Letter Sequence Approval |
---|
TAC:MF2588, Control Room Habitability (Approved, Closed) |
|
MONTHYEARML1235500402012-12-17017 December 2012 ISFSI Decommissioning Funding Plan Project stage: Request ML13098A0842013-03-27027 March 2013 Decommissioning Funding Status Report Project stage: Request ML13141A4082013-05-0909 May 2013 Submittal of Corporate Restructuring Project stage: Request ML13232A1562013-08-0606 August 2013 ISFSI, Nine Mile Point, Units 1, 2 and ISFSI and R.E. Ginna, and ISFSI, Application for Order Approving Transfer of Operating Authority and Conforming License Amendments. Part 1 of 2 Project stage: Request ML13232A1572013-08-0606 August 2013 ISFSI, Nine Mile Point, Units 1, 2 and ISFSI and R.E. Ginna, and ISFSI, Application for Order Approving Transfer of Operating Authority and Conforming License Amendments. Part 2 of 2 Project stage: Request ML13228A1862013-08-14014 August 2013 Supplement to Application for Order Approving Transfer of Operating Authority and Conforming License Amendments Project stage: Supplement ML13256A3642013-09-17017 September 2013 Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, and R.E. Ginna Nuclear Power Plant - Acceptance of Requested Licensing Action Regarding Direct License Transfer (TAC MF2584 - MF2588) Project stage: Acceptance Review ML13269A3122013-10-0202 October 2013 Request for Withholding Information from Public Disclosure for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, and R.E. Ginna Nuclear Power Plant (TAC Nos. MF2584, MF2585, MF2586, M Project stage: Withholding Request Acceptance ML13294A0392013-11-0707 November 2013 Notice of Consideration of Approval of Transfer of Renewed Facility Operating Licenses and Conforming Amendments,.. Project stage: Other ML13337A3902013-12-0505 December 2013 Request for Additional Information Regarding Order Approving Direct Transfer of Renewed Facility Operating License and Conforming Amendments Project stage: RAI ML13360A2002013-12-17017 December 2013 Response to Nrc'S Request for Additional Information Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments Project stage: Request ML13294A0702013-12-18018 December 2013 Consideration of Approval of Transfer of Renewed Facility Operating Licenses, Materials Licenses, and Conforming Amendments Containing SUNSI Project stage: Request ML14057A8492014-01-0909 January 2014 NRR E-mail Capture - January 09, 2014 - Report of the Nuclear Advisory Committee (MF2584-88) Project stage: Request ML14057A7132014-02-14014 February 2014 NRR E-mail Capture - Constellation License Transfer Tq RAI Responses (MF2584-88) Project stage: Request ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments Project stage: Request ML14063A1252014-03-24024 March 2014 Order Approving Direct Transfer of Licenses and Conforming Amendment, Independent Spent Fuel Storage Installation License, (Tacs. MF2584 and MF2585) Project stage: Other ML14078A6432014-03-24024 March 2014 MF2584-85 Calvert Cliffs Conforming Amendments Project stage: Other ML14078A6492014-03-24024 March 2014 Draft License Pgs Project stage: Draft Other ML14105A4722014-03-24024 March 2014 Order Approving Direct Transfer of Renewed Operating Licenses, Independent Spent Fuel Storage Installation License, and Conforming Amendments (TAC Nos. MF2584, MF2585, and L24780) Project stage: Other NRC-2013-0252, R.E. Ginna Nuclear Power Plant - Order Approving Direct Transfer of Renewed Operating License and Conforming License Amendment2014-03-25025 March 2014 R.E. Ginna Nuclear Power Plant - Order Approving Direct Transfer of Renewed Operating License and Conforming License Amendment Project stage: Other ML14078A5842014-03-25025 March 2014 Draft License Pgs Project stage: Draft Other ML14078A5782014-03-25025 March 2014 Conforming Amendment Page Project stage: Other ML14063A2112014-03-25025 March 2014 Order Approving Direct Transfer of Renewed Operating License and Conforming License Amendment Project stage: Other ML14106A1192014-03-25025 March 2014 R. E. Ginna Nuclear Power Plant - Order Approving Direct Transfer of Renewed Operating License and Conforming License Amendment Project stage: Other ML14091A2972014-04-0101 April 2014 Issuance of Amendments to Conform the Renewed Facility Operating Licenses and Materials License to Reflect the Direct Transfer of Operating Authority (TAC Nos. MF2584, MF2585, and L24780) Project stage: Approval ML14091A3662014-04-0101 April 2014 Issuance of Amendment to Conform the Renewed Facility Operating License to Reflect the Direct Transfer of Operating Authority Project stage: Approval ML14105A1362014-05-0808 May 2014 Request for Withholding Information from Public Disclosure for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, and R.E. Ginna Nuclear Power Plant Project stage: Withholding Request Acceptance ML14149A1112014-05-30030 May 2014 Correction Letter to the Direct Transfer of Operating Authority (Tac Nos. MF2584, MF2585 and MF2588) Project stage: Other 2013-08-06
[Table View] |
Similar Documents at Ginna |
---|
Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection 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-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23258A1382023-09-18018 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010 IR 05000244/20230052023-08-31031 August 2023 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report IR 05000244/20234012023-08-15015 August 2023 LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only) IR 05000244/20230022023-08-0303 August 2023 LLC - Integrated Inspection Report 05000244/2023002 ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 IR 05000244/20234022023-07-19019 July 2023 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only) RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23135A0412023-05-15015 May 2023 2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report ML23121A0482023-05-0101 May 2023 R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000244/20230012023-04-26026 April 2023 LLC - Integrated Inspection Report 05000244/2023001 ML23100A0302023-04-10010 April 2023 2023 10 CFR 50.46 Annual Report ML23114A1152023-03-29029 March 2023 Electronic Reporting of Exposure Data for 2022 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 ML23075A0872023-03-15015 March 2023 R. E. Ginna Nuclear Power Plant - Project Manager Assignment ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000244/20220062023-03-0101 March 2023 Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006) ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23060A1622023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators 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 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators ML22287A0692023-02-0808 February 2023 R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23031A2992023-02-0707 February 2023 R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request ML23010A0112023-02-0101 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value 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 IR 05000244/20223012023-01-20020 January 2023 Initial Operator Licensing Examination Report 05000244/2022301 IR 05000244/20220122023-01-12012 January 2023 LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012 ML22362A0382022-12-28028 December 2022 R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22348A2062022-12-14014 December 2022 Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator 2024-02-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 ML22094A1072022-06-22022 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 151 Adopt 10 CFR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22119A0942022-06-21021 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 150 Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 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) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21175A0012021-07-27027 July 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 145 Regarding Technical Specifications Change to Make a One-Time Exception to the Steam Generator Tube Inspection Requirements ML20353A1262021-03-11011 March 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues 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 ML20057E0912020-04-0303 April 2020 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19325D8242019-12-23023 December 2019 R. E. Ginna Nuclear Power Plant Issuance of Amendment No. 136 to Revise Technical Specification 5.5.15, Containment Leakage Rate Testing Program, to Extend Containment Integrated Leak Rate Test Frequency ML19252A2462019-10-29029 October 2019 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 134 to Revise the Emergency Response Organization Staffing Requirements ML19204A3492019-07-23023 July 2019 R. E. Ginna Nuclear Power Plant: License Amendment Request - Increase the Main Steam Safety Valve Lift Setpoint Tolerance 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 ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18213A3692018-11-13013 November 2018 Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML18309A2632018-11-0909 November 2018 R. E. Ginna Nuclear Power Plant - Correction to Amendment No. 131 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler 547, Clarification of Rod Position Requirements ML18295A6302018-10-31031 October 2018 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 131 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF 547, Clarification of Rod Position Requirements ML18214A1762018-08-31031 August 2018 Issuance of Amendment No. 130, Revise Technical Specification Surveillance Requirement 3.8.4.3, DC (Direct Current) Sources - Modes 1, 2, 3, and 4 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18190A4722018-07-12012 July 2018 R.E Ginna - Correction to Amendment No. 127 Related to Request to Delete a Modification Associated with the Risk-Informed, Performance Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (CAC No. MF9948; EPID L-2017-LLA-0253) ML18137A6142018-06-26026 June 2018 Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes ML18114A0252018-06-25025 June 2018 Issuance of Amendment No. 127, Modify License Condition 2.C.(3) Related to Commitment Associated with Implementation of National Fire Protection Association Standard 805 (CAC MF9948; EPID L-2017-LLA-0253) 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) ML17131A0662017-06-21021 June 2017 R. E. Ginna Nuclear Power Plant - Issuance of Amendment Regarding Use of Optimized Zirlo ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML16358A4242017-02-0909 February 2017 R. E. Ginna Nuclear Power Plant - Issuance of Amendment to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML16125A4852016-06-28028 June 2016 R. E. Ginna Nuclear Power Plant - Issuance of Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3 ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel ML14260A1512016-01-0505 January 2016 Issuance of Order and Conforming Amendments Concerning Pre-emption Authority (Tac Nos. MF2618 and MF2623) ML15271A1012015-11-23023 November 2015 Issuance of Amendment Regarding Transition to a Risk Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) 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 ML14232A3312014-08-21021 August 2014 Non-Proprietary, Correction to Amendment No. 116 Issued August 12, 2014, Revision to Technical Specification Section 3.6.5, 'Containment Air Temperature ML14232A1252014-08-12012 August 2014 R. E. Ginna Nuclear Power Plant - Redacted, Issuance of Amendment Revision to Technical Specification Section 3.6.5 Containment Air Temperature ML14091A3662014-04-0101 April 2014 Issuance of Amendment to Conform the Renewed Facility Operating License to Reflect the Direct Transfer of Operating Authority ML14106A1192014-03-25025 March 2014 R. E. Ginna Nuclear Power Plant - Order Approving Direct Transfer of Renewed Operating License and Conforming License Amendment ML14078A5782014-03-25025 March 2014 Conforming Amendment Page 2023-08-30
[Table view] Category:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML22234A1692022-08-22022 August 2022 R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in 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 ML22052A0132022-02-21021 February 2022 Application to Revise R. E. Ginna Technical Specification 3.1.8, Physics Tests Exception - Mode 2 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML20353A1262021-03-11011 March 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20057E0912020-04-0303 April 2020 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method ML18213A3692018-11-13013 November 2018 Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML16358A4242017-02-0909 February 2017 R. E. Ginna Nuclear Power Plant - Issuance of Amendment to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML16236A0962016-08-26026 August 2016 R. E. Ginna - Correction Letter to License Amendment No. 122 Licence Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3 ML16125A4852016-06-28028 June 2016 R. E. Ginna Nuclear Power Plant - Issuance of Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3 ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel ML15271A1012015-11-23023 November 2015 Issuance of Amendment Regarding Transition to a Risk Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) ML15275A2762015-10-0202 October 2015 R.E. Ginna - Supplemental Information Regarding TSTF-425 License Amendment Request ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15120A2842015-04-30030 April 2015 Response to Request for Additional Information Regarding Proposed License Amendment to Revise Technical Specifications to Adopt TSTF-523 ML14232A3312014-08-21021 August 2014 Non-Proprietary, Correction to Amendment No. 116 Issued August 12, 2014, Revision to Technical Specification Section 3.6.5, 'Containment Air Temperature ML14232A1252014-08-12012 August 2014 R. E. Ginna Nuclear Power Plant - Redacted, Issuance of Amendment Revision to Technical Specification Section 3.6.5 Containment Air Temperature ML14091A3662014-04-0101 April 2014 Issuance of Amendment to Conform the Renewed Facility Operating License to Reflect the Direct Transfer of Operating Authority ML13197A3502013-07-18018 July 2013 Correction to Amendment Approving the Use of Alternate Control and Shutdown Rod Position Monitoring System ML11129A0132011-05-0303 May 2011 Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0920905382009-07-23023 July 2009 R. E. Ginna - License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0900607412008-12-19019 December 2008 R. E. Ginna - Application to Revise Technical Specification Limiting Conditions of Operation (Lcos) 3.3.2, 3.3.4, and 3.8.1 ML0823201612008-08-27027 August 2008 R. E. Ginna - Tech Spec Pages for Amendment 105 Control Room Envelope Habitability ML0804605042008-02-0808 February 2008 License Amendment Request: Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over Pressure Limits ML0727707352007-10-0101 October 2007 R. E. Ginna, Technical Specifications, Amendment Spent Fuel Pool Storage Capacity ML0714103352007-05-16016 May 2007 Technical Specification (Ts), Revised TS 3.7.8, Service Water (SW) System ML0708903712007-03-28028 March 2007 R. E. Ginna - Tech Spec Pages for Amendment 101 Technical Specification 3.5.1 Regarding Emergency Core Cooling System Accumulators ML0706702082007-03-0101 March 2007 R. E. Ginna, Tech Spec Pages for Amendment 100 Regarding Steam Generator Tube Integrity Technical Specifications ML0627802212006-09-29029 September 2006 License Amendment Request: Change to Technical Specification 3.7.8, Service Water (SW) from an Electrical Train Based on a Pump Based Specification ML0621405252006-07-31031 July 2006 License Page 3, Technical Specifications Section 3.6.6 ML0620903672006-07-26026 July 2006 Technical Specifications, Revises TS 3.9.3, Containment Penetrations, to Allow an Emergency Egress Door, Access Door, or Roll Up Door, as Associated with the Equipment Hatch Penetration, to Be Open, But Capable of Being Closed ML0619205942006-07-11011 July 2006 R. E. Ginna, Tech Spec Pages for Amendment 97 Regarding 16.8 Percent Power Uprate ML0615300162006-05-31031 May 2006 Tech Spec Pages for Amendment 96 Regarding Revised Loss-of-Coolant Accident Analyses ML0612405632006-05-0404 May 2006 Corrected Tech Spec Page 5.6-3, to Amendment No. 94 Relaxed Axial Offset Control ML0612805492006-05-0101 May 2006 License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0608202122006-03-16016 March 2006 R. E. Ginna - Tech Spec Pages for Amendment 95 Main Feedwater Isolation Valves ML0532901022005-11-18018 November 2005 Application for Amendment to Facility Operating License Regarding the Testing Requirement for the Containment Spray Nozzles ML0531902132005-11-0707 November 2005 Application for Amendment to Facility Operating License Revising Technical Specification, Section 3.9.3. to Allow Refueling Operations with the Containment Equipment Hatch Open ML0519202452005-07-0707 July 2005 Technical Specification Pages Revision to Diesel Fuel Oil Requirements ML0513901662005-05-18018 May 2005 Technical Specification Page Modification of the Control Room Emergency Air Treatment System ML0512601812005-05-0505 May 2005 R. E. Ginna Nuclear Power Plant, Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0512602362005-04-29029 April 2005 R.E.Ginna - License Application Request Regarding Main Feedwater Isolation Valves ML0512602392005-04-29029 April 2005 License Amendment Request Regarding Revised Loss of Coolant Accident (LOCA) Analyses-Changes to Accumulator, Refueling Water Storage Rwst), and Administrative Control Technical Specifications ML0513003302005-04-29029 April 2005 License Amendment Request Regarding Adoption of Relaxed Axial Offset Control (RAOC) ML0510400672005-04-13013 April 2005 R. E. Ginna Tech Spec Pages for Amendment 89 Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports 2023-08-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April1, 2014 Ms. Mary G. Korsnick Acting Chief Executive Officer and Chief Nuclear Officer Constellation Energy Nuclear Group, LLC 100 Constellation Way, Suite 200C Baltimore, MD 21202 Mr. Bryan P. Wright Senior Vice President and Chief Financial Officer Constellation Energy Nuclear Group, LLC 100 Constellation Way, Suite 200C Baltimore, MD 21202
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT- ISSUANCE OF AMENDMENT TO CONFORM THE RENEWED FACILITY OPERATING LICENSE TO REFLECT THE DIRECT TRANSFER OF OPERATING AUTHORITY (TAC NO. MF2588)
Dear Ms. Korsnick and Mr. Wright:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 115 to Renewed Facility Operating License No. DPR-18 for R.E. Ginna Nuclear Power Plant. The amendment consists of changes to reflect the direct transfer of operating authority from R. E.
Ginna Nuclear Power Plant, LLC to Exelon Generation Company, LLC, as approved by Order dated March 24, 2014.
M. Korsnick and B. Wright The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, I)'
Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Amendment No. 115 to DPR-18 cc w/encl:
Mr. Joseph E. Pacher Vice President R. E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519 Additional Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 R.E. GINNA NUCLEAR POWER PLANT, LLC DOCKET NO. 50-244 R.E. GINNA NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 115 Renewed License No. DPR-18
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by R.E. Ginna Nuclear Power Plant, LLC (the licensee), dated August 6, 2013, as supplemented by letters and emails dated August 14, 2013, September 23 and 26, 2013, December 17, 2013, January 9, 2014, and February 5, 10, 14, and 21, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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 as indicated in the attachment to this license amendment.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
Eric J. eeds, Director Office of Nuclear Reactor Regulation
Attachment:
Changes to the License Date of Issuance: Apri 1 1, 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 115 RENEWED FACILITY OPERATING LICENSE NO. DPR-18 DOCKET NO. 50-244 Replace the following pages of the Renewed Facility Operating License with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 1 1 2 2 3 3 4 4 5 5 6 6 7 7 8
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-00001 R. E. GINNA NUCLEAR POWER PLANT. LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT RENEWED FACILITY OPERATING LICENSE NO. DPR-18 1, The U.S. Nuclear Regulatory Commission (the Commission) having previously made the findings set forth in License No. DPR-18 issued December 10, 1984, has now found that:
A. The application to renew License No. DPR-18 filed by Rochester Gas and Electric Corporation (RG&E)* complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I and all required notifications to other agencies or bodies have been duly made; B. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21 (a)(1), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21 (c), such that there is reasonable assurance that the activities authorized by this renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for R. E. Ginna Nuclear Power Plant (the facility), and that any changes made to the plant's current licensing basis in order to comply with 10 CFR 54.29(a) are in accord with the Act and the Commission's regulations; C. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance (i) that the facility can be operated at power levels up to 1520 megawatts (thermal) without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the regulations of the Commission (except as exempted from compliance in Section 2.D below);
E. R. E. Ginna Nuclear Power Plant, LLC (Ginna LLC) and Exelon Generation are technically and financially qualified to engage in the activities authorized by this renewed operating license in accordance with the rules and regulations of the Commission;
- By Order dated October 9, 2009, as superseded by Order dated October 30, 2009, the transfer of this license to R. E. Ginna Nuclear Power Plant, LLC, was approved. By Order dated , the transfer of the operating authority under this license to Exelon Generation Company, LLC was approved.
Amendment No. 115 I
F. Exelon Generation and Ginna LLC** have furnished proof of financial protection that satisfies the requirements of 10 CFR Part 140; G. The issuance of this renewed license will not be inimical to the common defense and security or to the health and safety of the public; and H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the Commission concludes that the issuance of Renewed Operating License No.
DPR-18 is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. On the basis of the foregoing findings regarding this facility, Facility Operating License No. DPR-18, is superseded by Renewed Facility Operating License No. DPR-18, hereby issued to RG&E and subsequently transferred to Ginna LLC and Exelon Generation to read as follows:
A. This renewed license applies to the R. E. Ginna Nuclear Power Plant, a closed cycle, pressurized, light-water-moderated and cooled reactor, and electric generating equipment which is owned by Ginna LLC (licensee). The facility is located on the licensee's site on the south shore of Lake Ontario, Wayne County, New York, about 16 miles east of the City of Rochester and is described in the licensee's Updated Final Safety Analysis Report (UFSAR}, as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," (a) Ginna LLC to possess and (b) Exelon Generation to possess, use and operate the facility at the designated location in Wayne County, New York, in accordance with the procedures and limitations set forth in this renewed license; (2) Exelon Generation pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material or reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as amended, and Commission Safety Evaluations dated November 15,1976, October 5, 1984, November 14, 1984, and August 30, 1995.
(a) Exelon Generation pursuant to the Act and 10 CFR Part 70, to receive and store four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20, 1979);
- Exelon Generation is authorized to act for R. E. Ginna Nuclear Power Plant, LLC and has exclusive responsibility and control over the physical possession, operation, and maintenance of the facility.
Amendment No. 115
(b) Exelon Generation pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20. 1979). as supplemented February 20,1980, and March 5, 1980; (3) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Part 20. Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1) Maximum Power Level Exelon Generation is authorized to operate the facility at steady-state power levels up to a maximum of 1775 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. XXX, are hereby incorporated in the renewed license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection (a) Exelon Generation shall implement and maintain in effect all fire protection features described in the licensee's submittals referenced in and as approved or modified by the NRC's Fire Protection Safety Evaluation (SE) dated February 14, 1979, and SE supplements dated December 17, 1980, February 6, 1981, June 22,1981, February 27, 1985, and March 21, 1985 or Amendment No. 115 I
configurations subsequently approved by the NRC, subject to provision (b) below.
(b) Exelon Generation may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(c) Deleted (4) Deleted (5) Deleted (6) Deleted (7) License Transfer (a) On the closing date of the transfer of the facility, Ginna LLC shall obtain from RG&E the greater of (1) $200,791,928 or (2) the amount necessary to meet the minimum formula amount under 10 CFR 50.75 calculated as of the date of closing for decommissioning funding assurance for the facility, and ensure the deposit of such funds into a decommissioning trust for the facility established by Ginna LLC.
(b) The decommissioning trust agreement must be in a form acceptable to the NRC.
(c) Ginna LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application and the requirements of the Order approving license transfer, and shall be consistent with the Safety Evaluation supporting that Order.
(8) Mitigation Strategy Exelon Generation shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equipment and materials
- 4. Command and control
- 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:
Amendment No. 115 I
- 1. Protection and use of personnel assets
- 2. Communications
- 3. Minimizing fire spread
- 4. Procedures for implementing integrated fire response strategy
- 5. Identification of readily-available pre-staged equipment
- 6. Training on integrated fire response strategy
- 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
- 1. Water spray scrubbing
- 2. Dose to onsite responders (9) Control Room Envelope Habitability Upon implementation of Amendment No. 105 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.9.4, in accordance with TS 5.5.16.c.i and the assessment of CRE habitability as required by 5.5.16.c.ii, shall be considered met. Following implementation:
(a) The first performance of SR 3.7.9.4 in accordance with Specification 5.5.16.c.i shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from February 8, 2005, the date of the most recent successful tracer gas test, as-stated in the April 6, 2007 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.16.c.ii, shall be within 3 years, plus the 9-month allowance of SR 3.0.2 as measured from February 8, 2005, the date of the most recent successful tracer gas test, as stated in-the April 6, 2007 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
(10) The existing E.D.F. International S.A.S. Support Agreement of approximately $145 million, dated November 6, 2009, may not be amended or modified without 30 days prior written notice to the Director of the Office of Nuclear Reactor Regulation or his designee. R. E. Ginna Nuclear Power Plant, LLC, CENG, or Exelon Generation shall not take any action to cause E.D.F. International S.A.S., or its successors and assigns, to void, cancel, or materially modify the E.D.F. International S.A.S. Support Agreement or cause it to fail to perform, or impair its performance under the E. D. F. International S.A.S. Support Agreement, without the prior written consent of the NRC. Exelon Generation shall inform the NRC in writing no later than 14 days after any funds are Amendment No. 115 I
provided to or for the CENG subsidiary licensee under the E.D.F.
International S.A.S. Support Agreement.
(11) Exelon Corporation shall, no later than the time the license transfers occur, enter into a Support Agreement of approximately $245 million with the licensee. The Exelon Corporation Support Agreement shall supersede the Support Agreement provided by Exelon Generation, dated March 12, 2012, in all respects and shall be consistent with the representations contained in the August 6, 2013 transfer application. R. E. Ginna Nuclear Power Plant, LLC, CENG, or Exelon Generation shall not take any action to cause Exelon Corporation, or its successors and assigns, to void, cancel, or materially modify the Exelon Corporation Support Agreement or cause it to fail to perform, or impair its performance under the Exelon Corporation Support Agreement, without the prior written consent of the NRC. The Exelon Corporation Support Agreement may not be amended or modified without 30 days prior written notice to the Director of the Office of Nuclear Reactor Regulation or his designee. An executed copy of the Exelon Corporation Support Agreement shall be submitted to the NRC no later than 30 days after the completion of the proposed transaction and license transfers. Exelon Generation shall inform the NRC in writing no later than 14 days after any funds are provided to or for the licensee under the Exelon Corporation Support Agreement.
(12) Exelon Corporation shall, no later than the time the license transfers occur, provide a parent guarantee in the amount of $165 million to ensure a source of funds for the facility in the event that the existing cash pool between the licensee and CENG is insufficient to cover operating costs.
The existing CENG cash pool arrangement shall be consistent with the representations contained in the 2009 Transfer Application dated January 22, 2009 (ADAMS Accession No. ML090290101 ). R. E. Ginna Nuclear Power Plant, LLC, CENG, or Exelon Generation shall not take any action to cause Exelon Corporation, or its successors and assigns, to void, cancel or materially modify the parent guarantee or cause it to fail to perform, or impair its performance under the parent guarantee without the prior written consent of the NRC.
