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Category:Letter type:RS
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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 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-24-002, 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-22-067, Constellation Radiological Emergency Plan Addendum and Procedure Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum and Procedure Revision 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 Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va 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-22-013, Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval2022-02-0909 February 2022 Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval N 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 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 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 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-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release 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 CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change 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 NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments 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 NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting ML21111A0042021-04-20020 April 2021 Response to Request to Request Clinton, Unit 1, COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements RS-21-037, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 22021-03-23023 March 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 RS-20-139, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.692020-11-24024 November 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 RS-20-096, Response to Request for Additional Information Related to Relief Request I4R-07 for the Fourth Inservice Inspection Interval2020-08-13013 August 2020 Response to Request for Additional Information Related to Relief Request I4R-07 for the Fourth Inservice Inspection Interval RS-20-095, Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval2020-08-13013 August 2020 Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information RS-20-069, Additional Information Supporting Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer2020-06-29029 June 2020 Additional Information Supporting Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer RS-20-067, Response to Request for Additional Information Related to Relief Request I4R-01 for the Fourth Inservice Inspection Interval2020-05-13013 May 2020 Response to Request for Additional Information Related to Relief Request I4R-01 for the Fourth Inservice Inspection Interval RS-20-045, Response to Request for Additional Information Related to Relief Request 14R.05 for the Fourth Inservice Inspection Interval2020-04-0101 April 2020 Response to Request for Additional Information Related to Relief Request 14R.05 for the Fourth Inservice Inspection Interval RS-19-112, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-12-0505 December 2019 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-150, Transmittal of Supplemental Information for Exelon Evaluation of Preliminary White Finding2018-12-20020 December 2018 Transmittal of Supplemental Information for Exelon Evaluation of Preliminary White Finding RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-103, Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation2018-08-29029 August 2018 Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-067, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-29029 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-11-15015 November 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-17-079, Response to Request for Additional Information Regarding the Permanent Extension of Leak Rate Testing2017-06-0101 June 2017 Response to Request for Additional Information Regarding the Permanent Extension of Leak Rate Testing RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-020, Response to RAI Concerning License Amendment Request to Revise Technical Specification Section 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-03-0202 March 2017 Response to RAI Concerning License Amendment Request to Revise Technical Specification Section 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-16-121, Response to Request for Additional Information Concerning License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation in USAR2016-06-0202 June 2016 Response to Request for Additional Information Concerning License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation in USAR RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure RS-16-077, Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2016-04-14014 April 2016 Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. RS-15-278, Supplement to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time2015-10-20020 October 2015 Supplement 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-15-260, 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-15-141, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment.2015-06-24024 June 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. 2024-08-09
[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 Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va 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
4300 Winfield Warrenville. IL Exelon Generation(!; 630 657 2000 Off IC!"
RS-15-260 10 CFR 50.90 September 30, 2015 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:
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
References:
(1) Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.S.
NRC, 11 Exigent License Amendment Request for a One-Time Extension of 11 the Shutdown Service Water Division 2 Subsystem Completion Time, dated September 10, 2015 (2) Letter from Eva Brown (U.S. NRC) to Bryan C. Hanson (Exelon Generation Company, LLC), "Clinton Power Station, Unit No. 1 - Request for Additional Information Related to One-Time Extension of Completion Time for Shutdown Service Water (TAC No. MF6705) (RS-15-264), 11 dated September 25, 2015 In Reference 1, Exelon Generation Company, LLC, (EGC) requested, in accordance with 1O 11 CFR 50.90, 11 Application for amendment of license, construction permit, or early site permit, NRC approval of a proposed one-time extension of the Completion Time (CT} to restore the Division 2 Shutdown Service Water (SX) subsystem to Operable status associated with Technical Specifications (TS) Limiting Condition for Operation (LCO) 3. 7.1, 11 Division 1 and 2 Shutdown Service Water (SX) Subsystems and Ultimate Heat Sink (UHS), 11 from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days.
