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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Text
NRC,FDRM 195 I2-7B)
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t U S ~ NUCLEAR REGULATORY C
'NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL ON DOCKET NUMBER So -0M FILE NUMBER TO FROM: DATE OF DOCUMENT Mr. Edson G. Case LeBoeuf, Lamb, Leiby & MacRae Washington, D. C. 20036 DATE RECEIVED LeBoeuf, Lamb, Leiby & MacRae I.ETTE R OTOR IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED ABORIGINAL RCUNC LASS IF I E D C3 cop v DESCRIPTION ENCLOSURE License No. DPR-18 apl For Amend:
tech specs proposed change concerning modifica-tions of requirements for diesel generator test>>
ing. ~ .Notorized 11/16/77........W/Att Cert of Svco ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
1p 15P DISTRIBUTION OF MATERIAL CONCERNING ONSITE EMERGENCY POWER SYSTEMS PLANT NAIIE. Re E, GINNA UNIT g 1 jcm 11/22/77 C? Rr oPS&Btf.
SAFETY FOR ACTION/INFORMATION BRANCH CHIEF:
INTERNAL DISTR I BUTION REG FILE I G E(2)
OELD MIPC HANAUER BENAROYA IPPOLITO EISENHUT SHAO BAER BUTLER GRIMES F. ROSA T. WAMBACH D. TONDI D. MCDONALD D. JAFFF, EXTERNAL DISTRIBUTION C NTROL NUMBER LPDR'6 CYS ACRS CATEGOR 7732so167
LEBOEUF, LAMB, LEIBY 8L MAC RAE l757 N STREET, N.W.
WAsHINGTQN, D. C. 20036 TELEPHONE 202 457 7600 CA8LC ADORC$ 8 LEON A. AI.LKN.JR. CAMERON F. MACRAE 2 RANDALL J. Lc80EVF,JR. I929-l976 CAMCRON F. MACRAK,IE 2 I 28WIH,WASHIHOTOH, 0.0.
JOSEPH K. BACHKLDKR.ZI ADRIAN C, LCISY l952 l975 CRNKST S. BALLARD.JR. GKRARD A,MAHER TELEX: 440274 O. S PETER BCRGEN 8 SHCILA H. MARSHALL OEOFFRY D. C. BEST JAMES G. McKLROY DAVID P. DICKS TAYLOR R. BRIGOS JAMES P. McGRANERY. JR!
PHILIP PALMER MCOUIOAN i OF COUHSCL CHARLES N. BVROER THOMAS E BVRKE
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JAM CS O MALLEY,JR.
J M I C H AC L PAR I S H i AHVIH C. UPTON i
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ROGER D.FELDMAN 4 JOHN A.RVDY CVGK N C R. FIDEL L 4 PAUL O. RUSSELL JACOB FRICDLANDCR HAROLD M. SKIDEI. I40 DONALD J. ORKENE CHARLES P. SIFTON BROADWAY JAMES A ORKERsII 4 HALCYON O. SKINNER JOHN L.GROSC 4 JOSEPH S.STRAUSS HEW YORK, H.Y. I0005 DOUGLAS W.HAWKS CARL D.HOBCLMAN SAMUEL M.SUGDKN TKLKPHOHC 2I2 289 II00 MICHAEL IOVCNKO EUGENE B, THOMAS,JR!4 JAMES F JOHNSON,4' LKONARD M TROSTCN+4 CAQLC ADORCSS RONAI.D D. JONES HARRY H.VOIOT+ 2 LCX K.LARSON+4 H. RICHARD WACHTKL LEBWIH, HEW YORK ORANT S.LEWIS OERARD P. WATSON TELEX: 42$ 4IS November 21, 1977 4RESIDCNT PARTNERS WASHINGTON OFFICF 4 ADMITTED 'TO THK DISTRICT OF COLUMBIA BAR l 'I2gI Mr. Edson G. Case \'IUUI.'
