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MONTHYEARRS-17-072, Fourth 10-Year Interval Inservice Inspection Program Relief Requests2017-05-30030 May 2017 Fourth 10-Year Interval Inservice Inspection Program Relief Requests Project stage: Request ML17171A2282017-06-22022 June 2017 Acceptance for Review of Proposed Fourth 10-Year Interval Inservice Inspection Program Relief Request Nos. 14R-01, 14R-02, 14R-03, 14R-04, 14R-06, 14R-07, 14R-08, and 14R-09 Project stage: Acceptance Review 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 Project stage: Approval 2017-06-22
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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 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) 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) 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
MONTHYEARRS-24-092, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS2024-09-19019 September 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS ML24260A0492024-09-16016 September 2024 Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000373/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005) IR 05000373/20244022024-08-28028 August 2024 County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer IR 05000373/20240022024-08-13013 August 2024 County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000373/20244202024-08-0505 August 2024 County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420 05000373/LER-2024-003, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024 Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions ML24178A2522024-06-27027 June 2024 County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000373/20240102024-05-29029 May 2024 County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24131A1512024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 IR 05000373/20240012024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24108A1562024-04-15015 April 2024 Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24071A2122024-03-12012 March 2024 County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection IR 05000373/20230062024-02-28028 February 2024 Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006) RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces IR 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 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 2024-09-06
[Table view] Category:Safety Evaluation
MONTHYEARML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces 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 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 2024-02-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHING.TON, 0.C. 20555-0001 January 23, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Offlcer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2, RELIEF FROM THE REQUIREMENTS OF THE ASME CODE AND OM CODE RE: RELIEF REQUESTS 14R-04, PROPOSED ALTERNATIVE TO INSERVICE INSPECTION INTERVAL (ISi) REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME CODE), SECTION XI, 2007 EDITION WITH THE 2008 ADDENDA FOR THE FOURTH SUBSEQUENT 10-YEAR ISi INTERVALS (CAC NOS. MF9764 AND MF9765; EPID L-2017-LLR-0034)
Dear Mr. Hanson:
By letter dated May 30, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17150A449), Exelon Generation Company, LLC (EGG, the licensee) submitted relief requests (RRs) associated with the fourth !nservlce Inspection (ISi) interval for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 20i7, and end on September 30, 2027, and will comply with the American Society of Mechanlcal Engineers Boiler and Pressure Vessel (ASME Code},Section XI, 2007 Edition with the 2008 Addenda.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1 ), the licensee requested the following RR for the LSCS fourth 10-year ISi interval:
Relief Request 14R-04 requests approval of alternative post-tensioning system inspection scheduling requirements for sites with two plants. EGC requested approval of a proposed alternative to the post-tensioning system inspection scheduling requirements of the American Society of Mechanical Engineers Baiter and Pressure Vessel Code (ASME Code},Section XI, IWL-2421, on the basis that the proposed alternative will provide an acceptable leve! of quality and satety. Relief Is requested for the remainder of the current fourth ISi interval. as well as the remaining term of the renewed facility operating licenses (NPF-11 for Unit 1 and NPF-18 for Unit 2}, which expire at midnight on April 17, 2042, and at midnight on December 16, 2043, for LSCS, Units 1 and 2. respectively. The fourth ISi interval, as weU as the remaining term of the renewed facility operating licenses, refers to the LSCS, Units 1 and 2, current fourth and upcoming fifth and sixth 120-month \SI program intervals.
The other RRs submitted by letter dated May 30, 2017 (ADAMS Accession No. ML17150A449),
have been addressed via separate correspondence.
- 8. Hanson The U.S. Nuclear Regulatory Commission (NRC} staff has reviewed the subject request, and concludes, as set forth in the enclosed safety evaluation (SE) that the alternative proposed by the licensee in the AR 14R-04, to use the modified surveillance schedule of ASME Code, Section Xi, IWL-2421 (b), based on treating the two primary concrete containment units at LSCS as a "twin containment site" provides an acceptable level of quality and safety. Accordingly, the NRG staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ).
