Letter Sequence Other |
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Results
Other: ML13317A957, ML14339A838, ML15156B134, ML15161A413, RS-13-020, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-13-025, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-13-129, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-14-203, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-14-213, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-15-024, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-15-033, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-17-022, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
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MONTHYEARRS-13-025, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-13-020, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML13134A0932013-06-0707 June 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML13176A3322013-06-25025 June 2013 NRR E-mail Capture - Order EA-12-051, Reliable Spent Fuel Pool Instrumentation - Request for Additional Information Project stage: RAI RS-13-129, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML13275A1212013-10-0909 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA -12-051, Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML13317A9572013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Quad Cities Nuclear Power Station, TAC Nos.: MF1048 and MF1049 Project stage: Other ML13220A3512013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies Project stage: Acceptance Review RS-14-213, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-14-203, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other ML14339A8382014-12-12012 December 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other RS-15-024, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-15-033, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other RS-15-088, Request for Schedule Relaxation from NRC Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Bases External Events2015-03-0404 March 2015 Request for Schedule Relaxation from NRC Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Bases External Events Project stage: Request RS-15-090, Supplemental Information - Request for Schedule Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-03-0606 March 2015 Supplemental Information - Request for Schedule Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Supplement ML15068A2062015-03-11011 March 2015 Relaxation of Certain Schedule Requirements for Order EA-12-049 Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events Project stage: Approval ML15161A4132015-06-11011 June 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML15156B1342015-06-25025 June 2015 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other RS-17-022, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2017-02-28028 February 2017 Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other 2014-12-12
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Category:Letter type:RS
MONTHYEARRS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval 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-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges 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-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023 Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program 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-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair 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-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022 Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage 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-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022 Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times 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-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station2022-05-25025 May 2022 Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022 CFR50.46 Annual Report RS-22-056, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-054, Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval2022-04-13013 April 2022 Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval 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-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel 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-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval 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 2024-01-03
[Table view] Category:Status Report
MONTHYEARML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III ML21091A0362021-03-30030 March 2021 Midamerican Energy Company, Decommissioning Funding Status Report Pursuant to 10 CFR 50.75(f)(1), Including ISFSI Decommissioning Funding (10 CFR 72.30) RS-18-011, Tenth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events ...2018-02-28028 February 2018 Tenth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events ... RS-17-156, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe.2017-12-11011 December 2017 Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe. RS-17-097, Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2017-08-28028 August 2017 Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) RS-17-069, Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe..2017-06-27027 June 2017 Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe.. RS-17-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-30030 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-16-046, Annual Property Insurance Status Report2017-03-29029 March 2017 Annual Property Insurance Status Report RS-17-022, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2017-02-28028 February 2017 Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events RS-17-008, Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident.2017-01-26026 January 2017 Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident. RS-16-150, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-08-26026 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-110, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2016-06-30030 June 2016 Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions RS-16-094, Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isl2016-04-25025 April 2016 Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isla RS-15-215, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order.2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order. RS-15-152, Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe..2015-06-30030 June 2015 Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe.. RS-15-024, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-15-033, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-14-213, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-14-025, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)2014-02-28028 February 2014 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) RS-14-015, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order No. EA-12-049)2014-02-28028 February 2014 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order No. EA-12-049) RS-13-128, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-13-129, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors RA-13-030, Annual Property Insurance Status Report2013-04-0101 April 2013 Annual Property Insurance Status Report ML13091A0112013-03-27027 March 2013 Midamerican Energy Company'S Decommissioning Funding Status Report for Their Twenty-Five Percent Share of Quad Cities, Units 1 and 2, Pursuant to 10 CFR 50.75(f)(1) RA-12-032, Annual Property Insurance Status Report2012-03-30030 March 2012 Annual Property Insurance Status Report ML1009200492010-04-0101 April 2010 Annual Property Insurance Status Report ML0909202562009-04-0101 April 2009 Annual Property Insurance Status Report RS-09-041, Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC2009-03-31031 March 2009 Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC ML0709305562007-03-30030 March 2007 Submittal of Midamerican Energy Company'S 2006 Decommissioning Funding Status Report Pursuant to 10 CFR 50.75(f)(1) ML0509101242005-03-30030 March 2005 Decommissioning Funding Status Report Pursuant to 10 CFR 50.75(f)(1) ML0508703272005-03-25025 March 2005 Annual Property Insurance Status Report RS-05-035, Report on Status of Decommissioning Funding for Reactors2005-03-24024 March 2005 Report on Status of Decommissioning Funding for Reactors ML0226002922002-09-17017 September 2002 Memorandum Regarding Report on the Status of Open TIAs Assigned to NRR 2023-02-15
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1 Exelon Generation ~
Order No. EA-12-049 RS-13-129 August 28, 2013 u.s. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for 8eyond-Design-8asis External Events (Order Number EA-12-049)
References:
- 1. NRC Order Number EA-12-049, " Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for 8eyond-Design-8asis External Events," dated March 12,2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for 8eyond-Design-8asis External Events," Revision 0, dated August 29,2012
- 3. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,"
Revision 0, dated August 2012
- 4. Exelon Generation Company, LLC's Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for 8eyond-Design-8asis External Events (Order Number EA-12-049), dated October 25, 2012
- 5. Exelon Generation Company, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for 8eyond-Design-8asis External Events (Order Number EA-12-049), dated February 28, 2013 (RS-13-025)
- 6. NRC Order Number EA-12-050, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents," dated March 12, 2012
- 7. NRC Order Number EA-13-109, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6,2013
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28,2013 Page 2 On March 12, 2012, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Exelon Generation Company, LLC (EGC). Reference 1 was immediately effective and directs EGC to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in of Reference 1.
Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial status report regarding mitigation strategies. Reference 5 provided the Quad Cities Nuclear Power Station, Units 1 and 2 overall integrated plan.
Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. The purpose 'o f this letter is to provide the first six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The enclosed report provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.
As described in Reference 5, full implementation of NRC Order EA-12-049 required mitigation strategies is dependent upon implementation of reliable hardened containment venting capability established in accordance with NRC Order EA-12-050 (Reference 6). NRC Order EA-13-109 (Reference 7) issued by the NRC on June 6, 2013, rescinded the requirements of Order EA-12-050 and established revised schedule time lines and implementation dates for reliable hardened containment vents capable of operation under severe accident conditions.
The revised schedule and implementation timeline contained in Order EA-13-1 09 delays the ability to achieve full implementation of the mitigation strategy requirements of Order EA 049. This need for relaxation from the implementation requirements of Order EA-12-049 is described in Section 5 of the enclosed update report. The request for relaxation of the full implementation schedule requirements of Order EA-12-049 will be submitted separately.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 28th day of August 2013.
Respectfully submitted,
~ I.~~
Glen T. Kaegi Director - Licensing &;egu:or;Affairs Exelon Generation Company, LLC
u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28,2013 Page 3
Enclosure:
- 1. Quad Cities Nuclear Power Station, Units 1 and 2 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station, Units 1 and 2 NRC Project Manager, NRR - Quad Cities Nuclear Power Station, Units 1 and 2 Ms. Jessica A. Kratchman, NRR/JLD/PMB, NRC Mr. Robert J. Fretz, Jr, NRR/JLD/PMB, NRC Mr. Robert L. Dennig, NRR/DSS/SCVB, NRC Mr. Eric E. Bowman, NRRlDPRlPGCB, NRC Illinois Emergency Management Agency - Division of Nuclear Safety
Enclosure Quad Cities Nuclear Power Station, Units 1 and 2 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (9 pages)
Enclosure Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 1 Introduction Quad Cities Nuclear Power Station, Units 1 and 2 developed an Overall Integrated Plan (Reference I in Section 8), documenting the diverse and flexible strategies (FLEX), in response to Reference 2. This enclosure provides an update of milestone accomplishments since submittal of the Overall Integrated Plan, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
2 Milestone Accomplishments None.
3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.
The revised target completion dates impact the order implementation date. An explanation of the impact of these changes is provided in Section 5 of this enclosure.
Milestone Schedule Target Revised Target Milestone Completion Activity Status Completion Date Date Submit 60 Day Status Report Oct 2012 Complete Submit Overall Integrated Plan Feb 2013 Complete Contract with RRC Complete Submit 6 Month Updates:
Complete with Update I Aug 2013 this submittal Update 2 Feb 2014 Not Started Update 3 Aug 2014 Not Started Page I of9
Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Target Revised Target Milestone Completion Activity Status Completion Date Date Update 4 Feb 2015 Not Started Update 5 Aug 2015 Not Started Update 6 Feb 2016 Not Started Update 7 Aug 2016 Not Started See Section 5 of Submit Completion Report Not Started this enclosure.