In Reference 2, the NRC requested that EGC provide additional information to support their review of the subject amendment request (i.e., Reference 1). The requested information is provided in Attachment 1 to this letter.
September 30, 2015 U. S. Nuclear Regulatory Commission Page 2 includes revised marked-up TS pages with the proposed changes indicated based on the additional information requested. Attachment 3 includes revised marked-up TS Bases pages with the proposed changes indicated based on the additional information provided in . The TS Bases pages are provided for information only and do not require NRC approval. A summary of the regulatory commitments associated with this letter and RS-15-246 (Reference 1) are documented in Attachment 4.
Subsequent to issuance of Reference 2, a follow-up question was provided in a call between Eva Brown (U.S. NRC) and Timothy Byam (Exelon Generation Company, LLC). This question concerned conflicting statements in Attachment 5 to Reference 1. On page 4-5 of Attachment 5 it states that the CPS PRA model for internal events received a peer review against Addendum A of the ASME/ANS PRA Standard. However, on page 4-6 of Attachment 5 it states the formal peer review was performed against Addendum B of the ASME/ANS PRA Standard. It has been determined that the statement on page 4-6 contains an editorial error and should have referred to Addendum A of the ASME/ANS PRA Standard. It has been confirmed that the formal industry peer review in October 2009 was performed against Addendum A of the ASME/ANS PRA Standard.
If you should have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2818.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 30th day of September 2015.
Patrick R. Simpson Manager - Licensing R
Exelon Generation Company, LLC Attachments:
- 1. Response to Request for Additional Information
- 2. Proposed Technical Specification Pages for Clinton Power Station
- 3. Proposed Technical Specification Bases Pages for Clinton Power Station (For Information Only)
- 4. Summary of Regulatory Commitments cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Clinton Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 1 Response to Request for Additional Information In a letter from Eva Brown (U.S. NRG) to Bryan Hanson (Exelon Generation Company, LLC),
"Clinton Power Station, Unit No. 1 - Request for Additional Information Related to One-Time 11 Extension of Completion Time for Shutdown Service Water (TAC No. MF6705) (RS-15-264),
dated September 25, 2015, the following request for additional information was provided.
NRC RA/ 1 The proposed change uses text that does not list an explicit expiration date for the proposed one-time condition. The term "outage window" does not appear to provide the necessary clarity for when entry into the condition would be allowed. The proposed construction of the Technical Specification (TS) does not provide clarity on whether or not repeated entry and exit of the condition is allowed and whether or not a cumulative limit is placed on time in the condition.
Address the explicit expiration date for the proposed one-time condition as well as a discussion of whether or not repeated condition entry would be possible and if a cumulative limit for time in the condition is not required.
EGC Response Exelon Generation Company, LLC (EGG) plans to replace the Clinton Power Station (CPS)
Division 2 Shutdown Service Water (SX) System pump during a CPS planned Division 2 SX System outage window scheduled for the week of October 26, 2015. The work is currently scheduled to begin October 26, 2015. Should weather prevent beginning the outage on October 26, the outage window will begin as soon as weather permits. As noted in Attachment 1 to the license amendment request (Reference 1), the scheduled pump replacement is anticipated to take approximately 137 hours0.00159 days <br />0.0381 hours <br />2.265212e-4 weeks <br />5.21285e-5 months <br /> with an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> contingency to account for potential weather delays. Once the pump replacement begins, the entire evolution is scheduled to be completed within 7 days. To account for p*otential weather delays the expected expiration date for the proposed one-time CT extension is defined as November 8, 2015.
Therefore, the duration of the proposed TS change is defined as October 26 - November 8, 2015. EGG has revised the proposed changes shown on the mark-up of the CPS Technical Specifications (TS) to reflect when the proposed extension would expire. The new proposed TS mark-ups and associated Bases mark-ups are provided in Attachments 2 and 3.
