Similar Documents at Ginna |
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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-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-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. ML22234A1692022-08-22022 August 2022 R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. ML22124A3162022-05-27027 May 2022 Summary of Combined Regulatory Audit in Support of Risk Informed Completion Times in Technical Specifications LAR and to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power ML22108A2482022-04-18018 April 2022 R.E.. Ginna Nuclear Power Plant - License Amendment Request to Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML22052A0132022-02-21021 February 2022 Application to Revise R. E. Ginna Technical Specification 3.1.8, Physics Tests Exception - Mode 2 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments ML21287A0062021-10-14014 October 2021 Supplemental Information No.1 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, - Risk-Informed Categorization and Treatment of Structu 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 ML21140A3242021-05-20020 May 2021 R. E. Ginna Nuclear Power Plant - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML21141A0092021-05-20020 May 2021 R. E. Ginna Nuclear Power Plant - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments ML20056E9582020-02-25025 February 2020 R. E. Ginna Nuclear Power Plant, License Amendment Request to Add a One-Time Note for Use of Alternate Residual Heat Removal Methods RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19045A2822019-02-15015 February 2019 R. E. Ginna Nuclear Power Plant - License Amendment Request (LAR) to Revise Technical Specification (TS) 5.5.15, Containment Leakage Rate Testing Program, for Permanent Extension of Type a Leak Rate Test Frequencies ML18158A1292018-06-0505 June 2018 License Amendment Request: Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML17321A1072017-11-16016 November 2017 R. E. Ginna, License Amendment Request to Revise Technical Specifications for Selected Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Channels to Incorporate Bypass Test Capability ML17304A9842017-10-31031 October 2017 R. E. Ginna Nuclear Power Plant - License Amendment Request to Revise Technical Specifications Surveillance Requirement SR 3.8.4.3, DC Sources - Modes 1, 2, 3, and 4, to Allow for a Modified Performance Discharge Test ML17186A2332017-06-30030 June 2017 License Amendment Request - Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition ML17164A1482017-05-31031 May 2017 Enclosure 3C - EAL Basis Document for R.E. Ginna Nuclear Power Station ML17164A1502017-05-31031 May 2017 Enclosure 3D - EAL Front Matter for R.E. Ginna Nuclear Power Station ML17164A1512017-05-31031 May 2017 Enclosure 3E - Procedure Matrix for R.E. Ginna Nuclear Power Station ML17164A1472017-05-31031 May 2017 Enclosure 3B - EAL Red-Line Basis Document for R.E. Ginna Nuclear Power Station RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16236A3002016-08-22022 August 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... ML16035A0152016-02-0404 February 2016 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. ML15210A3142015-07-29029 July 2015 License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel ML15166A0752015-06-0404 June 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 82014-08-29029 August 2014 License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8 ML13228A2652013-08-14014 August 2013 Independent Spent Fuel Storage Installations Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act & License Amendment 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 ML13093A0642013-03-28028 March 2013 License Amendment Request Pursuant to 10 CFR 50.90: Adoption of NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML11138A1592011-05-12012 May 2011 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R.E. Ginna, Application for Approval of Indirect Transfer of Control of Licenses ML1020404732010-07-16016 July 2010 R. E. Ginna - Request for Approval of the Constellation Energy Nuclear Group Cyber Security Plan ML0926800602009-09-18018 September 2009 R. E. Ginna - License Amendment Request: Administrative Revision of Inservice Test Program Technical Specification ML0920905382009-07-23023 July 2009 R. E. Ginna - License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0908901912009-03-23023 March 2009 R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0906304262009-02-26026 February 2009 R. E. Ginna and Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation - Supplement to Application for an Order Approving License Transfers and Conforming License Amendment Request ML0835308062009-02-23023 February 2009 R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits ML0903302752009-01-22022 January 2009 R. E. Ginna - Amendment to Application to Revise Technical Specification Limiting Conditions of Operation (Lcos) 3.3.2, 3.3.4, and 3.8.1 ML0902901012009-01-22022 January 2009 Application for an Order Approving License Transfers and Conforming License Amendment Request 2023-05-22
[Table view] Category:Technical Specification
