Letter Sequence Other |
---|
|
|
MONTHYEARML12102A1742012-05-0404 May 2012 Request for Additional Information Related to Relief Requests (RR)-1, RR-2, and RTR-3 for the Fifth 10-Year Interval Inservice Testing Program Plan Project stage: RAI ML12174A0102012-07-13013 July 2012 Relief Request -3 for Fifth 10-Year Interval Inservice Testing Program Plan Project stage: Other 2012-05-04
[Table View] |
|
---|
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: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] 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] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 13, 2012 Mr. William R. Gideon, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric 3581 West Entrance Hartsville, South Carolina H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 -REQUEST-3 FOR THE FIFTH 10-YEAR INTERVAL INSERVICE PROGRAM PLAN (TAC NO.
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. ML 12086A067), as supplemented by letter dated May 10, 2012, (ADAMS Accession No. ML 12138A041), Carolina Power & Light Company (the licensee), doing business as Progress Energy Carolinas, Inc., submitted Relief Request-3 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 requested approval to use an alternative test plan in lieu of certain 1ST requirements of the 2004 Edition through 2006 Addenda of the American SOCiety of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM) Code for the Category C check valves exercise tests or exams at 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 refueling outage-27 which was postponed to January 18, 2012. The duration of proposed alternative is for the fifth 1 O-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.
The details of the NRC staff review are included in the enclosed safety evaluation.
Section 50.55a(f) of 10 CFR, "Inservice Testing Requirements," requires in part, that the 1ST of certain ASME OM Code Class 1, 2, and 3 components must meet the requirements of the ASME OM W. Gideon -2 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. The NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii) and is in compliance with the ASME Code requirements.
Therefore, the licensee's proposed alternative is authorized in accordance with 10 CFR 50.55a(a)(3)(ii) 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.
Safety cc w/encl: Distribution via UNITED NUCLEAR REGULATORY 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-3 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. ML 12086A067), as supplemented by letter dated May 10, 2012 (ADAMS Accession No. ML 12138A041), Carolina Power & Light Company (the licensee), doing business as Progress Energy Carolinas, Inc., submitted Relief Request (RR)-3 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 requested approval to use an alternative test plan in lieu of certain 1ST requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM) Code for the Category C check valves exercise tests or exams at 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, if the licensee demonstrates (i) the proposed alternatives would provide an acceptable level of quality and safety or if (ii) compliance with the specified requirements would result in hardship or
-2 unusual difficulty without a compensating increase in the level of quality and safety. The licensee requested authorization of an alternative to the requirements of the ASME OM Code pursuant to 10 CFR 50.55a(a)(3)(i).
The NRC staff has previously approved this alternative for HBRSEP for the fourth 1ST 10-year interval on June 27,2002, (ADAMS Accession No. ML040700790).
3.0 TECHNICAL
EVALUATION The NRC staff has evaluated the information provided by the licensee in support of the request for relief from, or alternative to, the ASME OM Code requirements and the bases for disposition are documented below. 3.1 ASME OM Code Requirements ISTC-3510 "Exercising Test Frequency," states, in part, that "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, I STC-3550 , ISTC-3570, ISTC-5221, and ISTC-5222." ISTC-3522 "Category C Check Valves," (a), states, in part, that "During operation at power, each check valve shall be exercised or examined in a manner that verifies obturator travel using the methods in ISTC-5221.
Each check valve exercise test shall include open and close tests." ISTC-3530 "Valve Obturator Movement," states that, "The necessary valve obturator movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating lights that signal the required changes of obturator position, or by observing other evidence, such as changes in system pressure, flow rate, level, or temperature, that reflects change of obturator position." ISTC-5221 "Valve Obturator Movement," (a), states that, "The necessary valve obturator movement during exercise testing shall be demonstrated by performing both an open and a close test." ISTC-5221 (a)(2), states that, "Check valves that have a safety function in only the open direction shall be exercised by initiating flow and observing that the obturator has traveled either the full open position or to the position required to perform its intended function(s) (see ISTA-1100), and verify closure." ISTC-5221 (c)(2), states, in part, that, "the full stroke motion of the obturator shall be verified." 3.2 Component for which Relief is Requested The licensee requested relief from the following Category C, Isolation Valve Seal Water (IVSW) system valves: IVSW-71, IVSW-72, IVSW-74 through IVSW-97, IVSW 100A, IVSW-100B, and IVSW-100C.
