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Category:Code Relief or Alternative
MONTHYEARML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B2015-05-14014 May 2015 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) NRC 2013-0020, CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval2013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval ML13079A1412013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12286A1042012-11-15015 November 2012 Evaluation of Relief Requests RR-2 & RR-3 (ME7974 & ME7975) ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 ML0527001972006-01-18018 January 2006 Relief Request - Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 ML0526503122005-09-27027 September 2005 Relief Requests - the Previsions of ASME Section XI, IWA-5244, Buried Components, RR-1-26 and RR-2-34 NRC 2005-0084, Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 22005-07-0101 July 2005 Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 NRC 2005-0016, Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 162005-02-0404 February 2005 Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 16 NRC 2005-0015, Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 152005-01-21021 January 2005 Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 15 ML0408601612004-04-0101 April 2004 Request for Relief VRR 03-01 on a One Time Basis for Performing Inservice Testing of Relief Valve 1RH-861C ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0323104022003-09-10010 September 2003 Relief, MR 02 018-2 Pertaining to Reactor Vessel Closure Head Penetration Repair ML0306203282003-03-21021 March 2003 Relief, Use of Code Case N-600 for the Fourth 10-Year Interval, MB5403 and MB5404 ML0225401092003-03-21021 March 2003 Relief Request No 8 - Requirement for Scheduling of Components for Examination ML0302101262003-02-27027 February 2003 Relief, Alternative to Examine All Three Vessels of the Regenerative Heat Exchanger, MB5401 & MB5402 ML0225300062002-10-0808 October 2002 Code Relief, ASME Code Section XI, Relief Request 5 Regarding Visual Examination of Insulted Bolting on Borated Systems ML0225300232002-10-0808 October 2002 Relief, Granted for ASME Code Section XI, Relief Request 6 Regarding Evaluation of Leakage with Bolting In-Place NRC 2002-0073, Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-22002-08-28028 August 2002 Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-2 2023-11-09
[Table view] Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 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 L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System ML22140A1272022-05-25025 May 2022 Subsequent License Renewal Application Safety Evaluation Revision 1 Public ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public ML21148A2552021-07-21021 July 2021 Issuance of Amendment Nos. 269 and 271 Technical Specification Changes to Implement New Surveillance Methods for Transient Heat Flux Hot Channel Factor ML20363A1762021-02-23023 February 2021 Issuance of Amendment Nos. 268 and 270 Regarding Tornado Missile Protection Licensing Basis ML20241A0582020-09-25025 September 2020 Issuance of Amendment No. 267 for One-Time Extension of License Condition 4.I, Containment Building Construction Truss (EPID L-2020-LLA-0180 (COVID-19)) ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML19064A9042019-04-25025 April 2019 Issuance of Amendments to Extend Containment Leakage Rate Test Frequency ML19052A5442019-03-27027 March 2019 Issuance of Amendments 264 and 267 to Adopt TSTF-547, Clarification of Rod Position Requirements ML18289A3782018-11-26026 November 2018 Issuance of Amendments to Adopt Title 10 of Code of Federal Regulations 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18079A0452018-06-13013 June 2018 Issuance of Amendments Revision to the Point Beach Nuclear Plant Emergency Action Level Scheme (CAC Nos. MF9859 and MF9860 EPID L-2017-LLS-0278) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16241A0002016-09-23023 September 2016 Mitigating Strategies and Spent Fuel Pool Instrumentation Safety Evaluation ML16196A0932016-09-0808 September 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48 (C) ML16118A1542016-06-17017 June 2016 Issuance of Amendments ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML16035A5092016-03-0909 March 2016 Correction of Typographical Error in Safety Evaluation Associated with License Amendment Nos. 238 and 242 ML15293A4572015-11-25025 November 2015 Issuance of Amendments for the Steam Generator Technical Specifications, to Reflect Adoption of TSTF-510 ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 ML15161A5352015-06-24024 June 2015 Relief Request VR-01; Alternatives to Certain Inservice Testing Requirements of the American Society of Mechanical Engineers (ASME) Code of Operation and Maintenance of Nuclear Power Plants ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML14293A0022014-10-21021 October 2014 Issuance of Safety Evaluation Regarding Relief Request RR-5 ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material ML14014A2052014-01-30030 January 2014 Issuance of Relief Request Regarding Risk-Informed Inservice Inspection Program for the Fifth 10-Year Inservice Inspection Interval ML13329A0422013-12-20020 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L3) ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) ML13346A0402013-12-18018 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L2) ML13135A2712013-05-29029 May 2013 Safety Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12362A0092013-01-29029 January 2013 Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements ML12251A1552012-11-23023 November 2012 Issuance of Amendment to Renewed Facility Operating License Revised Cyber Security Plan Implementation Schedule Milestone 6 2024-01-23
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 7, 2015 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - RELIEF REQUEST RR-9, PROPOSED ALTERNATIVE FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE FOR SYSTEM LEAKAGE TEST (TAC NOS.
