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Category:Technical Specifications
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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
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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
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and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150
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Response to Request for Additional Information Regarding Proposed License Amendment to Revise Technical Specifications to Adopt TSTF-523
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R. E. Ginna - License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)
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R. E. Ginna, Tech Spec Pages for Amendment 100 Regarding Steam Generator Tube Integrity Technical Specifications
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License Amendment Request: Change to Technical Specification 3.7.8, Service Water (SW) from an Electrical Train Based on a Pump Based Specification
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License Page 3, Technical Specifications Section 3.6.6
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R. E. Ginna, Tech Spec Pages for Amendment 97 Regarding 16.8 Percent Power Uprate
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Tech Spec Pages for Amendment 96 Regarding Revised Loss-of-Coolant Accident Analyses
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License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
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R. E. Ginna - Tech Spec Pages for Amendment 95 Main Feedwater Isolation Valves
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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
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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
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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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(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
CS, CRFC, and NaOH Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray (CS), Containment Recirculation Fan Cooler (CRFC), and NaOH Systems LCO 3.6.1 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
