Letter Sequence Acceptance Review |
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MONTHYEARML0524205202005-08-25025 August 2005 8/25/05, Dresden, Units 2 and 3, Technical Specifications, Modify the Isolation Condenser System Heat Removal Capability Surveillance Requirement (SR) by Adding a Note to the Technical Specification Section SR 3.5.3.4 Project stage: Other ML0515402102005-08-25025 August 2005 8/25/05, Dresden, Units 2 and 3, License Amendment, Modify the Isolation Condenser System Heat Removal Capability Surveillance Requirement (SR) by Adding a Note to the Technical Specification Section SR 3.5.3.4 Project stage: Acceptance Review 2005-08-25
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Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, 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 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel 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 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 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 ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 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 SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23032A3602023-03-22022 March 2023 Issuance of Amendment Nos. 279 and 272 New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20343A1372020-12-0707 December 2020 Acceptance Review Dresden, Units 2 and 3, LAR for Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML20265A2402020-10-23023 October 2020 Issuance of Amendment Nos. 272 and 265 to Increase Allowable Main Steam Isolation Valve Leakage ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19301A3392019-12-0404 December 2019 Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, the Minimum Critical Power Ration Safety Limits ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18254A3672018-10-29029 October 2018 County 1 & 2; and Quad Cities 1 & 2 - Issuance of Amendments 220, 259, 252, 231, 217, 271 and 266 to Revise Technical Specification Requirements for Inoperable Snubbers ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18137A2712018-06-29029 June 2018 Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (Cac. Nos. MF9687 and MF9688; EPID L-2017-LLA-0228) (RS-17-060) ML17272A7832018-01-0808 January 2018 Issuance of Amendments to Adopt TSTF-542 TS Changes (CAC Nos. MF9295 and MF9296; EPID L-2017-LLA-0176) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML17037D2122017-02-16016 February 2017 Issuance of Amendments to Revise Surveillance Requirement for Secondary Containment Access Doors ML16218A4852016-10-20020 October 2016 DNPS Unit Nos. 2 and 3, QCNPS Unit Nos. 1 and 2 - Issuance of LAR to Renewed Facility Operating License Nos. DPR-19, 25, 29, 30 TS Revision to Support Areva Atrium 10XM Fuel Transition ML16141A7502016-06-0707 June 2016 Correction Letter to Renewed Facility Operating License No. DPR-19 License Page ML16111A1042016-05-11011 May 2016 Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) ML15343A1262016-04-29029 April 2016 Issuance of Amendments to Amend Facility Operating License Nos. DPR-19 and DPR-25 to Revise Technical Specifications to Support Use of a New Nuclear Criticality Safety Analysis Methodology ML15324A4392015-12-17017 December 2015 Issuance of Amendments (CAC Nos. MF5471-MF5476) ML15183A3512015-08-0505 August 2015 Issuance of Amendments Concerning Adding Topical References to Technical Specifications (TAC Nos. MF3359, MF3363, MF3361, and MF3362)(RS-13-288) ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15114A1882015-06-19019 June 2015 Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training ML14295A3002015-01-29029 January 2015 Issuance of Amendments Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements ML13079A3722013-06-20020 June 2013 Issuance of Amendments Staff Qualifications Education and Experience Eligibility Requirments for Licensed Operators (ME9047) ML1118613412011-08-10010 August 2011 Issuance of License Amendments Regarding Exelon Cyber Security Plan ML1018806162010-08-16016 August 2010 Issuance of Amendments Authorizing Alternative Methods of Verifying Leakage within the Drywell ML1006105942010-04-0101 April 2010 Issuance of Amendments RCS Leakage Detection Instrumentation and Core Operating Limits Report Changes ML0925101522009-10-20020 October 2009 License Amendments, Modify the Technical Specifications to Risk-informed Requirements Regarding Selected Required Action End States as Provided in Technical Specification Task Force (TSTF) Change Traveler TSTF-423, Revision 0 2023-08-03