Therefore, the NRC staff authorizes the use of AR 14R-04 at LSCS, Units 1 and 2, for the remainder of the current fourth ISi lnterval, as we!! as the remaining term of the renewed facility operating licenses (NPF-11 for Unit 1 and NPF~ 18 for Unit 2), which expire at midnight on April 17, 2042, and at midnight on December 16, 2043, for LSCS, Units 1 and 2, respectively. The fourth \SI Jnterva!, as well as the remaining term of the renewed facili1y operating licenses, refers to the LSCS, Units 1 and 2, current fourth and upcoming fifth and sixth 120-month ISi program intervals.
AU other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including th!rd*party rev!ew by the Authorized Nuclear lnservice Inspector.
Please contact the Project Manager, Bhalchandra K. Vaidya at (301)415-3308, if you have any questions.
Sincere!y, Jc__l' CJ Dav(d J. Wrona, /hief v_
Plant Licensing Branch !II Division of Operating Reactor Ucensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-37 4
Enclosure:
As stated cc w/enc!osure: Ustserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 14R-04 FOR POST-TENSIONING SYSTEM INSPECTION SCHEDULING REQUIREMENTS FOR SITES WITH TWO PLANTS LASALLE COUNTY STATION, UNITS 1 AND 2 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 DOCKET NOS. 50-373 AND 50-374
1.0 INTRODUCTION
By !etter dated May 30, 2017 (Agencywide Document Access and Management System (ADAMS) Accession No. ML17150A449), Exelon Generation Company, LLC (EGC), the licensee of LaSalle County Station (LSCS}, Units 1 and 2, requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Subsection IWL-2421, 2007 Edition with the 2008 Addenda, incorporated by reference in Title 10 of the Code of Federal Regulations ( 10 CFR) 50.55a "Codes and S1andards."
Specifically, pursuant to 10 CFR 50.55a(z)(1 ), EGG requested approval of a proposed alternative to posHensioning system inspection scheduling requirements of !WL-2421. The requested approval was for the remainder of the current fourth Cnservice inspection (IS!) program intefVa! (third 10-year containment inservice inspection (GISI) program interval) and tor the remaining 10-year inspection intervals of the LSCS renewed facility operatlng licenses (NPF-11 for Unit 1, expiring at midnight on April 17, 2042: and NPF-18 tor Unit 2, expiring at midnight on December 16, 2043), on the basis that the proposed alternative provides an acceptable !eve! o1 quality and safety.
2.0 REGULATORY EVALUATION
Regulation 10 CFR 50.55a(g)(4) requires that throughout the service lite of boiling- or pressurized-water-cooled nuclear power faCl!ities, !Sis, repairs, and replacements of ASME Code Class CC pressure retaining components and their integral attachments must meet ASME Code,Section XI, and addenda requirements as incorporated by reference in 10 CFR 50.55a and subject to specified conditions and llmitations. Subsection IWL of the ASME Code,Section X!, provides rules for CIS!
and repair/replacement activities ot the reinforced concrete and post tensioning systems of Class CC components. The regulation in 10 CFR 50.55a(z)( 1) states that alternatives to the requirements of paragraphs (b) through (h) of 10 CFR 50.55a, "Codes and Standards," or portions thereat, may Enclosure
be used when au1horized by the Director of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission (NRG) provided that the licensees proposed alternative demonstrates an acceptable !eve! of quality and safety. By this relief request (RR), EGC has proposed an alternative to the requirements of 10 CFA 50.55a(g)(4) for Subsection IWL-2421 regarding scheduling of ISi and testing of identical posHensioning systems for sites with multiple plants.
In paragraph IWL-2421(a) of the ASME Code,Section XI, 2007 Edition, 2008 Addenda, in the current code of record (COR), as well as of the previous applicable COR, states that the test schedule tor the unbonded posHensioning tendon system of concrete primary containments for sites with multiple plants may be modified as specified in !WL~2421{b) provided the toUowing are met:
- 1. Both primary containments utmze the same pre~stressing system and are essentially Identical in design;
- 2. PosHensioning operations for the two primary containments were completed not more than 2 years apart; and
- 3. Both containments are similarly exposed to or protected from the outside environment.
