Letter Sequence Other |
---|
|
|
MONTHYEARML22076A0322022-03-17017 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-03 Related to PIV Leak Test Frequency Project stage: Acceptance Review ML22256A1152022-09-29029 September 2022 Proposed Alternative to the Requirements of the ASME OM Code Project stage: Other 2022-03-17
[Table View] |
|
---|
Category:Code Relief or Alternative
MONTHYEARML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code ML23041A4262023-02-14014 February 2023 Proposed Alternative to the Requirements of the ASME OM Code ML23033A0982023-02-0303 February 2023 Authorization and Safety Evaluation for Alternative Request I6R-09, Revision 0, ML22332A5492022-12-21021 December 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22327A2632022-11-30030 November 2022 Authorization and Safety Evaluation for Alternative Request No. I6R-01, Rev. 0 ML22256A1152022-09-29029 September 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22265A0862022-09-28028 September 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22264A1752022-09-28028 September 2022 Proposed Alternative to the Requirements of the ASME OM Code 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 ML20169A5842020-07-15015 July 2020 Relief from the Requirements of the ASME Code 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 ML20036D9622020-02-0404 February 2020 Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency RS-20-006, Submittal of Relief Request for Revision to RV-03 Associated with Fifth Inservice Testing Interval2020-01-0202 January 2020 Submittal of Relief Request for Revision to RV-03 Associated with Fifth Inservice Testing Interval ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 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 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 ML18022A6162018-01-24024 January 2018 Approval of Alternatives to the ASME Code Regarding Reactor Vessel Penetration N-11B - Relief Request 15R-11, Revision 3 (CAC No. MF9286; EPID L-2017-LLR-0004) (RS-17-014) RS-18-004, Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-112018-01-0404 January 2018 Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 ML17221A2642017-08-25025 August 2017 Alternative to the Requirements of the ASME Code Regarding Reactor Pressure Vessel Nozzle Assemblies; Relief Request I5R-07 (CAC Nos. MF8989 and MF8990) (RS-16-256) ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML14055A2272014-02-28028 February 2014 Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Testing Program MF1462 ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0928602592010-02-0202 February 2010 Relief, Alternative to Nozzle to Vessel Weld and Inner Radius Examinations ML0907700142009-03-26026 March 2009 Request to Partially Implement Subsequent Edition of ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code), Section ISTC-522, Condition-Monitoring Program & Mandatory Appendix... ML0828201712008-11-25025 November 2008 Relief Request No. RV-30G from Main Steam Electrometric Relief Valve 0203-3C Test Interval ML0813305572008-06-27027 June 2008 Dresden/Quad Cities Relief Requests from 5-Year Test Interval for Main Steam Safety Valves ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0731300522007-11-20020 November 2007 Relief from 5-Year Test Interval for Main Steam Safety Valves ML0716300312007-08-0606 August 2007 Relief Request 14R-16 to Extend the First Period of the Fourth 10-year Inservice Inspection Interval for Twenty Reactor Pressure Vessel Welds ML0508303142005-05-10010 May 2005 Relief, Relief Request CR-39 for Third 10-Year Inservice Inspection Interval ML0426005632004-10-19019 October 2004 Amendments, Main Steam Line Relief Valves and Associated Relief Requests. TAC Nos. MC1792, MC1793, MC1794, and MC1795 ML0403307562004-02-20020 February 2004 Relief, Fourth 10-Year Inservice Testing Program Interval ML0335603862004-01-28028 January 2004 Fourth 10-Year Interval Inservice Inspection Relief Requests Nos.14R-01 Through 14R-01 Through 14R-09 (TAC Nos. MB7695 Through MB7712) RS-03-194, Fourth Interval Inservice Inspection Program Plan2003-10-10010 October 2003 Fourth Interval Inservice Inspection Program Plan SVP-03-096, Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program2003-09-11011 September 2003 Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program ML0319201482003-07-24024 July 2003 Relief Request, Witholding Information from Public Disclosure, ML0314208182003-05-28028 May 2003 Relief Request RV-30E, Inservice Testing Program Relief Regarding Main Steam Electronic Relief Valves and Safety/Relief Valves RS-03-099, Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program2003-05-16016 May 2003 Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program ML0312500182003-05-0808 May 2003 Relief, Inservice Testing Program Relief Regarding Main Steam Power Operated Relief Valves, MB8713 RS-03-091, Additional Information Regarding Relief Request RV-30E2003-05-0202 May 2003 Additional Information Regarding Relief Request RV-30E SVP-02-033, Code Relief Request CR-38, Inservice Inspection Program Relief Re 10 Hour Annual Training Requirements of ASME Section XI, 1995 Edition with 1996 Addenda, Appendix VII2002-04-0808 April 2002 Code Relief Request CR-38, Inservice Inspection Program Relief Re 10 Hour Annual Training Requirements of ASME Section XI, 1995 Edition with 1996 Addenda, Appendix VII ML0204200152002-02-21021 February 2002 Relief Request CR-37, Inservice Inspection Program Relief Regarding Examination of Pressure Retaining Welds in Piping Subject to Appendix Viii, Supplement 11 SVP-02-001, Request for Code Relief, Examination of Pressure Retaining Welds in Piping Subject to Appendix Viii, Supplement 11, Examination2002-01-0404 January 2002 Request for Code Relief, Examination of Pressure Retaining Welds in Piping Subject to Appendix Viii, Supplement 11, Examination 2023-05-08