Because the .proposed CT extension is a one-time change, there will not be repeated entry into the Required Action associated with the proposed CT extension. When the Division 2 SX subsystem is declared to be inoperable in support of the pump replacement it will remain inoperable until the pump is replaced, tested and declared operable again. Once the Division 2 SX pump is replaced, the proposed new Condition C will no longer be applicable and Condition B will be the condition entered whenever Division 1 or 2 SX subsystem is inoperable.
NRCRA/2 The license amendment request was submitted on a risk informed basis using the guidance of RG 1.177. Sections 3.0 and 4.0 of Attachment 1 to the submittal discussed some measures related to the defense-in-depth attributes in RG 1. 177 arising from general work control processes and identification of risk-significant configurations from the risk analysis. However, the NRG staff found the following two defense-in-depth attributes from RG 1. 177 were not adequately addressed:
System redundancy, independence, and diversity are preserved commensurate with the Page 1of4
ATIACHMENT 1 Response to Request for Additional Information expected frequency, consequences of challenges to the system, and uncertainties (e.g.,
no risk outliers).
Defense against potential common cause failures is preserved, and the potential for the introduction of new common cause failure mechanisms is assessed.
Specifically, the NRG staff did not find a discussion regarding the effects of the pump replacement activities on the risk of common cause failures beyond the commitment to protect SX Divisions 1 and 3. The pump replacement activity likely involves movements of heavy loads in and around the intake structure. Describe how risks from this activity were assessed and would be controlled. Specifically, the licensee is requested to provide a description of any protections against direct impact on protected SX division components, protection against hazards such as internal flooding that could result from a load drop on piping within the intake structure, and protection against initiating events, such as loss of plant service water or internal power distribution, that could require actuation of the SX system.
EGC Response The system description provided in Section 3.0 of Attachment 1 to the license amendment request (Reference 1) states that Division 1 and 2 of the SX system are cross-tied with double isolation valves to provide added flexibility to the system. The Tier 2 discussion provided in to Reference 1, states that 11 although not credited in the PRA evaluation supporting the proposed CT extension, there is a cross-tie between the Divisions 1 and 2 SX subsystems which will be available for use if conditions warrant it. 11 There is procedural guidance provided in CPS Procedure No. 3211.01, 11 Shutdown Service Water, 11 (Reference 2) for the operators to utilize this cross-tie in the event that it is needed and available.
The SX System does not operate during normal station operation and shutdown. During normal station operation and shutdown, the Plant Service Water (WS) System supplies water to safety-related equipment through SX System piping. The SX System pumps automatically start upon receiving a signal indicating either a loss-of-coolant accident (LOCA), or a low pressure signal from the SX System header which indicates a loss-of-offsite power (LOOP). The SX System pump start then causes the isolation valves between the SX System and WS System to close.
CPS Updated Safety Analysis Report (USAR) Section 9.2.1.2.3 states that the SX System provides a reliable source of cooling water for station auxiliaries which are essential to safe shutdown of the station following a design-basis loss-of-coolant accident. The SX System consists of three divisions which correspond to the three electrical safety divisions. Any two of these divisions operating together are adequate to assure safe shutdown of the station. The three SX System divisions are separated and protected to ensure that in any of the following events sufficient equipment remains operational to safely shut down the station.
- 1. safe shutdown earthquake,
- 2. design-basis flood,
- 3. tornado,
- 4. flooding or steam release from equipment failure such as pipe or tank rupture,
- 5. pipe whip and jet forces resulting from pipe rupture, Page 2 of 4
ATTACHMENT 1 Response to Request for Additional Information
- 6. missiles resulting from equipment failure,
- 7. fire,
- 8. LOCA, and
- 9. LOOP The system is also designed so that no single-failure of a component will compromise the ability of the system to safely shut down the unit. The SX System pump cubicles and all system piping are protected from tornado generated missiles and floods. Watertight doors designed to withstand the hydrostatic head of the maximum flood level are provided for all doorways located on both the entrance walls and the internal walls of the SX System pump rooms which are below the maximum flood level.