-3 3.3 Licensee's Basis for Relief Request The licensee stated in the March 16, 2012, submittal that the 3/8 inch penetration check valves in the IVSW system have no safety function in the closed direction and are required to open in order to provide seal water to selected containment penetrations during a design-basis accident (DBA). The IVSW system operates to limit the release of fission products if leakage occurs. The licensee indicated that no credit is taken for the operation of the IVSW system when calculating off site accident dose. The licensee stated that the IVSW system is a qualified seal water system according to the requirements of 10 CFR Part 50 Appendix J "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." The IVSW system is maintained at a minimum pressure of 1.1 times the peak accident pressure related to the design basis loss-of-coolant accident (LOCA). Therefore, the design and qualification of the system eliminates the need for these valves to close during a DBA in the unlikely event that closure is required.
The licensee stated that the disassembly to verify the obturator closure or modifications to facilitate 1ST for closure, (1) is impractical based on the large number of valves requiring verification and the insignificance associated with their failure to close and (2) may lead to maintenance induced errors associated with re-assembly.
The small size and construction of IVSW valves prohibits the ability to perform partial disassembly/inspection in a manner representative of its inservice condition (e.g., valve removal and decontamination activities could alter disc position).
The ISVW system is a standby system that is typically operated during refueling outages to facilitate testing. Based on the infrequent use of the ISVW system, the licensee stated that the valve obturator exhibits minimal wear. The licensee adopted bi-directional check valve testing to counter the effects of a faulty test strategy associated with the inability to detect a detached valve disc. The licensee stated that a satisfactory forward flow check valve test could be completed when the valve disc is detached and laying in the bottom of the valve body. Based on the design and materials of construction associated with these check valves, disc failure with subsequent migration into associated systems is not likely since the size of the disc exceeds the inner diameter of the valve outlet. The licensee stated that the failure of the valve in this manner would be detected by the current test method that is performed at refueling outages in conjunction with required 10 CFR Part 50 Appendix J leak rate testing. The licensee stated that based on the design and qualification of the ISVW system, compliance with the ASME OM Code requirements would result in an unusual hardship without a compensating increase in the level of quality and safety. 3.4 Licensee's Proposed Alternative Examination The licensee stated that as an alternative to the ASME OM Code testing requirements, the 3/8 inch penetration check valves installed in the IVSW system will be tested in the open position at refueling intervals.
The licensee also indicated that closure verification will not be performed.
3.S NRC Staff Evaluation Section SO.SSa(f) of 10 CFR, "Inservice Testing Requirements," requires in part, that the 1ST of certain ASME OM 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 SO.SSa. The licensee alternative request was based on applying the rule of 10 CFR SO.SSa(a)(3)(i).
However, the alternative method described in IST-RR-3 is more in line with 10 CFR SO.SSa(a)(3)(ii).
Therefore, the NRC staff reviewed IST-RR-3 on the basis that complying with the specified ASME Code requirement would result in hardship or unusual difficulty without increase in the level of quality and safety.
The IVSW system assures the effectiveness of certain containment isolation valves during any condition that requires containment isolation, by providing a water seal at the valves. These valves are located in lines that are connected to the reactor coolant system, or that could be exposed to the containment atmosphere in the event of a LOCA. The system provides a simple and reliable means for injecting seal water between the seats and stem packing of the globe and double disc types of isolation valves, and into the piping between closed diagram type isolation valves. This system operates to limit the fission product release from the containment.
The NRC staff evaluated the technical aspects of IST-RR-3 against the criteria in the ASME OM Code. ISTC-S221 (a)(2) requires closure verification of check valves that only have a safety function in the open direction.