[Table view] Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days 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-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 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 ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program 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-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- Information Meeting (Open House) with a Question-And-Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station 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 ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter 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 ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23144A3632023-05-26026 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 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 ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report 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 RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) 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 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) 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 ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code 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 ML23041A4262023-02-14014 February 2023 Proposed Alternative to the Requirements of the ASME OM Code ML22347A2412023-02-0606 February 2023 Issuance of Amendment Nos. 294 and 290 Control Rod Scram Times (Public) - ML22332A5492022-12-21021 December 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22298A0022022-12-15015 December 2022 Issuance of Amendment Nos. 293 and 289 Transition to GNF3 Fuel (EPID L-2021-LLA-0159) (Public) ML22217A0442022-12-0707 December 2022 Issuance of Amendment Nos. 292 and 288 Control Rod Scram Times ML22308A1602022-12-0202 December 2022 Issuance of Amendment Nos. 291 and 287 New Fuel Vault and Spent Fuel Storage Pool Criticality Methodologies ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22311A0032022-11-0909 November 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22256A1152022-09-29029 September 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22265A0862022-09-28028 September 2022 Proposed Alternative to the Requirements of the ASME OM Code ML22264A1752022-09-28028 September 2022 Proposed Alternative to the Requirements of the ASME OM Code 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) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21267A3172021-12-13013 December 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting (6th ISI Interval) (Epids L-2021-LLR 0029, 0030) 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) 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 ML21166A1682021-06-25025 June 2021 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 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) 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 ML20169A5842020-07-15015 July 2020 Relief from the Requirements of the ASME Code 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 ML20150A3282020-06-26026 June 2020 Issuance of Amendment Nos. 281 and 277 to Increase Allowable Main Steam Isolation Leakage ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20094F8332020-04-0909 April 2020 Issuance of Amendment No. 276, Revise Technical Specification 3.6.1.3 Related to Increased Allowed Main Steam Isolation Valve Leakage (Emergency Circumstances) 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 ML19301A3392019-12-0404 December 2019 Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, the Minimum Critical Power Ration Safety Limits ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 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 ML18353A2292019-01-28028 January 2019 Issuance of Amendment Nos. 273 and 268 Regarding Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18348B2512019-01-15015 January 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4460 & MF4461; EPID L-2014-JLD-0054) 2023-09-21
[Table view] |
Text
September 29, 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:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - PROPOSED ALTERNATIVE TO THE REQUIREMENTS OF THE ASME OM CODE (EPID L-2022-LLR-0014)
Dear Mr. Rhoades:
By letter dated February 17, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22048B569), Constellation Energy Generation, LLC, (the licensee) submitted an alternative request to the U.S. Nuclear Regulatory Commission (NRC) to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), associated with valve inservice testing (IST) at Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50 Section 55a, paragraph (z), subparagraph (1) (10 CFR 50.55a(z)(1)), to implement alternative request RV-03 for the frequency of the testing of certain pressure isolation valves at QCNPS on the basis that the proposed alternative provides an acceptable level of quality and safety.
Although the licensee referred to this submittal as a relief request, this submittal represents an alternative request in accordance with 10 CFR 50.55a(z)(1).