Modifications Development &
Implementation:
Unit 1 Modification Development (All Feb 2014 Started April 2014 FLEX Phases)
Unit 1 Modification Implementation (All Apr 2015 Not Started FLEX Phases)
Unit 2 Modification Development (All Mar 2015 StaIted FLEX Phases)
Unit 2 Modification Implementation (All Apr 2016 Not Started FLEX Phases)
Procedures:
Create Site-Specific Procedures Apr 2015 Not Started Validate Procedures (NEI 12-06, Sect.
Apr 2015 Not Started 11.4.3)
Create Maintenance Procedures Apr 2015 Not Started Perform Staffing Analysis Nov 2014 Not Started Storage Plan and Construction Apr 2015 Started FLEX Equipment Acquisition Apr2015 Started Training Completion Apr 2015 Not Started Regional Response Center Operational Dec 2014 Started Started See Section 5 of Unit 1 FLEX Implementation Apr 2015 this enclosure.
Started See Section 5 of Unit 2 FLEX Implementation Apr 2016 this enclosure.
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Quad Cities Nuclear Power Station, Units I and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Target Revised Target Milestone Completion Activity Status Completion Date Date Started See Section 5 of Full Site FLEX Implementation Apr 2016 this enclosure.
4 Changes to Compliance Method There are no changes to the compliance method as documented in the Overall Integrated Plan (Reference 1).
5 Need for RelieflRelaxation and Basis for the RelieflRelaxation NRC Order EA-12-049 (Reference 2) requires implementation of Mitigation Strategies to include procedures, guidance, training, and acquisition, staging. or installing of equipment needed for the strategies. The Overall Integrated Plan (Reference I) provided the Quad Cities Station response to NRC Order EA-12-049. The cover letter identifies that delays in implementing the Hardened Containment Vent System as required by NRC order EA-12-050 (Reference 5) will also affect implementation of the Mitigation Strategies Order EA-12-049 actions. The Reference 1 enclosure describes the Quad Cities Station Mitigation Strategies that are based on venting the containment using the Hardened Containment Vent System. It also describes that a modification to install a Hardened Containment Vent System (HCVS) is required. Thus the Quad Cities Station NRC Order EA-12-049 response provided in Reference 1 was premised on installation and use of a Hardened Containment Vent System as required by NRC Order EA-12-050.
Upon issuance of NRC Order EA-13-1 09 (Reference 3), the NRC staff changed technical and schedule requirements applicable to the Hardened Containment Vent System and rescinded the requirements of the NRC Order EA-12-050. As a result, full compliance to the Mitigation Strategies required by NRC Order EA-12-049 and described in Reference 1 for Quad Cities Station Units 1 and 2 will not be achieved until compliance to NRC Order EA-13-109 is achieved. Therefore, relaxation from the Mitigation Strategies (FLEX) full implementation date. as specified in NRC Order 12-049,Section IV .A.2 requirements is needed. The associated request for relaxation will be submitted separately.
In summary, the Quad Cites Overall Integrated Plan for Mitigation Strategies (Reference 1) will be met as planned and scheduled, except for areas impacted by NRC Order EA-13-109 on the Hardened Containment Vent System, which will be discussed in a separate request for relaxation.
6 Open Items from Overall Integrated Plan and Draft Safety Evaluation The following tables provide a summary of the open items documented in the Overall Integrated Plan (Reference I) or the Draft Safety Evaluation (SE) (when available), and the status of each item.
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Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Overall Integrated Plan Open Item Status Reference Sequence of 1. The times to complete actions in the Events Timeline are Not Started Events (p. 4) based on operating judgment, conceptual designs, and current supporting analyses. The final timeline will be time validated once detailed designs are completed and procedures are developed, and the results will be provided in a future six-month update.
Sequence of 2. Issuance of BWROG document NEDC-33771P, "GEH Completed. Attached to Events (p. Evaluation of FLEX Implementation Guidelines," on this 6-month update 4,5) 0113112013 did not allow sufficient time to perform the (Attachment 1) analysis of the deviations between Exelon's engineering analyses and the analyses contained in the BWROG document prior to submittal of this Integrated Plan. This analysis is expected to be completed, documented on Attachment 1B, and provided to the NRC in the August 2013 six-month status update.
Sequence of 3. Additional work will be performed during detailed design Not Started Events (p. 6) development to ensure Suppression Pool temperature will support RCIC operation, in accordance with approved BWROG analysis, throughout the event.
