Letter Sequence Approval |
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MONTHYEARML0200705642002-01-0808 January 2002 Proposed No Significant Hazards Consideration Determination (TAC Nos. MB2352 and MB2353) Project stage: Other ML0204602962002-02-11011 February 2002 Tech. Spec. Pages for Amendment Nos. 203 and 199 - Issuance of Amendment Reactor Protective System Instrumentation Scram Discharge Volume Water Level High Project stage: Approval ML0201001312002-02-11011 February 2002 Issuance of License Amendments, Technical Specifications Change - Reactor Protection System Instrumentation Scram Discharge Volume Water Level High Project stage: Approval 2002-01-08
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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:License-Operating (New/Renewal/Amendments) DKT 50
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 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 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 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 ML22347A2412023-02-0606 February 2023 Issuance of Amendment Nos. 294 and 290 Control Rod Scram Times (Public) - 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 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 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) ML21301A2192021-11-10010 November 2021 Request for Withholding Information from Public Disclosure for Quad Cities Nuclear Power Station, Units 1 and 2 License Amendment Request Regarding Transition to GNF3 Fuel ML21301A2202021-11-10010 November 2021 Request for Withholding Information from Public Disclosure for Quad Cities Nuclear Power Station, Units 1 and 2 License Amendment Request Regarding Transition to GNF3 Fuel 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 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 ML20150A3282020-06-26026 June 2020 Issuance of Amendment Nos. 281 and 277 to Increase Allowable Main Steam Isolation Leakage 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 ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions 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 ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control 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 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 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML17311A1622017-12-0101 December 2017 Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML17037D2122017-02-16016 February 2017 Issuance of Amendments to Revise Surveillance Requirement for Secondary Containment Access Doors ML16218A4852016-10-20020 October 2016 DNPS Unit Nos. 2 and 3, QCNPS Unit Nos. 1 and 2 - Issuance of LAR to Renewed Facility Operating License Nos. DPR-19, 25, 29, 30 TS Revision to Support Areva Atrium 10XM Fuel Transition ML16231A1312016-10-17017 October 2016 Issuance of Amendments Regarding Spent Fuel Pool Criticality Methodology for Fuel Channel Bow/Bulge (Cac. Nos. MF7160 and MF7161) RS-16-133, Certification of Permanent Cessation of Power Operations2016-06-20020 June 2016 Certification of Permanent Cessation of Power Operations ML16111A1042016-05-11011 May 2016 Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) ML15324A4392015-12-17017 December 2015 Issuance of Amendments (CAC Nos. MF5471-MF5476) ML15183A3512015-08-0505 August 2015 Issuance of Amendments Concerning Adding Topical References to Technical Specifications (TAC Nos. MF3359, MF3363, MF3361, and MF3362)(RS-13-288) ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15114A1882015-06-19019 June 2015 Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation ML15106A9472015-04-24024 April 2015 Correction to Amendments Regarding Battery Surveillance Requirements (TAC Nos. MF4589 and MF4590) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training ML15056A7722015-03-30030 March 2015 Issuance of Amendments Regarding 2023-08-07
[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
February 11, 2002 Mr. Oliver D. Kingsley, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
ISSUANCE OF AMENDMENTS - TECHNICAL SPECIFICATIONS CHANGE -
REACTOR PROTECTION SYSTEM INSTRUMENTATION SCRAM DISCHARGE VOLUME WATER LEVEL HIGH FOR QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MB2352 AND MB2353)
Dear Mr. Kingsley:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 203 to Facility Operating License No. DPR-29 and Amendment No. 199 to Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2. The amendments are in response to your application dated July 6, 2001, as supplemented by your letters dated October 25, 2001, and December 17, 2001.
The amendments revise technical specifications (TS) Section 3.3.1.1, Reactor Protection System Instrumentation, to modify the description for Reactor Protection System (RPS)
Function 7.a, Scram Discharge Volume Water Level - High. This change supports a planned upgrade to the scram discharge volume level instrumentation from Fluid Components International thermal switches to Magnetrol float switches. These float switches are more reliable than the existing thermal switches, which are highly sensitive to a steam environment, since they respond to actual water level increases within the scram discharge volume. These types of Magnetrol float switches are used successfully in various applications at Quad Cities.
