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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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 25, 2008 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNIT 1 - RELIEF REQUEST NO. RV-30G FROM MAIN STEAM ELECTROMATIC RELIEF VALVE 0203-3C TEST INTERVAL (TAC NO. MD8996)
Dear Mr. Pardee:
By letter dated June 19, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081720346), Exelon Generation Company, LLC ( the licensee),
submitted Relief Request (RR) No. RV-30G for Quad Cities Nuclear Power Station (QCNPS),
Unit 1. The licensee requested authorization to use an alternative to an inservice testing provision in the American Society of Mechanical Engineers (ASME), Code for Operation and Maintenance of Nuclear Power Plants (OM Code) in accordance with Title 10 of the Code of Federal Regulations, (10 CFR) Part 50, Section 55a.
The licensee proposed an alternative to the requirement in ASME OM Code Mandatory Appendix I, Section 1-1330(a) (1998 Edition through 2000 Addenda) requiring that Class 1 pressure relief valves be tested every 5 years. The alternative was proposed for QCNPS, Unit 1 main steam electromatic relief valve (ERV) 0203-3C. The alternative requests approval to extend the test interval for ERV 0203-3C until the 20th QCNPS, Unit 1 refueling outage (Q1 R20), which is approximately 2 months beyond 5 years.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's analysis in support of its request for relief. The NRC staff has concluded that the proposed alternative provides an acceptable level of quality and safety.
C. Pardee -2 Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the alternative to extend the test interval for ERV 0203-3C until the 20th OCNPS, Unit 1 01 R20, requested by RR RV-30E, is authorized for OCNPS, Unit 1 ERV 0203-3C, which is a test interval of approximately 5 years and 2 months.
s~~
Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE TEST INTERVAL FOR ELECTROMATIC RELIEF VALVE 0203-3C EXELON GENERATION COMPANY, LLC QUAD CITIES NUCLEAR POWER STATION, UNIT 1 RELIEF REQUEST RV-30G DOCKET NO. 50-254
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated June 19, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081720346), Exelon Generation Company, LLC (the licensee) submitted Relief Request (RR) RV-30G, for Quad Cities Nuclear Power Station (QCNPS), Unit 1. The licensee requested authorization to use an alternative to an inservice testing (1ST) provision in the American Society of Mechanical Engineers (ASME), "Code for Operation and Maintenance of Nuclear Power Plants" (OM Code) in accordance with Title 10 of the Code of Federal Regulations (10 CFR),
Part 50, Section 55a.
The licensee proposed an alternative to the requirement in the ASME OM Code (1998 Edition through 2000 Addenda), which is the current Code of Record for the QCNPS, Unit 1 1ST program. The alternative was proposed for QCNPS, Unit 1 main steam electromatic relief valve (ERV) 0203-3C. The alternative requests approval to extend the test interval for ERV 0203-3C for approximately 2 months on a 1-time basis.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(f), "Inservice Testing Requirements," ASME Code Class 1,2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs (a)(3)(i) and (a)(3)(ii) of 10 CFR 50.55a. Section 50.55a(a)(3)(i) of 10 CFR allows the Commission to authorize alternatives to ASME OM Code requirements upon a finding that the proposed alternatives would provide an acceptable level of quality and safety.
In Attachment 9 to a letter dated January 15, 2004 (ADAMS Accession No. ML040220182), the licensee requested, in part, relief from Subsection ISTC 3510 and proposed an alternative to exercise test the relief valves, including ERV 0203-3C, at the frequency required by Section 1-1330. The NRC staff authorized the proposed alternative by letter dated Enclosure
-2 October 19, 2004 (ADAMS Accession No. ML042600563), for the duration of the fourth 10-year 1ST interval for QCNPS, Unit 1, which ends on February 18, 2013.
In the current RR RV-30G, the licensee requested authorization of an alternative to the 5-year test requirement in Mandatory Appendix I, "Requirements for Inservice Testing of Nuclear Power Plant Pressure Relief Devices," Section 1-1330, "Test Frequencies, Class I Pressure Relief Valves," Paragraph (a), "5-Year Test Interval," of the 1998 Edition through 2000 Addenda of the ASME OM Code. The alternative was requested for ERV 0203-3C. The NRC staff's findings with respect to authorizing alternatives to the ASME OM Code are given below.
