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Category:Letter
MONTHYEARIR 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 ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged 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 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 ML22125A1942022-05-12012 May 2022 Request for Withholding Information from Public Disclosure for H.B. Robinson Steam Electric Plant, Unit 2 IR 05000261/20220012022-05-0202 May 2022 Integrated Inspection Report 05000261/2022001 IR 05000261/20224012022-04-19019 April 2022 Security Baseline Inspection Report 05000261/2022401 ML22098A2262022-04-11011 April 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22083A0032022-03-29029 March 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System IR 05000261/20210062022-03-0202 March 2022 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 (Report No. 05000261/2021006) 2024-01-08
[Table view] 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:Safety Evaluation
MONTHYEARML24009A2712024-01-24024 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 ML16217A1182016-09-13013 September 2016 Steam Electric Plants, Shearon Harris Nuclear Power Plant,Unit 1 -Issuance of Amendments 271, 299, 152 and 246 Re Change in Corporate Form of Duke Energy Progress, Inc ML16061A4722016-04-28028 April 2016 Issuance of Amendment to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors 2024-01-24
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 13, 2012 Mr. William R. Gideon, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 - RELIEF REQUESTS-1 FOR THE FIFTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM PLAN (TAC NO. ME8258)
Dear Mr. Gideon:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 16,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12086A067), as supplemented by letter dated May 10, 2012 (ADAMS Accession No. ML12138A041),
Carolina Power & Light Company (the licensee), doing business as Progress Energy Carolinas, Inc., submitted Relief Request (RR)-1 for the Inservice Testing (1ST) Program Plan for the fifth 1O-year Interval for the H. B. Robinson Steam Electric Plant, Unit No.2 (HBRSEP).
The licensee proposed alternative testing methods and acceptance criteria described in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) Code Case OMN-18, for the pumps listed in Table 3-1 of the safety evaluation (SE). This alternative will be used in lieu of current pump testing methods and acceptance criteria described in the ASME OM Code for HBRSEP. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), the licensee requested to use proposed alternatives on the basis that the alternatives provide an acceptable level of quality and safety.
The fourth 10-year interval in HBRSEP began on February 19.2002. and was scheduled to end on February 18, 2012. As allowed by ASME Section XI, IWA-2430(d)1 the licensee extended the fourth 10-year interval through July 20,2012, to complete the refueling outage-27 which was postponed to January 18, 2012. The duration of proposed alternative is for the fifth10-year 1ST interval that begins on July 21,2012, and ends on February 18, 2022.
As discussed with the licensee on July 9,2012, the NRC staff is concerned with the amount of information provided in the submittal that required revision after review by and questions from the NRC staff, and your request for multiple concurrent reviews with a short review timeframe.
The uncharacteristic inattention to detail observed in the submittal resulted in the need to focus limited resources to address mostly administrative issues. Additional attention to ensure a high quality submittal would allow for a more efficient use of review resources, and better ability of the NRC staff to accommodate requests for a shortened review timeframe.
W. Gideon -2 The details of the NRC staff review are included in the enclosed SE. The NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR SO.SSa(a)(3)(i) and is in compliance with the ASME OM Code requirements.
The use of ASME Code Case OMN-18 for IST-RR-1 is authorized until such time as the ASME Code Case OMN-18 is published in a future version of Regulatory Guide (RG) 1.192 "Operation and Maintenance Code Case Acceptability, ASME OM Code" and incorporated by reference in 10 CFR SO.SSa(b). At that time, if the licensee intends to continue implementing this ASME Code Case, it must follow all provisions of ASME Code Case OMN-18 with the conditions as specified in RG 1.192 and limitations as specified in 10 CFR SO.SSa(b)(4), (b)(S), and (b)(6), if any.
Therefore, the licensee's proposed alternatives for IST-RR-1 is authorized for the fifth 10-year 1ST interval at HBRSEP, which begins on July 21,2012, and ends on February 18, 2022.
Sincerely, IRA by Eva Brown fori Douglas A. Broaddus, Chief Plant licensing Branch 11-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. SO-261
Enclosure:
Safety Evaluation cc w/encl: Distribution via listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON THE FIFTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM PLAN RELIEF REQUEST-1 AND RELIEF REQUEST-2 CAROLINA POWER & LIGHT COMPANY H.B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO.2 DOCKET NO. 50-261
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 16, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12086A067), as supplemented by letter dated May 10, 2012 (ADAMS Accession No. ML12138A041),
Carolina Power & Ught Company (the licensee), doing business as Progress Energy Carolinas, Inc., submitted Relief Request (RR)-1 for the Inservice Testing (1ST) Program Plan for the fifth 10-year Interval for the H. B. Robinson Steam Electric Plant, Unit No.2 (HBRSEP).
