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Category:Letter type:RS
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-102, Supplement to 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, and TSTF-5912024-10-21021 October 2024 Supplement to 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, and TSTF-591 RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-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-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information 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-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report 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-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 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-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-080, 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-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H 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-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request 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-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-101, 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-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 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-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 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-22-049, 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 2024-07-31
[Table view] Category:Status Report
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-21-103, Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station2021-09-28028 September 2021 Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station RS-17-063, 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-16-090, Report of Full Compliance with 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)2016-08-16016 August 2016 Report of Full Compliance with 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-16-106, Fourth 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..2016-06-30030 June 2016 Fourth 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-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-16-022, Sixth 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)2016-02-26026 February 2016 Sixth 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-15-202, Fifth 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)2015-08-28028 August 2015 Fifth 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-15-148, 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 Accident..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 Accident.. RS-15-028, 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) ML15061A0892015-02-27027 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-15-019, 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-14-302, First Six-Month Status Report 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 Accident Condition2014-12-17017 December 2014 First Six-Month Status Report 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 Accident Condition RS-14-198, 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) RS-14-010, 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 Number 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 Number EA-12-049) RS-14-020, 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-13-118, 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-13-119, 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) RA-13-030, Annual Property Insurance Status Report2013-04-0101 April 2013 Annual Property Insurance Status Report RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors 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 RS-10-055, Report on Status of Decommissioning Funding for Shutdown Reactors2010-03-29029 March 2010 Report on Status of Decommissioning Funding for Shutdown Reactors 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 ML1019703412008-02-14014 February 2008 Memo to T. Hanley Dresden Station Radiological Groundwater Protection Program Status Report - 4th Quarter 2007 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 ML0229404782002-10-0303 October 2002 Revision to Unit 3 Cycle 17 Core Operating Limits Report ML0226002922002-09-17017 September 2002 Memorandum Regarding Report on the Status of Open TIAs Assigned to NRR 2024-09-18
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ExelonGenera Order No. EA-13-109 RS-15-148 June 30, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
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 Accident Conditions (Order Number EA-13-109)
References:
- 1. 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
- 2. NRC Interim Staff Guidance JLD-ISG-2015-01, "Compliance with Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 0, dated April 2015
- 3. NEI 13-02, "Industry Guidance for Compliance with NRC Order EA-13-109, BWR Mark I
& II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 1, dated April 2015
- 4. Exelon Generation Company, LLC's Answer to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 26, 2013
- 5. Exelon Generation Company, LLC 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 Accident Conditions (Order Number EA-13-109), dated June 30, 2014 (RS-14-058)
- 6. Exelon Generation Company, LLC First Six-Month Status Report 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 Accident Conditions (Order Number EA-13-109), dated December 17, 2014 (RS-14-302)
- 7. NRC letter to Exelon Generation Company, LLC, Dresden Nuclear Power Station, Units 2 and 3 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC No.
MF4462 and MF4463), dated February 11,2015
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-13-109 June 30, 2015 Page 2 On June 6, 2013, the U.S. 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 require their BWRs with Mark I and Mark II containments to take certain actions to ensure that these facilities have a hardened containment vent system (HCVS) to remove decay heat from the containment, and maintain control of containment pressure within acceptable limits following events that result in loss of active containment heat removal capability while maintaining the capability to operate under severe accident (SA) conditions resulting from an Extended Loss of AC Power (ELAP). Specific requirements are outlined in of Reference 1.
Reference 1 required submission of a Phase 1 Overall Integrated Plan pursuant to Section IV, Condition D by June 30, 2014. Reference 2 endorses industry guidance document NEI 13-02, Revision 1 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial answer to the Order regarding reliable hardened containment vents capable of operation under severe accident conditions. Reference 5 provided the Dresden Nuclear Power Station, Units 2 and 3 Phase 1 Overall Integrated Plan.