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23032A3602023-03-22022 March 2023 Issuance of Amendment Nos. 279 and 272 New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies ML22335A5442022-12-20020 December 2022 Authorization and Safety Evaluation for Alternative Request I6R-01, ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22298A2802022-11-29029 November 2022 Authorization and Safety Evaluation for Alternative Request I6R-02 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21267A3172021-12-13013 December 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting (6th ISI Interval) (Epids L-2021-LLR 0029, 0030) ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21076A3712021-08-17017 August 2021 Approval of Certified Fuel Handler Training and Retraining Program ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20265A2402020-10-23023 October 2020 Issuance of Amendment Nos. 272 and 265 to Increase Allowable Main Steam Isolation Valve Leakage ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20008D2762020-01-13013 January 2020 Safety Evaluation in Support of Request for Relief Associated with the Fifth Ins)Inservice Inspection Interval Relief Request I5R-04, Revision 2 ML19301A3392019-12-0404 December 2019 Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, the Minimum Critical Power Ration Safety Limits ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18254A3672018-10-29029 October 2018 County 1 & 2; and Quad Cities 1 & 2 - Issuance of Amendments 220, 259, 252, 231, 217, 271 and 266 to Revise Technical Specification Requirements for Inoperable Snubbers ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18137A2712018-06-29029 June 2018 Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (Cac. Nos. MF9687 and MF9688; EPID L-2017-LLA-0228) (RS-17-060) ML18079A3822018-04-27027 April 2018 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML18060A3242018-03-0909 March 2018 Relief Request I5R-16 Approval of Alternative to Use the Performance Demonstration Initiative Program for Weld Overlay Inspection Qualifications ML18022A6162018-01-24024 January 2018 Approval of Alternatives to the ASME Code Regarding Reactor Vessel Penetration N-11B - Relief Request 15R-11, Revision 3 (CAC No. MF9286; EPID L-2017-LLR-0004) (RS-17-014) ML17272A7832018-01-0808 January 2018 Issuance of Amendments to Adopt TSTF-542 TS Changes (CAC Nos. MF9295 and MF9296; EPID L-2017-LLA-0176) ML17121A0492017-10-30030 October 2017 Safety Evaluation by the Office of Nuclear Reactor Regulation for the Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) 2023-09-28
[Table view] |
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August 25, 2005 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS RE: ISOLATION CONDENSER SURVEILLANCE REQUIREMENTS (TAC NOS. MC5835 AND MC5836)
Dear Mr. Crane:
The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No.
215 to Facility Operating License No. DPR-19 and Amendment No. 207 to Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3. The amendments are in response to your application dated January 21, 2005.
The amendments modify the Isolation Condenser System heat removal capability surveillance requirement (SR) by adding a note to the technical specification Section SR 3.5.3.4. This note allows a delay of 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after adequate reactor power is achieved to perform the test.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Maitri Banerjee, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249
Enclosures:
- 1. Amendment No. 215 to DPR-19
- 2. Amendment No. 207 to DPR-25
- 3. Safety Evaluation cc w/encls: See next page
August 25, 2005 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS RE: ISOLATION CONDENSER SURVEILLANCE REQUIREMENTS (TAC NOS. MC5835 AND MC5836)
Dear Mr. Crane:
The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No.
215 to Facility Operating License No. DPR-19 and Amendment No. 207 to Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3. The amendments are in response to your application dated January 21, 2005.
The amendments modify the Isolation Condenser System heat removal capability surveillance requirement (SR) by adding a note to the technical specification Section SR 3.5.3.4. This note allows a delay of 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after adequate reactor power is achieved to perform the test.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Maitri Banerjee, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249
Enclosures:
- 1. Amendment No. 215 to DPR-19
- 2. Amendment No. 207 to DPR-25
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrDlpmLpdiii (A)(HNieh) RidsAcrsAcnwMail OGC, O15B18 PDIII-2 R/F RidsNrrDlpmLpdiii2 (GSuh) GHill (4), T5C3 RidsNrrDlpmDpr RidsNrrLAPCoates RidsNrrPMMBanerjee TBoyce RidsOgcRp George Thomas, SRXB/DSSA RidsRgn3MailCenter (MRing)
Package No.: ML051540222 ADAMS Accession Number: ML051540210 Nrr-058 TS Page: ML052420520 Nrr-100 *NLO w/ comments OFFICE PM:LPD3-2 LA:LPD3-2 SC:SRXB-A SC:IROB-A OGC SC:LPD3-2 NAME MBanerjee PCoates FAkstulewicz TBoyce NWildermann GSuh DATE 8/25/05 6/6/05 06/23/05 6/30/05 7/19/05 8-25-05 OFFICIAL RECORD COPY
Dresden Nuclear Power Station, Units 2 and 3 cc:
Site Vice President - Dresden Nuclear Power Station Vice President of Operations - Mid-West Exelon Generation Company, LLC Boiling Water Reactors 6500 N. Dresden Road Exelon Generation Company, LLC Morris, IL 60450-9765 4300 Winfield Road Warrenville, IL 60555 Dresden Nuclear Power Station Plant Manager Exelon Generation Company, LLC Vice President - Licensing and Regulatory 6500 N. Dresden Road Affairs Morris, IL 60450-9765 Exelon Generation Company, LLC 4300 Winfield Road Regulatory Assurance Manager - Dresden Warrenville, IL 60555 Exelon Generation Company, LLC 6500 N. Dresden Road Director - Licensing and Regulatory Affairs Morris, IL 60450-9765 Exelon Generation Company, LLC 4300 Winfield Road U.S. Nuclear Regulatory Commission Warrenville, IL 60555 Dresden Resident Inspectors Office 6500 N. Dresden Road Associate General Counsel Morris, IL 60450-9766 Exelon Generation Company, LLC 4300 Winfield Road Chairman Warrenville, IL 60555 Grundy County Board Administration Building Manager Licensing - Dresden, 1320 Union Street Quad Cities and Clinton Morris, IL 60450 Exelon Generation Company, LLC 4300 Winfield Road Regional Administrator Warrenville, IL 60555 U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President, Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. DPR-19
- 1. The Nuclear Regulatory Commission (Commission) has found that:
A. The application for amendment by the Exelon Generation Company, LLC (licensee) dated January 21, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, are hereby incorporated into this renewed operating license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 25, 2005
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 207 License No. DPR-25
- 1. The Nuclear Regulatory Commission (Commission) has found that:
A. The application for amendment by the Exelon Generation Company, LLC (licensee) dated January 21, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 207, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 25, 2005
ATTACHMENT TO LICENSE AMENDMENT NOS. 215 AND 207 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment number and contain a marginal line indicating the area of change.
Remove Page Insert Page 3.5.3-2 3.5.3-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 215 TO FACILITY OPERATING LICENSE NO. DPR-19 AND AMENDMENT NO. 207 TO FACILITY OPERATING LICENSE NO. DPR-25 EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249
1.0 INTRODUCTION
By application dated January 21, 2005, Exelon Generation Company, LLC (licensee, EGC) requested approval of changes to the Technical Specifications (TSs) for the Dresden Nuclear Power Station (DNPS) Units 2 and 3. The staffs original proposed no significant hazards consideration determination was published in the Federal Register on May 24, 2005 (70 FR 29793).
The proposed changes would revise the Isolation Condenser (IC) TS surveillance requirement SR 3.5.3.4 by adding a note. This note states that the IC system heat removal capability surveillance is not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after adequate reactor power is achieved to perform the test. This note is needed to allow performance of the surveillance test and to ensure IC system operability after an outage if maintenance or modifications were performed during the outage that could affect the IC heat removal capability. Traditionally, this test is performed during power operation, a necessary condition for the test, with a frequency of 60 months. However, during an upcoming outage of DNPS, Exelon is planning to conduct eddy current testing (ECT) of the IC tubes. Because some tubes may be plugged based on the ECT results, a post tube plug testing is required to demonstrate the decay heat removal capacity of the IC. At present, the TS prevents entering Modes 1, 2, or 3 if the surveillance test is required.
The proposed addition of the note to the TS will allow the licensee to enter Modes 1, 2, or 3 without the surveillance test.
2.0 REGULATORY EVALUATION
The Commissions regulatory requirements that are related to the content of the TS are contained in Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR). The IC system is included in the TS in accordance with criterion 4 of 10 CFR 50.36(c)(2)(ii). Section 50.36(c)(3) requires that TS include surveillance requirements.