A copy of the related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Mahesh Chawla, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.: 50-254 and 50-265
Enclosures:
- 1. Amendment No. 203 to DPR-29
- 2. Amendment No. 199 to DPR-30
- 3. Safety Evaluation cc w/encls: See next page
O. Kingsley Quad Cities Nuclear Power Station Exelon Generation Company, LLC Units 1 and 2 cc:
Exelon Generation Company, LLC Illinois Department of Nuclear Safety Site Vice President - Quad Cities Office of Nuclear Facility Safety 22710 206th Avenue N. 1035 Outer Park Drive Cordova, Illinois 61242-9740 Springfield, Illinois 62704 Exelon Generation Company, LLC Document Control Desk-Licensing Station Manager - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N. 4300 Winfield Road Cordova, Illinois 61242-9740 Warrenville, Illinois 60555 Exelon Generation Company, LLC Mr. John Skolds Regulatory Assurance Manager - Quad Cities Chief Operating Officer 22710 206th Avenue N. Exelon Generation Company, LLC Cordova, Illinois 61242-9740 4300 Winfield Road Warrenville, Illinois 60555 U.S. Nuclear Regulatory Commission Quad Cities Resident Inspectors Office Mr. John Cotton 22712 206th Avenue N. Senior Vice President, Operation Support Cordova, Illinois 61242 Exelon Generation Company, LLC 4300 Winfield Road William D. Leech Warrenville, Illinois 60555 Manager - Nuclear MidAmerican Energy Company Mr. William Bohlke P.O. Box 657 Senior Vice President, Nuclear Services Des Moines, Iowa 50303 Exelon Generation Company, LLC 4300 Winfield Road Vice President - Law and Warrenville, Illinois 60555 Regulatory Affairs MidAmerican Energy Company Mr. Robert J. Hovey One River Center Place Vice President 106 E. Second Street Mid-West Regional Operating Group P.O. Box 4350 Exelon Generation Company, LLC Davenport, Iowa 52808 4300 Winfield Road Warrenville, Illinois 60555 Chairman Rock Island County Board Mr. Christopher Crane of Supervisors Senior Vice President 1504 3rd Avenue Mid-West Regional Operating Group Rock Island County Office Bldg. Exelon Generation Company, LLC Rock Island, Illinois 61201 4300 Winfield Road Warrenville, Illinois 60555 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351
O. Kingsley Quad Cities Nuclear Power Station Exelon Generation Company, LLC Units 1 and 2 Mr. Jeffrey Benjamin Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Mr. K. A. Ainger Director - Licensing Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Mr. Robert Helfrich Senior Counsel, Nuclear Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555
ML020100131 TS Accession No.: ML020460296 OFFICE PM:LPD3-2 PM:LPD3-2 LA:LPD3-2 SC:EEIB OGC SC:LPD3-2 NAME MChawla FLyon CRosenberg EMarinos RHoefling AMendiola DATE 01/16/02 01/17/02 01/10/02 01/17/02 01/24/02 02/11/02 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 203 License No. DPR-29
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated July 6, 2001, as supplemented by your letters dated October 25, 2001, and December 17, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 203, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 11, 2002
EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 199 License No. DPR-30
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated July 6, 2001, as supplemented by your letters dated October 25, 2001, and December 17, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 199, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 11, 2002
ATTACHMENT TO LICENSE AMENDMENT NOS. 203 AND 199 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by number and contain marginal lines indicating the area of change.
Remove Pages Insert Pages 3.3.1.1-9 3.3.1.1-9
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 203 TO FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 199 TO FACILITY OPERATING LICENSE NO. DPR-30 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265
1.0 INTRODUCTION
By letter dated July 6, 2001, the Exelon Generation Company, LLC, (Exelon, the licensee) submitted a request to the Nuclear Regulatory Commission (NRC) to amend the Technical Specifications (TS) for the Quad Cities Nuclear Power Station, Units 1 and 2. The proposed TS change will permit replacement of thermal switches made by Fluid Components International (FCI), to float switches made by Magnetrol, in the scram discharge volume (SDV) instrumentation of the reactor protection system (RPS) to interface with the existing RPS logic.
Further, in response to NRCs request, the licensee provided additional information by letters dated October 25, 2001, and December 17, 2001.
The proposed amendment will modify the description of Function 7.a of TS Table 3.3.1.1-1, Reactor Protection System Instrumentation from Thermal Switch to Thermal Switch (for Unit 1 only through cycle 17) Float Switch.
The proposed plant design changes are scheduled for implementation during the next refueling outage on Unit 2 in February 2002. A similar design change will be implemented on Unit 1 during the 17th refueling outage scheduled to begin in October 2002.
The October 25, 2001, and December 17, 2001, supplements provided clarifying information that was within the scope of the original Federal Register notice and did not change the staffs initial proposed no significant hazards considerations determination.
2.0 BACKGROUND
INFORMATION The RPS has protection and monitoring functions which have been designed to ensure safe operation of the reactor. The RPS initiates a reactor scram when one or more monitored
parameters exceed their specified limits, to preserve the integrity of the fuel cladding and the reactor coolant system (RCS), and minimize the energy that must be absorbed following a loss-of-coolant accident (LOCA).