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the proposed alternative request RV-03 to establish performance-based leak testing intervals for valves at QCNPS within the scope of this request will provide an acceptable level of quality and safety where those valves have demonstrated successful leak test performance during the two most recent periodic leak tests. 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 NRC staff authorizes the proposed alternative request RV-03 for the sixth 10-year IST interval at QCNPS, which will begin on February 18, 2023, and is scheduled to end on February 17, 2033.
All other ASME OM Code requirements as incorporated by reference in 10 CFR 50.55a for which relief or an alternative was not specifically requested, and granted or authorized (as appropriate), in the subject request remain applicable.
D. Rhoades If you have any questions, please contact the Project Manager, Robert Kuntz at 301-415-3733 or via e-mail at Robert.Kuntz@nrc.gov.
Sincerely, Digitally signed by Nancy L. Nancy L. Salgado Date: 2022.09.29 Salgado 08:49:37 -04'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ALTERNATIVE REQUEST RV-03 CONSTELLATION ENERGY GENERATION, LLC QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265
1.0 INTRODUCTION
By letter dated February 17, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22048B569), Constellation Energy Generation, LLC (the licensee) submitted alternative request RV-03 to the U.S. Nuclear Regulatory Commission (NRC) for use of an alternative to specific inservice testing (IST) requirements in the 2017 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) at the Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS) for the sixth 10-year IST interval.
Specifically, RV-03 request an alternative for the frequency of the testing of certain pressure isolation valves (PIVs) at QCNPS pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50 Section 55a, paragraph (z), subparagraph (1) (10 CFR 50.55a(z)(1)), on the basis that the proposed alternative provides an acceptable level of quality and safety. Although the licensee referred to this submittal as a relief request, this submittal represents an alternative request in accordance with 10 CFR 50.55a(z)(1).
The QCNPS sixth 10-year IST interval will begin on February 18, 2023, and is scheduled to end on February 17, 2033.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, state that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the IST requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and (3) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), to the Enclosure
extent practical within the limitations of design, geometry, and materials of construction of the components.
The NRC regulations in 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, specify requirements for containment isolation valve (CIV) leakage tests.
In proposing an alternative to IST requirements in the applicable edition or addenda of the ASME OM Code as incorporated by reference in 10 CFR 50.55a, a licensee must demonstrate that (1) the proposed alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1), 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 in accordance with 10 CFR 50.55a(z)(2).
The IST requirements in the ASME OM Code (2017 Edition), as incorporated by reference in 10 CFR 50.55a, related to this alternative request are as follows:
ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, paragraph ISTC-3630, Leakage Rate for Other Than Containment Isolation Valves, states:
Category A valves with a leakage requirement not based on an Owner's 10 CFR 50, Appendix J program, shall be tested to verify their seat leakages within acceptable limits. Valve closure before seat leakage testing shall be by using the valve operator with no additional closing force applied.
Subparagraph (a), Frequency, in paragraph ISTC-3630 states:
Tests shall be conducted at least once every 2 years.
ASME OM Code, Section ISTC, paragraph ISTC-3630, subparagraph (b), states in part that the valve seat test shall be made with the pressure differential in the same direction as when the valve is performing its function with specific exceptions. ASME OM Code, Section ISTC, paragraph ISTC-3620, Containment Isolation Valves, states in part that CIVs with a leakage rate requirement based on an Appendix J program commitment shall be tested in accordance with the Owners 10 CFR Part 50, Appendix J program. ASME OM Code, Section ISTC, paragraph ISTC-3620, also states that CIVs with a leakage requirement based on other functions shall be tested in accordance with paragraph ISTC-3630.
Guidance for implementation of acceptable leakage rate test methods, procedures, and analyses for 10 CFR Part 50, Appendix J, Option B, is provided in Regulatory Guide (RG) 1.163 Performance-Based Containment Leak-Test Program (ML003740058). RG 1.163 endorses Nuclear Energy Institute (NEI) 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR 50 Appendix J, Revision 0, dated July 26, 1995, with the limitation that the Type C component test intervals cannot extend greater than 60 months.