The licensee proposed alternative testing methods and acceptance criteria described in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) Code Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly Within +/- [plus or minus] 20 % [percent] of Design Flow," for the pumps listed in Table 3-1 of the safety evaluation (SE). This alternative will be used in lieu of current pump testing methods and acceptance criteria described in the ASME OM Code for HBRSEP.
The fourth 10-year interval in HBRSEP began on February 19, 2002, and was scheduled to end on February 18, 2012. As allowed by ASME Section XI, IWA-2430(d)1 the licensee extended the fourth 10-year interval through July 20, 2012, to complete the refueling outage-27 which was postponed to January 18, 2012. The duration of proposed alternative is for the fifth10-year 1ST interval that begins on July 21,2012, and ends on February 18, 2022.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(f), "Inservice Testing ReqUirements," requires in part, that the 1ST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs (a)(3)(i) or (a)(3)(ii) of 10 CFR 50.55a.
In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety. Paragraph 50.55a(a)(3) of 10 CFR states, in part, that alternatives to the requirements of 10 CFR 50.55a may be used, when authorized by the NRC,
- 2 if the licensee demonstrates (i) the proposed alternatives would provide an acceptable level of quality and safety or if (ii) compliance with the speci'fied requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The licensee requested authorization in IST-RR-1 of an alternative to the requirements of the ASME OM Code pursuant to 10 CFR 50.55a(a)(3)(i). The NRC staff approved a similar request to HBRSEP IST-RR-1, for Perry Nuclear Power Plant, Unit 1, on October 8,2009 (ADAMS Accession No. ML092640690).
3.0 TECHNICAL EVALUATION
The NRC staff has evaluated the information provided by the licensee in support of 1ST RR-1 for relief from, or alternative to, the ASME OM Code requirements and the bases for disposition are documented below.
3.1 IST-RR-1 3.1.1 ASME Code Requirements The applicable ASME OM Code edition and addenda for HBRSEP is the 2004 Edition through the 2006 Addenda.
ISTB-2000, "Supplemental Definitions," defines the uniform criteria for designating Group A and Group B pumps.
ISTB-3000, "General Testing Requirements," and Table ISTB-3000-1, "Inservice Test Parameters," define and compare parameters (e.g., pressure, flow rate, vibration) measured during Group A, Group B, and comprehensive pump tests.
ISTB-3400, "Frequency of Inservice Tests," states that, "An inservice test shall be run on each pump as specified in Table ISTB-3400-1."
Table ISTB-3400-1, "Inservice Test Frequency," notes that Group A and Group B tests shall be performed quarterly, and comprehensive pump tests shall be performed biennially.
Table ISTB-351 0-1, "Required Instrument Accuracy," defines the required instrument accuracies for Group A, Group B, and comprehensive pump tests.
Table ISTB-5121-1, "Centrifugal Pump Test Acceptance Criteria," defines the required acceptance criteria for centrifugal pumps for Group A, Group B, and comprehensive tests.
ISTB-5123, "Comprehensive Test Procedure," provides the specific requirements for the comprehensive test for centrifugal pumps (except vertical line shaft centrifugal pumps).
Table ISTB-5221-1, "Vertical Line Shaft and Centrifugal Pumps Test Acceptance Criteria,"
defines the required acceptance criteria for vertical line shaft centrifugal pumps for Group A, Group B, and comprehensive tests.
- 3 ISTB-5223, "Comprehensive Test Procedure," provides the specific requirements for the comprehensive test for vertical line shaft centrifugal pumps.
Table ISTB-5321-2, "Reciprocating Positive Displacement Pump Test Acceptance Criteria,"
defines the required acceptance criteria for reciprocating positive displacement pumps for Group A. Group B and comprehensive tests.
ISTB-5323, "Comprehensive Test Procedure," provides the specific requirements for the comprehensive test for positive displacement pumps.
