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Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML21259A0992021-11-0404 November 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21214A2222021-08-10010 August 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21209A9962021-08-0202 August 2021 Proposed Alternative Request IST-RR-8 Related to the Inservice Testing Program ML21202A3982021-07-27027 July 2021 Relief Request Proposed Alternatives to American Society of Mechanical Engineers Operation and Maintenance Code Isolation Valve Seal Water System ML21068A4172021-03-17017 March 2021 Summary of Meeting with Duke Energy Progress, LLC, Regarding a Proposed Relief Request Concerning Containment Inspections of Liners and Moisture Barriers for the H. B. Robinson Steam Electric Plant, Unit 2 ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20090F8932020-04-29029 April 2020 Relief Request RA-19-0138 Regarding Proposed Alternative to ASME Code, Section XI Volumetric Examination Frequency Requirements RA-19-0428, Relief Request RA-19-0428 for One-Time Pressure Relief Valve Test Frequency Extension2020-02-0404 February 2020 Relief Request RA-19-0428 for One-Time Pressure Relief Valve Test Frequency Extension ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads RNP-RA/13-0018, Relief Request (RR)-8 from Fifth Ten-Year Inservice Inspection Program Plan2013-03-13013 March 2013 Relief Request (RR)-8 from Fifth Ten-Year Inservice Inspection Program Plan ML12314A2882012-12-11011 December 2012 Relief Request-2 for the Fifth 10-Year Interval Inservice Testing Program Plan RNP-RA/12-0113, Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-Year Inservice Inspection...2012-10-25025 October 2012 Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-Year Inservice Inspection... RNP-RA/12-0101, Relief Request (RR)-7 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-year Inservice Inspection Program Plan2012-10-0505 October 2012 Relief Request (RR)-7 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-year Inservice Inspection Program Plan ML12262A3622012-10-0101 October 2012 Relief Request No. 2 for the Fifth 10-Year Interval Inservice Inspection Program Plan RNP-RA/12-0079, Revised Response to NRC Request for Additional Information Related to Relief Request (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan2012-08-0909 August 2012 Revised Response to NRC Request for Additional Information Related to Relief Request (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan ML12181A1262012-07-13013 July 2012 Relief Request-4 for the Fifth 10-Year Interval Inservice Inspection Program Plan ML12174A0182012-07-13013 July 2012 Relief Request-1 for the Fifth 10-Year Interval Inservice Testing Program ML12174A0102012-07-13013 July 2012 Relief Request -3 for Fifth 10-Year Interval Inservice Testing Program Plan ML12167A2152012-07-13013 July 2012 Relief Request (RR)-6 for the Fifth 10-Year Interval Inservice Inspection Program Plan ML12115A0692012-05-0404 May 2012 Request for Additional Information Related to Relief Requests RR-5 and RR-6 for the Fifth Ten-Year Interval Inservice Inspection Program Plant RNP-RA/08-0129, Request for Extension for Implement Ion of License Amendment Related to Control Room Habitability2009-01-0707 January 2009 Request for Extension for Implement Ion of License Amendment Related to Control Room Habitability ML0827302702008-10-22022 October 2008 Request for Relief from ASME Code, Section XI, Appendix Viii, Supplement 2 and Supplement 10 Weld Examination Requirements ML0427400822004-09-29029 September 2004 Third 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 34 ML0411702632004-04-21021 April 2004 Relief, ASME Code, Section XI, Appendix Viii, Supplement 10, Qualification Requirements for Inspection of Dissimilar Metal Piping Welds, for the Fourth 10-year Inservice Inspection (ISI) Interval, MC1639 RNP-RA/03-0125, Inservice Testing Program, Relief Request IST-RR-8 for Comprehensive Tests2003-10-0707 October 2003 Inservice Testing Program, Relief Request IST-RR-8 for Comprehensive Tests ML0233101712002-11-26026 November 2002 Relief, Examination of Control Rod Drive Mechanism Housing Seal Weld 2023-09-25
[Table view] Category:Letter
MONTHYEARIR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000261/20240112024-06-0303 June 2024 Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping IR 05000261/20240012024-05-0909 May 2024 Integrated Inspection Report 05000261/2024001 IR 05000261/20240102024-04-30030 April 2024 Biennial Problem Identification and Resolution Inspection Report 05000261/2024010 IR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 IR 05000261/20220022022-08-0909 August 2022 Integrated Inspection Report 05000261 2022002, 07200060 2022001 and Exercise of Enforcement Discretion ML22213A0682022-08-0505 August 2022 Request for Withholding Information from Public Disclosure for H. B. Robinson Steam Electric Plant, Unit 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves IR 05000261/20220112022-07-19019 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000261/2022011 ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 2024-08-01
