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Category:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML22234A1692022-08-22022 August 2022 R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML22052A0132022-02-21021 February 2022 Application to Revise R. E. Ginna Technical Specification 3.1.8, Physics Tests Exception - Mode 2 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML20353A1262021-03-11011 March 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20057E0912020-04-0303 April 2020 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method ML18213A3692018-11-13013 November 2018 Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML16358A4242017-02-0909 February 2017 R. E. Ginna Nuclear Power Plant - Issuance of Amendment to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML16236A0962016-08-26026 August 2016 R. E. Ginna - Correction Letter to License Amendment No. 122 Licence Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3 ML16125A4852016-06-28028 June 2016 R. E. Ginna Nuclear Power Plant - Issuance of Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3 ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel ML15271A1012015-11-23023 November 2015 Issuance of Amendment Regarding Transition to a Risk Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) ML15275A2762015-10-0202 October 2015 R.E. Ginna - Supplemental Information Regarding TSTF-425 License Amendment Request ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15120A2842015-04-30030 April 2015 Response to Request for Additional Information Regarding Proposed License Amendment to Revise Technical Specifications to Adopt TSTF-523 ML14232A3312014-08-21021 August 2014 Non-Proprietary, Correction to Amendment No. 116 Issued August 12, 2014, Revision to Technical Specification Section 3.6.5, 'Containment Air Temperature ML14232A1252014-08-12012 August 2014 R. E. Ginna Nuclear Power Plant - Redacted, Issuance of Amendment Revision to Technical Specification Section 3.6.5 Containment Air Temperature ML14091A3662014-04-0101 April 2014 Issuance of Amendment to Conform the Renewed Facility Operating License to Reflect the Direct Transfer of Operating Authority ML13197A3502013-07-18018 July 2013 Correction to Amendment Approving the Use of Alternate Control and Shutdown Rod Position Monitoring System ML11129A0132011-05-0303 May 2011 Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0920905382009-07-23023 July 2009 R. E. Ginna - License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0900607412008-12-19019 December 2008 R. E. Ginna - Application to Revise Technical Specification Limiting Conditions of Operation (Lcos) 3.3.2, 3.3.4, and 3.8.1 ML0823201612008-08-27027 August 2008 R. E. Ginna - Tech Spec Pages for Amendment 105 Control Room Envelope Habitability ML0804605042008-02-0808 February 2008 License Amendment Request: Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over Pressure Limits ML0727707352007-10-0101 October 2007 R. E. Ginna, Technical Specifications, Amendment Spent Fuel Pool Storage Capacity ML0714103352007-05-16016 May 2007 Technical Specification (Ts), Revised TS 3.7.8, Service Water (SW) System ML0708903712007-03-28028 March 2007 R. E. Ginna - Tech Spec Pages for Amendment 101 Technical Specification 3.5.1 Regarding Emergency Core Cooling System Accumulators ML0706702082007-03-0101 March 2007 R. E. 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Ginna, Tech Spec Pages for Amendment 97 Regarding 16.8 Percent Power Uprate ML0615300162006-05-31031 May 2006 Tech Spec Pages for Amendment 96 Regarding Revised Loss-of-Coolant Accident Analyses ML0612405632006-05-0404 May 2006 Corrected Tech Spec Page 5.6-3, to Amendment No. 94 Relaxed Axial Offset Control ML0612805492006-05-0101 May 2006 License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0608202122006-03-16016 March 2006 R. E. Ginna - Tech Spec Pages for Amendment 95 Main Feedwater Isolation Valves ML0532901022005-11-18018 November 2005 Application for Amendment to Facility Operating License Regarding the Testing Requirement for the Containment Spray Nozzles ML0531902132005-11-0707 November 2005 Application for Amendment to Facility Operating License Revising Technical Specification, Section 3.9.3. to Allow Refueling Operations with the Containment Equipment Hatch Open ML0519202452005-07-0707 July 2005 Technical Specification Pages Revision to Diesel Fuel Oil Requirements ML0513901662005-05-18018 May 2005 Technical Specification Page Modification of the Control Room Emergency Air Treatment System ML0512601812005-05-0505 May 2005 R. E. Ginna Nuclear Power Plant, Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0512602362005-04-29029 April 2005 R.E.Ginna - License Application Request Regarding Main Feedwater Isolation Valves ML0512602392005-04-29029 April 2005 License Amendment Request Regarding Revised Loss of Coolant Accident (LOCA) Analyses-Changes to Accumulator, Refueling Water Storage Rwst), and Administrative Control Technical Specifications ML0513003302005-04-29029 April 2005 License Amendment Request Regarding Adoption of Relaxed Axial Offset Control (RAOC) ML0510400672005-04-13013 April 2005 R. E. Ginna Tech Spec Pages for Amendment 89 Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports 2023-08-30