Portions of the SX System are located in the circulating water screen house, the auxiliary building, the fuel building, the diesel generator building, the control building, and the containment. Except for the circulating water screen house, all of these buildings are Seismic Category I structures. The cubicles for the SX System pumps in the screen house are Seismic Category I. The SX System piping is routed from the pump cubicles underground beneath the floor of the screen house to the* wall of the screen house. The portion of the screen house below the floor through which the SX System piping is routed is also Seismic Category I.
Therefore, all the areas through which the SX System is routed are Seismic Category I.
The shutdown service water system equipment is the only equipment in the screen house that is required to safely shut down the reactor or to maintain it in a safe shutdown condition. The three shutdown service water pumps and strainers are in their own missile-protected cubicles.
Each cubicle has its own cooling unit which is electrically segregated from the others. Each cubicle is flood protected by bulkhead doors. No single failure of the equipment associated with one cubicle will have a detrimental effect on the rest of the system.
Replacement of the Division 2 SX pump will require the use of a crane to lift the pump assembly from the screen house. Measures will be in place to ensure that the required heavy load lift does not present the potential for damaging the protected Division 1 and 3 systems. These compensatory measures include:
- 1. Protected systems will be posted in accordance with EGC procedure OP-AA-108-117, "Protected Equipment Program, 11 (Reference 3). This procedure provides guidance for protecting equipment in order to minimize plant risk.
- 2. Access to the Division 2 SX subsystem pump room will be directly into the room and Security will ensure individuals entering room have required security access requirements. Access into the Division 2 SX subsystem pump room will not be allowed from the Division 1 or Division 3 SX subsystem pump rooms (i.e., the flood protection doors between the divisional pump rooms will remain closed to preclude potential internal flood propagation between SX divisions given a postulated load drop).
- 3. Rigging of the screen house roof plugs, Division 2 SX pump motor, and the Division 2 SX pump will all be controlled to stay within the Division 2 foot print in the screen house.
EGC will setup a pathway that lays out the Division 2 area and will utilize spotters for Page 3 of 4
ATTACHMENT 1 Response to Request for Additional Information controls. The designated load path will ensure protection against a potential for a load drop on piping within the intake structure and protection against initiating events that could require actuation of the SX system.
The movement of Division 2 SX pump, pump motor, and screen house roof plugs has been planned to ensure that the loads will not travel over the WS System or the Circulating Water System pumps. In addition, there are no Division 1 or Division 3 SX System piping or electrical components in the planned load path for removal of the Division 2 SX System pump.
In summary, based on the approved safe load path and the above compensatory measures, EGC Has taken appropriate actions to ensure protections against direct impact on protected SX division components, protection against hazards such as internal flooding that could result from a load drop on piping within the intake structure, and protection against initiating events, such as loss of plant service water or internal power distribution, that could require actuation of the SX system. The compensatory measures listed above are identified as commitments in Attachment 4.
References
- 1. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Exigent License Amendment Request for a One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time, 11 d~ted September 10, 2015
- 2. CPS Procedure No. 3211.01, "Shutdown Service Water," Revision 31d
- 3. Exelon Generation Company Procedure OP-AA-108-117, Protected Equipment Program,"
Revision A Page 4 of 4
ATTACHMENT 2 Proposed Technical Specification Pages for Clinton Power Station
Division 1 and 2 SX Subsystems and UHS 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Division 1 and 2 Shutdown Service Water (SX) Subsystems and Ultimate Heat Sink (UHS)
LCO 3.7.1 Division 1 and 2 SX subsystems and the UHS shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS water volume not A.1 Restore UHS water 90 days within limit volume to within limit.
