Letter Sequence Other |
|---|
|
|
MONTHYEARML0624201472006-08-31031 August 2006
R. E. Ginna Nuclear Power Plant, RAI Regarding Test Frequency for Accumulator Boron Concentration,
Project stage: RAI
ML0627802212006-09-29029 September 2006
License Amendment Request: Change to Technical Specification 3.7.8, Service Water (SW) from an Electrical Train Based on a Pump Based Specification
Project stage: Request
ML0630300272006-10-24024 October 2006
R. E. Ginna - Response to Request for Information License Amendment Request: Emergency Core Cooling System (ECCS) Accumulator Boron Concentration Verification Frequency
Project stage: Response to RAI
ML0634800852006-12-0707 December 2006
Addendum to September 29, 2006 Submittal Change to Technical Specification 3.7.8 Service Water (SW) from an Electrical Train Based to a Pump Based Specification
Project stage: Request
ML0633900512006-12-13013 December 2006
Request for Additional Information, Regarding Service Water Pump Operability Requirements,
Project stage: RAI
ML0704706442007-02-12012 February 2007
R. E. Ginna - Response to Request for Additional Information and Revised Mark-Up Regarding Service Water Pump Operability Requirements
Project stage: Response to RAI
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
Project stage: Other
ML0706505352007-03-28028 March 2007
R. E. Ginna - License Amendment 101 Technical Specification 3.5.1 Regarding Emergency Core Cooling System Accumulators
Project stage: Approval
ML0710900602007-05-0808 May 2007
Correction Letter to Amendment No. 101 Technical Specification 3.5.1 Emergency Core Cooling System Accumulators
Project stage: Acceptance Review
ML0714103352007-05-16016 May 2007
Technical Specification (Ts), Revised TS 3.7.8, Service Water (SW) System
Project stage: Other
ML0710902382007-05-16016 May 2007
License Amendment, Revised Technical Specification 3.7.8 Regarding Service Water System Pumps
Project stage: Acceptance Review
2006-09-29
[Table View] |
Similar Documents at Ginna |
|---|
Category:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023
R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications
ML22234A1692022-08-22022 August 2022
R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
ML22090A0862022-04-29029 April 2022
Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position
RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022
Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V
ML22052A0132022-02-21021 February 2022
Application to Revise R. E. Ginna Technical Specification 3.1.8, Physics Tests Exception - Mode 2
ML21347A0382022-01-13013 January 2022
Issuance of Amendments to Revise Reactor Coolant Leakage Requirements
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021
Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML20353A1262021-03-11011 March 2021
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation
ML20167A0072020-09-11011 September 2020
R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues
ML20057E0912020-04-0303 April 2020
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method
ML18213A3692018-11-13013 November 2018
Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation
ML16358A4242017-02-0909 February 2017
R. E. Ginna Nuclear Power Plant - Issuance of Amendment to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML16236A0962016-08-26026 August 2016
R. E. Ginna - Correction Letter to License Amendment No. 122 Licence Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3
ML16125A4852016-06-28028 June 2016
R. E. Ginna Nuclear Power Plant - Issuance of Amendment Request to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program - Adoption of TSTF-425, Revision 3
ML15352A1642016-03-17017 March 2016
Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel
ML15271A1012015-11-23023 November 2015
Issuance of Amendment Regarding Transition to a Risk Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c)
ML15275A2762015-10-0202 October 2015
R.E. Ginna - Supplemental Information Regarding TSTF-425 License Amendment Request
ML15223B2502015-08-14014 August 2015
and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150
ML15161A3802015-07-30030 July 2015
R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409)
ML15120A2842015-04-30030 April 2015
Response to Request for Additional Information Regarding Proposed License Amendment to Revise Technical Specifications to Adopt TSTF-523
ML14232A3312014-08-21021 August 2014
Non-Proprietary, Correction to Amendment No. 116 Issued August 12, 2014, Revision to Technical Specification Section 3.6.5, 'Containment Air Temperature
ML14232A1252014-08-12012 August 2014
R. E. Ginna Nuclear Power Plant - Redacted, Issuance of Amendment Revision to Technical Specification Section 3.6.5 Containment Air Temperature
ML14091A3662014-04-0101 April 2014
Issuance of Amendment to Conform the Renewed Facility Operating License to Reflect the Direct Transfer of Operating Authority
ML13197A3502013-07-18018 July 2013
Correction to Amendment Approving the Use of Alternate Control and Shutdown Rod Position Monitoring System
ML11129A0132011-05-0303 May 2011
Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)
ML0920905382009-07-23023 July 2009
R. E. Ginna - License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)