Acting Director 2 U9 Office of Nuclear Reactor NOW
~>>ULAIQKT Regulation Q A~~TB2$$ 5 ION U.S. Nuclear Regulatory ~, F Commission Washington. D- C. 20555 t cp t f Il Re: Rochester, Ga's 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 Corpora-tion, we hereby transmit three (3) signed originals and nineteen (19) copies of a document entitled, "Application for Amendment to Operating License." This Application seeks to amend Technical Specification 4.6 set forth in Appendix A to Provisional Operating License No. DPR-18, to modify the requirements for diesel generator testing. Forty (40) copies of this proposed change and of the safety evaluation there-for are also transmitted herewith."
A Certificate of Service showing service of the'se documents upon the persons listed therein is also enclosed.
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Enclosures
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
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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 ("RGGE"), holder of Provisional Operating License No. DPR-18, hereby requests that the Technical Specification 4.6 set forth in Appendix A to that license be amended to modify the requirements for diesel generator testing. This request for a change in the Technical Specifications is submitted to eliminate conflicting requirements for diesel generator testing.
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.
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 /&today of November 1977.
GARY L. REISS NOTARY PUBLlC, State o5 N. Y. Monroe Co.
My Cornrnission Expires March 30, 19......
BEFORE THE UNXTED STATES NUCLEAR REGULATORY COMMXSSION
)
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ROCHESTER GAS AND ELECTRXC ) Docket No. 50-244 CORPORATION )
(R. E. Ginna Nuclear Power )
Station, Unit, No. 1) )
CERTIFICATE OF SERVXCE I hereby certify that I have served a document entitled, "Application for Amendment to Operating License" together with a copy of the proposed changes to Technical Specifications and the safety evaluation therefor by mailing copies thereof first class, postage prepaid to each of the following persons this 21st day of November, 1977:
Chairman, Atomic Safety L. Dow Davis, IV, Esq.
and Licensing Board Office of the Executive U.S. Nuclear Regulatory Legal Director Commission U.S. Nuclear Regulatory Washington, D. C. 20555 Commission Washington, D. C. 20555 Atomic Safety and Licensing Appeal Board Edward Luton, Esq.
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'4580 Dr. Emmeth A. Luebke Atomic Safety and Licensing Warren B. Rosenbaum, Esq. 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, Esp.
Union Carbide, Corporation New York State Energy Office P.'. Box Y Swan Street Building Oak Ridge, Tennessee 37830 Core I, Second Floor Empire State Plaza Mr. Robert N. Pinkney Albany, New York 12223 Supervisor Town of Ontario 107 Ridge Road Nest Ontario, New York 14 519 Arthur M. Schwartzst in LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
ATTACHMENT A
- 1. Replace Technical Specification pages 4.6-1 and 4.6-2 with the revised pages 4 '-1, 4.6-1a and 4.6-2.
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4.6 Emer enc Power S stem Periodic Tests A licabilit Applies to periodic testing and s'urveillance requirements of the emergency power system.
~Ob ective To verify that the emergency power system will respond promptly and properly when required.
The following tests and surveillance shall be performed as stated:
4.6.1 Diesel Generators Each diesel generator shall be demonstrated operable:
a~ Except during cold or refueling shutdown at least once per 31 days by:
- 1. Verifying the fuel level in the.day tank,
- 2. Verifying a minimum oil storage of 10,000 gallons is at the station,
- 3. Verifying the fuel transfer pump can be started and transfer fuel from the storage system to the day tank,
- 4. Verifying the diesel starts from normal standby conditions,
- 5. Verifying the generator is synchronized, loaded to at least 1950 kw but less than the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 2250 kw and operates for at least 60 minutes but less than 120 minutes,
- 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.
- b. The tests in specification 4.6.la will be performed prior to exceeding 5% power if the time since the last test exceeds 31 days.
C ~ At least once per 92 days by veri'fying that a sample of diesel fuel from the fuel storage tank is within the following limits:
water and sediment, 0.10 volume percent viscosity, SSU at 100oF 32 to 45 4.6-1 Proposed
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- d. At least once per 18 months dur'ing shutdown by:
- 1. Inspecting the diesel in accordance with the manufacturer's recommendations for this class of standby service,
- 2. Verifying the generator capability to reject a load of 295 KW without tripping,
- 3. Simulating a loss of offsite power in conjunction with a safety injection test signal and:
(a) Verifying de-energization of the emergency buses and load shedding from the emergency buses.
