Letter Sequence Approval |
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MONTHYEARML23261A0032023-09-15015 September 2023 NRR E-mail Capture - NRC Acceptance Review of Clinton Amendment Request to Revise Timing of Reactor Water Cleanup Isolation Valves Project stage: Acceptance Review ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation Project stage: Other ML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing Project stage: Approval 2024-01-24
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Category:Letter
MONTHYEARIR 05000461/20240022024-08-0909 August 2024 Integrated Inspection Report 05000461/2024002 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition ML24220A2772024-08-0707 August 2024 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000461/2025010 ML24212A2212024-08-0202 August 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-LNE-0000) (Docket Number: 50-461) ML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing ML24158A0772024-07-0303 July 2024 Notice of Consideration of Approval of Partial Site Release, Public Meeting, and Request for Comments (EPID L-2023-LLA-0088) - Letter ML24163A3252024-06-28028 June 2024 Aging Management Regulatory Audit Plan ML24163A3242024-06-28028 June 2024 LRA - Portal Letter ML24179A3112024-06-27027 June 2024 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24176A0272024-06-25025 June 2024 Confirmation of Initial License Examination, July 2025 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes IR 05000461/20240122024-05-20020 May 2024 Biennial Problem Identification and Resolution Inspection Report Report 05000461/2024012 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20240012024-05-0707 May 2024 Integrated Inspection Report 05000461/2024001 ML24120A3462024-04-30030 April 2024 Ltr. to Douglas Lankford, Chief, Miami Tribe of Oklahoma; Re., CPS Section 106 Consultation ML24120A3452024-04-30030 April 2024 Ltr. to Lester Randell, Chairman, Kickapoo Tribe of Indians of the Kickapoo Reservation in Kansas; Re., CPS Section 106 Consultation ML24120A3442024-04-30030 April 2024 Ltr. to Gena Kakkak, Chairman, Menominee Indian Tribe of Wisconsin; Re., CPS Section 106 Consultation ML24120A3432024-04-30030 April 2024 Ltr. to Darwin Kaskaske, Chairman, Kickapoo Tribe of Oklahoma; Re., CPS Section 106 Consultation RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24107B0312024-04-29029 April 2024 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process IR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 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 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000461/20230032023-11-0808 November 2023 Integrated Inspection Report 05000461/2023003 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000461/20233012023-09-12012 September 2023 NRC Initial License Examination Report 05000461/2023301 RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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 IR 05000461/20234202023-08-29029 August 2023 Security Baseline Inspection Report 05000461/2023420 RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20230022023-08-0404 August 2023 Integrated Inspection Report 05000461/2023002 RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release ML23209A8102023-07-28028 July 2023 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary ML23202A0992023-07-24024 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004 ML23194A1662023-07-19019 July 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release IR 05000461/20234012023-07-19019 July 2023 Cyber Security Inspection Report 05000461/2023401 ML23191A8772023-07-11011 July 2023 Operator Licensing Examination Approval Clinton Power Station July 2023 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 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 RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release 2024-08-09
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing 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 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 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 ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 ML22263A4732022-11-10010 November 2022 Issuance of Amendment No. 247 Adoption of TSTF-230, Revision 1 ML22292A0352022-11-10010 November 2022 Issuance of Amendment No. 246 Secondary Containment and the Fuel Building Railroad Airlock (EPID L-2022- LLA-0055) ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 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) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21306A0002021-12-21021 December 2021 License Amendment to Revise Degraded Voltage Relay Allowable Values 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) ML21132A2882021-06-28028 June 2021 Issuance of Amendment No. 238, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21090A1932021-05-19019 May 2021 Issuance of Amendment No. 237 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20266G3432020-10-14014 October 2020 Issuance of Amendment No. 235 Regarding Operation of the Emergency Auxiliary Reserve Transformer Load Tap Changer 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 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 ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications ML19238A3082019-09-30030 September 2019 Issuance of Amendment - Regarding