NOTE---------- ------ - - -NOTES---- - - ---
Not applicable 1. Enter applicable replacement of Conditions and Division 2 SX pump Actions of LCO 3.8.1, during the Division 2 11 AC Sources-Operating, 11 SX system outage for diesel generator made window from October 26 inoperable by SX.
through November 8, 2015. 2. Enter icable Conditions and Required Actions of LCO 3.4.9, B. Division 1 or 2 SX "Residual Heat Removal subsystem inoperable. (RHR) Shutdown Cool Shutdown, 11 for RHR shutdown cooling subsystem made inoperable by sx.
B.l Restore SX subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.
(continued)
CLINTON 3.7 1 Amendment No. +/--&+
Division 1 and 2 SX and UHS 3.7.1 Actions (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
NOTE------- -- ------------NOTES------------
Only applicable during 1. Enter applicable replacement of Conditions and Required Division 2 SX pump Actions of LCO 3.8.1, during the Division 2 11 AC Sources-Operating, 11 SX system outage for diesel generator made window from October 26 inoperable by SX.
through November 8, 2015. 2. Enter applicable Conditions and Required Actions of LCO 3.4.9, C. Division 2 SX 11 Residual Heat Removal subsystem inoperable. (RHR} Shutdown Cooling System-Hot Shutdown, 11 for RHR shutdown cooling subsystem made inoperable by sx.
C.1 Restore Division 2 SX 7 Days subsystem to OPERABLE status.
en. Required Action and ----------NOTE---------------
associated r~m~1c LCO 3.0.4.a is not Time of Condition B or applicable when entering C not met. MODE 3.
en.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> BE. Action and BE.l Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met.
BE. 2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR Division 1 and 2 SX subsystems inoperable.
CLINTON 3.7 2 Amendment No. +/--9-!; I
Division 1 and 2 SX Subsystems and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.l Verify UHS water volume is ~ 593 acre-ft. In accordance with UHS Erosion, Sediment Monitoring, and Dredging Program SR 3.7.1.2 Verify each required SX subsystem manual, In accordance power operated, and automatic valve in the with the flow path servicing safety related systems Surveillance or components, that is not locked, sealed, Frequency or otherwise secured in position, is in the Control Program correct position.
SR 3.7.1.3 Verify each SX subsystem actuates on an In accordance actual or simulated initiation signal. with the Surveillance Frequency Control Program CLINTON 3.7-3 Amendment No. +/--9 I
ATTACHMENT 3 Proposed Technical Specification Bases Pages for Clinton Power Station (For Information Only)
Division 1 and 2 SX Subsystems and UHS B 3.7.1 BASES (continued)
ACTIONS A.1 If the UHS is inoperable (i.e., the UHS water volume is not within the limit), action must be taken to restore the inoperable UHS to OPERABLE status within 90 days. The 90 day Completion Time is reasonable considering the time required to restore the required UHS volume, the margin contained in the available heat removal capacity, and the low probability of a DBA occurring during this period.
B.1 If the Division 1 or 2 SX subsystem is inoperable, it must be restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. With the unit in this condition, the remaining OPERABLE Division 1 or 2 SX subsystem is adequate to perform the heat removal function. However, the overall reliability is reduced because a single failure in the OPERABLE Division 1 or 2 SX subsystem could result in loss of the SX function. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time was developed taking into account the redundant capabilities afforded by the OPERABLE subsystem and the low probability of a DBA occurring during this period.
Condition B is modified by a Note. The Note indicates that this Condition is not applicable during replacement of the Division 2 SX pump during the Division 2 SX system outage window from October 26 through November 8, 2015.
The Required Action is modified by two Notes indicating that the applicable Conditions of LCO 3.8.1, "AC Sources-Operating," and LCO 3.4.9, "Residual Heat Removal (RHR)
Shutdown Cooling System-Hot Shutdown," be entered and the Required Actions taken if the inoperable SX subsystem results in an inoperable DG or RHR shutdown cooling subsystem, respectively. This is in accordance with LCO 3.0.6 and ensures the proper actions are taken for these components.