NUREG-1433, Revision 3, Standard Technical Specifications, General Electric Plants, BWR/4," Revision 3, dated March 31, 2004, incorporates the general guidance regarding limiting conditions for operation scoping criteria set forth in the Commissions Final Policy Statement on Technical Specification Improvement for Nuclear Power Reactors, Published in the Federal Register on July 23, 1993 (58 FR 39132) and incorporated in 10 CFR 50.36 effective August 18, 1995. Within this general framework, licensees may revise the TSs to
adopt current improved standard technical specification format and content provided that plant-specific review supports a finding of continued adequate safety.
The staff finds that the licensee in Section 5.2 of its submittal identified the applicable regulatory requirements.
3.0 TECHNICAL EVALUATION
The staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment which are described in Sections 5.0 and 4.0 of the licensees submittal. The detailed evaluation below will support the conclusion that: (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.
The IC system provides for decay heat removal from the reactor in the event that the reactor becomes isolated from the turbine and the main condenser. It is an Engineered Safety Feature System. The IC consists of two tube bundles immersed in a large water storage tank. The IC system operates by natural circulation. During operation of the IC, steam flows from the reactor, condenses in the tubes of the heat exchanger, and the condensate returns by gravity to the reactor. Automatic initiation occurs when reactor pressure exceeds about 1070 psig for more than 15 seconds.
10 CFR 50.36(c)(3) defines SR as requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that the facility operation will be within safety limits, and that the limiting conditions for operation will be met.
SR 3.5.3.4 verifies the capability of the IC system to remove the design decay heat. The IC system is designed for a heat removal rate of 252.5X106 BTU/HR. The system is required to be operable during Modes 1 (Run), 2 ( Start-Up), and 3 (Hot Shutdown) with reactor pressure above 150 psig. If some of the condenser tubes are plugged during maintenance and testing, a heat removal capability surveillance is required before declaring the system to be operable.
The reactor vessel supplies the heat load required during the surveillance test and the surveillance test can not be performed until adequate steam is available for the test. This requires the unit to be in Mode 1 (Run) and a power level between 60 to 75 percent reactor power as indicated in the plant procedures. The proposed addition of the note to the TS will allow the licensee to postpone the test for 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />. The proposed delay time of 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> is a reasonable time to stabilize the reactor operating conditions during the start-up.
In the current emergency core cooling system (ECCS) TS SR 3.5.1.7, the following note is included: Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test. This note is included in the ECCS TS to ensure that proper reactor operating conditions are available to complete the surveillance requirements. The proposed TS change follows the same approach the staff approved previously for the ECCS systems.
Before the start-up, the licensee will perform an engineering evaluation to assure that the required IC decay heat removal capability is available with margin. The licensee will then confirm the heat removal capability of the IC during power operation by performing TS SR
3.5.3.4 once the necessary reactor operating conditions are reached. The reactor will not be operated in Mode 1 without some assurance that the necessary safety functions could be met should a plant event occur.
If there is no IC system degradation, the heat removal capability surveillance test required by TS SR 3.5.3.4 is only performed once in 60 months.
The proposed addition of the note to TS SR 3.5.3.4 and the proposed addition to the corresponding Bases Section are acceptable as explained above.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of Illinois official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (70 FR 29793). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The IC system heat removal capability test is being performed in an upcoming outage and will be repeated once in every 60 months. The methodology and the acceptance criteria for the surveillance test is not changed. The surveillance is still required to demonstrate the same heat removal capability. The proposed changes are acceptable since the proposed change does not alter the system or its operation. The staff reviewed the proposed change for compliance with 10 CFR 50.36 and agreement with the guidance set forth in NUREG-1433. The staff concludes that the proposed change to the DNPS, Units 2 and 3 TS are acceptable.
The Commission has concluded, based on the considerations discussed above, that: (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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
Letter from P. Simpson, Exelon Generating Company LLC to US Nuclear Regulatory Commission Request for Amendment to Technical Specifications Associated with Isolation Condenser System Heat Removal Capability Surveillance, dated January 21, 2005.
Principal Contributor: George Thomas, SRXB/DSSA 301-415-1814 Date: August 25, 2005