Adoption of TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19109A0012019-06-12012 June 2019 Issuance of Amendment Regarding Recapture of Low-Power Testing Time ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation 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 ML18113A0452018-05-29029 May 2018 Issuance of Amendments to Revise Technical Specification Requirements for Secondary Containment ML18072A0502018-04-30030 April 2018 Issuance of Amendment Regarding the Spent Fuel Pool Level (CAC No. MF9962; EPID L-2017-LLA-0258) ML18110A3542018-04-24024 April 2018 Correction to Facility Operating License ML18043A5052018-03-22022 March 2018 Issuance of Amendment to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MF9666; EPID L-2017-LLA-0223) ML17324A3542018-01-22022 January 2018 Issuance of Amendment Regarding Residual Heat Removal Subsystem Operability Requirements During Decay Heat Removal Operations (CAC No. MF9684; EPID L-2017-LLA-0225) ML17237A0102017-09-26026 September 2017 Issuance of Amendment 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) ML17027A0382017-02-22022 February 2017 Issuance of Amendment Regarding Inservice Leak and Hydrostatic Testing Operations ML16217A3322016-08-17017 August 2016 Issuance of Amendment Concerning Incorporation of Revised Alternative Source Term (CAC No. MF7336) (RS-16-019) RS-16-132, 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) ML15251A5842015-12-18018 December 2015 Issuance of Amendment Concerning Revision to Integrated Leak Test Intervals (TAC No. MF5291)(RS-14-308) ML15280A2582015-10-22022 October 2015 Issuance of Amendment Related to One-Time Extension of Completion Time for Shutdown Service Water (TAC No. MF6705)(RS-15-264) 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) 2024-07-11
[Table view] Category:Safety Evaluation
MONTHYEARML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing 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 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan 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 ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22292A0352022-11-10010 November 2022 Issuance of Amendment No. 246 Secondary Containment and the Fuel Building Railroad Airlock (EPID L-2022- LLA-0055) ML22263A4732022-11-10010 November 2022 Issuance of Amendment No. 247 Adoption of TSTF-230, Revision 1 ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications 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) ML22047A1272022-02-22022 February 2022 Relief from the Requirements of the American Society of Mechanical Engineers Code ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21306A0002021-12-21021 December 2021 License Amendment to Revise Degraded Voltage Relay Allowable Values ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) 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 ML21132A2882021-06-28028 June 2021 Issuance of Amendment No. 238, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21166A1682021-06-25025 June 2021 ML21090A1932021-05-19019 May 2021 Issuance of Amendment No. 237 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems 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 ML20268C2322020-11-0404 November 2020 Proposed Alternative I4R-06 to the Requirements of the ASME Code ML20266G3432020-10-14014 October 2020 Issuance of Amendment No. 235 Regarding Operation of the Emergency Auxiliary Reserve Transformer Load Tap Changer 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 ML20218A6602020-09-0202 September 2020 Proposed Alternative I4R-01 to the Requirements of the ASME Code ML20232A1882020-09-0101 September 2020 Proposed Alternative I4R-02 to the Requirements of the ASME Code ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20219A2022020-09-0101 September 2020 Proposed Alternative I4R-05 to the Requirements of the American Society of Mechanical Engineers Code ML20212L3902020-08-31031 August 2020 Proposed Alternative I4r-03 to the Requirements of the Asme Code (Epid L-2019-Llr-0114) 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 ML20163A7172020-06-26026 June 2020 Proposed Alternative to the Requirements of the ASME Code ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML20010E8702020-01-27027 January 2020 Proposed Alternative to the Requirements of the ASME Code ML19238A3082019-09-30030 September 2019 Issuance of Amendment - Regarding Adoption of TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19109A0012019-06-12012 June 2019 Issuance of Amendment Regarding Recapture of Low-Power Testing Time ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements 2024-07-11
[Table view] Category:Technical Specifications