ISTC-S221 (c) requires a sample disassembly examination program for certain check valves that have been determined to be impractical to test. Closure verification after a successful open direction test ensures that the internals of the check valve assembly are still in place and remain intact. The IVSW valves are in-line spring loaded ball check valves. The internal ball provides a seal against an o-ring seat to provide leak tight shutoff. The internal ball provides the valve closure and seal is secured in a leak tight body joint and seat assembly.
The internal ball is physically unable to migrate away from the valve assembly and, therefore, would not adversely impact the function of the overall IVSW system. The IVSW system, when actuated, delivers seal water through the check valves between two isolation pOints located outside the containment at a minimum pressure of 1.1 times the peak calculated containment accident pressure related to the design basis LOCA. The resulting water seal blocks leakage of the containment through valve seats and stem packing. The possibility of leakage from the containment past the isolation pOints is prevented by assuring that if leakage does exist, it will be from the seal water system into the containment.
The IVSW check valves have no safety function in the closed direction and are required to open to provide seal water to selected containment penetrations.
According to the HBRSEP Updated Final Safety Analysis Report Revision No. 22, Section 6.8.2.1, "Isolation Valve Seal Water System -System Description," relief valves are provided in the system to prevent over-pressurization of the system if a pressure control valve fails or if a seal water injection line communicates with a high-pressure line due to a check valve failure in the seal water line. Disassembly to verify obturator closure or modifications to facilitate 1ST for closure is impractical based on the large number of valves requiring verification and the insignificance associated with their failure to close.
-The NRC staff has reviewed the valve design and configuration and finds that the likely mode of failure is leakage through the valve seat. Because of the valve's unique design, failure of the ball-shaped disc would not result in subsequent migration into associated systems, and therefore would not adversely impact the safety function of the IVSW calculated containment accident pressure related to the design-basis LOCA. Therefore, containment out leakage will be prevented when the IVSW system is in operation following a LOCA. Incomplete valve closure or leakage will also be detected by pressure and water level instruments associated with the seal injection tank. As a result, closure verification by a sample disassembly program of the IVSW system valves is unnecessary and would result in hardship without a compensating increase in the level of quality and safety. Therefore, the NRC staff finds the proposal of testing the affected valves to only the open position acceptable.
4.0 CONCLUSION
The NRC staff determines that the proposed alternative, described in IST-RR-3, provides reasonable assurance that valves IVSW-71, IVSW-72, IVSW-74 through IVSW-97, IVSW-100A, IVSW-100B, and IVSW-100C are operationally ready and provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR SO.SSa(a)(3)(ii) and is in compliance with the ASME OM Code requirements.
Therefore, the NRC staff authorizes the proposed alternative in IST-RR-3 for the fifth 1ST interval at HBRSEP Unit No.2 currently scheduled to begin on July 21,2012, and ends on February 18. 2022. 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:
Michael Farnan Date of issuance:
July 13, 2012 W. Gideon -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. The NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.5Sa(a)(3)(ii) and is in compliance with the ASME Code requirements.
Therefore, the licensee's proposed alternative is authorized in accordance with 10 CFR SO.SSa(a)(3)(ii) 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.
Safety cc w/encl: Distribution via DISTRIBUTION:
PUBLIC LPL2-2 RtF RidsAcrsAcnw MailCTR Resource RWolfgang, NRR RidsNrrDor1LpI2-2 RidsNrrPMRobinson RidsNrrLABClayton RidsOgcRp RidsRgn2MailCenter RidsNrrDeEptb M. Farnan, NRR ADAMS Access ion No' ML 12174A010
..
- Via Memo I OFFICE LPL2-2/PM LPL2-2/LA DE/EPTB/BC*
DSS/SCVB/BC LPL2-2/BC LPL2-2/BC NAME ABillochColon BClayton RWolfgang(A)
HWalker(A)
DBroaddus (EBrown forI ABiliochColon DATE 6/21/12 6/22112 6/13112 7/5/12 7/13/12 7/13112 OFFICIAL RECORD COpy