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML21259A0992021-11-0404 November 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21242A2982021-09-21021 September 2021 Proposed Alternative to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21155A2132021-08-26026 August 2021 Plant ML21214A2222021-08-10010 August 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21209A9962021-08-0202 August 2021 Proposed Alternative Request IST-RR-8 Related to the Inservice Testing Program ML21202A3982021-07-27027 July 2021 Relief Request Proposed Alternatives to American Society of Mechanical Engineers Operation and Maintenance Code Isolation Valve Seal Water System ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20097F0882020-06-19019 June 2020 Relief Request RA-19-0106 Regarding Proposed Alternative to ASME Code Case N-729-4 Volumetric or Surface Examination Requirements EPID-L-2019-LLR-0065) ML20058E8992020-06-18018 June 2020 Issuance of Amendment No. 267 Regarding Change to Surveillance Requirement 3.8.2.1 ML20021A0132020-02-19019 February 2020 Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML19205A2892019-09-24024 September 2019 Issuance of Amendment No. 266 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19121A4822019-06-11011 June 2019 Staff Evaluation the 2017 Annual Report of Changes and Error Corrections Affecting the Large-Break Loss-of-Coolant Accident Analysis ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18115A1502018-05-25025 May 2018 Issuance of Amendment 258 Regarding Request to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (CAC No. MF9544; EPID L-2017-LLA-0206) ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17102A9232017-05-18018 May 2017 Nonproprietary Issuance of Amendments Revising Technical Specifications for Methodology Reports DPC Ne 1008 P Revision 0, DPC Nf 2010 Revision 3 and DPC Ne 2011 P Revision 2 (CAC Nos. MF6648, MF6649, MF7693/MF7694) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17039A1532017-03-23023 March 2017 H.B. Robinson, Unit 2 - Issuance of Amendment 250 to Adopt Technical Specification Task Force (TSTF) Change Traveler TSTF-339, Revision 2, "Relocate TS Parameters to the COLR," Consistent with WCAP-14483 (CAC No. MF7615) ML16337A2642017-02-0303 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard 805 ML16201A1952016-10-11011 October 2016 Issuance of Amendment to Extend Containment Leakage Test Frequencies 2024-07-12
[Table view] |
Text
August 10, 2021 Mr. Ernest J. Kapopoulos, Jr.
Site Vice President H. B. Robinson Steam Electric Plant Duke Energy Progress, LLC 3581 West Entrance Road, RNPA01 Hartsville, SC 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 - PROPOSED ALTERNATIVES TO AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS (EPID L-2021-LLR-0020)
Dear Mr. Kapopoulos:
By letter dated March 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21088A139), Duke Energy Progress, LLC (Duke Energy, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) requirements at H. B. Robinson Steam Electric Plant, Unit 2 (Robinson, RNP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Paragraph 50.55a(z)(1), the licensee requested to use an alternative in alternative request IST-RR-5, regarding pump inservice testing (IST), on the basis the proposed alternative would provide an acceptable level of quality or safety.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that Duke Energy has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1). The NRC staff determines that proposed alternative IST-RR-5 provides an acceptable level of quality and safety. Therefore, the NRC staff authorizes the use of alternative request IST-RR-5 for the Sixth 10 year IST program interval at RNP, which begins on February 19, 2022, and is scheduled to end on February 18, 2032.
All other ASME OM Code requirements for which relief or an alternative was not specifically requested and approved remain applicable.
E. Kapopoulous If you have any questions, please contact Project Manager, John Klos at 301-415-5136 or by e-mail to John.Klos@nrc.gov.
Sincerely, Digitally signed by David David J. J. Wrona Date: 2021.08.10 Wrona 12:28:32 -04'00' David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
Safety Evaluation cc: ListServ
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PROPOSED ALTERNATIVE REQUEST IST-RR-5 REGARDING THE SIXTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM DUKE ENERGY PROGRESS, LLC H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 EPID L-2021-LLR-0021
1.0 INTRODUCTION
By letter dated March 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21088A139), Duke Energy Progress, LLC (Duke Energy, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain requirements of the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code), at H. B. Robinson Steam Electric Plant, Unit 2 (RNP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Paragraph 50.55a(z)(1), the licensee requested to use the proposed alternative in Alternative Request IST-RR-5, regarding pump inservice testing (IST), on the basis that the proposed alternative would provide an acceptable level of quality or safety.