MONTHYEARML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing 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-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-048, 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls)2022-03-31031 March 2022 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls) ML22111A2142022-03-31031 March 2022 2 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21193A1302021-07-14014 July 2021 Correction to Amendment No. 238 Issued June 28, 2021, Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-16-228, Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition 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) ML15251A5842015-12-18018 December 2015 Issuance of Amendment Concerning Revision to Integrated Leak Test Intervals (TAC No. MF5291)(RS-14-308) ML15280A2582015-10-22022 October 2015 Issuance of Amendment Related to One-Time Extension of Completion Time for Shutdown Service Water (TAC No. MF6705)(RS-15-264) RS-15-260, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time2015-09-30030 September 2015 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time RS-15-246, Exigent License Amendment Request for One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time2015-09-10010 September 2015 Exigent License Amendment Request for One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) RS-15-121, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment.2015-04-21021 April 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-308, License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment.2014-11-17017 November 2014 License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process ML1122319432011-10-0404 October 2011 Issuance of License Amendment No. Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Values to Licensee Control RS-11-117, License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources - Operating.2011-08-15015 August 2011 License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources - Operating. RS-11-073, License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies.2011-06-13013 June 2011 License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies. ML1109702192011-05-0606 May 2011 Correction to Issuance of License Amendments Regarding Risk-informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a License-controlled Program RS-10-050, License Amendment Request to Remove Operating Mode Restrictions for Performing Division 3 AC Sources Surveillance Testing2010-10-28028 October 2010 License Amendment Request to Remove Operating Mode Restrictions for Performing Division 3 AC Sources Surveillance Testing RS-10-148, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2010-10-0808 October 2010 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-10-131, License Amendment Request to Revise Technical Specifications Limiting Condition for Operation 3.7.6, Main Turbine Bypass System2010-09-23023 September 2010 License Amendment Request to Revise Technical Specifications Limiting Condition for Operation 3.7.6, Main Turbine Bypass System RS-10-039, License Amendment Request to Administratively Revise Technical Specifications2010-06-0404 June 2010 License Amendment Request to Administratively Revise Technical Specifications RS-10-093, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B2010-05-21021 May 2010 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML1002000052010-01-15015 January 2010 License Amendment, Modify CPS License Condition 2.B.(6) and Create New License Conditions 1.J, 2.B.(7) and 2.C.(25) as Part of a Pilot Program to Irradiate Cobalt (Co)-59 Target to Produce Co-60 RS-09-074, License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies2009-06-26026 June 2009 License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies ML0907108682009-04-0202 April 2009 Licensed Amendment, Adopted TSTF-2, Relocate the 10-year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML0829400102008-10-30030 October 2008 Issuance of Amendment Technical Specification Change as Part of Implementation of TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil ML0826103082008-09-12012 September 2008 Tech Spec Pages for Amendment 181 License Amendment to Increase the Interval Between Local Power Range Monitor ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0819601482008-06-30030 June 2008 Tech Spec Page for Amendment 179 Regarding TS Changes Related to Surveillance Frequency for Scram Discharge Volume Water Level Float Switch RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0731003892007-10-31031 October 2007 Technical Specifications, Changes Resulting from the Incorporation of TSTF-448, Control Room Habitability. RS-07-133, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil Using Consolidated Line Item Improvement Process2007-09-27027 September 2007 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil Using Consolidated Line Item Improvement Process RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators 2024-07-11
[Table view] |
Text
July 11, 2024
David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UN IT NO. 1 - ISSUANCE OF AMENDMENT NO. 254 RE: REVISION OF REACTO R WATER CLEANUP ISOLATION VALVE TIMING (EPID L-2023-LLA-0118)
Dear David Rhoades:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 254 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No. 1. The amendment is in response to your letter dated August 21, 2023, as supplemented by letter dated May 9, 2024.
The amendment revises the reactor water cleanup (RWCU) system isolation functions that are listed in Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, Table 3.3.6.1-1, Primary Containment and Drywell Isolation Instrumentation.
Specifically, the change increases the allowable value for Function 4.b, Differential Flow-Timer, and renames Function 4.b as Diffe rential Flow Timer - High. In addition, new functions are added for a differential flow timer - high-high trip and an associated differential flow high-high timer.
D. Rhoades
A copy of the Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions next monthly Federal Register notice.