Sequence of 4. Initial calculations were used to determine the fuel pool Not Started Events (p. 7) timelines. Formal calculations will be performed to validate this information during development of the Spent Fuel Pool Cooling strategy detailed designs, and will be provided in a future six-month update.
Multiple 5. Procedures and programs will be developed to address Not Started Sections storage structure requirements, haul path requirements, and FLEX equipment requirements relative to the external hazards applicable to Quad Cities Programmatic 6. Quad Cities Nuclear Power Station will implement an Not Started controls (p. 8) administrative program for FLEX to establish responsibilities, and testing and maintenance requirements.
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Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Overall Integrated Plan Open Item Status Reference Multiple 7. Detailed designs based on the current conceptual designs Started Sections will be developed to determine the final plan and associated mitigating strategies. Analysis will be performed to validate that the plant modifications, selected equipment, and identified mitigating strategy can satisfy the safety function requirements of NEI 12-06. Once these designs and mitigating strategies have been fully developed, Exelon will update the integrated plan for Quad Cities Nuclear Power Station during a scheduled six-month update. This update will include any changes to the initial designs as submitted in this Integrated Plan.
Maintain 8. Guidance will be provided to ensure that sufficient area is Started Core Cooling available for deployment and that haul paths remain Phase I accessible without interference from outage equipment (p.13) during refueling outages.
Maintain 9. Evaluation of the spent fuel pool area for steam and Not Started Spect Fuel condensation has not yet been performed. The results of this Pool evaluation and the vent path strategy, if needed, will be Coooling provided in a future six-month update.
Phase 1 (p.32)
Safety to. Habitability conditions will be evaluated and a strategy Started Function will be developed to maintain RCIC habitability Support (p.
42)
Safety 11. Habitability conditions will be evaluated and a strategy Not Started Function will be developed to maintain Main Control Room Support (p. habitability.
42)
Safety 12. Battery Room Ventilation: Alternate ventilation will be Not Started Function provided to address Hydrogen generation and cold weather, Support (p. as required.
43)
Safety 13. Fuel Oil Supply to Portable Equipment: A detailed fuel Not Started Function oil supply plan will be developed.
Support (p.
43)
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Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Overall Integrated Plan Open Item Status Reference 4. Provide alternate cooling to the RCIC rooms. Procedure Not Started lA, Item 20 to be developed.
(p.59)
Section Draft Safety Evaluation Open Item Status Reference N/A N/A N/A 7 Potential Draft Safety Evaluation Impacts There are no potential impacts to the Draft Safety Evaluation identified at this time.
8 References The following references support the updates to the Overall Integrated Plan described in this enclosure.
- 1. Quad Cites Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)," dated February 28, 2013.
- 2. NRC Order Number EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12,2012.
- 3. NRC Order EA-13-109, "Issuance of Order to Modify Licenses with Regard to reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013.
- 4. Proprietary NEDC-33771 P, GEH Evaluation of FLEX Implementation Guidelines, Revision I, January 2013.
- 5. NRC Order EA-12-050, "Order to Modify Licenses with Regard to Reliable Hardened Containment Vents," dated March 12, 2012.
9 Attachments I. Quad Cities Station FLEX Integrated Plan Analyses Reconciliation to NEDC-33771P, Rev. I Page 6 of9
Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 ATTACHMENT 1 Quad Cities Station FLEX Integrated Plan Analyses Reconciliation to NEDC-33771P, Rev 1 (Reference 4)
NOTE: NEDC-33771P, Rev 1, Appendices Band D (BWR/4 Mark I with RCIC (No Venting, Suction From Suppression Pool, and Venting Starting at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, Suction From CST)) are most similar to the Quad Cities Station FLEX Plan strategy for maintaining Containment Integrity. Notable differences between the input parameters used in the Quad Cities Station FLEX analyses and the NEDC-33771P, Rev 1, analyses are noted below in the Gap and Discussion column.