MF4142 AND MF4143)
Dear Mr. McCartney:
By letter dated May 13, 2014, NextEra Energy Point Beach, LLC (NextEra) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements specified in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, at the Point Beach Nuclear Plant (Point Beach), Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), 50.55a(a)(3)(i),
NextEra submitted Relief Request RR-9. requesting relief from the system pressure test of the emergency diesel generator subsystem components required by ASME Section XI, IWD-5220.
In lieu of the required system pressure test, NextEra proposed to use existing technical specification tests to demonstrate an equivalent level of quality and safety.
By Federal Register Notice 79 FR 65776, dated November 5, 2014, which became effective on December 5, 2014, the paragraph headings in 10 CFR 50.55a were revised. Accordingly, relief requests that had been previously covered by 10 CFR 50.55a(a)(3)(i) are now covered under the equivalent 10 CFR 50.55a(z)(1) and relief requests that had been previously covered by 10 CFR 50.55a(a)(3)(ii) are now covered under the equivalent 10 CFR 50.55a(z)(2).
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that NextEra has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore; the NRC staff determines that the proposed alternative provides an acceptable level of quality and safety.
E. McCartney If you have any questions, please contact Mahesh Chawla at (301) 415-8371, or via e-mail at Mahesh. Chawla@nrc.gov.
David L. Pelton, C ief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
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 REGARDING RELIEF REQUEST RR-9 FOR THE FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301 (TAC NOS. MF4142 AND MF4143)
1.0 INTRODUCTION
By letter dated May 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14133A365), and as supplemented by letter dated December 8, 2014 (ADAMS Accession No. ML14342A417), NextEra Energy Point Beach, LLC (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) associated with system leakage tests for Emergency Diesel Generator subsystems at Point Beach Nuclear Plant, Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(a)(3)(i),
the licensee requested to use the proposed alternative on the basis that the alternative examination provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
In this relief request, the licensee proposes to use alternatives to the requirements of ASME Section XI, IWA-5220 pursuant to 10 CFR 50.55a(a)(3)(i). By Federal Register Notice 79 FR 65776, dated November 5, 2014, which became effective on December 5, 2014, the paragraph headings in 10 CFR 50.55a were revised. Accordingly, relief requests that had been previously covered by 10 CFR 50.55a(a)(3)(i) are now covered under the equivalent 10 CFR 50.55a(z)(1 ), and relief requests that had been previously covered by 10 CFR 50.55a(a)(3)(ii) are now covered under the equivalent 10 CFR 50 55a(z)(2).
Adherence to Section XI of the ASME Code is mandated by 10 CFR 50.55a(g)(4), which states, in part, that ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI.
Enclosure
Section 50.55a(z) of 10 CFR states, in part, that alternatives to the requirements of paragraph (g) of 10 CFR 50.55a may be used, when authorized by the NRC, if the licensee demonstrates that: (1) the proposed alternative provides 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.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory basis exists for the licensee to request and the Commission to authorize the proposed alternative requested by the licensee. Accordingly, the NRC staff has reviewed and evaluated the licensee's request pursuant to 10 CFR 50.55a(z)(1 ).
3.0 TECHNICAL EVALUATION
3.1 ASME Code Components Affected
Component: Emergency Diesel Generator Subsystems; starting air, glycol cooling (G-03 and G-04 only) and fuel oil ASME Code Class: Code Class 3 Examination Category: D-B Item Number: 02.10 3.2 Applicable Code Edition and Addenda The Code of Record for the fifth 10-year inservice inspection (ISi) interval for Point Beach Nuclear Plant, which commenced on August 1, 2012, is ASME Code,Section XI, 2007 Edition with Addenda through 2008.