MONTHYEARRS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. 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 ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin RS-21-082, Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC2021-08-13013 August 2021 Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC ML20339A2212020-11-20020 November 2020 Technical Specifications Bases, Rev 101 JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19150A5112019-05-10010 May 2019 Revision 90 to Technical Specification Bases ML18176A3272018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... ML15166A0752015-06-0404 June 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1212904852012-04-20020 April 2012 LAR File for Rod Indication/Attachment 1 Mrpi LAR ML11129A0132011-05-0303 May 2011 Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0908901912009-03-23023 March 2009 R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0835308062009-02-23023 February 2009 R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits ML0834600512008-12-0404 December 2008 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision of Tech Spec. 3.9.3 to Allow Refueling Operations Inside Containment with Both Personnel Hatch Air Lock Doors Open Under Administrative Control, and Obtain Regulatory Rev ML0723504322007-08-16016 August 2007 R. E. Ginna - Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0604802442006-02-15015 February 2006 Technical Specification Pages Re Relaxed Axial Offset Control ML0534702012005-12-0808 December 2005 R. E. Ginna Nuclear Power Plant, 5.5.1 Offsite Dose Calculation Manual (ODCM) ML0519501232005-07-0707 July 2005 License Amendment Request Regarding Extended Power Uprate ML0513003302005-04-29029 April 2005 License Amendment Request Regarding Adoption of Relaxed Axial Offset Control (RAOC) ML0507702042005-03-14014 March 2005 R. E. Ginna, Replacement Pages Associated with the Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0507603812005-03-10010 March 2005 R. E. Ginna - Application for Amendment to Facility Operating License Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension ML0506203062005-03-0101 March 2005 R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints ML0426800472004-09-22022 September 2004 Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints ML0402307292004-01-22022 January 2004 R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2 ML18142B9481977-12-22022 December 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18142B9501977-11-21021 November 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18143A2121977-01-0606 January 1977 R. E. Ginna - Forwards Copies of Application for Amendment to Operating License ML18142B9881976-01-21021 January 1976 R. E. Ginna - Forwards Copies of Proposed Change to Technical Specifications to Change Surveillance Requirements for Integrated Leakage Rate from Containment, and Copies of Application for Amendment to Operating License. ML18142C0271974-10-15015 October 1974 Transmittal of Rge Application for Amendment to Technical Specifications for Inspection Requirement for Hydraulic Snubbers ML18142C0281974-10-15015 October 1974 Letter Submitted Application for Amendment to Technical Specification, Consisting a Request for a Change to the License Maybe Amended to Add Inspection Requirement for Steam Generator Tubes ML18142C0291974-09-30030 September 1974 Letter Requesting a Proposed Change to the Technical Specification to Increase the Indicated Water Level to the Accumulators to Conform to Accident Analysis Assumptions ML18142C0321974-07-0909 July 1974 Submittal of Application for Amendment to Applicant'S Technical Specifications, Describing Duties and Responsibilities of the Plant Review and Audit Groups 2022-08-10
[Table view] Category:Amendment
MONTHYEARRS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. 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 ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML18176A3272018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML0908901912009-03-23023 March 2009 R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0835308062009-02-23023 February 2009 R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits ML0834600512008-12-0404 December 2008 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision of Tech Spec. 3.9.3 to Allow Refueling Operations Inside Containment with Both Personnel Hatch Air Lock Doors Open Under Administrative Control, and Obtain Regulatory Rev ML0723504322007-08-16016 August 2007 R. E. Ginna - Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0604802442006-02-15015 February 2006 Technical Specification Pages Re Relaxed Axial Offset Control ML0534702012005-12-0808 December 2005 R. E. Ginna Nuclear Power Plant, 5.5.1 Offsite Dose Calculation Manual (ODCM) ML0519501232005-07-0707 July 2005 License Amendment Request Regarding Extended Power Uprate ML0507603812005-03-10010 March 2005 R. E. Ginna - Application for Amendment to Facility Operating License Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension ML0506203062005-03-0101 March 2005 R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints ML0426800472004-09-22022 September 2004 Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints ML0402307292004-01-22022 January 2004 