Sincerely,
/RA/
Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-461
Enclosures:
- 1. Amendment No. 254 to NPF-62
- 2. Safety Evaluation
cc: Listserv
CONSTELLATION ENERGY GENERATION, LLC
DOCKET NO. 50-461
CLINTON POWER STATION, UNIT NO. 1
AMENDMENT TO FACILITY OPERATING LICENSE
Amendment No. 254 License No. NPF-62
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Constellation Energy Generation, LLC (the licensee) dated August 21, 2023, as supplemented by letter dated May 9, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 254, are hereby incorporated in the license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented prior to startup from the fall 2025 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications
Date of Issuance: July 11, 2024
ATTACHMENT TO LICENSE AMENDMENT NO. 254
FACILITY OPERATING LICENSE NO. NPF- 62
CLINTON POWER STATION, UNIT NO. 1
DOCKET NO. 50-461
Replace the following pages of the Facility Operating License No. NPF-62 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT
Page 3 Page 3
Technical Specifications
REMOVE INSERT 3.3-59 3.3-59
(4) Constellation Energy Generation, LLC, pursuant to the Act and to 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
(5) Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components;
(6) Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation; and
(7) Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level
Constellation Energy Generation, LLC is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 254, are hereby incorporated into this license.
Constellation Energy Generation, LLC, shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 254 Primary Containment and Drywell Isolation Instrumentation 3.3.6.1
Table 3.3.6.1-1 (page 5 of 6)
Primary Containment and Drywell Isolation Instrumentation
APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE
- 3. RCIC System Isolation (continued)
- j. Drywell Pressure - High 1,2,3 2 I SR 3.3.6.1.1 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
- k. Manual Initiation 1,2,3 1 J SR 3.3.6.1.6 NA
- 4. Reactor Water Cleanup (RWCU) System Isolation
- a. Differential Flow - 1,2,3 2 I SR 3.3.6.1.1 66.1 gpm High SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8
- b. Differential Flow Timer 1,2,3 2 I SR 3.3.6.1.2 863 seconds
- High SR 3.3.6.1.4 SR 3.3.6.1.6
- c. RWCU Heat Exchanger 1,2,3 2 per I SR 3.3.6.1.1 205°F Equipment Room room SR 3.3.6.1.2 Temperature-High SR 3.3.6.1.5 SR 3.3.6.1.6
- d. RWCU Pump Rooms 1,2,3 2 per I SR 3.3.6.1.1 202°F Temperature-High room SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- e. Main Steam Line Tunnel 1,2,3 2 I SR 3.3.6.1.1 171°F Ambient Temperature- SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6
- f. Reactor Vessel Water 1,2,3 4 I SR 3.3.6.1.1 -48.1 inches Level-Low Low, SR 3.3.6.1.2 Level 2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8
- g. Standby Liquid Control 1,2,3 2 L SR 3.3.6.1.6 NA System Initiation
- h. Manual Initiation 1,2,3 2 J SR 3.3.6.1.6 NA
(c) 2 N SR 3.3.6.1.6 NA
- i. Differential Flow - 1,2,3 2 I SR 3.3.6.1.1 182.4 gpm High-High SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8
- j. Differential Flow Timer 1,2,3 2 I SR 3.3.6.1.2 47 seconds
- High-High SR 3.3.6.1.4 SR 3.3.6.1.6
(continued)
(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
CLINTON 3.3-59 Amendment No. 254 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELATED TO AMENDMENT NO. 254 TO
FACILITY OPERATING LICENSE NO. NPF-62
CONSTELLATION ENERGY GENERATION, LLC
CLINTON POWER STATION, UNIT NO. 1
DOCKET NO. 50-461
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated August 21, 2023 (Agencywide Documents Access and Managem ent System (ADAMS) Accession No. ML23233A168), Constellation Energy Generation, LLC (the licensee) submitted a license amendment request (LAR) for Clinton Power Station (Clinton), Unit No. 1, to revise the reactor water cleanup (RWCU) system isolation functions that are listed in Technical Specification (TS) 3.3.6.1, "Primary Containment and Drywell Isolat ion Instrumentation," Table 3.3.6.1-1, "Primary Containment and Drywell Isolation Instrumentation." Specifically, the change increases the allowable value for Function 4.b, "Differential Flow - Timer," and renames Function 4.b as "Differential Flow Timer - High." In addition, new functions are added for a differential flow -
high- high trip and an associated differential flow high - high timer. In response to a request for additional information (RAI), the licensee supplemented the LAR on May 9, 2024 (ML24130A221). The supplement provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published the Federal Register on October 31, 2023 (88 FR 74529).