3.3 Applicable Code Requirement ASME Code,Section XI, Table IWD-2500-1, Examination Category D-B, Item No 02.10 requires a system leakage test and a VT-2 visual examination each inspection period.
3.4 Proposed Alternative The licensee proposes to use existing technical specification testing of the emergency diesel generator (EOG) starting air, glycol cooling (G-03 and G-04) and fuel oil subsystems to demonstrate an equivalent level of quality and safety.
3.5 Licensee's Basis for Use of the Proposed Alternative The primary intent of technical specification surveillance testing is slightly different from ASME Code required examinations. Technical specifications are intended to demonstrate component operability, whereas the system leakage and hydrostatic tests required by the ASME Code,Section XI, are intended to demonstrate pressure boundary integrity. There are no VT-1 visual examinations imposed on the EOG subsystems due to pressure/temperature or size exemptions as allowed by the ASME Code,Section XI, IWD-1220. Therefore, verification of pressure
boundary structural integrity on EDG subsystems is not included in the PBNP ISi program.
Successful EDG operability testing requires the associated subsystems to maintain pressure boundary integrity and therefore, provides an equivalent level of quality and safety to that of ASME Section XI inspections. Those auxiliary support subsystems addressed within the scope of this request for relief include the starting air system, fuel oil system, and glycol cooling system (G-03 and G-04 only for glycol cooling).
The repeatability of auxiliary subsystem instrumentation (pressure, fluid level, and temperature) recorded during surveillance testing provides supporting data for the indirect verification of component integrity. Operations personnel are specifically trained in the testing of the standby EDGs and are aware of the necessity to maintain pressure boundary of the auxiliary subsystems. They are also aware of the necessity to maintain unobstructed flow characteristics for components discharging to a tank vented to atmosphere as do the diesel fuel oil transfer pumps. Although not a specific step in the surveillance procedure, verification of component pressure boundary integrity is administratively required of personnel performing standby EDG operability testing. If evidence of leakage is identified during the test, a condition report and/or work order is initiated with corrective actions or repairs implemented and follow-up confirmatory testing is performed.
The following paragraphs provide specific procedural actions which support the use of alternative operability testing in lieu of ASME Section XI system pressure testing and VT-2 visual examination.
Starting Air Auxiliary Subsystem PBNP surveillance test procedures TS-81, 82, 83, and 84 are performed monthly to demonstrate EDG operability. As part of these procedures, pressures of both right and left bank air receivers are recorded prior to and subsequent to starting the engine with the drop in pressure verified to occur at the air start motor outlet ports. The satisfactory completion of this test demonstrates the skid-mounted air start components are properly performing their function and provides positive indication the pressure boundary integrity of the starting air subsystem is intact. In addition to the monthly testing, lnservice Test Procedure IT-100 performs quarterly reverse exercising of the right/left bank air start receivers' inlet check valves. During the performance of this procedure, each air compressor is isolated with a vent path provided upstream of the air receiver supply check valves. Receiver pressure is observed for 15 minutes with stringent leakage criteria applied. If a through wall or otherwise excessive leak were to occur in the pressure boundary, seat leakage acceptance criteria for the check valves would be exceeded, resulting in a requirement to determine the source of the leak and repair/replacement. This data also provides a positive indication that pressure boundary integrity is being maintained for the starting air subsystem. Based on the monthly and quarterly test frequencies and the data collected during these alternative tests, PBNP considers that testing performed to satisfy the technical specification surveillance requirements provide an acceptable level of quality and safety as an alternative to ASME Section XI system pressure testing.
Fuel Oil Transfer Subsystem For the fuel oil transfer subsystem, an acceptable ASME Section XI pressure test would consist of a VT-2 visual examination of the outlet piping from the day tank to the engine. This is done
when the day tank is filled to design capacity and demonstrates the transfer pump's ability to provide adequate makeup flow to the day tank during system operation. For the fuel oil transfer subsystem, an acceptable ASME Section XI pressure test would consist of a VT-2 visual examination of the outlet piping (that extends from the day tank to the engine). The VT-2 visual examination is performed when two conditions are met: (1) the day tank is filled to design capacity, and (2) it has been demonstrated that the transfer pump is providing adequate flow.
