component Welds for the Fourth 10-Year Interval ML15196A2132015-08-17017 August 2015 Requests 1-RR-4-9 and 2-RR-4-9 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program ML15196A2272015-08-12012 August 2015 Requests 1-RR-5-3 and 2-RR-5-3 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A2212015-08-12012 August 2015 Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15079A0032015-05-0404 May 2015 Relief Requests 1-RR-5-5 and 2-RR-5-5 for Fifth 10-Year Interval for the Inservice Inspection Program ML15079A0022015-05-0404 May 2015 Relief Requests 1-RR-5-2 and 2-RR-5-2 for Fifth 10-Year Interval for the Inservice Inspection Program ML14329A1852014-12-0505 December 2014 Relief Requests for Fifth 10-Year Inservice Testing Program Interval (Tac Nos. MF3928 and MF3929) L-PI-14-117, Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929)2014-11-24024 November 2014 Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929) ML0807905632008-05-0909 May 2008 Relief Request 1-RR-4-6 for Piping Weld Examination Coverage for the Fourth Inservice Inspection Interval ML0617200152006-07-0303 July 2006 Relief, Evaluation of Relief Request 2-RR-4-6 for Reduced Examination Volume for Class 2 RHR Heat Exchanger Shell- to-Flange Weld ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 L-HU-05-028, ASME Section XI, ISI Request for Relief 21 & 222005-12-19019 December 2005 ASME Section XI, ISI Request for Relief 21 & 22 L-PI-05-038, Withdrawal of 4th Ten-Year Inspection Interval Lnservice Lnspection Program Relief Request No. 1-RR-4-12005-05-0505 May 2005 Withdrawal of 4th Ten-Year Inspection Interval Lnservice Lnspection Program Relief Request No. 1-RR-4-1 ML0509601872005-04-27027 April 2005 Evaluation of Relief Request Nos. 1-RR-4-2, 1-RR-4-3, 2-RR-4-3, 1-RR-4-4, and 2-RR-4-4 for the Fourth 10-Year Inservice Inspection Interval ML0507504282005-04-0707 April 2005 Evaluation of Relief Request to Use Code Case N-661. TAC MC3883 and TAC MC3884 ML0422200422004-10-18018 October 2004 Evaluation of Relief Request No. 16 for the Unit 2 3rd 10-year Interval Inservice Inspection Program ML0418902032004-07-27027 July 2004 Code Relief, Evaluation of Relief Request No. 20, Revision 1 - for the Third 10-Year Inservice Inspection Interval ML0411301922004-05-0303 May 2004 Relief, Limited Examinations Associated with the PINGP Unit 1, Third 10-year Inservice Inspection (ISI) Interval, MB7975 ML0409802342004-04-12012 April 2004 Prairie, Units 1 and 2, Relief Request Nos. 19 and 20 Associated with the 10-Year Interval Inservice Inspection Interval L-PI-04-044, Request for Relief No. 20, Revision 0, for Units 1 & 2, 3rd Ten Year Inservice Inspection Interval2004-03-30030 March 2004 Request for Relief No. 20, Revision 0, for Units 1 & 2, 3rd Ten Year Inservice Inspection Interval ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0332806022004-01-13013 January 2004 Prairie, Units 1 and 2, Relief, No. 15, Evaluation of Relief Request No. 15 for the Third 10-Year Interval Inservice Inspection Program ML0323301462003-10-0202 October 2003 Relief, Re the Fourth and Successive Inservice Inspection and Inservice Testing Program Intervals ML0321300802003-08-13013 August 2003 Relief, Re Using VT-1 Visual Examinations During Third 10-Year Interval Inservice Inspection Program ML0320506712003-07-30030 July 2003 Evaluation of Relief Request No. 18 to Perform a Visual Examination in Lieu of Volumetric Examination of Reactor Vessel Nozzle Inner Radius Sections Per Code Case N-648-1, MB8363 and MB8364 ML0316402462003-06-17017 June 2003 Relief Request, Third 10-Year Interval Inservice Inspection Program ML0232905782002-11-16016 November 2002 Request for Relief No. 9 for the Unit 2 Third 10-Year Interval Inservice Inspection Program ML0230102092002-11-0707 November 2002 Relief, Third 10-Year Interval Inservice Inspection Program ML0226202392002-10-0101 October 2002 Relief, Evaluation of Relief Request Associated with the Third 10-Year Interval Inservice Inspection Program (MB5388, 5399, 5390, & 5391) ML0212904282002-06-11011 June 2002 Relief Request, Related to the First Interval Inservice Inspection Program for Metal Containment ML0216105082002-05-31031 May 2002 Request for Relief No. 12 for the Unit 2 3rd 10-Year Interval Inservice Inspection Program 2024-04-24
