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Category:Letter type:RS
MONTHYEARRS-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-24-063, 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-24-061, 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-24-056, 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-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-23-078, 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-23-077, 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-23-042, 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel 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-22-101, 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 RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval 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-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-21-009, Proposed Relief Request Associated with Code Case N-9212022-01-18018 January 2022 Proposed Relief Request Associated with Code Case N-921 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-114, Request for Exemption from 10 CFR 2.109(b)2021-10-28028 October 2021 Request for Exemption from 10 CFR 2.109(b) 2024-07-31
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-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 ML24129A1352024-05-0808 May 2024 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-59 ML24108A0102024-04-30030 April 2024 Subsequent License Renewal Application RS-24-029, Subsequent Operating License Renewal - Appendix E - Applicants Environmental Report2024-02-29029 February 2024 Subsequent Operating License Renewal - Appendix E - Applicants Environmental Report 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-22-092, 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel 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-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-021, License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition2021-03-17017 March 2021 License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-21-016, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2021-01-29029 January 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20323A2542020-11-18018 November 2020 Markup of Proposed Technical Specifications Bases Pages RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-132, License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2020-10-29029 October 2020 License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-20-116, License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process RS-20-025, Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2020-02-24024 February 2020 Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-19-093, Secondary Containment Drawdown Analysis2019-10-17017 October 2019 Secondary Containment Drawdown Analysis RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-06-18018 June 2019 Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-12-0505 December 2018 Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-18-032, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2018-04-25025 April 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML18053A1832018-01-31031 January 2018 Enclosure 4 - Dresden Units 1, 2 & 3 - Evaluation of Proposed Changes RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1732018-01-31031 January 2018 Attachment 4A - Dresden Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1742018-01-31031 January 2018 Attachment 4B - Dresden Clean Emergency Plan EP-AA-1000 Pages RS-17-174, Additional Supplement to Dresden Nuclear Power Station, Units 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-12-21021 December 2017 Additional Supplement to Dresden Nuclear Power Station, Units 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-17-173, Supplement to Dresden Nuclear Power Station, Units 2 and 3 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-12-20020 December 2017 Supplement to Dresden Nuclear Power Station, Units 2 and 3 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements RS-17-060, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-0303 May 2017 Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-02-10010 February 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-09-28028 September 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-105, Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2016-04-26026 April 2016 Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings 2024-05-08
[Table view] Category:Report
MONTHYEARNMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 ML22047A1322022-02-15015 February 2022 Owner'S Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities RS-21-086, Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2021-08-23023 August 2021 Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20300A2352020-11-17017 November 2020 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting RS-20-070, Defueled Safety Analysis Report Update, Revision 102020-06-22022 June 2020 Defueled Safety Analysis Report Update, Revision 10 RS-19-093, Secondary Containment Drawdown Analysis2019-10-17017 October 2019 Secondary Containment Drawdown Analysis ML18138A3852019-03-0606 March 2019 Staff Assessment of Flood Hazard Integrated Assessment (CAC Nos. MG0221 and MG0222; EPID L-2017-JLD-0050) SVPLTR 19-0005, Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities2019-02-0808 February 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities RS-18-077, Defueled Safety Analysis Report Update, Revision 92018-06-20020 June 2018 Defueled Safety Analysis Report Update, Revision 9 ML18082A0812018-03-13013 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-conformances Identified in Response to Regulatory Issues Summary 2015-06, Tornado Missile... RS-18-003, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-01-12012 January 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML18052A4862017-02-12012 February 2017 Owner'S Activity Report Submittal; Fifth 10-Year Interval 2017 Refueling Outage Activities ML16291A0212016-11-0808 November 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 RS-16-124, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML16190A1162016-07-0606 July 2016 2015 Regulatory Commitment Change Summary Report RS-16-100, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation2016-04-0808 April 2016 Submittal of Post Accident Monitoring Report Instrumentation ML15307A0562015-11-0404 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanisms Reevaluation RS-15-265, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15251A3842015-08-31031 August 2015 Attachment 9 - NP-3305NP, Revision 1, Mechanical Design Report for Quad Cities and Dresden Atrium 10XN Fuel Assemblies - Licensing Report. (Non-Proprietary) ML15215A3372015-07-30030 July 2015 Holtec International Report No. HI-2146153, Revision 2, Licensing Report for the Criticality Analysis of the Dresden Unit 2 and 3 SEP for Atrium 10XM Fuel Design ML15097A5192015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Relating to Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi ML15007A4912015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) SVPLTR 15-0014, Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities2015-02-11011 February 2015 Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities RS-14-310, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality2014-12-30030 December 2014 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 RS-14-208, 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) ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14115A2692014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident RS-14-122, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reevaluation Report - Redacted2014-05-19019 May 2014 Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reevaluation Report - Redacted ML14153A0062014-04-29029 April 2014 Revision 4 to Local Intense Precipitation Evaluation Report RS-14-067, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of The..2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of The.. SVPLTR 14-0013, Owner'S Activity Report Submittal Fifth 10-Year Interval 2013 Refueling Outage Activities2014-02-28028 February 2014 Owner'S Activity Report Submittal Fifth 10-Year Interval 2013 Refueling Outage Activities RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. ML13220A2382013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A8292013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Dresden Nuclear Power Station Units 2 and 3, TAC Nos.: MF1046 and MF1047 ML13126A1792013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 1 of 13 ML13126A1802013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 13 of 13 ML13126A1812013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 2 of 13 ML13126A1832013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 3 of 13 ML13126A1842013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 4 of 13 ML13126A1852013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 5 of 13 ML13126A1862013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 6 of 13 ML13126A1872013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 7 of 13 ML13126A1882013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 8 of 13 ML13126A1892013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 9 of 13 ML13126A1902013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 10 of 13 2022-06-30
[Table view] Category:Technical
MONTHYEARNMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-21-086, Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2021-08-23023 August 2021 Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20300A2352020-11-17017 November 2020 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident RS-20-070, Defueled Safety Analysis Report Update, Revision 102020-06-22022 June 2020 Defueled Safety Analysis Report Update, Revision 10 RS-19-093, Secondary Containment Drawdown Analysis2019-10-17017 October 2019 Secondary Containment Drawdown Analysis RS-18-077, Defueled Safety Analysis Report Update, Revision 92018-06-20020 June 2018 Defueled Safety Analysis Report Update, Revision 9 RS-18-003, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-01-12012 January 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML15251A3842015-08-31031 August 2015 Attachment 9 - NP-3305NP, Revision 1, Mechanical Design Report for Quad Cities and Dresden Atrium 10XN Fuel Assemblies - Licensing Report. (Non-Proprietary) ML15215A3372015-07-30030 July 2015 Holtec International Report No. HI-2146153, Revision 2, Licensing Report for the Criticality Analysis of the Dresden Unit 2 and 3 SEP for Atrium 10XM Fuel Design RS-14-310, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality2014-12-30030 December 2014 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14115A2692014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. ML13220A2382013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A8292013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Dresden Nuclear Power Station Units 2 and 3, TAC Nos.: MF1046 and MF1047 ML13126A1852013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 5 of 13 ML13126A1842013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 4 of 13 ML13126A1832013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 3 of 13 ML13126A1812013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 2 of 13 ML13126A1862013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 6 of 13 ML13126A1802013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 13 of 13 ML13126A1792013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 1 of 13 ML13126A1882013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 8 of 13 ML13126A1872013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 7 of 13 ML13126A1902013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 10 of 13 ML13126A1892013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 9 of 13 ML12306A3932012-11-0101 November 2012 Request for a Written Response to NRC Observations and Concerns Regarding Dresden Station Response Plan for