Revision 3-A to NEI 94-01 allows the Type C containment isolation valve test intervals to be extended to 75 months with a permissible extension for non-routine emergent conditions of 9 months (84 months total). In a safety evaluation dated June 8, 2012 (ML121030286) and the corresponding approval letter dated December 6, 2012 (ML12226A546), the NRC staff determined that the guidance in NEI 94-01, Revision 3-A, is acceptable with the following conditions:
- 1. NEI 94-01, Revision 3, is requesting that the allowable extended interval for Type C local leak rate tests (LLRTs) be increased to 75 months, with a permissible extension (for non-routine emergent conditions) of nine months (84 months total). The staff is allowing the extended interval for Type C LLRTs be increased to 75 months with the requirement that a licensees post-outage report include the margin between the Type B and Type C leakage rate summation and its regulatory limit. In addition, a corrective action plan shall be developed to restore the margin to an acceptable level.
The staff is also allowing the non-routine emergent extension out to 84 months as applied to Type C valves at a site, with some exceptions that must be detailed in NEI 94-01, Revision 3. At no time shall an extension be allowed for Type C valves that are restricted categorically (e.g., boiling water reactor main steam isolation valves), and those valves with a history of leakage, or any valves held to either a less than maximum interval or to the base refueling cycle interval. Only nonroutine emergent conditions allow an extension to 84 months.
- 2. The basis for acceptability of extending the integrated leak rate testing (ILRT) interval out to once per 15 years was the enhanced and robust primary containment inspection program and the local leakage rate testing of penetrations. Most of the primary containment leakage experienced has been attributed to penetration leakage and penetrations are thought to be the most likely location of most containment leakage at any time. The containment leakage condition monitoring regime involves a portion of the penetrations being tested each refueling outage, nearly all LLRTs being performed during plant outages. For the purposes of assessing and monitoring or trending overall containment leakage potential, the as-found minimum pathway leakage rates for the just tested penetrations are summed with the as-left minimum pathway leakage rates for penetrations tested during the previous 1 or 2 or even 3 refueling outages. Type C tests involve valves which, in the aggregate, will show increasing leakage potential due to normal wear and tear, some predictable and some not so predictable.
Routine and appropriate maintenance may extend this increasing leakage potential. Allowing for longer intervals between LLRTs means that more leakage rate test results from farther back in time are summed with fewer just tested penetrations and that total used to assess the current containment leakage potential. This leads to the possibility that the LLRT totals calculated understate the actual leakage potential of the penetrations.
Given the required margin included with the performance criterion and the considerable extra margin most plants consistently show with their testing, any understatement of the LLRT total using a 5-year test frequency is thought to be conservatively accounted for. Extending the LLRT intervals beyond 5 years to a 75-month interval should be similarly conservative provided an estimate is made of the potential understatement and its acceptability determined as part of the trending specified in NEI 94-01, Revision 3, Section 12.1. When routinely scheduling any LLRT valve interval beyond 60-months and up to 75-months, the primary containment leakage rate testing program trending or monitoring must include an estimate of the amount of understatement in the Type B & C total, and must be included in a licensees post-outage report. The report must include the reasoning and
determination of the acceptability of the extension, demonstrating that the LLRT totals calculated represent the actual leakage potential of the penetrations.
3.0 TECHNICAL EVALUATION
3.1 Alternative Request RV-03 3.1.1 Applicable Code Edition The applicable OM Code of Record for the sixth 10-year IST interval at QCNPS is the 2017 Edition of ASME OM Code as incorporated by reference in 10 CFR 50.55a.
3.1.2 ASME Code Components Affected The components affected by the alternative request are provided on page 1 of 10 of 10 CFR 50.55a Relief Request: RV-03 included in the Attachment to the February 17, 2022, letter under item 1, ASME Code Components Affected.
3.1.3 Reason for Request Alternative request RV-03 describes the reason for the request pursuant to 10 CFR 50.55a(z)(1) to implement an alternative to certain testing requirements of ASME OM Code, Subsection ISTC, paragraph ISTC-3630(a) for specific valves on the basis that the alternative testing would provide an acceptable level of quality and safety. The alternative references Technical Specification (TS) 5.5.12, Primary Containment Leakage Rate Testing Program, which requires the establishment of a leakage rate testing program in accordance with the guidelines contained in NEI 94-01, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008. The request states that the alternative is intended to provide for performance-based scheduling of PIV tests at QCNPS to maintain radiation exposure of plant personnel as low as reasonably achievable.