This test is performed while the day tank is vented to atmosphere, which is its normal configuration. This is due to the day tank being vented to atmosphere. During the monthly performance of TS-81, 82, 83, and 84, the inventory in the day tank is drained down to the low-level setpoint for pump actuation. The pump is verified to automatically start and allowed to replenish the day tank inventory to the high level setpoint with verification the pump automatically stops. During this process, procedure steps require recording of the percentage of tank level when the transfer pump automatically starts, as well as the percentage of tank level upon cessation of pump operation. The pump flow rate is recorded during replenishment of day tank inventory for G-03 and G-04 with acceptance criteria applied to recorded flow rate values.
Discharge flow rate for G01 and G02 transfer pumps is not measured during the monthly performance of TS-81 and TS-82 as there is no flow instrumentation in the pumps discharge lines to G-01 and G-02 day tanks. The flow rate to G-01 and G-02 day tanks is measured during each Unit 1 refueling outage, utilizing an ultrasonic flow meter during inservice testing of unloader valves F0-3982A and F0-3983A. This data provides a positive indication that pressure boundary integrity is being maintained. Based on the technical specification surveillance testing frequency and the data collected during these alternative tests, PBNP considers the testing performed to satisfy the technical specification surveillance requirements provides an acceptable level of quality and safety as an alternative to ASME Section XI system pressure testing.
Glycol Cooling Subsystem (G-03 and G-04 Only)
Standby emergency diesel generators G-03 and G-04 are provided with a glycol cooling subsystem consisting of a coolant to air type heat exchanger. During the monthly performance of TS-83 and TS-84, coolant tank level as well as multiple point temperature indication is recorded prior to starting the engine, after 30 minutes of loaded run time, and prior to shut down, or hourly for extended runs. Normal values for all acquired data are provided in the procedure log-sheet as well as limits for the data recorded. This data provides a positive indication that pressure boundary integrity is being maintained. Based on the monthly frequency and data collected during these tests, PBNP considers the testing performed to satisfy the technical specification surveillance requirements provides an acceptable level of quality and safety as an alternative to ASME Section XI system pressure testing.
Any system leakage would be identified by the parameters monitored before a significant reduction in structural integrity of the components could occur. If evidence of leakage is identified as a result of surveillance testing, corrective actions or repairs would be implemented and a follow-up confirmatory test performed.
Technical specification surveillance requires standby emergency diesel generators to be subject to an inspection in accordance with procedures prepared per the manufacturer's recommendation. These examinations provide added assurance the components within the starting air, fuel oil transfer, and glycol cooling subsystems demonstrate pressure boundary
integrity and the ability to provide adequate flow for satisfactory Standby Emergency Diesel Generator operation.
The licensee stated that use of the technical specification surveillance requirements in lieu of ASME Section XI, Table IWD-5220-1 requirements provides an acceptable level of quality and safety and is an acceptable alternative to ASME Section XI system leakage and hydrostatic testing.
3.6 Duration of Proposed Alternative (as stated by the licensee)
The proposed alternative will be used for the fifth 10-year ISi Interval of the ISi program for PBNP that commenced on August 1, 2012, and is scheduled to end on July 31, 2022.
3.7 NRC Staff Evaluation The licensee sought relief from the requirements of ASME Code,Section XI, to perform VT-2 examinations on some Class 3 standby EOG subsystems. The licensee indicated that there are no VT-1 visual examinations imposed on the EOG subsystems because of pressure/temperature or size exemptions included in paragraph IWD-1220 of Section XI and, therefore, verification of pressure boundary structural integrity on EOG subsystems is not included in the PBNP ISi program. Specifically, the licensee requested relief for the starting air system, fuel oil system, and glycol cooling system (G-03 and G-04 only for glycol cooling). The licensee proposed an alternative to the Code requirements which included surveillance testing to demonstrate component operability, as required by the plant technical specifications. This surveillance testing is performed monthly in accordance with test procedures TS-81, 82, 83, and 84 to demonstrate EOG operability. The licensee also stated that operations personnel are specifically trained for the testing of the standby EDGs and that surveillance testing records pressure, level, and temperature which provides the supporting data for the verification of component integrity. Further, essentially the same relief was authorized by the NRC for use at PBNP during the fourth 10-year inspection interval by letter dated March 21, 2003 (ADAMS Accession No. ML030730567). Detailed information concerning specific tests performed on the starting air auxiliary subsystem, fuel oil transfer subsystem, and glycol cooling subsystem was provided by the licensee in its basis for requesting relief stated above.