External Flooding Events RS-09-165, Request for Approval of Updated Pipe Flaw Evaluation Report2009-12-0707 December 2009 Request for Approval of Updated Pipe Flaw Evaluation Report ML0908404302009-03-0505 March 2009 Medical Services (MS-1) Drill Report ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 RS-07-097, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit2007-07-10010 July 2007 Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit ML0715705102007-04-0505 April 2007 CC-AA-309-1001, Rev 3, Attachment 1, Design Analysis Major Revision Cover Sheet, 9389-46-19-3, Rev 004, Diesel Generator 2/3 Loading Under Design Bases Accident Condition. ML0715705012007-04-0505 April 2007 CC-AA-309-1001, Rev 3, Attachment 1, Design Analysis Major Revision Cover Sheet, 9389-46-19-1, Rev 003 Diesel Generator 3 Loading Under Design Bases Accident Condition ML0715705052007-04-0404 April 2007 CC-AA-309-1001, Rev 1, Attachment 1, Design Analysis Major Revision Cover Sheet, 989-46-19-2, Rev 003, Calculation for Diesel Generator 2 Loading Under Design Bases Accident Condition ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier ML0621300322006-05-31031 May 2006 GE-NE-0000-0053-8435-R1-NP, Rev 1, Dresden 2 & 3 and Quad Cities 1 & 2, Safety Valve Setpoint Tolerance Relaxation, May 2006 ML0606203682006-01-26026 January 2006 Attachment 3 (Technical Specifications) and 4 (Affidavit and Non-Proprietary Version of Attachment 2 to Exelon Letter Dated January 26, 2006) ML1024201462005-12-0707 December 2005 Groundwater Tritium Investigation Report, Dresden Generating Station, Project Number EXENW-18513-400 RS-05-064, Commitments and Plans Related to Extended Power Uprate Operation2005-05-13013 May 2005 Commitments and Plans Related to Extended Power Uprate Operation ML0514400842005-05-0505 May 2005 Enclosure 1, Attachment 2, 26A6266AB, Revision 4, Steam Dryer, GE Nuclear Energy, Design Specification Data Sheet, Dated May 5, 2005 ML0513601002005-04-30030 April 2005 Enclosure 2, Attachment 2, Replacement Steam Dryer Reactor Vessel Bracket Stress Report for Quad Cities 1, 2, and Dresden 2,3, GE-NE-0000-0034-4803-02, Non-Proprietary, Dated April 2005 ML0513300532005-04-25025 April 2005 Enclosure 3, Dresden Strain Gage Uncertainty Evaluation, SIA File No.: EXLN-17Q-301, Revision 0, Dated April 25,2005 ML0514400812005-04-24024 April 2005 Enclosure 1, Attachment 1, 26A6266, Rev 3, Steam Dryer, GE Nuclear Energy, Design Specification, April 24, 2005 RS-05-042, Additional Information Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-04-0606 April 2005 Additional Information Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations ML0507303262005-03-31031 March 2005 Non-Proprietary Dresden and Quad Cities Neutron Flux Evaluation ML0510902702005-01-31031 January 2005 Attachment 2, CDI Report No. 05-01, Rev 0, Revised Hydrodynamic Loads on Quad Cities Unit 2 Steam Dryer to 200 Hz, with Comparison to Dresden Units 2 & 3 Loads. RS-05-005, Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews2005-01-0505 January 2005 Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews 2022-06-30
[Table view] Category:Technical Specification
MONTHYEARML24129A1352024-05-0808 May 2024 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-59 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-22-092, 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 ML21179A0502021-06-21021 June 2021 Technical Specification Bases RS-21-036, Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2021-03-16016 March 2021 Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20323A2542020-11-18018 November 2020 Markup of Proposed Technical Specifications Bases Pages JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-06-18018 June 2019 Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-12-0505 December 2018 Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits ML17180A1262017-06-21021 June 2017 Technical Specification Bases - Affected Page List RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List2017-06-21021 June 2017 Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-09-28028 September 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-15-297, Request for License Amendment to Dresden Nuclear Power Station Technical Specification 3.8.1, AC Sources - Operating.2015-12-14014 December 2015 Request for License Amendment to Dresden Nuclear Power Station Technical Specification 3.8.1, AC Sources - Operating. RS-14-322, License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of.2014-12-22022 December 2014 License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of. RS-14-192, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process RS-12-036, License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr).2012-04-0303 April 2012 License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr). RS-11-100, Updated Final Safety Analysis Report (Ufsar), Revision 9, Affected Page List - Technical Specification Bases, Revision 542011-06-29029 June 2011 Updated Final Safety Analysis Report (Ufsar), Revision 9, Affected Page List - Technical Specification Bases, Revision 54 ML11202A2052011-06-29029 June 2011 Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases2011-06-29029 June 2011 Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases RS-10-165, Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation2010-10-0606 October 2010 Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation RS-10-028, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-03-0303 March 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. RS-10-024, Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program2010-02-16016 February 2010 Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program RS-09-152, Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System2009-11-10010 November 2009 Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System RS-09-104, Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage2009-08-28028 August 2009 Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program RS-07-066, Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function2007-08-0101 August 2007 Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function RS-07-097, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit2007-07-10010 July 2007 Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report2006-12-15015 December 2006 Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report ML0631700832006-11-0707 November 2006 Technical Specification, 2.0 Safety Limits ML0608802512006-03-17017 March 2006 Technical Specification Pages Regarding Offsite Power Instrumentation and Voltage Control ML0531301922005-10-17017 October 2005 Technical Specification Pages Pressure and Temperature Limits RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program RS-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits.2004-11-0404 November 2004 Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits. RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML0332104192003-11-26026 November 2003 Amendment, Reactor Coolant System Pressure and Temperature Limits RS-03-165, Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing2003-08-0808 August 2003 Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function2003-03-28028 March 2003 Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process RS-02-151, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)2002-08-16016 August 2002 Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High) ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2024-05-08
[Table view] Category:Amendment
MONTHYEARML24129A1352024-05-0808 May 2024 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-59 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-22-092, 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 JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-15-297, Request for License Amendment to Dresden Nuclear Power Station Technical Specification 3.8.1, AC Sources - Operating.2015-12-14014 December 2015 Request for License Amendment to Dresden Nuclear Power Station Technical Specification 3.8.1, AC Sources - Operating. RS-10-028, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-03-0303 March 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. RS-09-152, Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System2009-11-10010 November 2009 Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System RS-09-104, Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage2009-08-28028 August 2009 Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im RS-07-097, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit2007-07-10010 July 2007 Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report2006-12-15015 December 2006 Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report ML0631700832006-11-0707 November 2006 Technical Specification, 2.0 Safety Limits ML0608802512006-03-17017 March 2006 Technical Specification Pages Regarding Offsite Power Instrumentation and Voltage Control ML0531301922005-10-17017 October 2005 Technical Specification Pages Pressure and Temperature Limits RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program RS-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits.2004-11-0404 November 2004 Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits. RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML0332104192003-11-26026 November 2003 Amendment, Reactor Coolant System Pressure and Temperature Limits RS-03-165, Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing2003-08-0808 August 2003 Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function2003-03-28028 March 2003 Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2024-05-08
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10 CFR 50.90 RS-07-097 July 10, 2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-19 NRC Docket No. 50-237 Subject : Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Renewed Facility Operating License No. DPR-19 for Dresden Nuclear Power Station (DNPS), Unit 2.
The proposed change revises the values of the safety limit minimum critical power ratio (SLMCPR) in Technical Specification (TS) Section 2.1 .1, "Reactor Core SLs .' Specifically, the proposed change would require that for Unit 2, the minimum critical power ratio (MCPR) shall be >_ 1 .12 for two recirculation loop operation, or > 1 .14 for single recirculation loop operation .
This change is needed to support the next cycle of Unit 2 operation .
This request is subdivided as follows .
" Attachment 1 provides an evaluation supporting the proposed change .
" Attachment 2 contains the marked-up TS page, with the proposed change indicated .
" Attachment 3 provides a description of the SLMCPR evaluation for DNPS Unit 2 Cycle 21, as well as a summary of the Westinghouse establishment of a critical power ratio correlation for GNF GE14 fuel.
0 Attachment 4 contains an affidavit and non-proprietary version of Attachment 3.
July 10, 2007 U. S. Nuclear Regulatory Commission Page 2 The proposed change has been reviewed by the DNPS Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program .
EGC requests approval of the proposed change by November 1, 2007, to support startup following the next refueling outage for Unit 2 (i .e., D2R20), which is scheduled to start in October 2007. Once approved, the amendment will be implemented prior to startup from D2R20 . This implementation period will provide adequate time for the affected station documents to be revised using the appropriate change control mechanisms .
In accordance with 10 CFR 50.91(b), EGC is notifying the State of Illinois of this application for changes to the TS by transmitting a copy of this letter and its attachments to the designated State Official. contains information proprietary to Westinghouse Electric Company LLC, it is supported by an affidavit signed by Westinghouse, the owner of the information . The affidavit, provided in Attachment 4, sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390, "Public inspections, exemptions, requests for withholding ."