[Table view] Category:Letter
MONTHYEARIR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing ML24040A1712024-02-0909 February 2024 Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software IR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 2024-08-05
[Table view] |
Text
May 18, 2023 Mr. Christopher P. Domingos Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
REQUEST 1-RR-5-15 AND 2-RR-5-15 TO USE LATER EDITION OF ASME SECTION XI CODE FOR PERFORMANCE OF REPAIR/REPLACEMENT ACTIVITIES (EPID L-2023-LLR-0007)
Dear Mr. Domingos:
By letter dated March 3, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23062A141), Northern States Power Company (NSPM or the licensee), a Minnesota corporation doing business as Xcel Energy, submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of a later edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for performance of repair/replacement activities at Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),
Applicable ISI [Inservice Inspection] Code: Use of subsequent Code editions and addenda, NSPM requested to use later code editions and addenda for ISI items subject to the conditions specified in 10 CFR 50.55a(b). The licensee requested to use Article IWA-4000 of the 2019 Edition of the ASME Code,Section XI, including all related requirements and referenced paragraphs within, for the remainder of the fifth ISI interval. The current applicable Code of Record is the 2007 Edition through 2008 Addenda. The fifth ISI interval started on December 21, 2014, and is scheduled to end on December 20, 2024.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that NSPM has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv) and is in compliance with the requirements of the ASME code,Section XI.
C. Domingos If you have any questions, please contact the Project Manager, Brent Ballard, at 301-415-0680 or by e-mail to Brent.Ballard@nrc.gov.
Sincerely, Digitally signed by Venkataiah Sreenivas Date: 2023.05.18 10:16:47
-04'00' V. Sreenivas, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE PORTION OF A LATER EDITION OF THE ASME CODE FOR REPAIR REPLACEMENT ACTIVITIES NORTHERN STATES POWER COMPANY PRARIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By letter dated March 3, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23062A141), Northern States Power Company (NSPM or the licensee) submitted a request to use a portion of a later edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection [ISI] of Nuclear Power Plant Components. As noted in Regulatory Issue Summary (RIS) 2004-12 (ML042090436), licensees seeking to use later editions and addenda of the ASME Code,Section XI, that have been incorporated by reference, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv), are required to obtain NRC approval.
Specifically, pursuant to 10 CFR 50.55a(g)(4)(iv), NSPM requested to use the 2019 Edition of the ASME Code,Section XI, for the performance of repair/replacement activities for the remainder of the fifth ISI interval for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The current applicable Code of Record (COR) is the 2007 Edition through 2008 Addenda. The sixth ISI interval for PINGP, Units 1 and 2, will start on December 21, 2024.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(g)(4)(iv), 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 10 CFR 50.55a, Documents approved for incorporation by reference, subject to the conditions listed in paragraph (b) of 10 CFR 50.55a, Use and conditions on the use of standards, and subject to U.S. Nuclear Regulatory Commission (NRC or Commission) approval. Portions of editions may be used provided that all related requirements of the respective editions are met.