2.0 REGULATORY EVALUATION
2.1. System Description
The RWCU system continuously removes solid and dissolved impurities from the reactor water through filter demineralizers to maintain the purit y within specified limits. The system takes its suction within the drywell from the inlet of each reactor main recirculation pump and from the reactor pressure vessel bottom head. The process fluid is circulated with the cleanup pumps through a regenerative and nonregenerative heat exchanger for cooling, through the filter demineralizers for cleanup and back through the regenerative heat exchanger for reheating.
The regenerative and nonregenerative heat exchangers and filter demineralizers are located within the containment while the RWCU pumps are located within the auxiliary building. The processed water is returned to the reactor pressure vessel and/or the main condenser or
Enclosure 2
radwaste. Although the RWCU system is of importance to startup and long-term operation, the reactor may operate while the RWCU system is out of service.
The Updated Safety Analysis Report [USAR], Section 7.3.1.1.2.4.1.9, Reactor Water Cleanup (RWCU) System - High Differential Flow reads, in part:
High differential flow in the reactor water cleanup system could indicate a breach of the pressure boundary in the RWCU system. The RWCU system flow at the inlet to the system (suction from reactor recirculation lines) is compared with the sum of the flows at the outlets of the system (return to feedwater and flow to the Main Condenser). High differential flow initiates isolation of the RWCU system.
The RWCU system is monitored by the nuclear boiler leak detection system as described in USAR, Section 5.2.5.1, Leakage Detection Methods. The primary safety function of the leak detection system is to ensure that abnormal leakage from select systems within the primary containment and within selected areas of the plant outside the primary containment is detected, indicated, alarmed, and in certain cases isolated.
The RWCU system can be isolated by the following signals:
- 1. Reactor Vessel Water Level Low Low, Level 2;
- 2. Main Steam Tunnel Ambient Temperature High;
- 3. RWCU Differential Flow - High;
- 4. RWCU Equipment Areas (heat exchanger equi pment room or pump rooms) Ambient Temperature High;
- 5. Standby Liquid Control System Initiation; and
- 6. Manual Initiation.
Of these signals only the RWCU Differential Flow - High function is affected by the proposed TS changes contained within the LAR.
2.2 Description of the Proposed Changes
The LAR proposes the following changes to TS table 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation.
The proposed change extends the allowable value for the Function 4.b, Differential Flow Timer, length from 47 seconds to 863 seconds. This time delay works in conjunction with Function 4.a, Differential Flow - High, to prevent spurious trips during most RWCU operational transients.
Due to this relationship between Functions 4.a and 4.b, the proposed change also renames Function 4.b as Differential Flow Timer - High.
In addition, the proposed change adds the following new RWCU system isolation functions.
APPLICABLE REQUIRED CONDITIONS MODES OR CHANNELS REFERENCED SURVEILLANCE ALLOWABLE FUNCTION OTHER PER FROM REQUIREMENTS VALUE SPECIFIED FUNCTION REQUIRED CONDITIONS ACTION F.1
- i. Differential 1,2,3 2 I SR 3.3.6.1.1 182.4 gpm Flow - SR 3.3.6.1.2 High-High SR 3.3.6.1.6 SR 3.3.6.1.8
- j. Differential 1,2,3 2 I SR 3.3.6.1.2 47 seconds Flow SR 3.3.6.1.4 Timer - SR 3.3.6.1.6 High-High
2.3 Regulatory Discussion
The regulatory requirements in Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c) require that the TS include items in five specific categories related to station operation. These categories are (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operations (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
Regulation 10 CFR 50.36(c)(2)(i), Limiting conditions for operation, states, in part, that TSs will include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. Section 50.36(c)(2)(i) further states that [w]hen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met.