Accordingly, it is requested that the information be withheld from public disclosure in accordance with 10 CFR 2.390. A non-proprietary version of the information contained in is also provided in Attachment 4.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. John L. Schrage at (630) 657- 2821 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 10 "'
day of July 2007.
Respectfully, Patrick R . Simpson Manager - Licensing Attachments:
Attachment 1 : Evaluation of Proposed Change Attachment 2: Markup of Proposed Technical Specifications Page Attachment 3 : Dresden Unit 2 Cycle 21 SLMCPR (Proprietary)
Attachment 4: Westinghouse Application for Withholding, Affidavit, and Non-Proprietary Version of Dresden Unit 2 Cycle 21 SLMCPR
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 DESCRIPTION 2 .0 PROPOSED CHANGE 3 .0 BACKGROUND 4 .0 TECHNICAL ANALYSIS 5 .0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria
6.0 ENVIRONMENTAL CONSIDERATION
7 .0 REFERENCES Page 1 of 10
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit,"
Exelon Generation Company, LLC (EGC) requests an amendment to Renewed Facility Operating License No . DPR-19 for Dresden Nuclear Power Station (DNPS), Unit 2. The proposed change revises the values of the safety limit minimum critical power ratio (SLMCPR) in Technical Specification (TS) Section 2 .1 .1, "Reactor Core SLs ." Specifically, the proposed change would require that for Unit 2, the minimum critical power ratio (MCPR) shall be _> 1 .12 for two recirculation loop operation, or _> 1 .14 for single recirculation loop operation . This change is needed to support the next cycle of Unit 2 operation . The proposed change is described below.
2.0 PROPOSED CHANGE
TS Section 2.1 .1 .2 specifies the value for the SLMCPR . For DNPS Unit 2 and Unit 3, the current values specified are as follows.
For Unit 2 two recirculation loop operation, MCPR shall be z 1 .11, or for single recirculation loop operation, MCPR shall be z 1 .12 .
For Unit 3 two recirculation loop operation, MCPR shall be 2:1 .12, or for single recirculation loop operation, MCPR shall be ? 1 .14 .
The proposed change will revise TS Section 2.1 .1 .2 for Unit 2 to delete the Unit 2 SLMCPR specification and revise the Unit 3 SLMCPR specification to be applicable to both Unit 2 and Unit 3. The specification will read as follows :
For two recirculation loop operation, MCPR shall be > 1 .12, or for single recirculation loop operation, MCPR shall be >_ 1 .14 .
The deletion of the "Unit 3" from the specification is administrative, and does not change the current SLMCPR for DNPS Unit 3. provides the marked-up TS page indicating the proposed change.
3.0 BACKGROUND
The fuel cladding integrity SLMCPR is established to assure that at least 99.9% of the fuel rods in the core do not experience boiling transition during an anticipated operational occurrence (AOO) . To determine the explicit value for the cycle specific safety limit, a full core statistical analysis is performed . The core model incorporates the uncertainty in the measurement of core operating parameters, critical power ratio (CPR) calculation uncertainties, and the statistical uncertainty associated with the fuel vendor's correlation . The number of rods that might experience boiling transition as a function of the nominal MCPR is calculated.
The GNF NRC-approved methodology (i .e., References 1 and 2) was used previously to determine the appropriate SLMCPR values for the current DNPS Unit 2 fuel cycle (i.e.,
Cycle 20) . The Cycle 20 core contains all GNF GE14 fuel assemblies.
Page 2 of 10
ATTACHMENT 1 Evaluation of Proposed Change EGC will load Westinghouse SVEA-96 Optima2 fuel assemblies in DNPS Unit 2 for Cycle 21 with the result being a mixed core containing both GE14 and SVEA-96 Optima2 fuel assemblies. Therefore, the Westinghouse NRC-approved methodology (Reference 3) and further clarified in the EGC response to request for additional information (Reference 11) was used to determine the SLMCPR values for Cycle 21 . Unlike the GNF methodology, the Westinghouse methodology generates a unique SLMCPR value for each fuel product line present in the core. However, based on previous discussions with the NRC related to the Westinghouse methodology, EGC will apply the more conservative SVEA-96 Optima2 fuel SLMCPR to all fuel types in DNPS Unit 2 Cycle 21 rather than establishing a unique SLMCPR for the GE14 fuel .
4 .0 TECHNICAL ANALYSIS In Reference 4, the NRC issued a license amendment for DNPS that, in part, revised TS Section 5.6 .5 Core Operating Limits Report to allow Westinghouse methodologies, which have been generically approved by the NRC, to be used for core reload evaluations . The methodology used for SLMCPR evaluations is described in Reference 3, which was approved for use at DNPS as part of the Reference 4 license amendment. provides technical information to support the proposed change . A description of the SLMCPR evaluation for DNPS Unit 2 Cycle 21, as well as a summary of the Westinghouse establishment of a CPR correlation for GNF GE14 fuel, is provided in Attachment 3 . The following information is also provided to support the proposed change . This information was requested in support of a previously approved amendment for Quad Cities Nuclear Power Station (QCNPS), Unit 2 (i.e ., Reference 5).
Unit 2 _Cycle 21 Core Loa d ing Pattern The DNPS Unit 2 Cycle 21 core loading pattern was developed via a design collaboration between EGC and Westinghouse . Both Westinghouse and EGC used NRC-approved lattice physics codes and three-dimensional simulator codes to perform bundle and core design calculations, respectively . The Westinghouse core reload design group performed design calculations using the PHOENIX lattice physics code and the POLCA7 three-dimensional simulator code, while the EGC Nuclear Fuels (NF) core reload design group used the CASM04 lattice physics code and MICROBURN-B2 three-dimensional simulator code.
The core loading pattern was developed, reviewed, and approved in accordance with the EGC core reload design process and procedures. Consistent with this, NF worked with DNPS to develop and document the design goals, constraints, and requirements for the reload cycle.
Westinghouse design and manufacturing requirements were also incorporated . The Unit 2 Cycle 21 design criteria were approved by DNPS and NF management prior to the development and finalization of the core loading pattern .
Using the approved design criteria, Westinghouse and NF core reload design engineers performed numerous iterations on proposed SVEA-96 Optima2 bundle designs and core loading patterns. Designs were modeled and evaluated in both the Westinghouse POLCA7 core model and the NF MICROBURN-B2 core model . Engineers in both organizations reviewed proposed designs and collectively revised these designs until the design criteria were met .
Based on a comparison of the results from both core models to the design criteria, the core Page 3 of 10
ATTACHMENT 1 Evaluation of Proposed Change design was determined to ensure that cycle energy requirements, operating thermal margin goals, licensing requirements, and other design criteria were satisfied. In addition, the final bundle designs were reviewed to ensure that they comply with the Westinghouse SVEA-96 Optimal fuel manufacturing criteria .
Since this is the second reload of Westinghouse SVEA-96 Optimal fuel at DNPS, and the first reload at DNPS Unit 2, the DNPS Unit 2, Cycle 21 reload is considered a transition cycle . As such, there may be a relatively higher than normal uncertainty in the current prediction of the core reactivity and/or power distribution throughout the cycle . To account for this, thermal margins and cold shutdown margin were increased relative to recent DNPS cycles . In addition, in order to ensure that there will be sufficient operational flexibility, the core loading pattern was required to comply with the design thermal margin goals even if the core reactivity and operating control rod patterns are somewhat different than those that were developed based on the nominal hot core reactivity assumptions . This approach helped to ensure that the Cycle 21 core can be expected to operate at the targeted core thermal power levels with adequate thermal margins, even if the actual core reactivity and/or power distribution is somewhat different than predicted . In this way, sufficient operational flexibility and flexible control rod patterns were built into the design .
The prediction of the cycle energy capability for a given core design is dependent on the hot reactivity bias (i.e., hot target eigenvalue) that is assumed for the design cycle. This reactivity bias is also dependent on the three-dimensional core simulator code used to perform the design . Since the Unit 2 Cycle 21 core design was developed in collaboration between Westinghouse and NF using both the POLCA7 and MICROBURN-B2 core models, separate reactivity biases were established for use with each model . For POLCA7, Westinghouse used historical plant, bundle, and cycle operational data provided by NF to develop POLCA7 core models of recent DNPS cycles. Then, Westinghouse and NF reviewed the results of this POLCA7 benchmark and determined appropriate POLCA7 reactivity biases (i.e ., hot and cold target eigenvalues) for use with the Unit 2 Cycle 21 core design . In a similar manner, MICROBURN-B2 eigenvalue trends from recent DNPS cycles were reviewed to determine appropriate MICROBURN-B2 hot and cold target eigenvalues .
