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Category:Letter type:RS
MONTHYEARRS-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 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 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 RS-24-031, Updated Safety Analysis Report (Usar), Revision 232024-04-0101 April 2024 Updated Safety Analysis Report (Usar), Revision 23 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release 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 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 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 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 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 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 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 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 RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022 Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock 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-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-069, Third Inservice Inspection Interval Relief Request I3R-182021-06-28028 June 2021 Third Inservice Inspection Interval Relief Request I3R-18 RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations 2024-06-14
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24045A0262024-02-14014 February 2024 License Renewal Application RS-24-012, Application for Renewed Operating License - Appendix E, Applicants Environmental Report2023-11-30030 November 2023 Application for Renewed Operating License - Appendix E, Applicants Environmental Report 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 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 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 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments 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 ML21188A0202021-08-11011 August 2021 Issuance of Amendment No. 239 One-Time Extension of Containment Type a Integrated Leakage Rate Test Frequency RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency2021-02-24024 February 2021 License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-053, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2020-04-30030 April 2020 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-06-18018 June 2019 Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-116, Application to Revise Technical Specifications to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process (NEDO-33091), Revision 12018-09-28028 September 2018 Application to Revise Technical Specifications to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process (NEDO-33091), Revision 1 RS-18-105, License Amendment Request to Recapture Low-Power Testing Time2018-09-17017 September 2018 License Amendment Request to Recapture Low-Power Testing Time 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-18-032, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2018-04-25025 April 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML18053A1822018-01-31031 January 2018 Enclosure 3 - Clinton Power Station, Unit 1 - Evaluation of Proposed Changes RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1702018-01-31031 January 2018 Attachment 3A - Clinton Power Station, Unit 1 - Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1712018-01-31031 January 2018 Attachment 3B - Clinton Power Station, Unit 1 - Clean Emergency Plan EP-AA-1000 Pages RS-18-005, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation2018-01-0909 January 2018 License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements RS-17-076, License Amendment Request to Revise Spent Fuel Pool Level2017-07-18018 July 2017 License Amendment Request to Revise Spent Fuel Pool Level RS-17-017, License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations2017-05-0404 May 2017 License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process 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 RS-16-211, License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 12016-11-0404 November 2016 License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 1 ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-143, License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition2016-08-11011 August 2016 License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition ML16229A2792016-08-11011 August 2016 Attachments 1 - 7: Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition 2024-04-12
[Table view] |
Text
4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-17-076 10 CFR 50.90 July 18, 2017
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
License Amendment Request to Revise Spent Fuel Pool Level
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Appendix A, Technical Specifications (TS) of Facility Operating License (FOL) No. NPF-62 for Clinton Power Station (CPS), Unit 1. The proposed amendment revises the design value for the spent fuel storage pool in TS 4.3.2, "Drainage," to the appropriate value.
The current value in TS 4.3.2 was included in the original CPS TS. However, an inconsistency with the TS value, relative to the original design basis was identified during a U.S. Nuclear Regulatory Commission (NRC) Component Design Basis Inspection (CDBI) at CPS in 2016. When this discrepancy was identified during the CDBI, EGC entered the issue into the EGC Corrective Action Program (CAP).
The attached amendment request is subdivided as follows:
Attachment 1 provides a description and evaluation of the proposed changes.
Attachment 2 provides the marked-up TS page with the proposed change indicated.
The proposed amendment has been reviewed by the CPS Plant Operations Review Committee in accordance with the requirements of the EGC Quality Assurance Program.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State of Illinois official.
EGC requests approval of the proposed license amendment by July 18, 2018. Once approved, the amendment will be implemented within 60 days of issuance.
ATTACHMENT 1 Evaluation of Proposed Change Page 1 of 9
Subject:
License Amendment Request to Revise Spent Fuel Pool Level 1.0
SUMMARY
DESCRIPTION
2.0 DETAILED
DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration
4.3 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
ATTACHMENT 1 Evaluation of Proposed Change Page 2 of 9 1.0
SUMMARY
DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Appendix A, Technical Specifications (TS) of Facility Operating License (FOL) No. NPF-62 for Clinton Power Station (CPS), Unit 1. The proposed amendment revises the design value for the spent fuel storage pool in TS 4.3.2, "Drainage," to the appropriate value.
