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:Safety Evaluation
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23073A3682023-03-16016 March 2023 Authorization and Safety Evaluation for Proposed Alternative I6R-10, Revision 0 Related to the Steam Generators, ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22094A1072022-06-22022 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 151 Adopt 10 CFR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22119A0942022-06-21021 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 150 Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21250A3822021-09-29029 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request I6R-06 Alternate Inspection for Reactor Vessel Internals ML21246A1062021-09-22022 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Alternative Request GR-03, Valve Position Verification Testing Extension Sixth 10-Year Inservice Testing Program Interval ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21175A0012021-07-27027 July 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 145 Regarding Technical Specifications Change to Make a One-Time Exception to the Steam Generator Tube Inspection Requirements ML21166A1682021-06-25025 June 2021 ML20353A1262021-03-11011 March 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20090D2912020-06-0202 June 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0071). Supersedes ML20056D559 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20057E0912020-04-0303 April 2020 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method ML20056D5592020-03-13013 March 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval ML20055F8862020-03-13013 March 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-01 for the Sixth 10-Year Inservice Inspection Interval ML19325D8242019-12-23023 December 2019 R. E. Ginna Nuclear Power Plant Issuance of Amendment No. 136 to Revise Technical Specification 5.5.15, Containment Leakage Rate Testing Program, to Extend Containment Integrated Leak Rate Test Frequency ML19318E0802019-12-0202 December 2019 R. E. Ginna Nuclear Power Plant - Safety Evaluation of Alternative Request SR-1 Related to Snubber Program Aligned with Sixth 10-Year Inservice Testing Interval Program ML19252A2462019-10-29029 October 2019 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 134 to Revise the Emergency Response Organization Staffing Requirements ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19205A4532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives PR-01 and PR-02 for Sixth 10-Year Inservice Testing Program ML19205A3532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives GR-01, VR-01, and VR-02 for the Sixth 10-Year Inservice Testing Program (EPID L-2018-LLR-0382; EPID L-2018-LLR-0383) ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19100A0042019-04-22022 April 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request ISI-18 Regarding Fifth 10-Year Inservice Inspection Program Interval ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18213A3692018-11-13013 November 2018 Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML18295A6302018-10-31031 October 2018 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 131 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF 547, Clarification of Rod Position Requirements ML18214A1762018-08-31031 August 2018 Issuance of Amendment No. 130, Revise Technical Specification Surveillance Requirement 3.8.4.3, DC (Direct Current) Sources - Modes 1, 2, 3, and 4 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18190A4722018-07-12012 July 2018 R.E Ginna - Correction to Amendment No. 127 Related to Request to Delete a Modification Associated with the Risk-Informed, Performance Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (CAC No. MF9948; EPID L-2017-LLA-0253) ML18137A6142018-06-26026 June 2018 Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes ML18114A0252018-06-25025 June 2018 Issuance of Amendment No. 127, Modify License Condition 2.C.(3) Related to Commitment Associated with Implementation of National Fire Protection Association Standard 805 (CAC MF9948; EPID L-2017-LLA-0253) 2023-08-30
[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
[Table view] |
Text
N IS) RII3UTIO'll FOR PART 50 DOC, MATERIAL.
(TEMPORARY FORM)
CONTROL NO:
FILE.
FROM. e oeu, am . e) y a tPATE OF DOC DATE REC'D LTR TWX RPT OTHER
'Washington, D.C.
LeBoeuf, Lamb, Leiby 8 MacRae 1-21-76 1-21-76 XXX TO: ORIG CC OTHER SENT LOCAL PDR XXX 1 Si ned 0 CLASS UNCLASS PROPINFO .INPUT NO CYS,BEC.'9 DOCKET NO:
XXX 50-244 DESCRIPTION: Ltr. notarized.1-.16-76:.. ENC LOS'~",~~
Letter trans the following.......
Proposed Amdt. to OL/Change to Tech. Specs:
Consisting of revisions to .Tech. Specs. with regards to changing the'surveillance g,equire-ments for intergrated leakage ra'te from the facility's containment.;...