2.0 REGULATORY EVALUATION
Paragraph 50.55a(f)(4) of 10 CFR, Inservice testing standards requirement for operating plants, states, in part, that:
Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the inservice test requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in [10 CFR 50.55a(f)(2) and (3)] and that are incorporated by reference in [10 CFR 50.55a(a)(1)(iv)], to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulations in 10 CFR 50.55a(z), Alternatives to codes and standards requirements, state, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the NRC, if the licensee demonstrates (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
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 authorize, the proposed alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
The RNP Sixth 10-year IST program interval begins on February 9, 2022, and is scheduled to end on February 8, 2032. The applicable ASME OM Code edition for the RNP Sixth 10-year IST program interval is the 2017 Edition, which is incorporated by reference in 10 CFR 50.55a with conditions.
3.1 Licensees Alternative Request IST-RR-5 The applicable code requirements that the licensee stated for this proposed relief request alternative are; Paragraph ISTB-3300, Reference Values, states, in part, Reference values shall be obtained as follows: (a) Initial reference values shall be determined from the results of testing meeting the requirements of para. [paragraph] ISTB-3100, Preservice Testing, or from the results of the first inservice test.
Paragraph ISTB-3300(b), states, New or additional reference values shall be established as required by para. ISTB-3310 or ISTB-3320, or subpara. ISTB-6200(c).
Paragraph ISTB-3300(f), states, All subsequent test results shall be compared to these initial reference values or to new reference values established in accordance with para.
ISTB-3310 or ISTB-3320, or subpara. ISTB-6200(c).
Table ISTB-5121-1, Centrifugal Pump Test Acceptance Criteria, provides the values for the Alert Range and Required Action Range for inservice tests.
Table ISTB-5221-1, Vertical Line Shaft Centrifugal Pump Test Acceptance Criteria, provides the values for the Alert Range and Required Action Range for inservice tests.
Table ISTB-5321-1, Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria, provides the values for the Alert Range and Required Action Range for inservice tests.
Table ISTB-5321-2, Reciprocating Positive Displacement Pump Test Acceptance Criteria, provides the values for the Alert Range and Required Action Range for inservice tests.
The licensee requested to use the proposed alternative described below for the pumps listed in Table 1 and pumps in their IST program that meet the requirements of ASME OM Code Case OMN-22, Smooth Running Pumps, in the future.
Table 1 Component ID Pump Group Type ASME Description Code Class BA-A Pump Boric Acid (BA) A Centrifugal Horizontal 3 Transfer Pump Induction Motor A
BA-B Pump BA Transfer A Centrifugal Horizontal 3 Pump B Induction Motor DF-B Pump Diesel Fuel Oil A Rotary Positive 3 Transfer Pump Displacement Induction B Motor
Reason for Request
In its letter dated March 29, 2021, the licensee states, in part:
Code Case OMN-22 allows for alternative requirements for use with smooth running pumps in lieu of use of vibration values obtained in the reference value tests. For very low reference values, hydraulic noise and instrument accuracy can represent a significant portion of the reading and affect the repeatability of subsequent measurements. A smooth running pump could be subject to unnecessary increased testing if the measured vibration parameter exceeds an acceptable range based on these very low reference values.
Smooth running pumps have a much lower reference value for stable operation and the ranges for acceptable range and higher levels listed in the Alert Range do not allow for adequate vibration monitoring techniques to be applied to smooth running pumps.
Guidelines set forth in ASME OM Code Case OMN-22 allow for a very lower baseline vibration value with a pump vibration velocity of 0.050 in/sec [inches per second] when establishing the vibration reference value, which allows for trending of the pump vibration on a much lower scale than what is currently allowed.
ASME OM Code Case OMN-22, Smooth Running Pumps has not been approved by the NRC and a relief request is required for use of this Code Case.