For unbonded posHensionlng systems, paragraph IWL~2421 (b) specifies that when the conditions of IWL~2421(a) are met, the inspection dates and examination requirements may be as follows:
- 1. For the containment with the first structural integrity test (SIT), all examinations required by IWL-2500 shall be performed at 1, 3, and 10 years and every 1O years thereafter. Only the examinations required by IWL-2524 and IWL-2525 need be performed at 5 and 15 years and every 10 years thereafter; and
- 2. For each subsequent containment constructed at the site, au examinations requlred by IWL-2500 shall be pertormed at 1, 5, and 15 years and every 10 years thereafter.
Only the examinations required by !WL-2524 and IWL-2525 need be pertormed at 3 and 10 years and every 10 years thereaf1er.
3.0 TECHNICAL EVALUATION
3.1 AA 14A-04 The !icensee is requesting relief pursuant 10 CFR 50.55a(z)(1) from the post~tensioning system inspection scheduling requirements in IWL~2421 for sites with two plants, on the basis that the proposed alternative will provide an acceptable level of quaMy and safety.
3.1.1 ApplJcable ASME Code Requirements and Components Affected The licensee is requesting relief as part of eight RAs related to the fourth 10-year !nservice Inspection (IS!) Program interval. EGC is requesting relief from the ASME Code,Section XI, 2007 Edition, 2008 Addenda, concrete containment post-tensioning system testing and examination scheduling requirements recognizing the two LSCS primary containments as "twin containments."
3.1.2 Proposed Alternative and Basis for Request In this request, the licensee discusses how the modified test schedule of IWL~2421 (b) curren1!y in use through past NRC approvals will continue to be used for reinforced concrete (C!ass CC concrete containment components) pursuant to ASME Code,Section XI, Table IWL-2500-1, Examination Category L-B, "Unbanded PosHens!oning System," Examination Category L2.10, "Tendon," tests, and Examination Category L2.20, (tendon) 'Wires or Strands," examinations for sites with muttip!e plants.
The licensee previously stated the IWL-2421 (a) requirements for identification of unbonded post.tensioned concrete containments for sites with two plants as twins containments," noting that code requirements (i) and (W) are satisfied because LSCS, Units 1 and 2, primary containments utilize the same prestressing system, are essentially identical in design, and both primary containments are similarly exposed to or protected from the outside environment.
However for code requirement (ii), the !icensee notes the post.tensioning operations for the two plants were 29 months apart or 5 more months than the ASME Code allowance of 2 years.
The licensee discussed past NRC RR approvals that identified the LSCS primary containments as "twin containments." !n a letter dated June 3, 1994, the NRC !n Amendments No. 100 for LSCS, Unit 1, and No. 84 for LSCS, Unit 2, approved the use of the guidance contained in Regulatory Guide {RG) 1.35, "lnservice Inspection of Ungrouted Tendons in Prestresssed Concrete Containments, Revision 3," and the use of the provisions of surveillance requirement (SR) 3.0.2, in addition to the treatment of both LSCS primary containments as '"twin containments." The llcensee's request notes that the 2-year period was also specified in AG 1.35 but was based on the pertormance of SITS which tor the two LSCS primary containments were 55 months apart, and that assessment of deflections obtained from multiple SITs at several !ocations lead NRC to conclude the designation o1 the two primary containments as "twin containments" was acceptable. The licensee's request further notes that !t is similar in approach to the previously approved RR !3A-05 associated with the second 10-year CISI program interval approved by the NRC on January 15, 2008.
The licensee further stated that for the continued treatment of the two LSCS primary containments during the Third CISI 10-year Program Interval as "twin containments," !WL surveillances demonstrated that the 29 months apart completion of post-tensioning operations between the two LSCS primary containments is not a factor affecting the performance of the containments or contributing to unique conditions that may subject either of the two primary containments to a different potential structura! or tendon deterioration.