R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2 ML18142B9481977-12-22022 December 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18142B9501977-11-21021 November 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18143A2121977-01-0606 January 1977 R. E. Ginna - Forwards Copies of Application for Amendment to Operating License ML18142B9881976-01-21021 January 1976 R. E. Ginna - Forwards Copies of Proposed Change to Technical Specifications to Change Surveillance Requirements for Integrated Leakage Rate from Containment, and Copies of Application for Amendment to Operating License. ML18142C0271974-10-15015 October 1974 Transmittal of Rge Application for Amendment to Technical Specifications for Inspection Requirement for Hydraulic Snubbers ML18142C0281974-10-15015 October 1974 Letter Submitted Application for Amendment to Technical Specification, Consisting a Request for a Change to the License Maybe Amended to Add Inspection Requirement for Steam Generator Tubes ML18142C0291974-09-30030 September 1974 Letter Requesting a Proposed Change to the Technical Specification to Increase the Indicated Water Level to the Accumulators to Conform to Accident Analysis Assumptions ML18142C0321974-07-0909 July 1974 Submittal of Application for Amendment to Applicant'S Technical Specifications, Describing Duties and Responsibilities of the Plant Review and Audit Groups 2022-08-10
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DISTRIBUTION AFTER ISSUANCE OF OP TING LICENSE U.S. NUCI.EAR REGULATORY COMMISS, OOCKET NUMBER
~NRC EORM 195 I2 7BI PILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FROM: OATE OF OOCUMENT TO:
LeBoeuf, Lamb. Leiby & MacRae 12/22/77 Mri Edson Gi Case Washington~ Di C OATS RECEIVEO LeBoeuf, Lamb. Leiby & MacRae 12/27/77 CINOTOR IZE O PROP INPUT FORM NUMBER OF COPIES RECEIVEO I LG R ORIGINAL KKINCLASSIFIEO Cicor v OGSCRIPTION ENCLOSURE License No+ DPR-18 Appl for Amend: tech specs proposed change concerning addition of requirements for undervo1tage requirements
~ inotorized 12/16/77 of Serviceo ~ ~ ~
'/att Certificate (1-P) (2<
rr JAMES F. JOHNSON, EUGENC B. THOMASr JR 44 LEONARD M. TROSTENr4 @4rr j4rr'rrrrc CASLC ADDRESS HARRY H. VOIOT r 4
. RONALD D. JONES LEX K. LARSONS 4 ORANT S. LEWIS H. RICHARD WACHTKL OCRARO P. WAT9ON
'o '. LCSWIHr HEW YORK TCLCX: 4234IS 4 RCSIDENT PARTNERS WASHINGTON OFFICE 4 ADMITTED TO THC DISTRICT OF COLUMBIA BAR December 22, l977 Mr. Edson G. Case Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Station, Unit. No. 1 Docket No. 50-244
Dear Mr. Case:
As counsel for Rochester Gas and Electric Corporation, we hereby transmit three (3) signed originals and nineteen (l9) copies of a document entitled, "Application for Amend-ment to Operating License," together with forty (40) copies of proposed changes to Technical Specifications and accompany-ing safety evaluation. Thi's Application seeks to amend the Technical Specifications to add requirements for under-voltage protection.
A Certificate of Service showing service of these documents upon the persons listed therein is also enclosed.
Very truly yours, WTE/bg Enclosures
III BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )
)
ROCHESTER GAS AND ELECTRIC, ) Docket No. '50-244 CORPORATION '
. )
(R. E. Ginna Nuclear Power )
Station, Unit No. '1) )
CERTIFICATE OF SERVICE The undersigned hereby certifies that the "Application for Amendment to Operating License" together with a copy of the proposed changes to Technical Specifications and accom-panying safety evaluation were this twenty-second day of December, 1977, served, by first class mail, postage prepaid, on the following persons:
Chairman, Atomic Safety L. Dow Davis, IV, Esquire and Licensing Board Panel Office of the Executive Legal U.S. Nuclear Regulatory Director Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20555 Atomic Safety and Licensing Appeal Board Edward Luton, Esquire U.S. Nuclear Regulatory Atomic Safety and Licensing Commission Board Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Mr. Michael L. Slade Washington, D.C. 20555 1250 Crown Point Drive Webster, New York 14580 Dr. Emmeth A. Luebke Atomic Safety and Licensing Warren B. Rosenbaum, Esquire Board One Main Street East U.S. Nuclear Regulatory 707 Wilder Building Commission Rochester, New York 14614 Washington, D.C. 20555
)
Dr. A. Dixon Callihan Jeffrey L. Cohen, Esquire Union Carbide Corporation ~ New York State Energy P. O. Box Y Office Oak Ridge, Tennessee 37830 Swan Street Building Core I, Second Floor Mr. Robert N. Pinkney Empire State Plaza Supervisor Albany, New York 12223 Town of Ontario 107 Ridge Road West Ontario, New York 14519 h
Walter T. Eccard LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
UNITED STATES OF AMERICA NUCLEAR, REGULATORY COMMISSION In the Matter of )
)
Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant, )
Unit No. 1) )
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGSE"), holder of Provisional Operating License No. DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that License be amended to add require-ments for undervoltage protection. This request for a change in the Technical Specifications is submitted in accordance .with a letter from A. Schwencer, Chief, Operating Reactors Branch 51, dated June 3, 1977.