3.1.4 Licensees Proposed Alternative and Basis for Use Alternative request RV-03 proposes to perform PIV testing at intervals ranging from every refueling outage to every third refueling outage. The specific interval for each valve would be a function of its performance, and would be established in a manner consistent with the CIV process under 10 CFR Part 50, Appendix J, Option B, Performance-Based Requirements. The licensee states that a conservative control will be established such that if any valve fails its PIV test, the test interval will be reduced consistent with Option B requirements until good performance is reestablished.
The request states that the primary basis for the proposed alternative is the historically good performance of the PIVs at QCNPS. Tables RV-03-1 through RV-03-5 in the submittal summarize test data that demonstrate acceptable historical PIV performance for the Residual Heat Removal and Core Spray Systems. The submittal reports that the only recorded seat leakage failures of the PIVs at QCNPS were determined to be the result of the test methodology, and not due to any physical condition of the valves. In addition to NEI 94-01, the licensee states that bases for this request include (a) the performance of separate functional testing of motor-operated valve PIVs and condition monitoring of check valve PIVs per the ASME OM Code; (b) the low likelihood of valve mispositioning during power operations (e.g.,
procedures and interlocks); (c) the presences of relief valves in the low pressure (LP) piping, which might not provide inner-system loss of coolant accident mitigation for inadvertent PIV mispositioning, but their relief capacity can accommodate conservative PIV seat leakage rates; and (d) the presence of alarms that identify high pressure to LP leakage such that reactor operators can take appropriate action.
Based on this information, the request asserts that the proposed alternative to perform PIV testing at the specified performance-based intervals will continue to provide assurance of PIV operational readiness, and will provide an acceptable level of quality and safety pursuant to 10 CFR 50.55a(z)(1).
3.2 NRC Staff Evaluation Alternative request RV-03 proposes to perform the valve seat leakage testing at intervals ranging from every refueling outage (RFO) to every third RFO. The specific interval for each valve would be a function of its performance, and would be established in a manner consistent with the CIV process under 10 CFR Part 50, Appendix J, Option B. If any valve fails its PIV test, the test interval will be reduced consistent with Option B requirements until good performance is reestablished.
Alternative request RV-03, Tables RV-03-1 through RV-03-5, summarize test data that demonstrate good historical performance of the PIVs within the scope of the request at QCNPS. The tables provide leakage test results indicating little or no measurable leakage for some valves within the scope of the request as far back as 2006 at QCNPS. The request states that the only recorded seat leakage failures of PIVs at QCNPS were the result of the test methodology and not due to a physical condition of the valves. In addition, the licensee performs functional tests and/or performance indicator activities for each PIV within the scope of this request to ensure their functional capabilities in accordance with ASME OM Code as incorporated by reference in 10 CFR 50.55a.
Based on good valve performance history and functional tests and/or performance indicator activities for the PIVs, the NRC staff finds that the performance-based leak testing interval approach proposed in alternative request RV-03 for the PIVs within the scope of this request at QCNPS will provide an acceptable level of quality and safety as required by 10 CFR 50.55a(z)(1) where those valves have demonstrated successful leak test performance during the two most recent periodic leak tests.
4.0 CONCLUSION
As indicated above, the NRC staff finds that the proposed alternative request RV-03 to establish performance-based leak testing intervals for valves at QCNPS within the scope of this request will provide an acceptable level of quality and safety where those valves have demonstrated successful leak test performance during the two most recent periodic leak tests. 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 NRC staff authorizes the
proposed alternative request RV-03 for the sixth 10-Year IST interval at QCNPS, which will begin on February 18, 2023, and is scheduled to end on February 17, 2033.
All other ASME OM Code requirements as incorporated by reference in 10 CFR 50.55a for which relief or an alternative was not specifically requested, and granted or authorized (as appropriate), in the subject request remain applicable.
Principal Contributor: K. Hsu, NRR T. Scarbrough, NRR Date: September 29, 2022
ML22256A115 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EMIB/BC NRR/DORL/LPL3/BC NAME RKuntz SRohrer (SLent for) SBailey (RLi for) NSalgado DATE 9/13/2022 9/13/2022 9/6/2022 9/29/2022