3.0 TECHNICAL EVALUATION
FOR QCNPS RR RV-30G 3.1 Request No. RV-30G 3.1.1 ASME OM Code Requirement ASME OM Code, Section ISTC-2000, "Supplemental Definitions," 1998 Edition through 2000 Addenda, defines a power-operated relief valve as a valve that can perform a pressure-relieving function by either a signal from a pressure-sensing device or a control switch.
ASME OM Code, Section ISTC-3510, "Exercising Test Frequency," 1998 Edition through 2000 Addenda, states, "Power operated relief valves shall be exercise tested once per fuel cycle."
3.1.2 Proposed Alternative Testing The NRC previously approved the alternative in RR RV-30E for QCNPS Unit 1, in a letter dated October 19, 2004 (ADAMS Accession No. ML042600563), for the current QCNPS, Unit 1 1ST program that complies with the 1998 Edition through 2000 Addenda of the ASME OM Code.
The approved alternative authorizes the licensee to exercise test ERV 0203-3C at the frequency required by Section 1-1330 (once per 5 years) instead of once per fuel cycle.
The licensee states that the 5-year interval for ERV 0203-3C expires on March 17, 2009. The licensee is proposing to delay the exercise test for ERV 0203-3C up to approximately 2 months beyond March 17,2009, on a 1-time basis. The licensee states that ERV 0203-3C will be replaced during the upcoming QCNPS, Unit 1 refueling outage scheduled for spring 2009.
3.1.3 Basis for the Alternative The licensee installed ERV Serial Number BY-94637 in QCNPS, Unit 1 position 0203-3C, during the April 2005 refueling outage. The licensee states that this was a refurbished valve that was pre-installation tested in March 2004 and placed into controlled storage until installation in April 2005. The licensee has determined that exercise testing an ERV with steam as the test medium can contribute to undesirable seat leakage of the valve during subsequent plant operation, and therefore, the ERVs are exercise tested at a test facility instead of in situ. The licensee asserts that the requested delay is short (i.e. approximately 2 months) and delaying the exercise test approximately 2 months will not adversely affect the operability of the ERV.
-3 3.1.4 NRC Staff's Evaluation of Proposed Alternative QCNPS, Unit 1 TS Surveillance Requirement (SR) 3.0.2 permits a 25 percent extension of the ASME OM Code test frequencies specified in QCNPS, Unit 1 TS 5.5.6 to facilitate scheduling and in consideration of plant operating conditions that may not be suitable for conducting the test. The 25 percent extension is not intended to be used repeatedly or merely as an operational convenience to extend the interval beyond the test frequencies specified in TS 5.5.6. QCNPS, Unit 1 TS SR 3.0.2 and TS 5.5.6 provide provisions for extending ASME OM Code test frequencies that are up to 48 months in duration. For example, a 48 month ASME OM Code test frequency could be extended up to 12 months in accordance with the provisions in TS SR 3.0.2 and TS 5.5.6. The NRC staff finds that extending the exercise test frequency for ERV 0203-3C for up to 2 months is acceptable. This 2-month extension is significantly less that the TS allowed extensions for other ASME OM Code test frequencies that are 12 months to 48 months in duration. The 2-month extension for exercise testing ERV 0203-03 is acceptable on a 1-time basis, and therefore, cannot be used repeatedly or merely as an operation convenience to extend the interval beyond 60 months. Delaying the exercise test approximately 2 months beyond 5 years should not adversely affect the operational readiness of the ERV and, therefore, the alternative provides an acceptable level of quality and safety.
3.1.5 Conclusion Based on the NRC staff's review and evaluation of the information provided by the licensee, the staff concludes that extending the ERV 0203-03 exercise test interval for 2 months beyond 5 years is an acceptable alternative. The alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for QCNPS, Unit 1 ERV 0203-03 through the spring 2009 refueling outage on the basis that the alternative provides an acceptable level of quality and safety.
Principal Contributor: S. Tingen, NRR Date: November 25, 2008
C. Pardee -2 Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the alternative to extend the test interval for ERV 0203-3C until the 20th OCNPS, Unit 1 01 R20, requested by RR RV-30E, is authorized for OCNPS, Unit 1 ERV 0203-3C, which is a test interval of approximately 5 years and 2 months.
Sincerely, IRA!
Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254
Enclosure:
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DATE 11/18/08 11/18/08 9/23/08 11/19/08 11/25/08 OFFICIAL RECORD COpy