The current value in TS 4.3.2 was included in the original CPS TS. However, a discrepancy between the TS value and the original design basis was identified during a U.S. Nuclear Regulatory Commission (NRC) Component Design Basis Inspection (CDBI) at CPS in 2016. When this was identified during the CDBI, EGC entered the issue into the EGC Corrective Action Program (CAP).
2.0 DETAILED
DESCRIPTION
The proposed change revises the design value for the spent fuel storage pool level in TS 4.3.2 from the current value of 754 feet, 0 inches to 741 feet, 0 inches. The proposed TS states:
TS 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 741 feet, 0 inches.
provides the marked-up TS page with the proposed change indicated.
During an NRC CDBI at CPS in 2016, NRC inspectors identified an inconsistency between the site specific value in CPS TS 4.3.2 and the original design basis for the spent fuel storage pool, relative to the basis for the Design Features section of TS (i.e., as described in 10 CFR 50.36(c)(4)). Specifically, 10 CFR 50.36(c)(4) states:
"Design features to be included are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section." The current TS 4.3.2 value of 754 feet, 0 inches for the SFP level is not consistent with the regulatory basis for a "Design Feature." EGC has determined that the correct value for TS 4.3.2 is 741 feet, 0 inches. The basis and justification for this revised SFP level is described in Section 3.0, "Technical Evaluation."
ATTACHMENT 1 Evaluation of Proposed Change Page 3 of 9
3.0 TECHNICAL EVALUATION
Spent Fuel Storage Pool Design Basis The CPS spent fuel storage facility consists of a spent fuel pool (SFP), a fuel transfer pool (FTP), a fuel cask storage pool (FCSP), a fuel cask washdown area (FCWA), and an upper containment fuel pool (UCFP). The SFP, FTP, FCSP, and FCWA are adjacent to each other in the fuel building (FB) and are physically separated from each other by removable gates.
The structures housing the CPS spent fuel storage facility (i.e., the FB and containment) are designed to seismic Category I criteria, as are the fuel storage racks, pool liners, gates, and storage pools. These buildings are also designed against flooding and tornado missiles. Thus, the CPS spent fuel storage facility complies with the requirements of 10 CFR Part 50, Appendix B, "General Design Criteria" (GDC) 2 and the guidelines of Regulatory Guide (RG) 1.29, "Seismic Design Classification," and, RG 1.117, "Tornado Design Classification."
The CPS spent fuel storage facility complies with GDC 61, "Fuel storage and handling and radioactivity control" and RG 1.13, "Spent Fuel Storage Facility Design Basis," Revision 1.
Regulatory Position C.6 of RG 1.13 establishes the design criteria for TS 4.3.2:
"Drains, permanently connected mechanical or hydraulic systems, and other features that by maloperation or failure could cause loss of coolant that would uncover fuel should not be installed or included in the design. Systems for maintaining water quality and quantity should be designed so that any maloperation or failure of such systems (including failures resulting from the Safe Shutdown Earthquake) will not cause fuel to be
uncovered." The original design criteria for the SFP, FTP and FCSP (i.e., the FB spent fuel storage pools) established a level of SFP inventory that provides a safe shielding level:
"The level in the fuel storage pools will be maintained at a minimum of eight feet above the top of the fuel during normal station operation. These levels of water provide adequate shielding for personnel protection." The CPS SFP safe shielding level design criteria is consistent with the requirements of NUREG-0800, U.S. Nuclear Regulatory Commission Standard Review Plan," Chapter 9.1.3, "Spent Fuel
Pool Cooling and Cleanup System," Revision 4:
"The spent fuel pool and cooling systems have been designed so that in the event of failure of inlets, outlets, piping, or drains, the pool level will not be inadvertently drained below a point approximately 3 meters (10 feet) above the top of the active fuel."