3.1.2 Component for which Relief is Requested The licensee requested to use a modified quarterly Group A test for the 1ST in lieu of a quarterly Group A test and a biennial comprehensive test for the following pumps:
Table 3-1: Components for which Relief is Requested Pump Description Category Type BA-XFER-PMP-A Boric Acid (BA) Transfer Group A Horizontal Centrifugal Pump A BA-XFER-PM P-B BA Transfer Pump B Group A Horizontal Centrifu CCW-PMP-A Component Cooling Group A Horizontal Centrifugal Water (CCW) Pump A i CCW-PMP-B CCWPumpB Group A Horizontal Centrifugal I CCW-PMP-C CCWPumpC Group A Horizontal Centrifugal CHG-PMP-A Chemical Volume and Group A Reciprocating Positive Control System (CVCS) Displacement Charging Pump A CHG-PMP-B CVCS Charging Pump B Group A Reciprocating Positive Displacement CHG-PMP-C CVCS Charging Pum ... _ I i';roUP A Reciprocating Positive Displacement SWBP-A Service Water (SW) Group A Horizontal Centrifugal Booster Pump A SWBP-B SW Booster Pump B Group A Horizontal Centrifugal SW-PMP-A SW-PMP-B SWPumpA SWPumpB
! GroupA Group A Vertical Line Shaft Vertical Line Shaft SW-PMP-C SWPumpC mA Vertical Line Shaft SW-PMP-D SWPump D Group A Vertical Line Shaft 3.1.3 Licensee's Basis for Relief Request The licensee requested relief from the requirements of ASME OM Code ISTB-5123, ISTB-5223, ISTB-5323, Table ISTB-3400-1, Table ISTB-5121-1, Table ISTB-5221-1, and Table ISTB-5321-2. The ASME OM Code Committee has approved Code Case OMN-18, which states, in part, that "the Group A test may be performed quarterly within +/- 20 percent of pump design flow rate, with instrumentation meeting the requirements of Table IST8-351 0-1 for the comprehensive and preservice tests, and no comprehensive test is required."
-4 The ASME Code Case OMN-18 was published in the 2009 Edition of the ASME OM Code.
Code Case OMN-18 allows licensees to perform a Group A test in lieu of the biennial Comprehensive Pump Test (CPT) if the Group A tests are conducted at +/- 20% of the design flow rate and pressure instruments that meet the CPT accuracy requirement of +/- 0.5% are used. This Code Case was not reviewed for approval in Regulatory Guide (RG) 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code," dated June 2003.
The basis for this change is that a quarterly Group A pump test, performed at the CPT flow rate and with CPT required pressure instrument accuracy, provides more consistent data for trending than a Group A test in conjunction with a biennial CPT. The increased requirements provided by the proposed alternative on the parameters to be monitored during every quarterly pump test and the more accurate instruments that must consistently be used during quarterly testing of the pumps classified as Group A, allow the licensee to perform better trending of pump performance data due to the more precise and consistent requirements for each of the quarterly tests. Due to the increased requirements on the parameters imposed by the proposed alternative during all quarterly tests, there is no added value in performing the biennial CPT.
3.1.4 Licensee's Proposed Alternative Examination The licensee proposes that in lieu of the CPT requirements of Table IST8-3400-1, Group A tests will be performed quarterly within +/- 20% of the pump design flow rate, with pressure measuring instrumentation meeting the (+/- 0.5%) instrument accuracy requirements of Table IST8-3510-1 specified for the biennial CPT. In addition, the licensee has elected to restrict the upper limit for acceptable range to 106% of the reference value (flow rate, differential pressure, or discharge pressure), which is more conservative than the 110% upper limit established in Tables IST8-5121-1, IST8-5221-1, and IST8-5321-2 for Group A tests, as this limit provides needed margin while maintaining an acceptable level of quality and safety, and is consistent with the limit authorized by the NRC staff in a similar alternative request. The proposed change to the acceptance range is more restrictive than specified in the AMSE Code Case OMN-18.
Vibration testing will continue to be performed under the proposed modified Group A test and the acceptance criteria for vibration will be the same as required for Group A tests as shown in Tables IST8-5121-1, IST8-5221-1, and IST8-5321-2.
Using the provisions of the request as an alternative to those specified in IST8-5123, IST8-5223, and IST8-5323 will provide adequate indication of pump performance, permit consistent detection of component degradation, and continue to provide an acceptable level of quality and safety.
3.1.5 NRC Staff Evaluation The licensee proposed to perform a quarterly 1ST for all the pumps listed in Table 3-1 in accordance with a modified Group A test procedure, in lieu of a quarterly Group A test and a biennial CPT.