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SAFETY FOR ACTION/INFC.'RMATION SAB 1-22-76 ASSMNE6 AD ASSIGN'FDBPANCH CHlEF ANCH CHlEF JECT MANAGER PROJECT MANAGER LIC ASST. W/ ACRS ASST. , , ACRS ACKXOVrLEOGEr)
INTERNA FILES SYSTEMS SAFETY PLANT SYSTEMS STTF SAFETY & ENVIRO ANALYSIS DR HEINEMAN TEDESCO DENTON HULLER
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SCHROEDER ENGlNEERlNG BENAROYA LAINAS IPPOLITO ENVlRO TEC11.
ERNST S1TE ANALYSIS VOLLMER MIPC MACCARY BALLARD BUNCH KNIGHT OPERATING REACTORS SPANGLER J. COLLINS PROJECT MANAGEMENT SIHWEI STELLO 1REGER BOYD ICKI SITi+ TECH.
P. COLLINS OPERATlNG TECH QA>MIieLe AT&I HOUSTON REACTOR SAFETY EISENHUT STEPP SALTZMAN PETERSON ROSS SHAO HULiIAN RUTBERG MELTZ NOVAK BAER HELTEHES ROSETOCZY S CHWENCER MISCELLANEOUS CHECK GRIMES ughes E>Ts r(N ALDIS TRBI 11 T ION PDR N.Y. NATIONAL LAB W/ CYS BROOKHAVEN NAT. LAB
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WASHINGTON PARTNCRS January 21, 1976 gag/P~
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Mr. Ben C. Rusche II S
/gag Director Office of Nuclear Reactor Regulation 4LIII Jg lRI IOCF U.S. Nuclear Regulatory Commission Washington, D.C 20555 Re: Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant Unit No. 1 Docke't No. '50'-'2'4'4',
Mr. Rusche:
'ear On October 28, 1975, Rochester Gas and Electric Corporation filed a request for exemption from certain provisions of Appendix J to 10 C.F.R. Part 50. The re-quest for exemption serves as a basis for this request for change to technical specifications.
More specifically, this letter transmits forty
,'(40) copies of a proposed change to Technical Specifications 4.4.1 and 4.4.2 to change the surveillance requirements for integrated leakage rate from the facility's containment.
Xn addition, three (3) signed originals and nineteen (19) copies of a document entitled "Application for Amendment to Operating License" together with a Certificate of Service showing service of these documents upon the per<<
sons listed therein is also enclosed.
Very truly yours, LeBoeuf, Lamb, Leiby S MacRae Attorneys for Rochester Gas and Electric Corporation 832
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMXSSION Xn the matter of )
) Docket No. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION )
(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 Nuclear Regulatory Commission, Rochester Gas and Electric Corporation (nRGGEn), holder of Provisional Operating License No. DPR-18, hereby requests that Technical Specifications 4.4.1 and 4.4.2 set forth in Appendix A to that license be amended as set forth in Attachment A to this application.
This amendment effects the surveillance requirements for certain plant equipment but does not authorize any change in the types or any increase in the amounts of normal plant effluents or any change in the authorized power level of the facility. A safety evaluation is set forth in Attachment B.
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 Ke3.th W. Amz.sh Executive Vice President Subscribed and sworn to before me on this )(,~ day of January, 1976
-- ~QQ Notary Public.c AALENE K. BARNEY ffOTAN'PUBLIC, State of H.Y., Monroe County gy CommIssion Expires March 30, 19.T(
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ATTACHMENT A Replace 4.4.1 with the following:
4.4.1.1 Definitions Pa (psig) is the containment vessel design pressure of 60 psig.
Pt (psig) is the containment vessel reduced test pressure for periodic testing.
Lt (weight percent/24 hours) is the maximum allowable leakage rates of the containment vessel test atmosphere at pressure Pt.
La (weight percent/24 hours) is the maximum allowable leakage rate of the containment vessel test. atmosphere at pressure Pa, 0.2%/24 hrs.