Reference 1 requires submission of a status report at six-month intervals following submittal of the Phase 1 overall integrated plan. Reference 3 provides direction regarding the content of the status reports. Reference 6 provided the first six-month status report pursuant to Section IV, Condition D.3 of Reference 1 for Dresden Station. The purpose of this letter is to provide the second six-month status report for Phase 1 pursuant to Section IV, Condition D.3, 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. The enclosed report also addresses the NRC Interim Staff Evaluation open items contained in Reference 7.
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 30th day of June 2015 Respectfully submitted, Glen T. Kaegi Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosure:
Dresden Nuclear Power Station, Units 2 and 3 Second Six-Month Status Report for Phase 1 Implementation of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-13-109 June 30, 2015 Page 3 cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station, Units 2 and 3 NRC Project Manager, NRR - Dresden Nuclear Power Station, Units 2 and 3 Mr. Charles H. Norton, NRR/JLD/PPSD/JOMB, NRC Mr. John P. Boska, NRR/JLD/JOMB, NRC Illinois Emergency Management Agency - Division of Nuclear Safety
Enclosure Dresden Nuclear Power Station, Units 2 and 3 Second Six-Month Status Report for Phase 1 Implementation of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (7 pages)
Enclosure Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of Order EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" 1 Introduction Dresden Nuclear Power Station, Units 2 and 3 (Dresden Station) developed an Overall Integrated Plan (Reference 1 in Section 8), documenting the installation of a Hardened Containment Vent System (HCVS) that provides a reliable hardened venting capability for pre-core damage and under severe accident conditions, including those involving a breach of the reactor vessel by molten core debris, in response to Reference 2. This enclosure provides an update of milestone accomplishments since submittal of the Phase 1 Overall Integrated Plan, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
2 Milestone Accomplishments The following milestone(s) have been completed since the development of the Overall Integrated Plan (Reference 1), and are current as of June 30, 2015.
- Held preliminary/conceptual design meeting
- Kickoff meeting for S&L contract for Engineering Services, December 2, 2014
- First Six-Month Update, December 30, 2014
- 50% Design Review held on May 20, 2015 and May 26, 2015
- Second Six-Month Update (complete with this submittal) 3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan (01P). It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates which are subject to change as design and implementation details are developed.
The revised milestone target completion dates do not impact the order implementation date.
Target Comments Activity Milestone Completion Status Date Phase 1 HCVS Milestone Table Submit Overall Integrated Plan June 2014 Complete Submit 6 Month Updates:
Page 1 of 7
Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of HCVS Phase 1 June 30, 2015 Target Comments Activity Milestone Completion Status Date Phase 1 HCVS Milestone Table December Update 1 Complete 2014 Complete with Update 2 June 2015 this submittal December Update 3 Not Started 2015 Update 4 June 2016 Not Started December Update 5 Not Started 2016 Update 6 June 2017 Not Started December Update 7 Not Started 2017 Modifications:
Hold preliminary/conceptual design June 2014 Complete meeting December Kickoff Meeting with S&L Complete 2014 U3 Initial Design Engineering October 2015 Started Modification Complete U3 Implementation Outage (Phase 1) October 2016 Not Started U2 Initial Design Engineering October 2016 Not Started Modification Complete Operations Procedure Changes November Not Started Developed 2016 Site Specific Maintenance Procedure November Not Started Developed 2016 November U3 Training Complete Not Started 2016 November U3 Procedure Changes Active Not Started 2016 U3 Walk Through November Demonstration/Functional Test 2016 U2 Implementation Outage October 2017 Not Started U2 Training Complete November Not Started Page 2 of 7
Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of HCVS Phase 1 June 30, 2015 Target Comments Activity Milestone Completion Status Date Phase 1 HCVS Milestone Table 2017 November U2 Procedure Changes Active Not Started 2017 U2 Walk Through November Not Started Demonstration/Functional Test 2017 Submit Completion Report May 2018 Not Started 4 Changes to Compliance Method Dresden intends to make the following changes to the compliance method for Phase 1 as documented in the Phase 1 Overall Integrated Plan (Reference 1):
- The Dresden HCVS Design is replacing references to a Secondary Containment Isolation Valve (SCIV) with a rupture disc rated for a pressure sufficient to withstand leakage through the downstream PCIV during a Design Basis Accident or LLRT.