NEDC-Quad Cities 33771P Design Item Parameter of Interest Analyses Applied Gap and Discussion Value (Page Value Value Reference)*
Input Parameter Values 1 Core Thermal Power 17 2957 MWT N/A 2 Reactor Dome Pressure 17 1020 psia N/A Initial RPV Water Level above 3 17 533 inches N/A vessel zero MAAP model configured with Recirc pump 4 Primay system Leakage 17 38GPM N/A leakage 16 gpm/pump 5 RPV Depressurization Time 17 60 minutes N/A 6 RPV Depressurization Rate 17 80°F/hr N/A 7 RPV Maintained Pressure 17 200-250 psig N/A I Initial Containment Airspace I 8 17 82.5-150 of N/A Temperature 9 Initial Containment Pressure 17 0-1.2 psig N/A 10 Suppression Pool Level 17 14.05 ft N/A Initial Suppression Pool 11 17 92.5°F N/A Temp 12 DW Free Volume 17 158,236 ft3 N/A - ---- - -
- Actual values are contained in the Proprietary NEDC-33771P, Rev 1 (Reference 4)
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Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation o f FLEX August 28, 2013 ATIACHMENT 1 Quad Cities Station FLEX Integrated Plan Analyses Reconciliation to NEDC-3377IP, Rev 1 (Reference 4)
NOTE: NEDC-33771P, Rev 1, Appendices Band D (BWR/4 Mark I with RCIC (No Venting, Suction From Suppression Pool, and Venting Starting at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, Suction From CST)) are most similar to the Quad Cities Station FLEX Plan strategy for maintaining Containment Integrity. Notable differences between the input parameters used in the Quad Cities Station FLEX analyses and the NEDC-33771P, Rev 1, analyses are noted below in the Gap and Discussion column .
NEDC-Quad Cities 33771P Design Item Parameter of Interest Analyses Applied Gap and Discussion Value (Page Value Value Reference)*
MAAP Containment Venting starting when 13 Start of Venting 17 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> N/A pressure reaches 25 psia 14 Venting Flow Coefficient 17 K= 1.8 N/A 15 Venting Pipe Size 17 12" N/A Resultant Parameter Values Maximum Suppression Pool 34 329"F at 21.3 hrs 281"F Temperature (No venting)
Maximum WetWell The Plant (MAAP) analysis performed 34 341"F at 21.3 hrs 281"F Temperature (No venting) assumed containment failure at 120 psig.
Maximum Wetwell Pressure Therefore, the maximum containment 34 120 psia at 21.3 hrs 56psig (No venting) temperature values and pressure values are Maximum Drywell based on differing end points in both 34 328"F at 21.3 hrs 281"F analyses.
Temperature (No Venting)
Maximum Drywell Pressure 34 120 psia at 21.3 hrs 56psig (No venting) - - - -- - - --- -~-
- - - - - ----- -- - --~
- Actual values are contained in the Proprietary NEDC-33771P, Rev 1 (Reference 4)
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Quad Cities Nuclear Power Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28,2013 ATIACHMENT 1 Quad Cities Station FLEX Integrated Plan Analyses Reconciliation to NEDC-33771P, Rev 1 (Reference 4)
NOTE: NEDC-33771P, Rev 1, Appendices Band D (BWR/4 Mark I with RCiC (No Venting, Suction From Suppression Pool, and Venting Starting at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, Suction From CST)) are most similar to the Quad Cities Station FLEX Plan strategy for maintaining Containment Integrity. Notable differences between the input parameters used in the Quad Cities Station FLEX analyses and the NEDC-33771P, Rev 1, analyses are noted below in the Gap and Discussion column.
NEDC-Quad Cities 33771P Design Item Parameter of Interest Analyses Applied Gap and Discussion Value (Page Value Value Reference)*
Maximum Suppression Pool Temperature (Venting, CST 36 225°F at ~13 hrs 281°F The differences identified between the SHEX Suction) and MAAP analyses are due to the time in Maximum WetWell which containment venting was initiated.
Temperature (Venting, CST 36 242°F at > 24 hrs 281°F Analyses of the containment pressures and Suction) temperature prior to initiation of the venting Maximum Wetwell Pressure action are approximately equal. The time for 36 23.6 psia at 3.4 hrs 56psig (Venting, CST Suction) containment venting initiation in the MAAP analysis is based on pressure reaching 25 psia.
Maximum Drywell The SHEX venting was initiated at a longer Temperature (Venting, CST 36 26rF at > 24 hrs 281°F duration and higher containment pressure Suction) than MAAP (refer to NEDC-33771P, page 36).
Maximum Drywell Pressure 36 25 psia at 3.4 hrs 56psig (Venting, CST Suction) - - - - - - --------- --- - - -- --
- Actual values are contained in the Proprietary NEDC-33771P, Rev 1 (Reference 4)
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