Letter Sequence Other |
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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
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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