- An Argon purge system has been chosen as the method to prevent hydrogen deflagration. The Argon purge system will be used to rupture the disc to allow anticipatory venting.
5 Need for Relief/Relaxation and Basis for the Relief/Relaxation Dresden Station expects to comply with the order implementation date; therefore, no relief/relaxation is required at this time.
6 Open Items from Overall Integrated Plan and Interim Staff Evaluation The following tables provide a summary of the open items documented in the Phase 1 Overall Integrated Plan or the Interim Staff Evaluation (ISE) and the status of each item.
Open Open Items from 01P Status Item Confirm that at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> battery coping Deleted. Closed to ISE Open Item time is available. number 1.
2 Determine actions to enable wetwell (WW) Deleted. Closed to ISE Open Item venting following a flooding around the torus. number 2.
Determine how Motive Power and/or HCVS Deleted. Closed to ISE Open Item Battery Power will be disabled during normal number 3.
operation.
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Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of HCVS Phase 1 June 30 2015 4 Confirm that the Remote Operating Station Deleted. Closed to ISE Open Item (ROS) will be in an accessible area following number 12.
a Severe Accident (SA).
5 Confirm diameter on new common HCVS Deleted. Closed to ISE Open Item Piping. number 5.
6 Confirm suppression pool heat capacity. Deleted. Closed to ISE Open Item number 6.
7 Determine the approach for combustible Deleted. Closed to ISE Open Item gases. number 7.
8 Provide procedures for HCVS Operation. Deleted. Closed to ISE Open Item number 18.
Interim Staff Evaluation (ISE) Open Items Status 1 Make available for NRC staff audit Complete. EC 391973 Rev. 0 was documentation confirming that at least 6 completed to evaluate proposed battery hours battery coping time is available, load shed to support FLEX events. The evaluation addressed both 125V and 250V battery systems. The evaluation identified that with the load shed, the 125V and 250V batteries will maintain acceptable capacity for a minimum of six (6) hours. This time supports the FLEX Strategy time line actions.
2 Make available for NRC staff audit Started.
documentation that confirms the ability to operate HCVS following flooding around the suppression pool.
3 Make available for NRC staff audit Started.
documentation of a method to disable HCVS during normal operation to provide assurances against inadvertent operation that also minimizes actions to enable HCVS operation following an ELAP.
4 Make available for NRC staff audit the Started.
seismic and tornado missile final design criteria for the HCVS stack.
5 Make available for NRC staff audit Started. Refer to the response to ISE documentation of the licensee design effort to open item 6.
confirm the diameter on the new common HCVS piping.
6 Make available for NRC staff audit analyses Started. The required 1% vent capacity demonstrating that HCVS has the capacity to at the lower of PCPL or containment vent the steam/energy equivalent of one design pressure is being verified using percent of licensed/rated thermal power RELAP which models the line size and (unless a lower value is justified), and that the routing.
suppression pool and the HCVS together are In addition, MAAP analyses are being Page 4 of 7
Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of HCVS Phase 1 June 30, 2015 able to absorb and reject decay heat, such credited to verify that venting can be that following a reactor shutdown from full delayed for at least three (3) hours, power containment pressure is restored and which supports assuming a maximum then maintained below the primary decay heat rate of 1%.
containment design pressure and the primary containment pressure limit.
7 Provide a description of the final design of the Started. Argon purge system design in HCVS to address hydrogen detonation and progress.
deflagration.
8 Make available for NRC staff audit Started.
documentation of a determination of seismic adequacy for the ROS location.