ATTACHMENT 1 Evaluation of Proposed Change Page 4 of 9 The CPS SFP design, including the safe shielding level, was approved by the NRC in NUREG-0853, "Safety Evaluation Report related to the operation of Clinton Power Station Unit 1:"
"No connections are provided to the spent fuel pool that may cause the pool water to be drained below a safe shielding level. All lines that connect to the pool and extend below the safe level of the pool water are equipped with syphon breakers, check valves, or other means to prevent inadvertent pool drainage."
Spent Fuel Storage Pool Operation The water level in the FB spent fuel storage pools is normally maintained at an elevation of 754 feet, 0 inches. This level is approximately 27 feet above the top of irradiated fuel assemblies (i.e., elevation 726 feet, 73/4 inches) and approximately 19 feet above the safe shielding level.
The water level in the FB spent fuel storage pools is procedurally controlled by Operational Requirements Manual (ORM) 2.4.8, "Spent Fuel Storage, Cask Storage and Upper Containment Pools." Specifically, ORM 2.4.8 requires maintaining at least 23 feet of water above the top of irradiated fuel assemblies (i.e., elevation of 749 feet, 73/4 inches for the SFP and FCSP). The FCWA is normally empty (i.e., not filled with water).
Several fuel pool cooling system (FC) lines which are not equipped with check valves, discharge into the FB spent fuel storage pools below 754 feet, 0 inches. These FC lines, and the associated discharge elevations are described in Table 1 below. Since these FC discharge lines are not equipped with a check valve (i.e., to prevent inadvertent drainage), failure of any of one of these lines, external to the FB spent fuel storage pools, would result in a siphon effect, which in turn, would drain the spent fuel storage pools to the discharge elevation of the failed FC line. As depicted in Table 1, the lowest discharge point in the SFP is a 14-inch line at an elevation of 741 feet, 0 inches.
Alternatively, if there is no water in the FTP, FCSP, or FCWA, the potential failure of the gates separating these pools from the SFP would lower SFP level to 740 feet, 6 inches. The SFP gates are non-safety related but seismically supported. The SFP gates were analyzed for seismic SSE and thermodynamic (i.e., sloshing) loads with water on only one side of the gate, which is the bounding condition for largest loads on the gates. The gates are held in place in the FB (i.e., a seismic Category 1 structure) by support brackets. Therefore, the gates will not fail during a seismic event. However, the pneumatic gate seals are non-safety, non-seismic and supplied by the instrument air (IA) system. Each gate has two redundant seals, one on either side of the gate. The IA supply to each seal has a check valve to prevent loss of pressure to the seal on loss of IA. In addition, CPS maintains backup air bottles that are permanently connected to the IA system.
ATTACHMENT 1 Evaluation of Proposed Change Page 5 of 9 Table 1 FC Pipe DischargeLines not Equipped with Check Valves (1) Location Equipment ID NumberEquipment Type Elevation Spent Fuel Pool 1FC104A- 1/2" 1/2 inch Siphon Breaker 749 feet, 0 inches 1FC01FB-6" 6-inch Pipe Discharge 742 feet, 0 inches (2) 1FC107AA- 1/2" 1/2 inch Siphon Breaker 749 feet, 6 inches 1FC14CA-14" 14-inch Pipe Discharge 741 feet, 0 inches 1FC107AB- 1/2" 1/2 inch Siphon Breaker 749 feet, 6 inches 1FC14CD-14" 14-inch Pipe Discharge 741 feet, 0 inches Fuel Transfer Pool (1) 1FC105A- 1/2" 1/2 inch Siphon Breaker 751 feet, 0 inches Fuel Cask Storage Pool (1) 1FC106A- 1/2" 1/2 inch Siphon Breaker 750 feet, 0 inches 1FCH4A-4" 4 inch Drain Pipe (with a locked close valve
)742 feet, 6 inches (1) There is an additional 4-inch FC line in both the FTP and the FCSP that discharge to diffusers at an elevation of approximately 712 feet. Both of these lines are equipped with check valves to prevent inadvertent draining. (2) The 6-inch FC pipe in the SFP discharges at an elevation of 736 feet, 6 inches. However, the lowest elevation of the line outside of the SFP is 742 feet with a check valve. In the event of a failure of this line, the siphon effect would be limited to an elevation of 742 feet.