Lam and Ltm (weight percent/24 hours) are the total measured containment leakage rates of the containment vessel test atmosphere at pressures Pa and Pt respectively.
4.4.1.2 Pretest Re uirements
- a. A visual examination of the accessible interior and exterior surfaces of the containment structure shall be performed to uncover any evidence of structural deterioration which may affect either the containment structure integrity or leak-tightness. If there is evidence of structural deterioration, integrated leak rate testing shall not, be performed until appropriate corrective action has been taken. Except for repairs to correct structural deterioration, however, no repairs or adjustments shall be made during the period between the initiation of the inspection and the performance of the test.
- b. Closure of containment isolation valves shall be accom-plished by normal operation and without any preliminary exercising or adjustments.
- c. Venting Outside Containment Lines which penetrate the containment and which are open to the containment atmosphere as in (d), will be vented to the atmosphere outside of the containment. Where piping configurations outside containment exist such that the fluid in fluid carrying lines does not drain to expose the isolation valves to the atmosphere by opening existing, vents and drains, the fluid will be left in the lines.
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D. Venting Xnside Containment Portions of the fluid systems that are part of the reactor coolant pressure boundary and are open directly to the containment atmosphere under post-accident con-ditions and become an extension of the boundary of the containment will be opened or vented to the containment atmosphe e prior to and during the test. Portions of closed systems inside containment that penetrate con-.
ta'nment and that also pass inside the primary shield wall near the broken leg, and which are postulated to rupture as a result of a loss of coolant accident con-sistent, with the containment integrity analysis of section 14.3.4 of the FSAR, will be vented to containment atmosphere.
Where check valves or piping configurations exist between the primary shield wall and the containment penetration or in places where damage to the piping system is not postulated to occur as a result, of a LOCA such that fluid seals are formed as a result of normal operation and containment isolation, the fluid may, be left undisturbed.
That is, those portions of systems not postulated to rupture as the result of a LOCA need not be drained unless they drain unaided to the postulated breaks in the systems.
- e. Xsolation Valves Where two isolation valves exist in a single line which are e'ther check valves, or valves capable of automatic closure, or a combination thereof, no attempt need be made to vent to atmosphere from a point between the valves.
4.4.1.3 Conduct of Tests
- a. All integrated leak rate tests shall be conducted in accordance with the provisions of American National Standard N45.4-1972, Leakage Rate Testing of Containment Structures for Nuclear Reactors, March 16, 1972.
- b. The accuracy of each integrated leak rate test shall be verified by a supplemental test which confirms the accuracy of the test instrumentation and calculational methods by determining a leak rate which is within 0.25Lt of the test result,. Xf results are not within 0.25Lt the reason shall be determined, corrective action taken and a successful supplemental test performed.
- c. Xntegrated leak rate tests shall be conducted at an initial pressure (beginning of test} Pt.> 35 psig.
- d. If during the test, including the supplemental test, potentially excessive leakage paths are identified which will interfere with satisfactory completion of the test, or which result in the test not meeting the acceptance criteria, the test shall be terminated and the leakage through such paths shall be measured using local leakage testing methods. Repairs and/or adjustments to equipment shall be made and an integrated leak rate test performed.
4.4.1.4 Acce tance Criteria
- a. The leakage rate Ltm shall be less than 0.75 Lt.
- b. Lt shall be determined as Lt=La f Pt ) 1/2
( Pa I 4.4.1.5 Test Pre uenc
- a. A set of 3 integrated leak rate tests shall be performed at approximately equal intervals during each 10 year service period. The third test of each set shall be conducted when the plant is shut down for the 10-year plant inservice inspections.
- b. If any test fails to meet the acceptance criteria of 4.4.1.4.a the test schedule for subsequent regularly scheduled inservice tests shall be submitted to the Commission for review and approval.