ML0900607412008-12-19019 December 2008
R. E. Ginna - Application to Revise Technical Specification Limiting Conditions of Operation (Lcos) 3.3.2, 3.3.4, and 3.8.1
ML0823201612008-08-27027 August 2008
R. E. Ginna - Tech Spec Pages for Amendment 105 Control Room Envelope Habitability
ML0804605042008-02-0808 February 2008
License Amendment Request: Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over Pressure Limits
ML0727707352007-10-0101 October 2007
R. E. Ginna, Technical Specifications, Amendment Spent Fuel Pool Storage Capacity
ML0714103352007-05-16016 May 2007
Technical Specification (Ts), Revised TS 3.7.8, Service Water (SW) System
ML0708903712007-03-28028 March 2007
R. E. Ginna - Tech Spec Pages for Amendment 101 Technical Specification 3.5.1 Regarding Emergency Core Cooling System Accumulators
ML0706702082007-03-0101 March 2007
R. E. Ginna, Tech Spec Pages for Amendment 100 Regarding Steam Generator Tube Integrity Technical Specifications
ML0627802212006-09-29029 September 2006
License Amendment Request: Change to Technical Specification 3.7.8, Service Water (SW) from an Electrical Train Based on a Pump Based Specification
ML0621405252006-07-31031 July 2006
License Page 3, Technical Specifications Section 3.6.6
ML0620903672006-07-26026 July 2006
Technical Specifications, Revises TS 3.9.3, Containment Penetrations, to Allow an Emergency Egress Door, Access Door, or Roll Up Door, as Associated with the Equipment Hatch Penetration, to Be Open, But Capable of Being Closed
ML0619205942006-07-11011 July 2006
R. E. Ginna, Tech Spec Pages for Amendment 97 Regarding 16.8 Percent Power Uprate
ML0615300162006-05-31031 May 2006
Tech Spec Pages for Amendment 96 Regarding Revised Loss-of-Coolant Accident Analyses
ML0612405632006-05-0404 May 2006
Corrected Tech Spec Page 5.6-3, to Amendment No. 94 Relaxed Axial Offset Control
ML0612805492006-05-0101 May 2006
License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
ML0608202122006-03-16016 March 2006
R. E. Ginna - Tech Spec Pages for Amendment 95 Main Feedwater Isolation Valves
ML0532901022005-11-18018 November 2005
Application for Amendment to Facility Operating License Regarding the Testing Requirement for the Containment Spray Nozzles
ML0531902132005-11-0707 November 2005
Application for Amendment to Facility Operating License Revising Technical Specification, Section 3.9.3. to Allow Refueling Operations with the Containment Equipment Hatch Open
ML0519202452005-07-0707 July 2005
Technical Specification Pages Revision to Diesel Fuel Oil Requirements
ML0513901662005-05-18018 May 2005
Technical Specification Page Modification of the Control Room Emergency Air Treatment System
ML0512601812005-05-0505 May 2005
R. E. Ginna Nuclear Power Plant, Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process
ML0512602362005-04-29029 April 2005
R.E.Ginna - License Application Request Regarding Main Feedwater Isolation Valves
ML0512602392005-04-29029 April 2005
License Amendment Request Regarding Revised Loss of Coolant Accident (LOCA) Analyses-Changes to Accumulator, Refueling Water Storage Rwst), and Administrative Control Technical Specifications
ML0513003302005-04-29029 April 2005
License Amendment Request Regarding Adoption of Relaxed Axial Offset Control (RAOC)
ML0510400672005-04-13013 April 2005
R. E. Ginna Tech Spec Pages for Amendment 89 Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports
2023-08-30
[Table view] |
Text
(b) Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20, 1979) as supplemented February 20, 1980 and March 5, 1980; (3) 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. 101, are hereby incorporated in the renewed license. The 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- 101
Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Two ECCS accumulators shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 with pressurizer pressure > 1600 psig.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to boron concentration to within concentration not within limits.
limits.
B. One accumulator B.1 Restore accumulator to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable for reasons OPERABLE status.
other than Condition A.
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 Reduce pressurizer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> pressure to < 1600 psig.
D. Two accumulators D.1 Enter LCO 3.0.3. Immediately inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator motor operated isolation 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> valve is fully open.
SR 3.5.1.2 Verify borated water volume in each accumulator is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
> 1090 cubic feet (24%) and < 1140 cubic feet (83%).
R.E. Ginna Nuclear Power Plant 3.5.1-1 Amendment 101
Accumulators 3.5.1 SURVEILLANCE FREQUENCY SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
> 700 psig and <_790 psig.
I SR 3.5.1.4 Verify boron concentration in each accumulator is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (by
> 2550 ppm and < 3050 ppm. inleakage monitoring)
AND I 6 months (by sample)
SR 3.5.1.5 Verify power is removed from each accumulator 31 days motor operated isolation valve operator when pressurizer pressure is > 1600 psig.
R.E. Ginna Nuclear Power Plant 3.5.1-2 Amendment 101