Regulation 10 CFR 50.36(c)(3), Surveillance requirements, states that [s]urveillance requirements are requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
The regulations in 10 CFR, part 50, Domestic Licensing of Production and Utilization Facilities, Appendix A, General Design Criteria [GDC] for Nuclear Power Plants, includes the following GDCs applicable to the licensees LAR:
Criterion 4 - GDC 4, Environmental and dynamic effects design bases, states, in part, that structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents.
Criterion 54 - GDC 54 Piping systems penetrating containment, states, in part, that Piping systems penetrating primary reactor containment shall be provided with leak detection, isolation, and containment capabilities having
redundancy, reliability, and performance capabilities which reflect the importance to safety of isolating these piping systems.
NUREG-1434, Revision 5, Standard Technical Spec ifications for General Electric Plants, Boiling Water Reactor-6 (ML21271A582), provides ex ample TS LCOs and acceptable remedial actions that meet the requirements in 10 CFR 50.36(c)(2)(i) for a standard plant design.
3.0 TECHNICAL EVALUATION
3.1 NRC Staff Evaluation
3.1.1 Radiological Analysis
The NRC staff performed independent radiological consequence analyses confirming the licensees conclusion that the current Clinton design basis main steam line break (MSLB) accident analysis remains bounding. More specifically, the NRC staff verified that the radiological consequences for the RWCU system leak at the exclusion area boundary, low population zone, and main control room, would be a small fraction of the current licensing basis radiological consequences for the MSLB accident. The activity available for release from the RWCU system leak is that present in the reactor coolant, with two cases (i.e., Case 1 and Case 2) based on the maximum equilibrium and pre-accident iodine spike concentrations of 0.2 Ci/gm (millicurie per gram) and 4.0 Ci/gm dose equivalent I [iodine]-131, respectively. A comparison of the current design basis MSLB accident and the RWCU system leak radiological consequences is shown in Table 3 of the LAR. The NRC staff concludes that the licensees proposed changes, as described in the August 21, 2023, LAR, are acceptable from a radiological consequence perspective because t he NRC staffs independent analysis confirmed that the radiological consequences are a small fraction of the radiological consequences of the MSLB accident as described above.
3.1.2 RWCU Isolation System Performance
3.1.2.1 High Energy Line Break (HELB)
Since the RWCU system penetrates the containment boundary, 10 CFR, part 50, appendix A, Criterion 54, requires that the system be provided with leak detection, having redundancy, reliability, and performance capabilities, which reflect the importance to safety of isolating the piping system.
USAR, Section 5.2.5, Reactor Coolant Pressure Boundary and ECCS [Emergency Core Cooling System] System Leakage Detection System indicates that abnormal leakage from the reactor water cleanup system within the primary containment and within selected areas of the plant outside the primary containment is detected, indicated, alarmed, and isolated.
The LAR proposes the following changes to the RWCU system timer for detecting and isolating large breaks. Function 4.j, Differential Flow Timer - High - High, will be added to TS Table 3.3.6.1-1, with the current Allowable Value of 47 seconds. In addition, Function 4.i, Differential Flow Timer - high - high, will be added to TS, Table 3.3.6.1-1, with an Allowable Value of 182.4 gpm (gallons per minute).
To ensure the proposed TS changes are bounded by the existing design basis analyses for a guillotine break isolated within 47 seconds, the licensee analyzed inside containment
sub-compartment response for breaks up to 182.4 gpm for 863 seconds for the main steam tunnel (MST), RWCU heat exchanger and heat exchanger valve rooms, RWCU crossover pipe tunnel, filter demineralizer holding pump room, filter demineralizer valve room, and filter demineralizer rooms. The result of the licensee s analysis indicates that peak temperatures, pressures, and differential pressures, for each zone are bounded by the large break result in the base calculation or that the structure was evaluated to ensure allowable stresses were not exceeded. Therefore, existing containment sub-compartment responses for a double-ended guillotine break remain applicable.