- c. If two consecutive tests fail to meet the acceptance criteria of 4.4.1.4a, a retest shall be performed at each refueling shutdown or approximately every 18 months, whichever comes first, until two consecutive tests meet the acceptance criteria of 4.4.1.4a, after which time the retest schedule of 4.4.1.5a may be resumed.
4.4.1.6 Additional Re uirements
- a. A summary technical report shall be submitted to the Commission after the conduct of each integrated leak rate test. Information on any valve closure malfunction or valve leakage that requires corrective action before the test, shall be included in the report.
Delete 4.4.2.1.b Renumber 4.4.2.l.c as 4.4.2.l.b Replace 4.4.2.2 with the following:
4.4.2.4 Acce tance Criterion The total leakage from all penetrations and isolation valves shall not exceed 0.60La.
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.Replace 4.4.2.3.a h the, following:
- a. If at any time it is determined that the total leakage from all penetrations and isolation valves exceeds 0.60La, repairs shall be initiated immediately.
Replace 4.4.2.4 with the following:
4.4.2.4 Test Fre uenc
- a. Except as specified in b. and c. below, individual, penetrations and containment isolation valves shall be tested during each reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years.
- b. The containment equipment hatch and fuel transfer tube shall be tested at each refueling shutdown or after each use, if that. be sooner.
- c. The containment air locks shall be tested at intervals of no more than 6 months by pressurizing the space between the air lock doors. In addition, following opening of the air lock door during the interval, a test shall be performed by pressurizing between the dual seals of each door opened, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the opening, unless the reactor was in the cold shutdown condition at the time of the opening or has been subsequently brought to the cold shutdown condition. A test shall also be performed by pressurizing between the dual seals of each door within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of leaving the cold shutdown condition unless the doors have not been opened since the last test performed either by pressurizing the space between the air lock doors or by pressurizing between the dual door seals.
Replace pages 4.4.10 and 4.4.11 of the bases for specification 4.4 with the following:
The specification also allows for possible deterioration of the leakage rate between tests, by requiring that the total measured leakage rate be only 75% of the maximum allowable leakage rate.
The duration and methods for the integrated leakage rate test established by ANSI N45.4-1972 provide a minimum level of accuracy and allow for daily cyclic variation in temperature and thermal radiation. The frequency of the integrated leakage rate test is keyed to the refueling schedule for the reactor, because these tests can best be performed during refueling shutdowns. Re-fueling shutdowns are scheduled at approximately 1 year intervals.
The specified frequency of integrated leakage rate tests is based on three major considerations. First is the low probability of leaks in the liner, because of (a) the use of weld channels to test the. leaktightness of the welds during erection, (b) conformance of the complete
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containment to a 0.1% per day leak rate at 60 psig during preoperational testing, and (c) absence of any significant stresses in the liner during reactor operation. Second is the more frequent testing, at the full accident pressure, of those portions of the containment envelope that. are most likely to develop leaks during reactor operation (penetrations and isolation valves) and the low value (0.60 La) of the total leakage that is specified as acceptable from penetrations and isolation valves. Third is the tendon stress surveillance program, which provides assurance that an important part of the structural integrity of the containment is maintained.
The basis for specification of a total leakage of 0.60 La from penetrations and isolation valves is that only a portion of the allowable integrated leakage rate should be from those sources in order to provide assurance that the inte-grated leakage rate would remain within the specified limits during the intervals between integrated leakage rate tests.
Because most leakage during an integrated leak rate test occurs through penetrations and isolation valves, and because for most penetrations and isolation valves a smaller leakage rate would result from an integrated leak test than from a local test, adequate assurance of maintaining the integrated leakage rate within the specified limits is provided. The limiting leakage rates from the Recirculation Heat Removal Systems are judgment values based primarily on assuring that the components could operate without mechanical failure for a period on the order of 200 days after a design basis accident.
ATTACHMENT B Safet Evaluation The proposed changes to the technical specifications provide a conservative method of assuring that the leakage rate from the containment under accident conditions will remain within the speci-fied limits for the following reasons.