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-3-(b) Pursuant to the Act 6nd 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20, 1979), as supplemented February 20, 1980 and March 5, 1980;(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect;and is subject to the additional conditions specified below: (1) Maximum Power Level Ginna LLC is authorized to operate the facility at steady-state power levels up to a maximum of 1775 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, are hereby incorporated in the renewed license. The I licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection (a) The licensee shall implement and maintain in effect all fire protection features described in the licensee's submittals referenced in and as approved or modified by the NRC's Fire Protection Safety Evaluation (SE) dated February 14, 1979 and Amendment No. 99 3.6 3.6.6 LCO 3.6.1 CS, CRFC, and NaOH Systems 3.6.6 CONTAINMENT SYSTEMS Containment Spray (CS), Containment Recirculation Fan Cooler (CRFC), and NaOH Systems Two CS trains, four CRFC units, and the NaOH system shall be OPERABLE.-NOTE-In MODE 4, both CS pumps may be in pull-stop for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of interlock and valve testing of motor operated valves (MOVs) 857A, 857B, and 857C. Power may also be restored to MOVs 896A and 896B, and the valves placed in the closed position, for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the purpose of each test.APPLICABILITY:
MODES 1,2,3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CS train inoperable.
A.1 Restore CS train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.B. NaOH system inoperable.
B.1 Restore NaOH System to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.C.2 Be in MODE 5. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> D. One or two CRFC units D.1 Restore CRFC unit(s) to 7 days inoperable.
OPERABLE status.E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition D not AND met.E.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> R.E. Ginna Nuclear Power Plant'3.6.6-1 Amendment 99 CS, CRFC, and NaOH Systems 3.6.6 CONDITION REQUIRED ACTION COMPLETION TIME F. Two CS trains inoperable.
F.1 Enter LCO 3.0.3. Immediately OR Three or more CRFC units inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Perform SR 3.5.2.1 and SR 3.5.2.3 for valves 896A In accordance with and 896B. applicable SRs.SR 3.6.6.2 Verify each CS manual, power operated, and 31 days automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.SR 3.6.6.3 Verify each NaOH System manual, power operated, 31 days and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.SR 3.6.6.4 Operate each CRFC unit for > 15 minutes. 31 days SR 3.6.6.5 Verify cooling water flow through each CRFC unit. 31 days SR 3.6.6.6 Verify each CS pump's developed head at the flow In accordance with test point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.6.6.7 Verify NaOH System solution volume is > 3000 gal. 184 days SR 3.6.6.8 Verify NaOH System tank NaOH solution 184 days concentration is > 30% and < 35% by weight.SR 3.6.6.9 I-'erform required CRFC unit testing in accordance In accordance with with the VFTP. the VFTP SR 3.6.6.10 Verify each automatic CS valve in the flow path that is 24 months not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal.R.E. Ginna Nuclear Power Plant 3.6.6-2 Amendment 99 CS, CRFC, and NaOH Systems 3.6.6 SURVEILLANCE FREQUENCY SR 3.6.6.11 Verify each CS pump starts automatically on an actual 24 months or simulated actuation signal.SR 3.6.6.12 Verify each CRFC unit starts automatically on an 24 months actual or simulated actuation signal.SR 3.6.6.13 Verify each automatic NaOH System valve in the flow 24 months path that is not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal.SR 3.6.6.14 Verify spray additive flow through each eductor path. 5 years SR 3.6.6.15 Verify each spray nozzle is unobstructed.
Following maintenance which could result in nozzle blockage R.E. Ginna Nuclear Power Plant 3.6.6-3 Amendment 99