USAG14 Correlation The USAG14 correlation is the Westinghouse CPR correlation for GE14 fuel used in the Unit 2 Cycle 21 reload design and licensing analyses, and is the same correlation as that used to support the Reference 5 amendment for QCNPS, Unit 2 Cycle 19. As described in Reference 6, the USAG14 correlation sufficiently addresses the GNF Part 21 issue (i .e.,
Reference 7) with respect to critical power determination . The USAG14 correlation was generated based on GEXL14 CPR data that already reflected the GNF corrections to the GEXL14 CPR correlation that were made in response to the GNF Part 21 issue. Therefore, CPRs calculated with the USAG14 correlation match the values from the Part 21 corrected GEXL14 correlation (i.e., the GEXL14 correlation data revised by GNF to address the Part 21 issue) .
The USAG14 correlation was developed using the NRC-approved methodology described in Reference 3 . The USAG14 correlation, including a detailed description of the methodology used to develop the correlation, was submitted to the NRC in response to a request for additional information (i.e., response to NRC Request 8 in Attachment 2 of Reference 8) in Page 4 of 10
ATTACHMENT I Evaluation of Proposed Change support of an amendment request to allow the transition to SVEA-96 Optima2 fuel at DNPS and QCNPS . The NRC approved that amendment for DNPS and QCNPS in Reference 4.
In Attachment 7 of Reference 9, EGC submitted information to the NRC to address the measures taken to ensure compliance with the limitations and conditions discussed in the NRC's safety evaluation for CENPD-300-P-A . Attachment 7 of Reference 9 also included a description of the methodology used to derive the conservative adder to the operating limit minimum critical power ratio (OLMCPR), as required by Condition/Limitation 7 of the NRC safety evaluation for CENPD-300-P-A .
Adjustment Factor As described in Section 4 of Attachment 3, an adjustment factor is applied when using the USAG14 correlation . The adjustment factor applying to the USAG14 correlation is conservative .
The adjustment factor is specifically applied to establish the GE14 fuel OLMCPR that satisfies the 95/95 statistical criterion . A description of the process in generating USAG14 was previously provided to the NRC in response to NRC Request 8 in Attachment 2 of Reference 8.
C ore Flow Uncertainty The total core flow uncertainty values for dual-loop and single-loop operations that were applied for the Unit 2 Cycle 21 SLMCPR calculation are the same as those used in SLMCPR calculations for recent DNPS cycles . These uncertainties are consistent with values provided in General Electric (GE) Nuclear Energy topical report NEDC-32601P-A (i .e., Reference 10), in which GE updated their methodology and the inputs to be used in SLMCPR evaluations .
Reference 10 concluded that these core flow uncertainty values, which had also been previously approved for General Electric BWR Thermal Analysis Basis (GETAB) analyses, continued to be applicable and conservative . In Reference 1, the NRC approved NEDC-32601 P.
The total core flow uncertainty values are based on system performance . There is no impact on the total core flow uncertainty values as a result of the mixed core, since the GE14 and SVEA-96 Optima2 fuel are hydraulically compatible .
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Renewed Facility Operating License No. DPR-19 for Dresden Nuclear Power Station (DNPS), Unit
- 2. The proposed change revises the values of the safety limit minimum critical power ratio (SLMCPR) in Technical Specification (TS) Section 2 .1 .1, "Reactor Core SLs ."
Specifically, the proposed change would require that for Unit 2, the minimum critical power ratio (MCPR) shall be _> 1 .12 for two recirculation loop operation, or > 1 .14 for single recirculation loop operation . This change is needed to support the next cycle of Unit 2 operation .
Page 5 of 10
ATTACHMENT 1 Evaluation of Proposed Change According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not :
Involve a significant increase in the probability or consequences of an accident previously evaluated ; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated ; or Involve a significant reduction in a margin of safety.
EGC has evaluated the proposed change to the TS for DNPS, Unit 2, using the criteria in 10 CFR 50.92, and has determined that the proposed change does not involve a significant hazards consideration . The following information is provided to support a finding of no significant hazards consideration .
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The probability of an evaluated accident is derived from the probabilities of the individual precursors to that accident. The consequences of an evaluated accident are determined by the operability of plant systems designed to mitigate those consequences . Limits have been established consistent with NRC-approved methods to ensure that fuel performance during normal, transient, and accident conditions is acceptable. The proposed change conservatively establishes the SLMCPR for DNPS, Unit 2, Cycle 21 such that the fuel is protected during normal operation and during plant transients or anticipated operational occurrences (AOOs) .
Changing the SLMCPR does not increase the probability of an evaluated accident . The change does not require any physical plant modifications, physically affect any plant components, or entail changes in plant operation .
Therefore, no individual precursors of an accident are affected.
The proposed change revises the SLMCPR to protect the fuel during normal operation as well as during plant transients or AOOs. Operational limits will be established based on the proposed SLMCPR to ensure that the SLMCPR is not violated. This will ensure that the fuel design safety criterion (i.e., that at least 99.9% of the fuel rods do not experience transition boiling during normal operation and AOOs) is met . Since the proposed change does not affect operability of plant systems designed to mitigate any consequences of accidents, the consequences of an accident previously evaluated are not expected to increase .
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated .
Page 6 of 10
ATTACHMENT 1 Evaluation of Proposed Change
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response : No Creation of the possibility of a new or different kind of accident requires creating one or more new accident precursors . New accident precursors may be created by modifications of plant configuration, including changes in allowable modes of operation . The proposed change does not involve any plant configuration modifications or changes to allowable modes of operation . The proposed change to the SLMCPR assures that safety criteria are maintained for DNPS, Unit 2, Cycle 21 .
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated .
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response : No The SLMCPR provides a margin of safety by ensuring that at least 99.9% of the fuel rods do not experience transition boiling during normal operation and AOOs if the MCPR limit is not violated. The proposed change will ensure the current level of fuel protection is maintained by continuing to ensure that at least 99 .9%
of the fuel rods do not experience transition boiling during normal operation and AOOs if the MCPR limit is not violated . The proposed SLMCPR values were developed using NRC-approved methods . Additionally, operational limits will be established based on the proposed SLMCPR to ensure that the SLMCPR is not violated . This will ensure that the fuel design safety criterion (i.e., that no more than 0 .1% of the rods are expected to be in boiling transition if the MCPR limit is not violated) is met .
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based upon the above, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified .
5 .2 Applicable Regulatory Requirements/Criteria 10 CFR 50.36, "Technical specifications," paragraph (c)(1), requires that power reactor facility TS include safety limits for process variables that protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The fuel cladding integrity SLMCPR is established to assure that at least 99 .9% of the fuel rods in the core do not experience boiling transition during normal operation and AOOs. Thus, SLMCPR is required to be contained in TS .
10 CFR 50, Appendix A, General Design Criterion (GDC) 10 requires that the reactor core and associated coolant, control, and protection systems be designed with Page 7 of 10
ATTACHMENT 1 Evaluation of Proposed Change appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of AOOs. To ensure compliance with GDC 10, EGC has performed the plant-specific SLMCPR analyses using NRC-approved methodologies as prescribed in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,"
Section 4.4 . The SLMCPR ensures that sufficient conservatism exists in the operating limit MCPR such that, in the event of an AOO, there is a reasonable expectation that at least 99.9% of the fuel rods in the core will avoid boiling transition for the power distribution within the core including all uncertainties .
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
6 .0 ENVIRONMENTAL CONSIDERATION EGC has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation ." However, the proposed amendment does not involve : (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure . Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22, "Criterion for categorical exclusion ; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review,"
paragraph (c)(9) . Therefore, pursuant to 10 CFR 51 .22, paragraph (b), no environmental impact statement or environmental assessment needs be prepared in connection with the proposed amendment.