Proposed Alternative and Basis for Use The licensee further states, in part:
H. B. Robinson Steam Electric Plant (Robinson Nuclear Plant, RNP), Unit No. 2, proposes to utilize the provisions of Code Case OMN-22, Smooth Running Pumps. For those pumps with very low baseline vibration values ( 0.050 in/sec), the following vibration velocity criteria shall be applied to any vibration test points qualifying for the use of the minimum reference value:
Acceptable Range: 0.125 in/sec Alert Range: > 0.125 in/sec to 0.300 in/sec Required Action Range: > 0.300 in/sec
Supplemental Monitoring Pumps that will use the minimum reference value for one or more vibration points shall be included in the Owners Predictive Maintenance (PdM) program. The PdM program shall apply predictive monitoring techniques and perform vibration analysis beyond the trending of vibration levels specified in the ASME OM Code to provide early identification of pump performance issues. The Owner shall determine which PdM Supplemental Monitoring activities will be utilized on the pump.
At a minimum, the Owner shall perform spectral analysis of measured vibration of the applicable pumps. The Owner shall document the conclusion of the PdM performance analysis on the pump test record prior to the subsequent test with a conclusion of acceptable, degrading but acceptable, or unacceptable. Corrective action shall be initiated when an unacceptable trend in performance is identified.
Corrective Action If a measured pump vibration parameter falls within the alert range or the required action range specified above, then the 'Corrective Action' requirements of ISTB-6200 (2017 Ed.) shall be followed. The alert and required action ranges are established in accordance with this Code Case rather than the referenced pump tables.
If a PdM Supplemental Monitoring activity identifies a parameter outside the normal operating range or identifies a trend toward an unacceptable degraded state, action shall be taken to (1) identify and document the condition in the corrective action program, (2) increase monitoring to establish the rate of change of the monitored parameter, (3) review component-specific information to identify the degradation cause, (4) develop a plan to remove the pump from service to perform maintenance prior to significant performance degradation, and (5) address potential common cause issues applicable to other pumps based on the results of the analysis of the specific pump performance.
NRC Staffs Evaluation The licensee proposes to use ASME OM Code Case OMN-22 in its entirety for the pumps listed in Table 1, and other pumps in its IST program that meet the requirements of ASME OM Code Case OMN-22 in the future. The Code Case has been approved by the ASME OM Standards Committee, with the NRC representative voting in the affirmative. The Code Case has also been approved by the ASME Board of Nuclear Codes and Standards.
ASME OM Code Case OMN-22 is included in the proposed Revision 4 of Regulations Guide (RG) 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, (ADAMS Accession No. ML20120A629) where it is listed in the table of Code Cases acceptable for use.
There are no conditions. The Code Case can be used for any pump in a licensees IST program that meets the requirements of the Code Case. RG 1.192, Revision 4, is currently scheduled to be incorporated by reference in 10 CFR 50.55a in the spring of 2022. The Code Case is applicable to the 1990 Edition through the 2020 Edition of the ASME OM Code. This includes the 2017 Edition of the ASME OM Code, which will be the licensees Code of Record for its Sixth 10-year IST program interval.
The NRC staff finds that allowing the licensee use of ASME OM Code Case OMN-22 in their IST program provides an acceptable level of quality and safety for the pumps listed in Table 1, as well as any pumps meeting the requirements of Code Case OMN-22 in the future. The NRC staff finds this is acceptable because this alternative will provide adequate indication of pump performance, and the licensees Predictive Maintenance program will ensure the ability to detect trends toward unacceptable conditions in advance of pump performance reaching an unacceptable condition.
4.0 CONCLUSION
As set forth above, the NRC staff determines that proposed alternative IST-RR-5 provides an acceptable level of quality and safety for the pumps listed in Table 1 of this safety evaluation, and any pumps meeting the requirements of ASME OM Code Case OMN-22 in the future at RNP. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for alternative request IST-RR-5.
Therefore, the NRC staff authorizes the use of alternative request IST-RR-5 for the Sixth 10-year IST program interval at RNP, which begins on February 19, 2022, and is scheduled to end on February 18, 2032.
All other ASME OM Code requirements for which relief or an alternative was not specifically requested and approved remain applicable.
Principal Contributor: R. Wolfgang, NRR/DEX/EMIB Date: August 10, 2021
ML21214A222 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-2/LA NRR/DEX/EMIB/BC NRR/DORL/LPL2-2/BC NAME JKlos RButler ITseng DWrona DATE 08/02/2021 08/03/2021 07/09/2021 08/10/2021