The current RA states that to date both LSCS primary containments have met the required post-tensioning system surveillance acceptance criteria, or ASME Code,Section XI, repair and replacement activities have been completed to return them to acceptable condition. The request also states that the initiation of the IWL-2400 rolling 5 year schedule was based on the previous inspection dates under the station tendon surveiUance program prior to Subsection IWL being endorsed, The licensee further states that the modified inspection and examination schedu!e of !WL-2421(b) will continue to be used for LSCS, Unlts 1 and 2, tendon tests and wire/strand examinations throughout the requested relief intervals. To date, completed post~
tensioned system inspections include years 1, 3, 5, 10, 15, 20, 25, 30, 35 for LSCS, Unit 1; and for years 1, 3, 5, 10, 15, 20, 25, and 30 for LSCS, Unit 2, with the tendon and wire/strand 1ests being~completed every other 5 year period.
3.1.3 Duration of Proposed Alternative The licensee requested that the duration of the proposed alternative Is tor the fourth ISi and third C!S! 1O*year program Intervals as weU as for the remaining term of the renewed LSCS facility operating licenses. The applicab!e !Sis are the fourth and upcoming fifth and sixth 1O*year ISi program intervals.
3.2 Staff Evaluation The NRC staff reviewed the approvals of previous RRs (as discussed below} that considered the two LSCS primary containments as "twin containments" based on Subsection IWL~2421 (a) and the modified tendon testing and wire/strand examination schedule of IWL*2421(b) which establish precedence for this RR.
In a letter dated June 3, 1994 (ADAMS Accession No. ML021130097), the NRG approved the licensee's request to delete technical specifications Section 3/4.6.1.5. "Primary Containment Structural Integrity," and the associated SRs and replace them with the "lnservlce Inspection Program for Post~Tensioning Tendons." The program based on AG 1.35, Revision 3, recognized the two containments as "twin containments" not on the RG 1.35 recommended guidance of 24 months but on their 55 months apart SITs.
The NRC staff also approved Amendment No. 148 for Unit 1 and Amendment No. 134 for Unit 2, dated August 16, 2001 (ADAMS Accession No. ML012060445), which reauthorized treatment of the two LSCS primary containments as "twin containments." The amendments changed the AG 1.35, Revision 3, referenced in the "lnservice Inspection Program tor Post~
Tensioning Tendons" with the newly established regulatory requirement of 10 CFA 50.55a incorporating by reference Subsection IWL of the ASME Cade Section XI, 1998 Edition. The ASME Code, Subsection IWL-2421 (a), requirements to which the licensee referenced at the time of submittal recogni2ing the two primary containments as "twin containments are identical to the COR the licensee is using for this request for the third 10-year C!SI program interval.
Concurrently, the NRG also approved RR CR-32 (ADAMS Accession No. ML012050221 ), in which the staff concluded that the structural behavior of the two LSCS primary containments and their post-tensioning systems are simitar, aUowing them to be considered as "twin containments" for scheduling their tendon surveillance intervals.
On January 15, 2008, the NRC approved tor the second 10-year GISI program interval RR 13R-05 (ADAMS Accession No. ML073521568), which authorized LSCS to continue treatment of Its two primary containments as twin containments" and allowed the modified test schedule o1 IWL-2421 (b). In RR 13R-05, the licensee used the same approach as in RR CR-32.
The current and fourth !4R-04 RR seeks once again the recognition of the two LSCS containments as "twin containmentsn that would allow the modified schedule for the third 1O~year CISI program interval and for the remaining term of its renewed facility operating licenses. As previously stated, the RR was initiated pursuant 10 CFR 50.55a(g)(4)(ii) that requires the applicable "[i]nservice examination of components and system pressure tests conducted during successive 120-month inspection intervals ... [to] ... comp!y with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in paragraph [50.55](a) ... 12 months before the start of the 120-rnonth inspection Interval," which at the time of submittal was ASME Code,Section XI, 2007 Edition, 2008 Addenda.
. 5.