(b) Verifying the diesel starts from normal standby condition on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the automatically conneoted emergency loads with the following maximum breaker closure times after the initial starting signal
'or trains A and B not being exceeded A B Diesel plus Safety Injection Pump 20 sec 22 sec plus RHR Pump All breakers 40 sec 42 sec and operates for five minutes while its generator is
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loaded with emergency loads.
(c) Verifying that all diesel generator trips, except engine overspeed, low lube oil pressure, and overcrank, are automatically bypassed upon loss of voltage on the emergency bus and/or safety injection actuation signal.
4;6-la Proposed
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4.6.2 Station Batteries
- a. Every month the voltage of each cell (to the nearest 0.01 volt),
the specific gravity and temperature of a pilot cell in each battery shall be measured and recorded.
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- b. Every 3 months the, specific gravity of each cell, the tempera-ture reading of every fifth cell, the height of electrolyte, and the amount of water added shall be measured and recorded.
4.6-2 Proposed
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.Attachment B Technical Specification 4.6.1, diesel generator testing, now requires that the diesel generator '.be loaded to its nameplate rating (4.6.1.a) and that the electrical loads on the diesel generator not be increased beyond the long term rating of 1950kw (4.6.1.d).
The generator nameplate 'specifies 2500kVa and 80% power factor.
To remedy the inconsistency, the testing requirements for the diesel generator have been revised. In addition,'testing requirements have been expanded to include other components important to diesel generator operability. The Standard Technical Specifications published by the NRC have been used as guidance in preparation of the proposed Technical Specifications.
Operability of the diesel generators is assured by periodic
.testing on a 31 day interval. This includes assuring that at least 10,000 gallons of fuel oil are on site, as specified in FSAR Section 8.2.3 and checking the fuel oil level in the day fuel tank. Since the day tank provides fuel for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of diesel operation, the entire balance of the 10,000 gallon onsite supply need not be automatically available to each diesel. Operator action is acceptable to provide this fuel to the diesel. The fuel transfer pumps are tested. The diesel generator is loaded for at least 60 minutes to at least its continuous rating of 1950kw but not beyond its 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 2250kw. Finally, the diesel generatorbusses. is aligned to provide standby power to associated emergency By performing these tests, assurance is provided that, start, load, if operate required, the diesel generators would .accept and as assumed in the safety analyses.
The fuel oil is demonstrated to meet the manufacturer's recommended limits for viscosity, water and sediment at least once every 92 days. This will provide assurance of the acceptability of the diesel fuel.
At least once every 18 months, comprehensive testing will be performed during a shutdown. This includes testing that cannot be performed during normal plant operation. As in the present Technical Specifications, the diesel is inspected in accordance with the manu-facturer's instructions. Verification is obtained that the largest single emergency load, 295kw, can be rejected without tripping the diesel generator. The value of 295kw is based upon the 350 horse-power motor for a safety injection pump (see FSAR Table 8.2-1) . The specifications would continue to require testing the diesel generator by simulating a loss of offsite power in conjunction with a safety.
injection signal. Breaker closure times for loads are recorded and are required to meet acceptance criteria as established in the safety analyses.
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Each safeguards load which is automatically sequenced onto the diesel generator has its own individual timer which controls its loading. Because verification of the operability of the timer would require taking the entire train out of service or starting the entire train and because testing at refueling intervals in the past has not. disclosed unacceptable drift in the timer setpoints, it is proposed that timer testing be performed at refueling outages.
In addition, testing is performed to assure that generator trips are properly set. A more complete description og diesel generator trips may be found in Supplement 1 to Technical Supplement AcCoppanying Application for a Pull-Term Operating License, December 20; 1973'. (response to question 9) .
The Ginna design does not provide for full flow verification to demonstrate the magnitude of the automatically connected loads under simulated accident conditions. Pump's are supplied with small recirculation lines rather than full flow test. loops. Thus, con-firmatioq of acceptability'of diesel generator loadings has been provided through analyses. These analyses are summarized in Section 8.2.3 of the FSAR and in the discussion of Safety Guide 9 in the Technical Supplement Accompanying Application for a Full-Term Operating License.
By performing the proposed tests, assurance will be provided that the diesel generators will perform their required safety function if required.
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