Pursuant to 10 CFR 50.55a(a)(1)(ii)(C)(56), the 2019 Edition of the ASME Code,Section XI, has been incorporated by reference in paragraph (a) of section 50.55a with conditions. NRC RIS 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI, provides clarification to the requirements of 10 CFR 50.55a(g)(4)(iv).
Enclosure
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to approve the use of subsequent editions and addenda of the ASME Code as requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 The Licensees Proposed Use of Later Code Editions and Addenda The licensees COR for the fifth ISI interval is the 2007 Edition through the 2008 Addenda. In its March 23, 2023, letter, the license requested to use Article IWA-4000 of the 2019 Edition of ASME Code,Section XI, including all related requirements and referenced paragraphs within.
The requirements of Article IWA-4000 pertain only to repair/replacement activities. Thus, all ISI requirements of the 2007 Edition through the 2008 Addenda would still apply.
3.2 NRC Staff Evaluation Based on the requirements in 10 CFR 50.55a(g)(4)(iv), the NRC staff considered the following criteria in their review of the licensees application:
- 1. The proposed edition of the ASME Code is incorporated by reference in 10 CFR 50.55a(a).
- 2. The proposed edition of the ASME Code is subject to the conditions listed in 10 CFR 50.55a(b).
- 3. The licensee shall request Commission approval to use the proposed edition of the ASME Code.
- 4. If only portions of editions are to be used, all related requirements of the respective editions must be met.
In evaluating the first criterion, the NRC staff notes that 10 CFR 50.55a(a) incorporates by reference the ASME Code,Section XI, 2019 Edition, as published in the Federal Register on October 27, 2022 (87 FR 65148), becoming effective November 28, 2022. Therefore, the NRC staff finds that the first criterion has been satisfied.
In evaluating the second criterion, the NRC staff observes that the NSPM letter does not propose any alternatives to the provisions of the 2019 Edition of ASME Code,Section XI, IWA-4000, as incorporated by reference. Use of those portions of Section XI would, therefore, be subject to the conditions listed in 10 CFR 50.55a(b). With this understanding, the NRC staff finds that the second criterion has been satisfied.
In evaluating the third criterion, the NRC staff notes that NSPMs March 3, 2023, submittal constitutes a request to the Commission for approval to use a portion of a subsequent edition of the ASME Code,Section XI. Therefore, the NRC staff finds that the third criterion has been satisfied.
In evaluating the fourth criterion, the NRC staff observes that the NSPM letter commits to observing all related requirements and reference paragraphs in IWA-4000 of 2019 Edition of ASME Code,Section XI, as incorporated by reference. Therefore, the NRC staff finds that the fourth criterion has been satisfied.
Based on the above, the NRC staff finds that NSPM has satisfied each of the four criteria of 10 CFR 50.55a(g)(4)(iv) in its request to use a portion of ASME Code,Section XI, 2019 Edition, in lieu of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for the PINGP, Units 1 and 2, fifth interval ISI program COR. The NRC staff finds that the licensees proposal is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the use of Article IWA-4000 of the ASME Code,Section XI, 2019 Edition, for the remainder of the PINGP, Units 1 and 2, fifth ISI interval is acceptable because NSPM has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv) and is in compliance with the requirements of the ASME Code,Section XI. Therefore, the NRC staff approves the use of Article IWA-4000 of the ASME Code,Section XI, 2019 Edition, for the remainder of the fifth ISI interval at PINGP, Units 1 and 2, which is scheduled to end on December 20, 2024.
Principal Contributors: M. Benson, NRR/DNRL/NVIB M. Burton, NRR/DNRL/NPHP Date: May 18, 2023
ML23130A387 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NAME DBrockman BBallard SRohrer DATE 5/12/23 5/15/23 5/17/23 OFFICE NRR/DNRL/NVIB NRR/DNRL/NPHP NRR/DORL/LPL3/BC NAME ABuford MMitchell VSreenivas DATE 5/11/2023 5/11/23 5/18/23