9 Make available for NRC staff audit Not Started.
documentation that demonstrates adequate communication between the remote HCVS operation locations and HCVS decision makers during ELAP and severe accident conditions.
10 Provide a description of the strategies for Started. As described in the 01P, the hydrogen control that minimizes the potential HCVS torus vent path in each Dresden for hydrogen gas migration and ingress into unit, starting at and including the the reactor building or other buildings. downstream PCIV, will be a dedicated HCVS flow path. There are no interconnected systems downstream of the downstream, dedicated HCVS PCIV.
Interconnected systems are upstream of the downstream HCVS PCIV and are isolated by normally shut, fail shut PCIVs which, if open, would shut on an ELAP.
There is no shared HCVS piping between the two units.
The vent path will rely on an Argon purge system to prevent line failure due to hydrogen deflagration and detonation.
11 Provide descriptions of design details that Started. Refer to the response to ISE minimize unintended cross flow of vented item 10. This eliminates the possibility of fluids within a unit and between units on the cross flow of vented fluids within a unit site. and between the two units.
12 Make available for NRC staff audit an Started. Component location design in evaluation of temperature and radiological progress. The HCVS primary control conditions to ensure that operating personnel panel will be located in the Main Control can safely access and operate controls and Room (MCR).
support equipment.
13 Make available for NRC staff audit the final Started.
sizing evaluation for HCVS batteries/battery charger including incorporation into FLEX DG loading calculation.
14 Make available for NRC staff audit Started. Nitrogen system design in documentation of the HCVS nitrogen Page 5 of 7
Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of HCVS Phase 1 June 30, 2015 pneumatic system design including sizing and progress.
location.
15 Make available for NRC staff audit Started. Instrument design in progress.
descriptions of all instrumentation and controls (existing and planned) necessary to implement this order including qualification methods.
16 Make available for NRC staff audit the Started. Component location design in descriptions of local conditions (temperature, progress. The HCVS primary control radiation and humidity) anticipated during panel will be located in the MCR.
ELAP and severe accident for the components (valves, instrumentation, sensors, transmitters, indicators, electronics, control devices, etc.) required for HCVS venting including confirmation that the components are capable of performing their functions during ELAP and severe accident conditions.
17 Make available for NRC staff audit Started. The existing containment documentation of an evaluation verifying the isolation valves are being evaluated for existing containment isolation valves, relied their performance under wetwell venting upon for the HCVS, will open under the conditions.
maximum expected differential pressure during BDBEE and severe accident wetwell venting.
18 Make available for NRC staff audit Not Started.
procedures for HCVS operation.
7 Interim Staff Evaluation Impacts There are currently no impacts to the Interim Staff Evaluation identified at this time.
8 References The following references support the updates to the Phase 1 Overall Integrated Plan described in this enclosure.
- 1. Dresden Nuclear Power Station, Units 2 and 3, 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 Conditions (Order Number EA-13-109), dated June 30, 2014 RS-14-058.
- 2. NRC Order Number EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" dated June 6,2013.
- 3. NEI 13-02 [Rev. 1], "Industry Guidance for Compliance with NRC Order EA-13-109, BWR Mark I & II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" dated April 2015.
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Dresden Nuclear Power Station, Units 2 and 3 Second Six Month Status Report for the Implementation of HCVS Phase 1 June 30, 2015
- 4. NRC Interim Staff Guidance JLD-ISG- 2015-01 [Rev. 0], "Compliance with Order EA 109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions", dated April 2015 (Accession No. ML15104A118).
- 5. NRC Endorsement of Industry "Hardened Containment Venting System (HCVS) Phase 1, Overall Integrated Plan Template (EA-13-109) Rev. 0," dated May 14, 2014 (Accession No. ML14128A219).
- 6. NRC letter to Exelon Generation Company, LLC, Dresden Nuclear Power Station, Units 2 and 3 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC No. MF4462 and MF4463), dated February 11,2015 Page 7 of 7