The NRC staff audited, via the licensees electronic portal, the calculations pertaining to HELB listed in LAR, Attachment 5, Design Analysis IP-C-0096, "Setpoint Calculation Reactor Water Cleanup (RWCU) System Isolation-Differential Flow Timers, 1E31R615A(B), and 1E31R616A(B)," Revision 0B. In particular, the staff focused on the assumptions and the methodologies contained within both calculations 3C10-0377-001 and 3C10-1182-003. After reviewing the assumptions and the methodologies contained therein the staff identified one issue that needed further clarification with a staff/licensee audit discussion.
During the audit the licensee posted calculation ATD-0278 on the electronic portal in support of a licensee/staff discussion that occurred on March 20, 2024. The calculation provides analysis of HELB within the auxiliary buildings RWCU pump rooms. In the RAI-1 response of May 9, 2024, the licensee summarized calculation ATD-0278 as follows:
Calculation ATD-0278 evaluates high energy line breaks (HELB) in the RWCU pump rooms. As stated in this calculation, the mass and energy release uses a detection time of 0.7 seconds due to ambient temperature detection to initiate valve closure. This is much faster than the differential flow time delay of 45 seconds, and therefore, is unaffected by the proposed changes to the differential flow setpoints.
The NRC staff verified congruence between the conclusions presented in LAR, Section 3.4.1, and the results of the three identified calculations.
Based on the: (a) review of the LAR; (b) review of the Clinton USAR; (c) NRC staffs audit; (d) review of the RAI response; and (e) applicable regulatory requirements, the staff concludes that with approval of the proposed TS changes to TS Table 3.3.6.1, the RWCU system will continue to satisfy the requirements of 10 CFR 50, appendix A, Criterion 54.
3.1.2.2 Internal Flooding Analysis
Meeting the requirements of 10 CFR 50, appendix A, GDC 4, ensures that the structures, systems, and components important to safety will be appropriately protected from potential flooding from liquid-carrying components in the plant.
The licensee revised Calculation 3C10-0485-001 that documents the internal flooding analysis to determine the effects of the design modification and corresponding changes to TS, Table 3.3.6.1, on the maximum flood levels in sub-compartments both inside and outside containment.
Only the RWCU line breaks inside containment credit differential flow as the means for detection and isolation of breaks. The calculation was revised to address releases corresponding to double-ended guillotine breaks (i.e., isolated by the short timer 47 seconds) and the maximum release for intermediate pipe breaks (isolated by the long timer 863 seconds). The calculation evaluates both steady state flood levels due to flow in and out of a
cubicle, and flood levels due to total released inventory. Where steady state levels are considered, the double-ended guillotine break with fast isolation is bounding due to the higher flow rates. Where total released inventory is considered, the new setpoint release is bounding due to larger volume.
The licensee provided the impact on safe shutdown equipment with updated flood levels for the plant areas (i.e., Environmental Zone Code) contained in LAR, Table 2, Environmental Zones with increased flood levels.
With respect to the flooding effects on the plants structural analysis, the licensee stated that:
the existing design basis anal yses are bounding for compartment temperature and pressure. Therefore, the RWCU compartment structures do not require re-evaluation for changes in pressure or temperature. The increased flood levels were evaluated for impacts to the RWCU cubicles structure. The evaluation determined that the structures remain qualified for design basis loads.
The NRC staff audited, via the licensees electronic portal, the calculation pertaining to internal flooding analysis listed in LAR, Attachment 5, D esign Analysis IP-C-0096, "Setpoint Calculation Reactor Water Cleanup (RWCU) System Isolation-Differential Flow Timers, 1E31R615A(B), and 1E31R616A(B)," Revision 0B. In particular, the staff focused on the assumptions and the methodologies contained within Calculation 3C10-0485-001. After reviewing the assumptions and the methodologies contained therein, the NRC staff identified one issue that needed further clarification with a staff/licensee audit discussion.
During the audit, the NRC staff inquired whether a line break in the RWCU pump rooms located in the auxiliary building could leak into the building hallway such that the water flows down the floor plugs into the ECCS cubicles? In the RAI-2 response of May 9, 2024, the licensee provided the response to this audit question:
The RWCU pump rooms do not have watertight doors, and a line break in this area could flood into the Auxiliary Building hallway. However, the floor plugs in the Auxiliary Building hallway that are above the ECCS cubicles have seals to prevent a flood from leaking down into the ECCS cubicles.