7 .0 REFERENCES
- 1. Letter from F. Akstulewicz (NRC) to G . A. Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601 P, 'Methodology and Uncertainties for Safety Limit MCPR Evaluations ;' NEDC-32694P, 'Power Distribution Uncertainties for Safety Limit MCPR Evaluation ;' and Amendment 25 to NEDE-24011-P-A on Cycle Specific Safety Limit MCPR (TAC Nos . M97490, M99069, and M97491),"dated March 11, 1999
- 2. NEDO-10958-A, "General Electric BWR Thermal Analysis Basis (GETAB) : Data, Correlation, and Design Application," dated January 1977
- 3. CENPD-300-P-A, "Reference Safety Report for Boiling Water Reactor Reload Fuel,"
dated July 1996
- 4. Letter from M. Banerjee (NRC) to C. M. Crane (Exelon Generation Company, LLC),
"Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Page 8 of 10
ATTACHMENT 1 Evaluation of Proposed Change Units 1 and 2 - Issuance of Amendments Re : Transition to Westinghouse Fuel and Minimum Critical Power Ratio Safety Limits (TAC. Nos . MC7323, MC7324, MC7325 and MC7326)," dated April 4, 2006
- 5. Letter from M. Banerjee (NRC) to C . M. Crane (Exelon Generation Company, LLC),
"Quad Cities Nuclear Power Station, Unit 2 - Issuance of Amendment Re: Minimum Critical Power Ratio Safety Limit (TAC No. MC9243)," dated March 31, 2006
- 6. Letter from P. R. Simpson (Exelon Generation Company, LLC) to NRC, "Additional Information Supporting Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit," dated February 13, 2006
- 7. Letter from J . S. Post (GE Energy) to NRC, "Part 21 60 Day Interim Report Notification :
Critical Power Determination for GE14 and GE12 Fuel With Zircaloy Spacers," dated June 24, 2005
- 8. Letter from P. R. Simpson (Exelon Generating Company, LLC) to NRC, "Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel," dated January 26, 2006
- 9. Letter from P. R. Simpson (Exelon Generation Company, LLC) to NRC, "Request for License Amendment Regarding Transition to Westinghouse Fuel," dated June 15, 2005
- 10. NEDC-32601P-A, "Methodology and Uncertainties for Safety Limit MCPR Evaluations,"
dated August 1999 11 . Letter from D.M. Benyak (Exelon Generation Company, LLC) to NRC, "Additional Information Supporting Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit," dated October 19, 2006.
Page 9 of 10
ATTACHMENT 2 Markup of Proposed Technical Specifications Page DRESDEN NUCLEAR POWER STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-19 REVISED TECHNICAL SPECIFICATIONS PAGE 2.0-1
SLs 2 .0 2 .0 SAFETY LIMITS (SLs) 2 .1 SLs 2 .1 .1 Reactor Core SLs 2 .1 .1 .1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow :
THERMAL POWER shall be _< 25% RTP .
2 .1 .1 .2 With the reactor steam dome pressure >_ 785 psig and core flow >_ 10% rated core flow :
MGR R s ha ll he ~ 1 .12 ;
For 1pit 3 two recirculation loop operation, MCPR shall be >_ 1 .12, or for single recirculation loop operation, MCPR shall be >_ 1 .14 .
2 .1 .1 .3 Reactor vessel water level shall be greater than the top of active irradiated fuel .
2 .1 .2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be < 1345 psig .
2 .2 SL Violations With any SL violation, the following actions shall be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> :
2 .2 .1 Restore compliance with all SLs ; and 2 .2 .2 Insert all insertable control rods .
Dresden 2 and 3 2 .0- 1 Amendment No . 199/180
ATTACHMENT 4 Westinghouse Application for Withholding, Affidavit, and Non-Proprietary Version of Dresden Unit 2 Cycle 21 SLMCPR
Westinghouse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Directfax: (412) 374-4011 Washington, DC 20555-0001 e-mail: greshaja@westinghouse .co m Our ref. CAW-07-2302 June 27, 2007 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
NF-BEX-07-125 P-Attachment, "Dresden Unit 2 Cycle 21 SLMCPR" (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-07-2302 signed by the owner of the proprietary information, Westinghouse Electric Company LLC . The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations .
Accordingly, this letter authorizes the utilization of the accompanying affidavit by Exelon Generation.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-07-2302 and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355 .
Very truly yours, J. A. Gresham, Manager Regulatory Compliance and Plant Licensing Enclosures cc : J. Thompson/NRR
CAW-07-21302 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA :
ss COUNTY OF ALLEGHENY :
Before me, the undersigned authority, personally appeared J. A . Gresham, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
`A A. Gresham, Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed before me this 27th day of June, 2007 Notary Public '
COMMONWEALTH OF PENNSYLVANIA Notarial Seal Sharon L Marlde, Notary Pubric MonroWlle emo, Allegheny County My Convnfsslon fires Jan . 29,2011 Member, Pennsylvania Association of Notaries
2 CAW-07-2302 I am Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2 .390 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit .
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information .
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2 .390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse .
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public . Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows :
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc .) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies .
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability .
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product .
3 CAW-07-2302 (d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers .
It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse .
It contains patentable ideas, for which patent protection may be desirable .
There are sound policy reasons behind the Westinghouse system which include the following :
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors . It is, therefore, withheld from disclosure to protect the Westinghouse competitive position .
It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information .
Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense .
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage . If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage .
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage .
The information is being transmitted to the Commission in confidence and, tinder the provisions of 10 CFR Section 2 .390, it is to be received in confidence by the Commission .
(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
CAW-07-2302 (v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in NF-BEX-07-125 P-Attachment "Dresden Unit 2 Cycle 21 SLMCPR" (Proprietary), for review and approval, being transmitted by Exelon Nuclear letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse for "Dresden Unit 2 Cycle 21 SLMCPR" for review and approval .
This information is part of that which will enable Westinghouse to:
(a) Support Exelon's use of Westinghouse Fuel at Quad City and Dresden .
(b) Assist customer to obtain license change .
Further this information has substantial commercial value as follows .
(a) Westinghouse can use this information to further enhance their licensing position with their competitors .
(b) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar analyses and licensing defense services for commercial power reactors without commensurate expenses . Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information .
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money .
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended .
Further the deponent sayeth not .
Proprietary Information Notice Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval .
In order to conform to the requirements of 10 CFR 2 .390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted) . The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information . These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(t) of the affidavit accompanying this transmittal pursuant to 10 CFR 2 .390(b)(1).
Copyright Notice The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose . Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary .
Westinghouse Non-Proprietary Class 3 NF-BEX-07-125 NP-Attachment Exelon Generation Company Dresden Unit 2 Cycle 21 SLMCPR Westinghouse Electric Company Nuclear Fuel 4350 Northern Pike Monroeville, PA 15146 2007 Westinghouse Electric Company LLC, All Rights Reserved Page t of 33
Westinghouse Non-Proprietary Class 3 1.0 Introduction This document contains a description of the Safety Limit Minimum Critical Power Ratio (SLMCPR) evaluation for Dresden 2 (DNPS2) Cycle 21, as well as identification of the Critical Power Ratio (CPR) correlation for Global Nuclear Fuel (GNF) GE 14 legacy fuel, and the "conservative Adder" required by SER restriction 7 of Reference 3 .
Dual (DLO) and single (SLO) recirculation loop SLMCPRs of 1 .1 1 and 1 .12, respectively, were established for the GE14 fuel by GNF for DNPS2 Cycle 20, Ia,c As discussed in References 13 and 14, this conservative approach was also applied for DNPS3 Cycle 20, and Quad Cities Nuclear Power Station Unit I (QCNPS 1) Cycle 20, respectively .
The GNF NRC-approved methodology (References 1 and 2) was used previously to determine the appropriate SLMCPR values for the currently operating DNPS2 Cycle 20, which contains GNF GE 14 fuel assemblies . Consistent with the GNF methodology, the resulting Cycle 20 SLMCPRs apply to all fuel assemblies in the core, such that the same SLMCPRs are applied to all the GE14 fuel assemblies .
For DNPS2 Cycle 21, Exelon Generation Company, LLC (EGC) will load Westinghouse SVEA-96 Optimal fuel. Therefore, the Westinghouse NRC-approved methodology described in Reference 3, and further clarified in the response to Request for Additional Information (RAI) D13 of Reference 4, was used to determine the SLMCPRs for Cycle 21 . Further clarification of the Westinghouse SLMCPR methodology was also provided to the NRC in support of the transition to SVEA-96 Optimal fuel in the Quad Cities and Dresden Units as follows:
The response to NRC Request 19 in Reference 9 which supported the Licensing Amendment Request for transition to SVEA-96 Optimal fuel in the Dresden and Quad Cities plants provided in Reference 8, The technical information supporting the Quad Cities 2 Technical Specification SLMCPR changes transmitted by Reference 10 as supplemented by the clarifying information in Reference 11 .