The current instrumentation for the SDV - high level trip, Function 7.a of TS Table 3.3.1.1-1, Reactor Protection System Instrumentation, utilizes FCI thermal type level switches mounted directly in the scram discharge instrument volume (SDIV) to initiate a reactor scram when the monitored parameter exceeds its specified limit. If the SDV were to fill to a point where there is insufficient volume to accept the water from the control drives that are displaced during scram, control rod insertion would be hindered. This scram is required to be functional in Modes 1, Power Operation, 2, Startup, and 5, Refueling with any control rod withdrawn from a reactor core cell containing one or more fuel assemblies.
3.0 EVALUATION 3.1 Evaluation of Proposed Instrument Change The current SDV instrumentation consists of four internally mounted, non-indicating thermal switches, which monitor the SDV level. The switches are arranged in pairs on each of two SDVs, so each switch pair provides an input to RPS trip systems A and B. The sensor of each FCI thermal type level switch is mounted directly in the SDIV and comprises a pair of resistance temperature detectors (RTDs), one heated and the other one unheated. When covered with water, the temperatures and RTD outputs will approach the same value. The signals from the RTDs are compared via a bridge circuit and when the setpoint is reached, a trip signal is generated, which corresponds to a four-second time delay from the time of immersion. This delay desensitizes the instrument loop to transient type conditions in the SDIV, such as splashing, moisture/steam intrusion, etc.
The current setpoint incorporates the maximum delay, which ensures that the SDV is not full at the end of the time delay, and there is sufficient free volume in the SDV to provide rod insertion capability. The licensee stated that it has experienced spurious half and full scrams because the delay is inadequate to fully desensitize the instrument to low quality steam flow (steam/moisture environment).
The proposed replacement Magnetrol float switch consists of a float attached to a vertical shaft which magnetically actuates a switch on high water level. Since the replacement float switches will be installed external to the SDV, it eliminates sensitivity to transient conditions in the SDIV and thus eliminates spurious half or full scrams. The new assemblies will be mounted to actuate at the same level as the existing FCI sensors, and since there is no time delay involved in the new assemblies, the scram signal will be received 4 seconds earlier. Therefore, application of these float switches will eliminate the current four second time delays in the SDV instrumentation. There are no setpoint changes required due to the SDV instrumentation change.
The licensee has used these switches for multiple applications at Quad Cities, namely Table 3.3.5.1-1, ECCS Instrumentation, Sub-Function 3.d, CCST Level - Low, and Sub-Function 3.e, Suppression Pool Water Level - High. Also, the licensee states that the modification has been successfully evaluated under Exelons design change process and does
not introduce any new failure modes. Moreover, there is no credit taken for a scram initiated by this function for any of the design basis accidents or transients analyzed in the updated final safety analysis report.
During a telephone conference held on October 3, 2001, between NRC staff and Exelon representatives, the licensee was asked to provide additional information regarding the improved reliability of the upgrade instrumentation. In its letter dated October 25, 2001, the licensee stated that these switches have historically, throughout the nuclear industry, proven to be highly reliable since they require low maintenance and experienced little to no functional failure. These float switches provide increased accuracy of detecting actual water level within the SDV.
During the follow-up telephone conference held on November 29, 2001, between NRC staff and Exelon representatives, the licensee was asked to describe the process to determine the allowable value for the scram discharge volume instrumentation loop. In its letter dated December 17, 2001, the licensee stated that Exelon methodology as defined in procedure NES-EIC-20.04, Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy, was used to determine the allowable value (AV). This methodology has been reviewed and accepted by the NRC as part of the Quad Cities implementation of improved technical specifications (NRC letter from Anthony J. Mendiola to Exelon, dated March 30, 2001).
No changes were made to the analytical limit (AL) during the change to the new Magnetrol level switches. A Quad Cities evaluation and the placement of the new switches allowed the AV to remain unchanged. The evaluation demonstrated a significant margin between the AV and AL, due to the differences in the time response characteristics of the Magnetrol switches as compared to the FCI switches.
3.2 Conclusion The licensee proposes to replace the current FCI thermal type switches used in SDV instrumentation with Magnetrol float switches. These switches are free from sensitivity to steam/moisture changes in the SDIV, have increased accuracy in detecting actual water level, and have demonstrated more reliable operation in multiple applications at Quad Cities and in the nuclear industry. The overall effect of this modification is to provide an identical function as the previous SDV Water Level - High trip signal and to provide increased reliability and better overall performance of the SDV level trip function.
Based on the proven industry performance record of the float switches, including those installed at Quad Cities in similar applications, and the licensees use of NRC-approved calculation methodology to determine AVs for the SDV instrumentation loop, the NRC staff concludes that the proposed TS change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (67 FR 1520). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Subinoy Mazumdar Mahesh Chawla Date: February 11, 2002