The NRC staff verified agreement between the conclusions presented in LAR, Section 3.4.2, and the results of calculation 3C10-0485-001.
Based on the: (a) review of the LAR; (b) review of the Clinton USAR; (c) NRC staffs audit; (d) review of the RAI response; and (e) applicable regulatory requirements, the staff concludes that with approval of the TS changes to TS, Table 3.3.6.1, the RWCU system will continue to satisfy the requirements of 10 CFR 50, appendix A, Criterion 4.
3.1.3 Instrumentation Setpoint Analysis
The existing leak detection system nominal trip setpoints and timer settings were determined by the General Electric (GE) Design Specification and Design Spec Data Sheet (DSDS).
This amendment does not change the existing square root converters 1E31-K602A/B, 1E31-K603A/B, 1E31-K605A/B, summer cards 1E31-K604A/B and alarm cards 1E31-N609A/B.
The differential pressure transmitters for recirculation suction 1E31-N076A/B, feedwater return 1E31-N077A/B, and condenser return, 1E31-N075A/B are replaced as part of the modification with more accurate instruments to reduce the total instrument loop uncertainty. Therefore, the existing GE DSDS will remain valid for the uncertainty of the existing and unchanged 59 gpm differential flow - high setpoint and 66.1 gpm allowable value, 45 second differential flow timer-high - high setpoint and 47 seconds allowable value.
The licensee stated that they followed ISA 67.04-1994 methodology to determine the nominal trip setpoint (NTSP) of 164.2 gpm and allowable value of 182.4 gpm for the differential flow -
high - high, the NTSP of 840 seconds and the allowable value of 863 seconds for the differential flow timer - high. The licensee presented the calculation details of these setpoints and allowable values in Attachment 4 of th is LAR, Design Analysis IP-C-0132 RWCU Di Differential Flow Setpoint Analysis for Detecting Large Leaks," Revision 0. The setpoint methodology is presented in the licensee controlled Nuclear Station Engineering Standard CI-01.00, Instrument Setpoint Calculation Methodology Revision 4.
The NRC staff examined the licensees allowable value and trip setpoint calculations and confirmed these calculations are consistent with the method suggested in ISA 67.04-1994. The uncertainty terms included in the calculation are consistent with the terms suggested in ISA 67.04-1994. The allowance between the NTSP and the allowable value equals to the loop/channel as-found tolerance (AFT L) and AFTL value accounts for the loop device drift value and calibration effect. This NTSP calculation assures that the loop trip setpoint as-found condition does not exceed the allowable value provided this loop is operable. The NRC staff finds that these calculations are consistent with the method suggested in ISA 67.04-1994 and are, therefore, acceptable.
3.2 NRC Staff Conclusion
Based on the above, the NRC staff concludes that the proposed changes to TS 3.3.6.1, Table 3.3.6.1.1 provide reasonable assurance that TS 3.3.6.1 would continue to ensure operation of the facility in a safe manner. Therefore, the NRC staff concludes that the TS 3.3.6.1 proposed changes will continue to meet 10 CFR 50.36(c)(2) and (c)(3). Based on the above technical review results, the NRC staff finds that the TS changes proposed by the LAR are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendment on June 4, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR, part 20, and changes SRs.
The NRC staff has determined that the amendment involves 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 i ndividual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, published in the Federal Register on October 31, 2023 (88 FR 74529), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for catego rical 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) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: D. Nold J. Parillo M. Li F. Forsaty A. Russell
Date of Issuance: July 11, 2024
ML24157A324 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NRR/DSS/SCPB/BC NAME JWiebe SRohrer SMehta MValentin DATE 6/4/2024 6/6/2024 6/11/2024 5/30/2024 OFFICE NRR/DRA/ARCB/BC NRR/DEX/EICB/BC NRR/DSS/SNSB/BC(A) OGC - NLO NAME KHsueh SFanta RBeaton AGhoshNaber DATE 6/1/2024 6/7/2024 6/5/2024 6/24/2024 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME JWhited JWiebe DATE 7/11/2024 7/11/2024