The same SLMCPR methodology described in these references was followed to establish appropriate GE 14 and SVEA-96 Optimal SLMCPRs for DNPS2 Cycle 21 . Unlike the GNF methodology, [
Ia,c NF-BEX-07-125 NP-Attachment Page 2 of 33
Ia,c The EGC proposed license amendment to use the Westinghouse methodology for core reload evaluations at the Dresden and Quad Cities units was submitted to the NRC in Reference 8.
This submittal was approved by the NRC and supported the QC2 startup with a reload core containing SVEA-96 Optimal fuel (i.e., Cycle 19). 1t also supports DNPS3 Cycle 20 and QCNPS l Cycle 20 which are both operating with reload cores containing SVEA-96 Optimal fuel and will support the operation of DNPS2 Cycle 21 .
Condition 7 in the NRC safety evaluation for Reference 3 requires that a conservative factor applied to the GE14 Operating Limit Minimum Critical Power Ratio (OLMCPR) be identified Ia,c in licensee applications . The value of this factor for DNPS2, Cycle 21, is [ which was also used for the QCNPS 2 Cycle 19, and DNPS3 Cycle 20, and QCNPS 1 Cycle 20 licensing analyses .
2.0 GE14 SLMCPR for DNPS2 Cycle 21 Consistent with the Westinghouse methodology described in Reference 3, the treatment of the SLMCPR in mixed cores containing non-Westinghouse fuel [
Ia,c The Cycle 20 SLMCPR was determined by GNF based on plant- and cycle-specific analyses using GNF's NRC-approved methodology and uncertainties (References I and 2) as supplemented with DNPS2-specific uncertainties . The GNF evaluation used the GEXL14 correlation for GE 14 fuel . The GNF evaluation confirmed that the DLO and SLO SLMCPRs of 1 .11 and 1 .12, respectively, in Reference 5 bounded the calculated Cycle 20 results and, therefore, continued to be appropriate for Cycle 20 . [
Ia,c NF-BEX-07-125 NP-Attachment Page 3 of 33
I a,c 3.0 SVEA-96 Optimal SLMCPR for Cycle 21 In establishing the SLMCPR for Westinghouse SVEA-96 Optimal fuel assemblies, it is assumed that [
The SVEA-96 Optimal SLMCPR for DNPS2 Cycle 21 is based on a Reference Core design (SVEA-96 Optimal bundle designs, core loading pattern and state point depletion strategy) that represents realistic current plans for the Cycle 21 loading and operation . The Reference Core loading pattern for DNPS2 Cycle 21 is shown in Figure 1 . The Reference Core design was generated via collaboration between EGC and Westinghouse based on EGC's cycle assumptions and design goals. The Reference Core was designed to meet the cycle energy requirements, to satisfy all licensing requirements, to provide adequate thermal margins and operational flexibility, and to meet other design and manufacturing criteria established by EGC and Westinghouse .
In general, the calculated SLMCPR is dominated by the flatness of the assembly CPR distribution across the core, and the flatness of the relative pin CPR distribution based on the pin-by-pin power/R-factor distribution in each bundle . Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher SLMCPR .
The calculation of the SLMCPR as a function of cycle exposure captures the interplay between the relative fuel assembly CPR and bundle relative pin-by-pin CPR distributions established from the power/R-factor distributions and allows a determination of the maximum (limiting)
SLMCPR for the entire cycle. This limiting SLMCPR is applied throughout the entire cycle.
The SVEA-96 Optimal SLMCPR for DNPS2 Cycle 21 was determined as a function of cycle exposure based on radial assembly power distributions at least as flat as the cycle exposure-dependent radial power distributions from [
a,c NF-BEX-07-125 NP-Attachment Page 4 of 33
I a,c Accordingly, the SVEA-96 Optitna2 SLMCPR for dual recirculation loop (DLO) operation was calculated at 100% power and 100% flow at 12 cycle exposures throughout the cycle to assure that the limiting SLMCPR was identified . In addition, the dual recirculation loop SLMCRs were calculated at 100% power at the minimum allowed core flow at rated power (95 .3% flow), and a maximum core flow at rated power of 108% flow to confirm that a limiting SLMCPR had been established . Figure 3 shows a current DNPS2 power-flow snap which is applicable to Cycle 21 . While, as shown in Figure 3, DNPS2 Cycle 21 is not licensed for a maximum core flow of 108%, a flow window 95 .3% to 108% of rated core flow was analyzed .
Single recirculation loop (SLO) SVEA-96 Optimal SLMCPR calculations were also performed. These SLMCPR calculations were performed at [
a,c The single loop calculations used the same procedure as the dual loop cases, except that the single loop cases applied a larger uncertainty for the core flow .
The SLMCPR results for Cycle 21 are plotted in Figure 4. As shown in Figure 4, the dual recirculation loop SLMCPR [
Ia,c Since the uncertainties at each dual recirculation loop point are the same, this behavior is due to the interplay between the assembly relative CPRs and the relative fuel rod CPRs . In general, as the fraction of assembly or fuel rod CPRs in the vicinity of the minimum assembly or fuel rod CPR increases, the number of rods with a potential for experiencing dryout increases. Therefore, a larger SLMCPR is required to assure that less than 0.1 % of the rods are in dryout.
While control rod patterns at individual state points required to maintain margins to thermal limits may perturb the trend, experience has shown that the assembly CPR distributions tend to become [
I a,c Consequently, the peak SLMCPR tends to occur when the assembly CPR and rod CPR distributions combine to place the maximum number of fuel rod CPRs close to the minimum CPR.
This behavior is shown for the DNPS2 Cycle 21 SLMCPR by the relative assembly CPR and relative fuel rod histograms shown in Figures 5 through 16 and 17 through 22, respectively . In Figures 5 through 16, assembly types DA21 and DB21 refer to the SVEA-96 Optimal assembly types loaded in Cycle 21 . Assembly type [
I a,e NF-BEX-07-125 NP-Attachment Page 5 of 33
I a,c Inspection of the DLO histograms in Figures 5 through 14 and the relative fuel rod CPR histograms in Figures 17 through 22 lead to the following observations, which explain the SLMCPR behavior in Figure 4:
Therefore, the dual recirculation loop (DLO) SLMCPR results at rated conditions in Figure 4 can be explained in terms of [
I a,c The continued adequacy of a dual recirculation loop SLMCPR of [
NF-BEX-07-125 NP-Attachment Page 6 of 33
The single recirculation loop (SLO) results calculated at [
I a,c The relative fuel rod CPRs in the SLMCPR calculations are [
I a,c NF-BEX-07-125 NP-Attachment page 7 o f 33
I a,c In addition to the strong dependence on assembly CPR and relative fuel rod CPR distributions, the SLMCPR is strongly dependent on the distribution of assembly and relative fuel pin CPRs about their mean values leading to an overall distribution of fuel rod CPRs relative to their mean values . The wider these distributions, the higher the SLMCPR must be to prevent 0.1 % of the fuel rods from experiencing boiling transition. The distributions of fuel rod CPRs relative to their mean values are determined by the uncertainties relative to the mean CPRs.
Accordingly, the uncertainties used in establishing the SVEA-96 Optima2 SLMCPR for Cycle 21 are shown in Table 2.
4.0 Westinghouse CPR Correlation for GE14 Fuel The Westinghouse CPR correlation for GE14 fuel used in the DNPS2 Cycle 21 reload design and licensing analyses is the same as that used for QCNPS 12 Cycle 19, and described in the Response to NRC Request 8 in Reference 9 . Further clarification of the correlation was provided in the response to NRC Request 2 in Reference 11 as well as in Reference 12. This correlation is also used in the reload analysis supporting DNPS3 Cycle 20 and QCNPS l, Cycle 20 operation as discussed in References 13 and 14. [
1 a,c I a,c The determination of this value was also based on EGC's plans to continue to monitor the CPR performance of GE14 fuel using the GNF GEXL14 correlation within the POWERPLEX-III online core monitoring system rather than the USAG14 correlation . This approach is consistent with Westinghouse's NRC-approved methodology per Reference 3.
5.0 References
- 1. Letter, Frank Akstulewicz (NRC) to Glen A. Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601 P, Methodology and Uncertainties for Safety Limit MCPR Evaluations ;
NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-2401 I-P-A on Cycle Specific Safety Limit MCPR," (TAC Nos . M97490, M99069, and M97491), March 1 1, 1999.
NF-BEX-o7-125 NP-Attachment Page 8 of 33
- 2. General Electric BWR Thermal Analysis Basis (GETAB) : Data, Correlation, and Design Application, NEDO-10958-A, January 1977 .
- 3. Licensing Topical Report, Reference Safety Report for Boiling Water Reactor Reload Fuel, CENPD-300-P-A, July 1996.
- 4. CENPD-389-P-A, 10x 10 SVEA Fuel Critical Power Experiments and CPR Correlations : SVEA-96+,
August 1999.
- 5. Dresden Technical Specifications, Section 2.1 .1 .2
- 6. WCAP-16081-P-A, lOx 10 SVEA Fuel Critical Power Experiments and CPR Correlation : SVEA-96 Optirna2, March 2005.
- 7. Letter, Jason S. Post (GE) to NRC, Part 21 60 Day Interim Report Notification : Critical Power Determination for GE 14 and GE 12 Fuel With Zircaloy Spacers, MFN 05-058 Rev l, June 24, 2005, and GE Energy - Nuclear, 10 CFR Part 21 Communication, 60-Day Interim Report Notification and Transfer of Information, Critical Power Determination for GE 14 and GE 12 Fuel With Zircaloy Spacers, SC05-04 Rev l, June 24, 2005.
- 8. Letter, Patrick R . Simpson (Exelon Generation Company, LLC) to NRC, Request for License Amendment Regarding Transition to Westinghouse Fuel, dated June 15, 2005.
- 9. RS-06-009, Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel, January 26, 2006.
- 10. Letter from Patrick R. Simpson, Exelon Nuclear, to U.S. NRC, "Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit", QCNPS, Unit 2, December 15, 2005 .
11 . RS-06-024, "Additional Information Supporting Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit", QCNPS, Unit 2, February 13, 2006 .
- 12. RS-06-038, "Additional Information Supporting Request for Licensing Amendment Request Regarding Transition to Westinghouse Fuel and Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit", March 3, 2006.
- 13. Letter from NRC (John Honcharik) to EXELON GENERATION COMPANY, LLC, dated November 7, 2006, Dresden Nuclear Power Station, Unit 3- Issuance of Amendment RE: Minimum Critical Power Ratio Sgfe(y Limit (TAC No. MD2706) .
- 14. Letter from NRC (Joseph Williams) to EXELON GENERATION COMPANY, LLC, dated May 3, 2007, Quad Cities Nuclear Power Station, Unit 1- Issuance of Amendment RE: Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit (TAC No. MD4008) .
NF-BEX-07-125 NP-Attachment Page 9 o1' 33
Table 1- Comparison of DNPS2 Cycle 20 and 21 Cores Description Dresden 2 Dresden 2 Cycle 20 Cycle 21 Number of Bundles in Core 724 724 Limiting Cycle Exposure Point N/A (GNF proprietary) Near EOC Cycle Exposure at Limiting Point N/A (GNF proprietary) 14.00 GWD/MTU (14205 EFPH)
Reload Fuel Type GE14 _ SVEA-96 Optima-2 Reload Batch Average Weight % Enrichment 3 .93 w/o 3.99 w/o Reload Batch Fraction (%') 34.80% 33.70cTc Batch Fraction of SVEA-96 O tima2 Fuel 0.00% 33.70dn Batch Fraction of GNF GE 14 Fuel 100.00% 66.30%
Core Average Weight % Enrichment 4 .00 w/o 3.97 w/o Licensing Analysis Safety Limit MCPR (DLO) 1 .11 for all fuel types a ,c Licensing Analysis Safety Limit MCPR (SLO) 1 .12 for all fuel types a ,c NF-BEX-07-125 NP-Attachment Page 10 of 33
Table 2 - Uncertainties used in Dresden 2 Cycle 21 SVEA-96 Optimal SLMCPR Determination NF-BEX-U7-125 NP-Attachment Page L 1 of 33
1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 9 41 43 45 47 49 51 53 55 57 59 60 20 20 20 20 19 j 19 20 20 20 2 58 20 20 20 20 19 20120 19 20 20 21 56 20 20 0 20 20 20 19 1 2 2 1 19 20 0 20 54 20 19 19 20 19 2 4 4 4 3 13 4 4 42 4 2 19 20 52 19 20 19 19 i 1 19 3 1 3 1 1 1 3 1 3 N 19 20 19 f
50 20 20 20 19 4 4 4 4 1 3 2 3 ( 3 2 3 1 4 19 20 20 20 48 20 19 19 1 1 3 1 3 2 3 2 3 1 I 1 3 2 3 2 1 1 19 19 20 46 20 19 19 4 3 1 3 1 3--2 3 t 3 1 3 1 3 2 3 3 4 19 19 20 44 20 20 1 4 1 3 1 3 2 3 1 3 Ill 3 1 3 2 1 4 1 20 20 42 20 20 19 1 4 3 1 3 2 3 2 1 2 313 2 1 2 3 3 4 1 19 20 20 D
40 20 20 20 2 19 d 2 3 2 3 2 3] 2 3 1 1 1 3 2 3 2 3 2 4 19 2 20 20 20 38 20 20 20 4 3 1 3 2 3 2 3 1 3 2 3 13 2 3 1 3 2 3 1 3 4 20 20 20 36 20 20 19 4 1 3 2 3 1 1 2 3 1 2 2 1 2 2 1 3 2 2 3 1 4 19 20 20 34 20 19 1 4 3 2 3 1 3 2 3 2 2 3 3 3 3 2 2 3 3 2 3 4 1 19 20 32 1920 9 77 0 2 3 1- 3 1 31 _ 3_ 2 3 _1 1 _ 1 3 2 11 .1_1 3 2 20 t9 30 2 3 1 3 1 3 1 3 2 3 1t1 3 2C31 3 1 3 2 20 19 28 20 19 1 4 3 2 3 1 3 2 3 2 2 3 313 3 2 2 3 2 3 1 3 2 3 4 1 19 20 26 20 20 19 4 1 3 2 3 1 1 2 3 1 2 2 1 2 2 1 3 2 1 1 3 2 3 1 4 19 20 20 24 20 20 20 4 3 1 3 2 3 2 3 113 2 3 1 3 2 3 1 3 2 3 2 3 1 3 4 20 20 20 22 20 20 20 2 19 4 2 3 2 3 2 3 2 3 1 1 1 3 2 3 2 3 2 3 2 4 19 2 20 20 20 17 20 20 20 19 1 4 3 1 3 2 3 2 1 2 3 1 3 2 1 2 3 2 3 1 3 4 1 19 20 20 18 20 20 1 4 1 3 1 3 2 3 1 3 Ill 3 1 3 2 3 1 3 1 4 1 20 20 16 20 19 19 4 3 1 3 1 3 2 3 1 3 3 1 3 2 3 1 3 1 3 4 19 19 20 14 20 19 19 1 T1 3 1 3 2 3 2 31111 1 3 232 3 2 3 1 3 1 1 19 19 20 12 20 20 20 19 4 4 4 4 1 3 2 313 2 3 1 4 4 4 4 19 20 20 20 10 19 20 19 19 i 1 19 3 1 3 1 1 1 3 1 3 19 1 1 19 19 20 19 6 20 19 19 20 19 2 4 4 4 3 1 3 4 4 4 2 19 20 19 19 20 6 20 20 20 20 20 20 19 1 2 1 2 1 19 20 20 20 20 20 20 4 20 20 20 20 19 20120 19 20 20 20 20 2 20 20 20 20 19119 20 20 20 20 Fuel T Bundle Name # Assem ID Ra Cycle First loaded 19 GE14-P10DNAB418-16GZ-t00T-145-T6-2646 80 JLJ277-JLJ356 19 20 GE14-P10DNAB389-18GZ-1007-145-T6-2650 148 JLJ101-JLJ268 19 1 GE14-P10DNAB390-16GZ-1007-145-T6-2851 140 JLU501-JLU640 20 2 GE14-P100NAB397-18GZ-t00T-145-T6-2852 112 JLU641-JLU752 20 3 12-3 .97-11G8 .00-4GZ8 .00-3G6 .G 0 188 DRA001-DRA188 21 4 O t2-4 .04-10G7 .00-2GZ7 .00-2G6 .0 0 56 DRA189-DRA244 21 Figure 1 - Dresden 2 Cycle 21 - Reference Loading Pattern NF-BEX-07-125 NP-Altachment Page 1 2 of 33