The licensee has a history in using the PBNP corrective action program to successfully identify instances of leakage associated with the EDGs. The EDGs are tested every month by operations personnel, who are often assisted by the plant system engineers. The EDGs are run to test their ability to start when required and to look for any problems that may have occurred while standing idle. During the testing, the EOG systems are examined for leakage. The licensee monitors the diesels three times each day by walk-downs. During the walkdown, operations personnel look at the appropriate water level, sump tank fuel level, starting air bank pressure, fuel oil day tank level, service water pressure, glycol expansion tank levels, and storage tanks. The operations personnel also take a general look at the diesels. If the readings are not within specifications, the Duty Shift Supervisor is informed and appropriate action is initiated. Also, the diesels are thoroughly examined as part of Routine Maintenance Procedures. Any significant discrepancies require the initiation of an Action Request and, if appropriate, a Work Order to correct the identified discrepancies. Further, the PBNP ISi program requires periodic pressure testing of the service water (SW) piping. The SW piping goes through and around the diesels G-01 and G-02, and is part of their cooling system. During
conduct of the periodic SW pressure testing, the VT-2 examiners are required to go around and look above and below the diesels for leakage. The examiners are trained to report any evidence of a discrepant condition, and while not specifically looking at the diesel systems, would likely notice any evidence of obvious leakage. The licensee concluded that the proposed alternative provides an acceptable level of quality and safety.
The licensee proposed to use existing surveillance tests that are required by the current plant technical specifications as an alternative to the ASME Code-required pressure testing. The required surveillance testing is routinely performed on various portions of the subject system and is intended to demonstrate component operability. As such, the tests provide an indirect verification of the leakage integrity of the pressure boundary, in lieu of a direct visual examination performed under normal operating pressure.
The subject subsystems receive these tests every 30 days, which is a much more frequent testing schedule than the system pressure testing required by the ASME Code (approximately each 40 and 120 months). During each surveillance test, pressure drop, fluid level, flow rates and/or temperature data is monitored. Each of these indicators has associated allowable values which, if exceeded, would alert an operator of potential problems, including pressure boundary leakage. The NRC staff expects that system leakage would be identified by the parameters monitored before a significant reduction in structural integrity of the components could occur. If evidence of leakage is identified as a result of surveillance testing, corrective actions or repairs would be implemented and a follow-up confirmatory test performed. In its December 8, 2014, response to the staff's RAI (ADAMS Accession No. ML14342A417), the licensee confirmed that any repairs or replacement of Class 3 piping covered by this relief request would be conducted in accordance with ASME Code,Section XI, IWA-4000.
The NRC staff finds that the proposed surveillance testing, although not a direct examination and less sensitive to small leakage than the ASME Code-required pressure testing, is performed at more frequent intervals and the parameters monitored should ensure that the leakage integrity of the pressure boundary is maintained. Therefore, the NRC staff concludes that the proposed alternative provides an acceptable level of quality and safety for components in the EOG subsystems.
The NRC staff finds that the alternative testing requirements described above are acceptable because the surveillance testing would detect any leakage in the system, which is the main objective of the ASME Code-required VT-2 examinations. The NRC staff also finds that the surveillance testing performed in accordance with the requirements of the plant technical specifications provides an acceptable level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the proposed alternative provides an acceptable level of quality and safety. Accordingly, the staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ).
Therefore, the staff authorizes the proposed alternative for the fifth ISi interval at Point Beach Nuclear Plant, Units 1 and 2.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: M. Audrain, NRR/DE Date: May 7, 2015
ML15099A018 *via email dated April 2, 2015 OFFICE LPL3-1/PM LPL3-1/LA EPNB/BC* LPL3-1/BC NAME MChawla MHenderson DAiiey DPelton DATE 04/30/2015 04/28/2015 04/02/2015 05/07/2015