As noted above, in the review of past RR approvals, IWL*2421 for ASME Code,Section X!,
2007 Edition, 2008 Addenda, reads the same as in the previous editions. However, during the approval of RR IR3-05, even though there were identical assessments of !WL-2421 in past relief considerations, the NRG staff expressed concerns when deliberated on the structural integrity evaluation of one unit when !Sis SRs performed in the other ("twln") unit yielded quest!onable sampled tendon prestress forces or degraded tendons, The licensee in response to a relevant request tor additional information, stated that inspections and testing of the post-tensioning system follow a plant procedure to evaluate the same condltion(s) at the other site unit in the event of tailed acceptance criteria in one unit. Furthermore, the licensee considers the identified unacceptable condition(s) in the Corrective Action Program for appropriate resolution. leading the NRC staff to conclude of the existence of "a sound procedure and rationale approach to address tendon integrity issues.
In 2016, the NRG also pe1formed a comprehensive review of the "twin containments" and of the identical tendon prestressing systems at both LSCS primary containment units as documented in NUREG-2205, "Safety Evaluation Report Related to the License Renewal of LaSalle County Station, Units 1 and 2, Docket Nos. 50-373 and 50-374, Exelon Generation Company" (ADAMS Accession No. ML16271A039). During its review, the staff verified that the licensee period!cally evaluates the condition of the "twin containments1' and their unbonded post-tensioning systems through measurements and 1rending of sampled tendon prestressing forces consistent with the ASME Code,Section XI, Subsection IWL, based concrete containment tendon prestress program and the guidance in RG 1.35.1 (ADAMS Accession No. ML003740040).
Consideration was also given ln this RR to extend the IWL~2421(b) modified test schedule based on the recognition that the two LSCS primary containments remain as "twin containments" per IWL-2421{a} discussed above for the remaining term of LSCS renewed facmty operating licenses. On June 11, 2010, the NRC granted an RR to Southern Nuclear Operating Company (ADAMS Accession No. ML100900129), that also involved a relief from the requirements of IWL-2400 for concrete and unbonded post-tensioning system of twin units for the remaining term ot the then ISi interval and for an subsequent !SI intervals provided the requirements in Subsection IWL-2400 of applicable ASME Code COR for these subsequent intervals remains the same as for the one being approved, and that all applicable ASME Code,Section XI, Editions and Addenda for subsequent 120-month inspection intervals are in accordance with 10 CFR 50.55a(g)(4)(ii).
Based on past NRG approvals considering the LSCS, Units 1 and 2, as a "twin containment site" for continuity of inspections, and supplemental reviews and the approvals noted above, the staf1 finds that the EGC's proposed alternative in RR 14R-04, with regard to SRs of the post-tensioning systems of LSCS, Units 1 and 2, would continue to provide acceptable leve! of quality and safety tor the fourth 10-Year 1Sl {third 10-year GISI} program intervals and for subsequent !SI and CIS! intervals, including the requirements of !WL-:2421, "Sites with Multiple Plants" for the applicable ASME COR for these subsequent intervals, including third-party review by the Authorized Nuclear lnservice Inspector.
4.0 CONCLUSION
The NRC staff has reviewed the subject request, and concludes, as set forth above, that the alternative proposed by the licensee in the relief mquest 14R-04, to use the modified surveiUance schedule of ASME Code,Section XI, IWL-2421(b}, based on treating the two primary concrete containment units at LSCS as a "twin containment site," provides an
acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1).
Therefore, the NRG staff authorizes the use of RR 14R-04 at LSCS, Units 1 and 2, for the remainder of the current fourth ISi interval, as well as the remaining term of the renewed facility operating licenses (NPF-11 for Unit 1 and NPF-18 for Unit 2), which expire at midnight on April 17, 2042, and at midnight on December 16, 2043, for LSCS, Units 1 and 2, respectively. The fourth IS! interval, as well a$ the remaining term of the renewed facility operating licenses, refers to the LSCS, Units 1 and 2, current fourth and upcoming fifth and sixth 120-month !SI program intervals.
AU other ASME Code,Section XI. requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear
!nservice Inspector.
Principal Contributor: A. Prinaris, NRR/ESEB Date of issuance: January 23, 2018
ML18011B111
"") No Substantial chance from SE lnout Memorandum and email OFFICE NRR/LPL31PM NRRILPL3/LA NRR/DE/ESEBIBC(') NRRILPL3/BC NAME BVaidva SRohrer BWittick DWrona DATE 01/23/18 01/16/18 01/12/18 12/13/17 01/23/18