Spent Fuel Storage TS Requirement CPS TS 4.3.2, "Drainage," as part of TS Section 4.0, "Design Features," states that the spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 754 feet. The NRC approved the s pent fuel storage pool design, as well as TS Section 5.0, "Design Features," TS 5.6.2, "Drainage," in NUREG-0853.
As stated in NUREG-0853, the Standard Technical Specifications for BWR-4 and BWR-5 plants were used as the basis for the original CPS TS. The "Drainage" Design Feature in the original CPS TS (i.e., TS 5.6.2) was consistent with the same note in NUREG-0123, "Standard Technical Specifications, General Electric BWR/5 Plants," Draft Revision 4.
This TS was retained and renumbered to TS 4.3.2 as an administrative change during conversion of the CPS TS to the Improved Technical Specifications (ITS) (i.e., NUREG-1434, Standard Technical Specifications, General Electric BWR/6 Plants). This conversion was approved by the NRC on December 2, 1994 as part of Amendment 95 to CPS FOL 62, (ADAMS Accession No. ML021000089). In both NUREG-0123 and NUREG-1434, the value specified in the "Drainage" TS is bracketed, and therefore requires a site-specific value.
ATTACHMENT 1 Evaluation of Proposed Change Page 6 of 9 Justification for Proposed Change The proposed value for the SFP level in TS 4.3.2 (i.e., 741 feet, 0 inches) is consistent with both GDC-61 and Regulatory Position C.6 of RG 1.13, Revision 1. Specifically, the failure of any FC discharge lines at or above this value would not cause the fuel to be uncovered.
In addition, the proposed value, which is approximately 13 feet above the top of irradiated fuel assemblies, is consistent with NUREG-0800, Chapter 9.1.3, "Spent Fuel Pool Cooling and Cleanup System," Revision 4:
"The spent fuel pool and cooling systems have been designed so that in the event of failure of inlets, outlets, piping, or drains, the pool level will not be inadvertently drained below a point approximately 3 meters (10 feet) above the top of the active fuel." Finally, the proposed value is consistent with the original CPS design basis, as approved by the NRC in NUREG-0853:
"The level in the fuel storage pools will be maintained at a minimum of eight feet above the top of the fuel during normal station operation. These levels of water provide adequate shielding for personnel protection." "No connections are provided to the spent fuel pool that may cause the pool water to be drained below a safe shielding level. All lines that connect to the pool and extend below the safe level of the pool water are equipped with syphon breakers, check valves, or other means to prevent inadvertent pool drainage."
ATTACHMENT 1 Evaluation of Proposed Change Page 7 of 9
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria The following NRC requirements and guidance documents are applicable to the review of the proposed changes.
10 CFR 50, Appendix A, GDC 61, "Fuel storage and handling and radioactivity control," requires that the fuel storage and handling, radioactive waste, and other systems which may contain radioactivity shall be designed to assure adequate safety under normal and postulated accident conditions. These systems shall be designed (1) with a capability to permit appropriate periodic inspection and testing of components important to safety, (2) with suitable shielding for radiation protection, (3) with appropriate containment, confinement, and filtering systems, (4) with a residual heat removal capability having reliability and testability that reflects the importance to safety of decay heat and other residual heat removal, and (5) to prevent significant reduction in fuel storage coolant inventory under accident conditions.
10 CFR 50.36, "Technical specifications," details the content and information that must be included in a station's Technical Specifications (TS). As described in 10 CFR 50.36(c)(4), "Design Features," are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
RG 1.13, "Spent Fuel Storage Facility Design Basis," Regulatory Position C.6 establishes the design criteria for drains, permanently connect ed mechanical or hydraulic systems, and other features that by maloperation or failure could cause loss of coolant that would uncover fuel should not be installed or included in the design.