1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 60 17 16 16 16 16~ 16 16 16 16 17 58 16 17 16 16 17 161 16 17 16 16 17 16 56 17 17 16 17 16 19 19 19 200, 19 19 19 16 17 17 17 54 17 16 17 20 20117 2 1 1 1 1 2 17 20 17 16 17 52 17 17 16 19 20 19 19 1 19 1 20120 1 19 1 19 19 19 16 17 17 50 17 17 19 19 20 1 2 2 20 1 19 1 1 1 19 1 20 2 2 20 19 19 17 17 48 17 16 16 19 17 2 20 2 20 1 20 1 20120 1 20 1 20 2 2 17 19 16 16 17 46 17 17 19 20 2 1 2 20 1 20 2 20 1 1 1 20 2 20 1 20 1 2 20 19 17 17 44 18 20 20 1 20 2 20 1 20 2 20 2 17117 2 20 2 20 1 2 20 1 20 20 16 42 16 17 20 19 2 2 20 1 19 2 17 1 20 2 1 2 20 1 17 2 19 20 2 2 19 20 17 16 40 17 17 16 17 2 20 1 20 2 20 2 17 2 16110 2 17 2 20 2 1 20 2 19 17 16 17 17 38 16 16 19 2 20 1 20 2 17 2 20 1 11 1 I 1^ 17 1 20 2 17 20 1 20 1 2 19 16 16 36 16 16 19 1 19 1 20 2 20 1 17 1 20 1 20 1 20 1 20 1 17 1 2 20 1 19 1 19 16 16 34 16 17 19 1 1 19 1 20 2 202 . . . . . 17 1 20 1 . _ 1. .1_ 20 1 17 2 20 20 1 19 1 1 19 17 16 32 16_16 20 _2 20 1 17__2 1_6__1 20__1 20120 1_ 20 _1__16 2__17 20 2 _20 16 16 30 16 16 20 2 20 1 17 2 18 t 20 i=7 720 1 16 2 17 20 2 2016 1 + 16 28 16 17 19 1 19 1 20 2 20 2 17 1 20 1 1 1 20 1 17 2 20 2 1 1 19 17 16 26 16 16 19 19 1 20 2 20 1 17 1 20 1 20 1 20 1 20 1 17 1 20 2 20 1 19 1 19 16 16 24 16 16 19 2 1 20 1 20 2 17 2 20 1 17 1 I 1 17 1 20 2 17 2 20 1 20 1 U21 16 16 22 17 17 16 17 19 2 20 1 20 2 20 2 17 2 16116 2 17n 20 2 20 1 20 2 19 17 17 20 16 17 20 19 2 2 20 1 19 2 17 1 20 2 1 2 20 1 17 2 19 1 20 2 2 19 20 17 16 18 16 20 20 1 20 2 20 1 20 2 20 2 17117 2 20 2 20 1 20 2 20 1 20 20 16 16 17 17 19 20 2 1 002 2 2 1 2 20 19 17 17 14 17 16 16 19 17 2 20 2 20 20 20 1 20 10 20 10 20 21 20 2 17 19 16 16 17 12 17 17 19 19 20 1 2 2 20 1 19 1 1 1 19 1 20 2 2 1 20 19 19 17 17 10 17 17 16 19 20 19 19 1 19 1 20 1 20 1 19 1 19 19 20 19 16 17 17 8 17 16 17 20 20 17 2 1 1 2 1 2 1 1 2 17 20 20 17 16 17 6 17 17 16 t7 16 19 19 19 20 1 20 19 19 19 16 17 16 17 17 4 16 17 16 16 17 161 16 17 16 16 17 16 2 17 16 16 16 16116 16 16 16 17 Fuel T e Bundle Name A Assem ID Ran C cle First Loaded 16 E14-PIOHNA8411-4G7 .0J9G6,0-t00T-145-T6-2484 104 JLA161-JLA280 18 17 E14-P10HNA8408-16GZ-1007-145-T6-2483 120 JLA001-JLA160 16 19 GE14PlOONA8418-16GZ-10OT-145-T6-2646 80 JLJ277-JLJ356 19 20 E14-P10DNAB389-18GZ-t00T-145-T6-2650 168 JLJ101ALJ268 19 1 GE14-P10DNA6390-1662-1007-145-176-2851 140 JLU501-JLU640 20 2 GE14-P10DNAB397-18GZ-1007-145-T6-2852 112 JLU641-JLU752 20 Figure 2 - Dresden 2 Cycle 20 - Reference Loading Pattern NF-BEX-(77-125 NP-Attachment Page 1 3 of 33
100% LFU Po~,er = 2957 NMh 100% Gyre F1czv = 98 .0 t81b/hr D
A: 50 .4 % P / 31 .0 % F B: 58 .0 % P / 40 .0 °s F C: 100 .0 % P / 95 .3 $ F IVHd.LA L~Ta f3Cxntiy D: 100 .0 % P / 100 .0 % F 17 .2 P / 100 .0 % F F: 17 .2 % P / 33 .7 % F G t3-G: 85 .4 's P / 88 .3 % F la Ert Rated T)exml PDw-r (100% Rcz--r = 2527 W,,)
Laid Line L \ 100°IvCRTP y
[grad Line,-
l00°I~LF'U "L1 lrntitire y
y 04o 70"/c (RIP fr a Lad lire T,v)Rinp Nbritn.unRurvSpaed Nitnl (judaicn E
10 C hvitadm Irtakck Line 0 t0 20 30 4) 50 (D 70 80 9) Im 110 Ch1e Flow (%)
Figure 3 - DNPS Power Flow Map (Nominal Feedwater Temperature)
NF-BEX-07-125 NP-Attachment Page 1 4 of 33
Figure 4 - Dresden 2 Cycle 21 SLMCPR Results for SVEA-96 Optima2 Fuel NF-BEX-07-125 NP-Attachment Page 1 5 of 33
Figure 5 - Assembly Histograms NF-BEX-07-125 NP-Attachment Page 1 6 of 33
Figure 6 - Assembly Histograms ax NF-BEX-07-125 NP-Attachment Page 17 of 33
Figure 7 -- Assembly Histograms NF-BEX-07-(25 NP-Attachment
Figure 8 - Assembly Histograms NF-13EX-i17-135 NP-Attachment
Figure 9 - Assembly Histograms ax NF-BEX-07-125 NP-Attachment Page 20 of 33
Figure 10 - Assembly Histograms a,c NF-BEX-07-125 NP-Attachment Page 2 1 of 33
Figure L 1 - Assembly Histograms a,c NF-BEX-07-125 NP-Attachment Page 2 2 of 33
Figure 12 - Assembly Histograms NF-BEX-07-125 NP-Attachment Page 2 3 of 33
Figure 13 - Assembly Histograms ax NF-BEX-07-125 NP-Attachment Page 2 4 of 33
Figure 14 - Assembly Histograms NF-BEX-07-125 NP-Attachment
Figure 15 - Assembly Histograms a,c NF-BEX-07-125 NP-Attachment Page 2 6 of 33
Figure 16 - Assembly Histograms ax NF-BEX-07-125 NP-Attachment Page 2 7 of 33
Figure 17-Relative Fuel Rod Histograms a,c NF-BEX-07-125 NP-Attachment Page 2 8 of 33
Figure 18-Relative Fuel Rod Histograms NF-BEX-07-125 NP-Attachment
Figure 19 - Relative Fuel Rod Histograms a,c NF-BEX-07-125 NP-Attachment Page 30 of 33
Figure 20 - Relative Fuel Rod Histograms a,c NF-BEX-07-125 NP-Attachment Pa,,c 3 1 of 33
Figure 21 -Relative Fuel Rod Histograms NF-BEX-07-125 NP-Attachment
Figure 22 - Relative Fuel Rod Histograms ax Page 3 3 ot 33 NF-BEX-07-125 NP-Attachment