The ASME OM Code requires that for Group A pumps, a Group A test be performed every quarter, and a CPT be performed biennially. The Group A test is performed within +/- 20% of the pump design flow rate and the pressure instrument accuracy is +/- 2%. The upper limit for the "Acceptable Range" for flow rate, differential pressure, and discharge pressure is 110% of
-5 the reference values, and the high value for the "Required Action Range" for flow rate, differential pressure, and discharge pressure is greater than 110% of the reference values. The CPT is performed within +/- 20% of the pump design flow rate, the pressure instrument accuracy is +/- 0.5%, and the upper limit of the "Acceptable Range" and "Required Action Range" for flow rate, differential pressure, and discharge pressure is 103% of the reference values. Vibration monitoring is performed during both the Group A tests and the CPTs.
The licensee proposes that for the pumps listed in Table 3-1, a modified Group A quarterly test will be performed using ASME OM Code Case OMN-18, with modified "Acceptable" and "Required Action" ranges, and the biennial CPT will not be performed. The modified Group A quarterly test would be performed within +/- 20% of the pump design flow rate, using more accurate pressure instrumentation that is required for a CPT (+/- 0.5% instead of +/- 2%). The licensee will use a more limiting upper bound of 106% of the reference value for the "Acceptable RangeD for flow rate, differential pressure, and discharge pressure, in lieu of 110% of the reference value that is normally required by the ASME OM Code for Group A tests. However, this upper bound of 106% is greater than the upper bound value of 103% for the biennial CPT.
Using more accurate pressure gauges and a more limiting "Acceptable Range" (compared to the Group A test "Acceptable Range") during every modified quarterly Group A test compensates for the elimination of the CPT with its more limiting "Acceptable Range" upper bound value of 103%.
ASME Code Case OMN-18 was published in the 2009 Edition of ASME OM Code. This Edition of the ASME OM Code has not been incorporated by reference into 10 CFR 50.55a, and OMN 18 has not been incorporated into RG 1.192. However, the NRC staff has reviewed OMN-18, and currently has no concerns with its usage, providing that the upper end values of the Group A test "Acceptable Ranges" for flow, differential pressure, and pressure are 106% of the respective reference values, and the high values of the "Required Action Ranges" for flow, differential pressure, and pressure are greater than 106% of the respective reference values.
The NRC staff considers the proposed alternative acceptable because all of the tests will be performed with pressure gauges with +/- 0.5% accuracy. The elimination of the CPT, with its more limiting "Acceptable Range" upper bound of 103% of the reference value, is compensated for by using more accurate pressure instrumentation on every quarterly test. Regular testing with more accurate instrumentation and tighter acceptance criteria will provide for better trending of pump performance. Therefore, the NRC finds that the proposed alternative provides an acceptable level of quality and safety for testing and acceptance criteria for the pumps listed in Table 3-1.
4.0 CONCLUSION
The NRC staff finds that the proposed alternative described in IST-RR-1 provides an acceptable level of quality and safety for the pumps listed in Tables 3-1. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i) and is in compliance with the ASME OM Code's requirements.
Therefore, the NRC staff authorizes the alternative described in 1ST-RR-1 for the HBRSEP fifth, 10-year, 1ST interval, which begins on July 21, 2012, and ends on February 18, 2022.
The use of ASME Code Case OMN-18 for IST-RR-1 is authorized until such time as the ASME Code Case OMN-18 is published in a future version of RG 1.192 and incorporated by reference
- 6 in 10 CFR SO.SSa(b). At that time. if the licensee intends to continue implementing this ASNIE Code Case. it must follow all provisions of ASME Code Case OMN-18 with conditions as specified in RG 1.192 and limitations as specified in 10 CFR SO.SSa(b)(4). (b)(S), and (b)(6), if any.
All other ASME Section XI requirements for which relief was not specifically requested and authorized by the NRC staff will remain applicable including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Robert Wolfgang Date of issuance: July 13, 2012
W. Gideon -2 The details of the NRC staff review are included in the enclosed SE. The NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i) and is in compliance with the ASME OM Code requirements.
The use of ASME Code Case OMN-18 for IST-RR-1 is authorized until such time as the ASME Code Case OMN-18 is published in a future version of Regulatory Guide (RG) 1.192 "Operation and Maintenance Code Case Acceptability, ASME OM Code" and incorporated by reference in 10 CFR 50.55a(b). At that time, if the licensee intends to continue implementing this ASME Code Case, it must follow all provisions of ASME Code Case OMN-18 with the conditions as specified in RG 1.192 and limitations as specified in 10 CFR 50.55a(b)(4), (b)(5), and (b)(6), if any.
Therefore, the licensee's proposed alternatives for IST-RR-1 is authorized for the fifth 10-year 1ST interval at HBRSEP, which begins on July 21, 2012, and ends on February 18, 2022.
Sincerely, IRA by Eva Brown forI Douglas A. Broaddus, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
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