The proposed technical specification change is set forth in Attachment A to this Application. A safety evaluation is set forth in Attachment B. This evaluation also demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents- or any change in the authorized power level of the facility.
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WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation By L. D. White, Jr.
Vice President, Electric and Steam Production Subscribed and sworn to before me on this (Q day of December 1977.
STC: II CN K trIDA IIOTARY PUBLIC, State of II.Y, I tonrce County gy Commission Expires Inarch 30, 197+
Attachment A
- 1. Remove pages 2.3-4, 2.3-8, 3.5-4, 3;5-4a, and 4.1-7.
- 2. Insert the enclosed revised pages 2.3-4, 2.3-8, 2.3-9, 3.5-4a, and 4.1-7.
- f. Low reactor coolant flow > 90% of normal indicated flow.
- g. Low reactor coolant pump frequency > 57.5 Hz.
2.3.1.3 Other reactor t'ri s
- a. High pressurizer water level < 92% of span
- b. Low-low steam generator water level > 5% of narrow range instrument span 2.3.2 Protective instrumentation settings for reactor trip interlocks shall be as follows:
2.3.2.1 Remove bypass of "at power" reactor trips at high power (low pressurizer pressure and low reactor coolant flow) for both loops:
Power range nuclear flux -' 8.5% of rated power (1) (Note: During cold rod drop tests, the r
pressurizer high level trip may be bypassed.)
2.3.2.2 Remove bypass of single loss of flow trip at high power:
Power range nuclear flux -' 50% of rated power 2.3.3 Relay settings for 480 volt safeguards bus protection shall be as follows:
2.3.3.1 Loss of voltage relay operating time' 8.5 seconds for 480 volt safeguards bus voltages < 368 volts 2.3.3.2 Degraded voltage relay operating times and setpoints, for 480 volt safeguards bus voltages < 414 volts and 368 volts. See Figure 2.3-1.
Basis:
The high flux reactor trip (low set point) provides redundant protection in the power range for a power excursion beginning from low power. This trip value was used in the safety analysis.
2.3-4 PROPOSED
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the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase. For this reason the single pump loss of flow trip can be bypassed below 50%
power.
The loss of voltage and degraded voltage trips ensure opera-bility of safeguards equipment during a postulated design basis event concurrent with a degraded bus voltage condition. (9) (10)
References:
(1) FSAR 14.1.1 (2) FSAR, Page 14-3 (3) FSAR 14.3.1 (4) FSAR 14.1.2 (5) FSAR 7.2, 7.3 (6) FSAR'.2.1 (7) FSAR 14.1.6 (8) FSAR 14.1.9 (9) Letter from L.D. White, Jr. to A. Schwencer, NRC, dated July 21, 1977 (10) Letter from L.D. White, Jr. to A. Schwencer, NRC, dated September 30, 1977 PROPOSED 2.3-8
J ill
40 1600 0
I0 Ul pearaded Voltage Protection "8 1400 E' Figure 2. 3-1
'I 1200 ~
I e4 l5 I
S4 0 1000 l5 I
8 ~ ~ ~ ~ I C
800 I 8
l5 0 600 4
8 l5 400 8 I Q I (Allowable Rela 0s crating 200 I 4 ~
0 Secondary Volts (120 Volts) 70 80 90 92 103. 5. 120 Primary Volts (480 Volts) 240 320 368 414 480 Percent Volts (460 Volt Base) 52% 70% 80% 90% 104%
Safeguards Bus Voltage 2.3-9
Page 3 of 3 1 2 3 4 5 6 NO. of MIN. MIN. ~
PERMISSIBLE OPERATOR ACTION NO. of CHANNELS OPERABLE DEGREE OF BYPASS IF CONDITIONS OF CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS COLUMN 3 or 5 CANNOT BE MET
- 17. Circulating Water Flood Protection a.Screenhouse Power operation may be con-tinued for a period of up to 7 days with 1 channel in-operable or for a period ~
24 hrs. with two channels-~
inoperable.
b.Condenser Power operation may be con-tinued for a period of up to 7 days with 1 channel in-operable or for a period of 24 hrs. with two channels inoperable.
- 18. Loss of Voltage Maintain hot shutdown or 480 Volt Safe- 2/bus 1/bus 1/bus
- place bus on diesel generator guards Bus 19- Degraded Voltage Maintain hot shutdown or 480 Volt Safe- 2/bus 1/bus 1/bus
- place bus on diesel generator guards Bus NOTE 1: When block condition exists, maintain normal operation.
F.P. = Full Power
.* Not Applicable
- If both rod misalignment monitors (a and b) are inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or more, the nuclear overpower trip shall be reset to 93% of rated power in addition to the increased surveillance noted.
- If a functional unit is operating with the minimum operable channels, the number of channels to trip the reactor will be column 3 less column 4.
+ A channel is considered operable with 1 out of 2 logic or 2 out of 3 logic.
PROPOSED
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TABLE 4.1-1 (CONTINUED Channel Check Calibrate Test Remarks
- 25. Containment Pressure M Narrow range containment pressure
(-3.0, +3 psig excluded)
- 26. Steam Generator Pressure
- 27. Turbine First Stage Pressure-
- 28. Emergency Plan Radiation Instruments
- 29. Environmental Monitors N.A. N.'A.
- 30. Loss of Voltage 480 N.A.
Volt Bus
- 31. Degraded Voltage 400 Volt N.A.
Safeguards Bus Each Shift M Monthly D Daily P Prior to each startup if not done previous week B/N Biweekly Each Refueling Shutdown Quarterly N.A. Not applicable PROPOSED
/
Attachment B By letter dated June 3, 1977, the NRC requested that RG&E assess the susceptibility of safety related electrical equipment with regard to (1) sustained degraded voltage conditions at the offsite power sources and (2) interaction between the offsite and onsite emergency power sources.
An analysis of undervoltage protection at Ginna Station was performed and submitted to the NRC in a letter dated July 21, 1977.
This analysis reviewed the current undervoltage protection and described a modification which would reduce the Station's su cep-tibility to a sustained degraded voltage. The basis for the modification was described; however, due to lack of specific in-formation regarding certain equipment, specific setpoints for the additional undervoltage protection could not be established.
Following receipt of additional information, RGsE submitted suggested setpoints in a letter to the NRC dated September 30, 1977. The proposed specifications are identical to those pre-sented in the September 30 letter.
The proposed Specifications will provide protection both for complete loss of 480 volt bus voltage and for degraded bus voltage.
The loss of voltage protection, provided by existing equipment, will assure that assumptions of all safety analyses are met for a complete loss of voltage to safeguards equipment. Specifically, equipment will be loaded onto the diesel generators within the time assumed in the safety analyses. The undervoltage relay
~1 protection, which was identified as "second-level protection" in the June 3 NRC letter and in our two subsequent letters, will protect equipment against a bus voltage which is greater than the loss of voltage relay setpoint but less than the voltage guaranteed by equipment manufacturers for continuous duty for Ginna safeguards equipment. The proposed undervoltage setpoints will provide the required protection while also assuring that spurious trips will-not occur while equipment is being sequenced onto the diesel generators.
Loss of voltage and degrade voltage conditions simulated during the refueling shutdown are performed to verify both system per-formance and relay calibration. The safeguards 480 volt loss of voltage and degraded voltage protection systems are not part of the reactor protection system. It is not practical to simulate these conditions during plant operation to satisfy a monthly test requirement.
Based on the analyses provided in our letters of July 21, 1977 and September 30, 1977, the proposed Technical Specification will provide protection against 480 volt bus undervoltage.
As stated in our letter of July 21, 1977, we expect that, following receipt of approval of the modification design by the NRC, detailed engineering and procurement of equipment will re-quire approximately 9 months. Installation must be performed at a cold or refueling shutdown and would require approximately two weeks. The effective date of a Technical Specification should be set consistent with this schedule.
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