C.1 During replacement of the Division 2 SX pump in the Division 2 SX system outage window from October 26 through November 8, 2015, the Division 2 SX subsystem is inoperable, and it must be restored to OPERABLE status within 7 days. This Completion Time is based upon a risk-informed assessment that concluded that the associated risk with the system in the specified configuration is acceptable.
Condition C is modified by a Note. The Note indicates that this Condition is only applicable during replacement of the Division 2 SX pump during the Division 2 system outage (continued)
CLINTON B 3.7-4 Revision No. ~
Division 1 and 2 SX Subsystems and UHS B 3.7.1 BASES ACTIONS (continued) window from October 26 through November 8, 2015.
Required Action C.l is modified by two Notes as described in Action B.1 above.
(continued)
If the Required Action and associated Completion Time of Condition B or C is not met, the plant must be brought to a condition in which the overall plant risk is minimized. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 8) and because the time spent in MODE 3 to perform the necessary repairs to restore the system to OPERABLE status will be short. However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state. The allowed Completion Time is reasonable, based on operating
, to reach the required conditions from full power conditions in an orderly manner and without challenging plant systems.
Required Action GD.1 is modified by a Note that prohibits the application of LCO 3.0.4.a. This Note clarifies the intent of the Required Action by indicating that it is not permissible under LCO 3.0.4.a to enter MODE 3 from MODE 4 with the LCO not met. While remaining in MODE 3 presents an acceptable level of it is not the intent of the Required Action to allow entry into, and continue operation in, MODE 3 from MODE 4 in accordance with LCO 3.0.4.a.
However, where allowed, a risk assessment may be performed in accordance with LCO 3.0.4.b. Consideration of the results of this risk assessment is required to determine the acceptability of entering MODE 3 from MODE 4 when this LCO is not met.
If the Required Action and associated Completion Time of Condition A or B are not met, or both Division 1 and 2 SX subsystems are , the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the CLINTON B 3.7-5 Revision No. ~ I
Division 1 and 2 SX Subsystems and UHS B 3.7.1 BASES (continued)
ACTIONS E.l and E.2 (continued) required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.1.1 REQUIREMENTS This SR verifies UHS water volume is 2 593 acre-feet (excluding sediment) . The Surveillance Frequency is in accordance with UHS Erosion, Sediment Monitoring and Dredging Program.
With regard to UHS water volume values obtained pursuant to this SR, as read from plant indication instrumentation, the specified limit is considered to be a nominal value and therefore does not require compensation for instrument indication uncertainties (Ref. 9).
SR 3.7.1.2 Verifying the correct alignment for each manual, power operated, and automatic valve in each Division 1 and 2 SX subsystem flow path provides assurance that the proper flow paths will exist for Division 1 and 2 SX subsystem operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve is also allowed to be in the nonaccident position and yet considered in the correct position, provided it can be automatically realigned to its accident position within the required time.
This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.
Isolation of the SX subsystem to components or systems does not necessarily affect the OPERABILITY of the associated SX subsystem. As such, when all SX pumps, valves, and piping are OPERABLE, but a branch connection off the main header is isolated, the associated SX subsystem needs to be evaluated to determine if it is still OPERABLE. Alternatively, it is acceptable and conservative to declare an SX subsystem inoperable when a branch connection is isolated.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
CLINTON B 3.7-6 Revision No. +/--6 I
ATTACHMENT 4 Summary of Regulatory Commitments
Summary of Regulatory Commitments The following table identifies commitments made in this document and RS-15-246. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.)
COMMITMENT TYPE COMMITMENT COMMITTED DATE ONE-TIME PROGRAM-OR 11 0UTAGE 11 ACTION MATIC (YES/NO) (YES/NO)
Implement the compensatory Upon implementation Yes No measures (items 1 through 5) of the one-time listed in Attachment 1 of RS extension of the SX 246, Section 3.0, Tier 2 train Completion Time.
Discussion Implement Compensatory Upon implementation Yes No measures (items 1 through 3) of the one-time listed in Attachment 1 of RS extension of the SX 260, Response to RAI 2 train Completion Time