The proposed change does not involve any physical changes to the structures, systems, or components at CPS. The proposed change reflects current plant configuration of the spent fuel storage fuel design and assure safe operation by continuing to meet applicable regulations and requirements.
4.2 No Significant Hazards Consideration
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Facility Operating License No. NPF-62 for Clinton Power Station (CPS), Unit 1. The proposed amendment revises the design value for the spent fuel storage pool (SFP) in Technical Specifications (TS) 4.3.2, "Drainage," to the appropriate value.
ATTACHMENT 1 Evaluation of Proposed Change Page 8 of 9 According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of any accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety. EGC has evaluated the proposed change, using the criteria in 10 CFR 50.92, and has determined that the proposed change does not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration.
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
No physical changes to the facility will occur as a result of this proposed amendment. The proposed changes will not alter the physical design. The proposed change will revise the current TS 4.3.2 value for the SFP level design to be consistent with the original design basis value and the applicable regulatory requirements. The proposed value will continue to ensure that inadvertent draining of the SFP will not result in the uncovering of spent fuel, as well as provide adequate shielding for personnel protection.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident pr eviously evaluated?
Response: No.
The proposed change does not alter the physical design, safety limits, or safety analysis assumptions associated with the operation of the plant. Accordingly, the change does not introduce any new accident initiators, nor does it reduce or adversely affect the capabilities of any plant structure, system, or component to perform their safety function. The proposed change will revise the current TS 4.3.2 value for the SFP level design to be consistent with the original design basis value and the applicable regulatory requirements. The proposed value will continue to ensure that inadvertent draining of the SFP will not result in the uncovering of spent fuel, as well as provide adequate shielding for personnel protection.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
ATTACHMENT 1 Evaluation of Proposed Change Page 9 of 9
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed change conforms to NRC regulatory guidance regarding the content of plant Technical Specifications. The proposed change does not alter the physical design, safety limits, or safety analysis assumptions associated with the operation of the plant.
Therefore, the proposed change does not involve a significant reduction in a margin of
safety.
Based on the above evaluation, EGC concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92, paragraph (c), and accordingly, a finding of no significant hazards consideration is justified.
4.3 Conclusions
In conclusion, based on the considerations discussed above, (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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
EGC has evaluated the proposed amendment for environmental considerations. The review has resulted in the determination that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
ATTACHMENT 2 Proposed Technical Specifications Changes for Clinton Power Station, Unit 1
Clinton Power Station, Unit 1 Facility Operating License No. NPF-62
AFFECTED TECHNICAL SPECIFICATIONS PAGE
4.0-2 Design Features
4.0 CLINTON
4.0-2 Amendment No. 170
4.0 DESIGN
FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. k eff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.2 of the USAR;b.A nominal fuel assembly center to center storage spacing of 7 inches within rows and 12.25 inches between rows in
the low density storage racks in the upper containment
pool; andc.For the fuel storage racks supplied by Nuclear Energy Services (NES), a nominal fuel assembly spacing of 6.4375 inches in the high density storage racks in the spent fuel pool or fuel cask storage pool. For the fuel storage racks supplied by Holtec International, a nominal fuel assembly spacing of 6.243 inches in the high density storage racks in the spent fuel pool or fuel cask storage pool.4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a. k eff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in
Section 9.1.1 of the USAR; andb.A nominal fuel assembly center to center storage spacing of 7 inches within rows and 12.25 inches between rows in the new fuel storage racks.
4.3.2 Drainage
The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation
754 ft 0 inches. 4.3.3 Capacity 4.3.3.1 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3796 fuel assemblies. The fuel cask storage pool is designed and shall be maintained with a storage capacity limited to no more than 363 fuel assemblies. 4.3.3.2 No more than 160 fuel assemblies may be stored in the upper containment pool.