(13) Within 14 days of the license transfers, Exelon Generation shall submit to the NRC the Nuclear Operating Services Agreement reflecting the terms set forth in the application dated August 6, 2013. Section 7.1 of the Nuclear Operating Services Agreement may not be modified in any material respect related to financial arrangements that would adversely impact the ability of the licensee to fund safety-related activities authorized by the license without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.
(14) Within 10 days of the license transfers, Exelon Generation shall submit to the NRC the amended CENG Operating Agreement reflecting the terms set forth in the application dated August 6, 2013. The amended and restated Operating Agreement may not be modified in any material respect concerning decision making authority over safety, security and Amendment No. 115 I
reliability without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.
(15) At least half the members of the CENG Board of Directors must be U.S.
citizens.
(16) The CENG Chief Executive Officer, Chief Nuclear Officer, and Chairman of the CENG Board of Directors must be U.S. citizens. These individuals shall have the responsibility and exclusive authority to ensure and shall ensure that the business and activities of CENG with respect to the facility's license are at all times conducted in a manner consistent with the public health and safety and common defense and security of the United States.
(17) CENG will retain its Nuclear Advisory Committee (NAC) composed of U.S. citizens who are not officers, directors, or employees of CENG, EDF Inc., Constellation Nuclear, LLC, or CE Nuclear, LLC. The NAC will report to, and provide transparency to, the NRC and other U.S. governmental agencies regarding foreign ownership and control of nuclear operations.
(18) The NAC shall prepare an annual report regarding the status of foreign ownership, control, or domination of the licensed activities of power reactors under the control, in whole or part, of CENG. The NAC report shall be submitted to the NRC within 30 days of completion, or by January 31 of each year (whichever occurs first). No action shall be taken by CENG or any entity to cause Constellation Nuclear, LLC, Exelon Generation, or their parent companies, subsidiaries or successors to modify the NAC report before submission to the NRC. The NAC report shall be made available to the public, with the potential exception of information that meets the requirements for withholding such information from public disclosure under the regulations of 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."
D. The facility requires an exemption from certain requirements of 10 CFR 50.46(a)(1). This includes an exemption from 50.46(a)(1), that emergency core cooling system (ECCS) performance be calculated in accordance with an acceptable calculational model which conforms to the provisions in Appendix K (SER dated April 18, 1978). The exemption will expire upon receipt and approval of revised ECCS calculations. The aforementioned exemption is authorized by law and will not endanger life property or the common defense and security and is otherwise in the public interest. Therefore, the exemption is hereby granted pursuant to 10 CFR 50.12.
E. Exelon Generation shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27827 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "R. E. Ginna Amendment No. 115 I
Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," submitted by letter dated May 15, 2006.
Exelon Generation shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 113.
F. The Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Ginna LLC shall complete these activities no later than September 18, 2009, and shall notify the Commission in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) following issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs and activities described in the supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
G. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC.
H. This renewed license is effective as of the date of issuance and shall expire at midnight on September 18, 2029.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By J. E. Dyer, Director Office of Nuclear Reactor Regulation
Attachment:
Appendix A- Technical Specifications Date of Issuance: May 19, 2004 Amendment No. 115 I
Packag_e: ML14063A195 L e t ter: ML14091A366 OFFICE NRR/DORULPLI-1/PM NRR/DORULPLI-1/LA NRRIDIRS/IFIB* NRRIDRAIAPHB/BC* NMSS/SFST/LB/BC*
NAME NMorgan KGoldstein AKock SWeerakkody MSampson DATE 4/1/2014 4/1/2014 (via email) 2/28/2014 3/5/2014 3/6/2014 OFFICE QTE* OGC* NRR/DORULPLI-1/BC NRRIDORUD* NMSS/D*
NAME SUttal BBeasley MEvans CHaney DATE 3/6/2014 3/21/2014 4/1/2014 3/20/2014 3/21/2014 OFFICE NRRID*
NAME ELeeds DATE 3/24/2014
- Concurred on the Order package dated March 24, 2014, wh1ch mcluded the draft conform1ng amendments. No changes were made.