Those lines postulated to be broken by a loss of coolant accident, as given in the containment integrity analysis, will be vented both inside and outside containment. Thus the full differ-ential pressure will be applied across the isolation valve penetra-tion for all these lines even though all of these lines may not be open to containment atmosphere under accident conditions or may be part of closed systems outside containment.
Even though no vent. need be established between containment isolation valves during the test, this condition duplicates the post accident condition. The possibility that an isolation valve may fail to close is considered by performing the integrated leak test after closing the isolation valves by normal operation and without any preliminary exercising or adjustment. Periodic local leakage testing of the isolation valves assures that the valves are operable.
Conduct of the integrated leak rate test in accordance with ANSX N45.4-1972 will assure that the test results are valid.
An appropriate factor is to be applied to reduce criterion for reduced pressure testing. Although it isthedifficult acceptance to establish the relationship between leakage rates at different test pressures for a specific containment, mass flow through orifices will generally behave as a function of the square root of the differ-ential pressure. Thus, in the absence of extensive test data, the square root relationship is believed to be valid and will reduce the maximum allowable leakage rate by an appropriate amount for reduced pressure testing.
Testing personnel air lock doors by pressurizing the space between the doors at least once during each 6 month interval will preclude structural deterioration or wear from causing excessive leakage. The proposed method of testing personnel air lock doors within the six month intervals after an opening of a door will adequately ensure the integrity of the doors by detecting damage to the seals which may have resulted during the opening of the air lock. Testing the air locks by pressurizing between the seals will require approximately 1S minutes whereas testing by pressurizing the entire access hatch will require approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. By not inhibiting entry and inspections inside the containment, if they are required, the procedure tends to augment the safe operation of the plant.
The total leakage from penetrations and isolation valves during local leakage tests are limited to 0.60 La. This will pro-vide adequate assurance of maintaining the integrated leakage rate within the specified limits because most leakage during an inte-grated leak rate test occurs through penetrations and isolation valves and because for most penetrations and isolation valves a smaller leakage rate would result from an integrated leak test than from a local test.
The maximum allowable leakage rate at 60 psig has previously been shown to result in offsite doses, under postulated accident conditions, well within the requirements of 10 CFR Part 100.
Thus the test methods and procedures to be applied to meet the requirements of Appendix J to 10 CFR Part 50 will result. in a valid test to determine the integrity of the reactor containment and will provide assurance that under accident conditions the leakage rate from the containment will remain within the specified limits.
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSXON dANR4 jg)gw-
~Ay W In the Matter of )
)
ROCHESTER GAS AND ELECTRXC ) Docket. No. 50-244 CORPORATION (R. E. Ginna )
Nuclear Power Plant, )
Unit No. 1) )
CERTXFICATE OF SERVICE I hereby certify that X have served a document entitled "Application for Amendment to Operating License" by mailing copies thereof first, class, postage prepaid, to each of the following persons this 21st day of January, 1976.
Chairman, Atomic Safety C. John Clemente, Esq.
and Licensing Board Panel New York State Department U.S. Nuclear Regulatory of Commerce Commission 99 Washington Avenue Washington, D.C. 20555 Albany, New York 12210 Atomic Safety and Licensing L. Dow Davis, IV, Esq.
Appeal 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 Mr. Michael Slade 1250 Crown Point Drive Edward Luton, Esq.
Webster, New York 14580 Atomic Safety and Licensing Board Panel Warren B. Rosenbaum, Esq. U,S. Nuclear Regulatory One Main Street East Commission 707 Wilder Building Washington, D.C. 20555 Rochester, New York 14614
~
Dr. Emmeth A. Luebke Mr. Robert N. Pinkney Atomic Safety and Licensing Supervisor, Town of Ontario Board Panel 107 Ridge Road West U.S. Nuclear Regulatory Ontario, New York 14519 Commission Washington, D.C. 20555 Dr. A. Dixon Callihan Union Carbide Corporation P. O. Box Y.
Oak Ridge, Tennessee 37830 H pe M. Babcock LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation