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EPID:L-2022-LLR-0028, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs (Open) |
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Category:Code Relief or Alternative
MONTHYEARML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23262B4442023-09-26026 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-14 ML22194A9152022-07-15015 July 2022 Proposed Alternative I4-R13 for Repair of Recirculation Flow Control Valves RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0202 March 2022 Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques RS-19-066, Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency2019-06-28028 June 2019 Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19121A3172019-05-20020 May 2019 Relief Request 13R-15, Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Code, Section X1, Rules for Inservice Inspection (EPID-L-2018-LLR-0123) 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 JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds RS-18-112, End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval2018-09-19019 September 2018 End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18011B1112018-01-23023 January 2018 Relief from the Requirements of the ASME Code and OM Code Relief Requests I4R-04, Proposed Alternatives to Various Inservice Inspection Interval (ISI) Requirements of the American Society of Mechanical Engineers, Section XI, 2007 Edition ML18003A2472018-01-0808 January 2018 Relief from the Requirements of the ASME Code and OM Code Relief Requests I4R-01 (CAC Nos. MF9758 and MF9759; EPID L-2017-LLR-0057) ML17354A8542018-01-0303 January 2018 Approval of Alternative to the ASME Code Regarding Inspection of Hydrogen Recombiner System Piping - Relief Request I4R-08 (CAC Nos. MF9772 and MF9773; EPID L-2017-LLR-0036) RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-012017-11-10010 November 2017 County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01 ML17261A0782017-10-12012 October 2017 Request for Additional Information Regarding Relief Request I4R-01 (CAC Nos. MF9758 and MF9759; EPID L-2017-LLR-0057) ML17171A3202017-07-0505 July 2017 Relief from the Requirements of the ASME Code Regarding Relief Request I4-R-10, Proposed Alternative to Utilize Code Case N-513-4 ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17059C5832017-03-0101 March 2017 Relief from ASME Code for OM Code Re. RR RV-01 Proposed Alternative to Inservice Testing Requirement of ASME Code for OM Code ML17024A2652017-02-22022 February 2017 Letter to Licensee, Approvals of Relief Requests-G-01, RP-01, and RP-04 for the Fourth 10-Year Inservice Testing Intervals (MF8490, MF8491, MF8492, MF8493, MF8498, and MF8499) ML17047A5862017-02-22022 February 2017 Letter to Licensee, Approvals of Relief Requests-RP-02, and RP-03 for the Fourth 10-Year Inservice Testing Intervals (CAC Nos. MF8494 - MF8497) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML15226A4122015-10-30030 October 2015 MF5654 & MF5655, Letter to Licensee -Authorization of RR-I3R14 (MF5654 & MF5655-Lasalle RRI3R14(08-14-2015) ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0925703212009-09-21021 September 2009 Relief Request CR-26, Inservice Inspection Program Relief Regarding Examination Coverage for the Second 10-Year Inservice Inspection Interval, MD9817 - MD9818 ML0809301222008-05-0707 May 2008 Request for Relief from ASME OM Code for the Third Inservice Testing Interval ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0736105872008-01-30030 January 2008 Request for Relief Nos. I3R-03, I3R-04, I3R-08, I3R-09 and I3R-10: Third 10-Year Interval Inservice Inspection Program Plan ML0333001472004-01-28028 January 2004 Relief Request, Shell Weld Inspection, TAC No MB9755 and MB9756 ML0219800132002-07-29029 July 2002 Code Relief, Relief Request RV-13 to Delay Sr/V Setpoint Testing 2023-09-26
[Table view] Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report IR 05000373/20234012023-11-0707 November 2023 County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401 RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000374/20230102023-10-11011 October 2023 NRC Inspection Report 05000374/2023010 IR 05000373/20233012023-09-15015 September 2023 Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212A9012023-08-0303 August 2023 Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report IR 05000373/20230022023-08-0101 August 2023 County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis ML23192A5272023-07-12012 July 2023 NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 ML23186A2062023-07-0606 July 2023 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010 ML23181A1502023-06-30030 June 2023 Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report 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 IR 05000373/20230112023-06-26026 June 2023 County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167A0352023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel ML23171A9562023-06-12012 June 2023 Post Exam Ltr RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000373/20230012023-05-10010 May 2023 County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001 ML23123A2202023-05-0303 May 2023 Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23121A1612023-05-0101 May 2023 Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23107A1822023-04-18018 April 2023 Operator Licensing Examination Approval Lasalle County Station, May 2023 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000373/20220062023-03-0101 March 2023 Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006) RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station ML23024A1372023-02-0303 February 2023 Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2 ML23031A1972023-01-31031 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011 IR 05000373/20220042023-01-31031 January 2023 County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 2024-01-05
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report ML23262B4442023-09-26026 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-14 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements ML22341A2222022-12-28028 December 2022 Issuance of Amendment Nos. 257 and 243 to Renewed Facility Operating Licenses New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies and Changes to Core Operating Limits Report ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22194A9152022-07-15015 July 2022 Proposed Alternative I4-R13 for Repair of Recirculation Flow Control Valves ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML21362A7212022-02-0404 February 2022 Issuance of Amendment Nos. 255 and 241 Revision to Technical Specifications to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21162A0692021-09-0707 September 2021 Issuance of Amendment Nos. Xxx and Yyy Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21188A0192021-07-28028 July 2021 Proposed Alternative I4R-12, Revision 2 from Code Surface Examinations Requirements of the ASME Code for Valves 2B33 F60A and 2B33 F60B Repairs ML21158A2282021-07-13013 July 2021 Issuance of Amendments to Renewed Facility Operating Licenses a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML21166A1682021-06-25025 June 2021 ML21082A4222021-05-27027 May 2021 Issuance of Amendment Nos. 249 and 235 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19217A3062019-09-10010 September 2019 Relief Request RV-03, Relief from the Requirements of the ASME Code Related to Pressure Isolation Valve Testing Frequency ML19218A3652019-08-29029 August 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19121A5052019-06-24024 June 2019 Issuance of Amendments to Renewed Facility Operating Licenses Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator ML19121A3172019-05-20020 May 2019 Relief Request 13R-15, Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Code, Section X1, Rules for Inservice Inspection (EPID-L-2018-LLR-0123) 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 ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML19025A2882019-02-14014 February 2019 Issuance of Amendments to Renewed Facility Operating Licenses Revision of Technical Specifications to Adopt TSTF-334-A ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18311A2652019-01-0202 January 2019 Issuance of Amendments Nos. 233 and 219 to Renewed Facility Operating Licenses License Amendment Request for Temporary Extensions to Technical Specifications ML18278A0302018-12-19019 December 2018 Issuance of Amendments 232, 218 to Renewed Facility Operating Licenses Request to Revise the Technical Specifications Surveillance Requirement to Revise the Lower Setpoint Tolerance for Safety/Relief Valves ML18254A3672018-10-29029 October 2018 County 1 & 2; and Quad Cities 1 & 2 - Issuance of Amendments 220, 259, 252, 231, 217, 271 and 266 to Revise Technical Specification Requirements for Inoperable Snubbers ML18226A2022018-10-15015 October 2018 Issuance of Amendments to Renewed Facility Operating Licenses Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control 2023-09-26
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July 15, 2022 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNIT 1 PROPOSED ALTERNATIVE I4-R13 FOR REPAIR OF RECIRCULATION FLOW CONTROL VALVES (EPID L-2022-LLR-0028)
Dear Mr. Rhoades:
By application dated March 2, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22061A000), as supplemented by letters dated March 3 and 4, 2022 (ML22062B658 and ML22063B176, respectively), Constellation Energy Generation, LLC (the licensee) submitted request I4-R13 in accordance with paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to certain requirements of 10 CFR 50.55a, Codes and standards, for LaSalle County Station (LaSalle), Unit 1.
During the February 2022 refueling outage L1R19 for LaSalle, Unit 1, the licensee identified two degraded reactor recirculation flow control valves.Section XI of the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), as incorporated in 10 CFR 50.55a, requires, in part, that the repair of these valves be performed in accordance with the applicable construction code. The proposed alternative to the ASME Code,Section XI, would allow the licensee to use enhanced visual testing for the repair of the two valves, instead of performing the liquid penetrant testing and radiographic examinations required by the construction code. Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use the proposed alternative on the basis that complying with the specific ASME Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application, as supplemented, and concluded that the licensee adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, on March 7, 2022, the NRC staff verbally authorized the licensee to use the proposed alternative described in its application, as supplemented, at LaSalle, Unit 1, for the repair of the two degraded reactor recirculation flow control valves during refueling outage L1R19. By email dated March 7, 2022 (ML22066A762),
the NRC staff provided a summary of the verbal authorization to the licensee. The enclosed safety evaluation documents the NRC staffs detailed technical basis for the verbal authorization.
D. Rhoades All other ASME Code,Section XI, requirements for which an alternative was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
If you have any questions, please contact Bhalchandra Vaidya at 301-415-3308 or via email to Bhalchandra.Vaidya@nrc.gov.
Sincerely, Digitally signed by Scott Scott P. Wall P.Date:
Wall 2022.07.15 12:09:08 -04'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-373
Enclosure:
Safety Evaluation cc: ListServ
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PROPOSED ALTERNATIVE REQUEST I4-R13 FOR THE REPAIR OF RECIRCULATION FLOW CONTROL VALVES LASALLE COUNTY STATION, UNIT 1 CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-373
1.0 INTRODUCTION
By application dated March 2, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22061A000), as supplemented by letters dated March 3 and 4, 2022 (ML22062B658 and ML22063B176, respectively), Constellation Energy Generation, LLC (the licensee) submitted request I4-R13 in accordance with paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to certain requirements of 10 CFR 50.55a, Codes and standards, for LaSalle County Station (LaSalle), Unit 1.
During the February 2022 refueling outage L1R19 for LaSalle, Unit 1, the licensee identified two degraded reactor recirculation flow control valves.Section XI of the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), as incorporated in 10 CFR 50.55a, requires, in part, that the repair of these valves be performed in accordance with the applicable construction code. The proposed alternative to the ASME Code,Section XI, would allow the licensee to use enhanced visual testing (EVT-1) for the repair of the two valves, instead of performing the liquid penetrant testing (PT) and radiographic examinations required by the construction code. Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use the proposed alternative on the basis that complying with the specific ASME Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
On March 7, 2022, the U.S. Nuclear Regulatory Commission (NRC) staff verbally authorized the licensee to use the proposed alternative described in its application, as supplemented, at LaSalle, Unit 1, for the repair of the two degraded reactor recirculation flow control valves during refueling outage L1R19. By email dated March 7, 2022 (ML22066A762), the NRC staff provided a summary of the verbal authorization to the licensee. This safety evaluation documents the NRC staffs detailed technical basis for the verbal authorization.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(g)(4) state, in part, that ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access Enclosure
provisions and the preservice examination requirements, set forth in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the applicable editions and addenda of the ASME Code to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulations in 10 CFR 50.55a(g)(4)(ii) require, in part, that inservice examination of components and system pressure tests conducted during successive 10-year inservice inspection intervals (i.e., after the initial 10-year interval) must comply with the latest edition and addenda of the ASME Code (or the optional ASME Code cases) incorporated by reference in 10 CFR 50.55a(a) 18 months before the start of the 10-year interval subject to the conditions listed in 10 CFR 50.55a(b).
The regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements in paragraphs (b) through (h) of 10 CFR 50.55a may be 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.
3.0 TECHNICAL EVALUATION
3.1 Licensees Request 3.1.1 Components Affected The affected components are the reactor recirculation flow control valves 1B33-F060A (valve A) and 1B33-F060B (valve B) for LaSalle, Unit 1.
3.1.2 Applicable ASME Code Requirements The 2007 Edition through 2008 Addenda of the ASME Code,Section XI, is applicable to the current inservice inspection interval at LaSalle, Unit 1. The weld repairs for valves A and B must meet the requirements of paragraph IWA-4411 of the ASME Code,Section XI, which states, in part, that welding, brazing, fabrication, and installation shall be performed in accordance with the Owners Requirements and in accordance with the Construction Code of the item. The applicable construction code is the 1971 Edition with the Summer 1972 Addenda of the ASME Code,Section III. The 1971 Edition of the ASME Code,Section III, includes the following requirements applicable to the repair of valves A and B:
Paragraph NB-2571 requires, in part, that the internal surface of the component be examined using magnetic particle or liquid penetrant methods after machining.
Paragraph NB-2578 states that elimination of defects shall be in accordance with paragraph NB-2538. Subparagraph NB-2538(a)(3) states that after defect elimination, the area is re-examined by the magnetic particle method or the liquid penetrant method to assure that the defect has been removed or the indication reduced to an acceptable size.
Subparagraph NB-2539.4 requires each repaired weld to be examined by magnetic particle or liquid penetrant methods, and repair cavities, the depth of which exceeds the lesser of 3/8 inches or 10 percent of the section thickness, to be radiographed.
3.1.3 Reason for Request During the February 2022 refueling outage L1R19 for LaSalle, Unit 1, the licensee discovered excessive wear in the internals and lower body of valves A and B. The valves would require repair in accordance with Section XI and Section III of the ASME Code. The repair of the valves would consist of machining and grinding the inside surface of the valves and building up the inner surface with weld metal, installing the new valve internals, and welding an anti-rotation device into place.
In accordance with 10 CFR 50.55a(z)(2), the licensee stated that compliance with the requirements specified in Section 3.1.2 of this safety evaluation would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The licensee stated, in part, that performing the required PT and radiographic examinations was a hardship due to the significant radiologic dose that would be received by personnel performing these examinations.
3.1.4 Proposed Alternative The licensee proposed to use EVT-1 in lieu of PT for the various stages of the repair for both the pressure-retaining weld buildup on the valve body as well as for the installation of a fillet weld to fix the anti-rotation device in place. In addition, the licensee would not perform the radiographic examinations.
3.2 NRC Staffs Evaluation The licensee stated that the repairs of valves A and B would consist of machining and grinding the inside surface of the valves and building up the inner surface with weld metal, installing the new valve internals, and welding an anti-rotation device into place. The worn areas of valves A and B would be machined to restore the valve body dimensions and tolerances that support internal components. As part of the repair, additional weld material will be applied to valve A and machined to approximately 0.157 inches above the required minimum wall thickness in the area of wear. While no additional weld material buildup was planned for valve B, the licensee stated that welding may be required in the final repair plan. The final configuration of valve B would leave the valve with greater than 0.200 inches above the required minimum wall thickness in the area of wear.
To enhance design and performance of valves A and B, the licensee stated it would install modified lower plug guides made of 316 stainless steel, Stellite-overlayed material. The modified guides includes an anti-rotation segment similar to the original guide design. The material of the anti-rotation segment is specified as 304L stainless steel material. The anti-rotation segment will be fillet welded or partial penetration welded along its entire outer curved edge on the top face with an appropriately qualified and suitable material for the design of the weld joint.
The licensee proposed to use EVT-1 in lieu of PT for the various stages of the repair for both the pressure-retaining weld buildup on the valve body as well as for the installation of a fillet weld to fix the anti-rotation device in place. EVT-1 is an examination technique that uses remote camera equipment to perform visual inspections of components. The effectiveness of EVT-1 has been extensively researched by the NRC, and this research is summarized in NUREG/CR-7246, Reliability Assessment of Remote Visual Examination, dated August 2018 (ML18228A516). The research found that EVT-1 provides generally reliable detection (i.e.,
80 percent probability of detection at 95 percent confidence level) of flaws with crack openings wider than approximately 25 microns (0.001 inches). EVT-1 is not considered to be equivalent to PT, and EVT-1 is more sensitive to issues such as lighting angle, viewing angle, and surface scratches, which can hide small cracks. The use of EVT-1, as opposed to PT, could result in small cracks being left in the welds. While not as effective as PT, the NRC staff finds that the use of EVT-1 provides reasonable assurance that if there is significant cracking in the welded surfaces it would be detected.
As part of the proposed alternative, the licensee would not perform a radiographic examination of the final repair. Radiographic examinations are used to detect possible subsurface weld defects, such as porosity, lack of fusion, and slag. Not performing the radiographic examinations increases the probability that such weld defects will remain in the repair. The EVT-1 may be able to detect surface-breaking flaws but would be unable to detect embedded flaws.
The licensee stated that it performed wear rate calculations to ensure that wear does not challenge the minimum wall thickness due to the internal design change for the valves. The licensee calculated a wear rate of 0.00015 inches per operating cycle for the flow control components of valves A and B. Uncertainties in the calculations were addressed through conservative assumptions described in the licensees letter dated March 3, 2022. The licensee stated that the calculated wear rate is sufficiently low to support operation with the modified valve designs to the end of the operating life for the plant.
The weld buildups and final repairs for valves A and B would restore the required minimum wall thickness with possible small weld defects left in place. The NRC staff notes that the primary damage mechanism in the area to be repaired is wear. The NRC staff determined that the presence of small cracks or weld defects, such as porosity and slag, would not significantly increase the risk of structural failure of the repaired areas. The licensee stated that the wear on valves A and B was associated with a sustained operation in low-flow conditions. The licensee has taken corrective actions to significantly reduce the time spent operating under such conditions in the future. The NRC staff determined that additional wear of the repaired areas would not be expected since the modified lower plug guides will be made of 316 stainless steel and the anti-rotation device will be welded into place. In addition, the wear rate calculations show that the valve body is not expected to experience thinning due to wear below the minimum wall thickness for current licensed life of the facility. Therefore, the NRC staff concludes that, given the nature of the subject repair, EVT-1 is sufficient to provide reasonable assurance of the structural integrity of the repaired valves.
The licensee estimated that performing the required PT examination would result in a radiological dose that is 2.326 person-rem higher than performing the proposed EVT-1 examination. The licensee also estimated that performing the required radiographic examination would result in a radiological dose of 0.906 person-rem. In accordance with 10 CFR 50.55(z)(2),
the NRC staff finds that it would be a hardship for the licensee to perform the PT and radiographic examinations required by the ASME Code because of the higher radiological dose that would be received in comparison to the proposed alternative.
Based on the above, the NRC staff finds that the licensee has demonstrated that compliance with the specified PT and radiographic examination requirements in the ASME Code for the repair of valves A and B would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety in accordance with 10 CFR 50.55a(z)(2).
4.0 CONCLUSION
As set forth above, the NRC staff determined that the licensees proposed alternative for the repair of valves A and B would provide reasonable assurance of the structural integrity of the valves. The NRC staff also determined that complying with the specified PT and radiographic examination requirements in the ASME Code for the repair of valves A and B would result in hardship or unusual difficulty without a compensating increase in the 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 50.55a(z)(2). Therefore, the NRC authorizes the licensee to use the proposed alternative described in its application, as supplemented, at LaSalle, Unit 1, for the repair of valves A and B during refueling outage L1R19.
All other ASME Code,Section XI, requirements for which an alternative was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Stephen Cumblidge, NRR Date: July 15, 2022
ML22194A915 OFFICE DORL/LPL3/PM DORL/LPL3/LA DNRL/NPHP/BC DORL/LPL3/BC NAME BVaidya (BPurnell for) SRohrer MMitchell NSalgado (SWall for)
DATE 7/14/2022 7/14/2022 6/9/2022 7/15/2022