ML071410335

Technical Specification (Ts), Revised TS 3.7.8, Service Water (SW) System

ML071410335
Person / Time
Site:	Ginna
Issue date:	05/16/2007
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MD0686, TAC MD3118
Download: ML071410335 (3)

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. 102, 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. 102

SW System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water (SW) System I LCO 3.7.88 Four SW pumps and the SW loop header shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SW pump A.1 Restore SW pump to 14 days inoperable. OPERABLE status.

B. Two SW pumps B.1 Restore SW pump(s) to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. 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. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Three or more SW pumps D.1 or loop header inoperable. - NOTE -

Enter applicable conditions and Required Actions of LCO 3.7.7, "CCW System,"

for the component cooling water heat exchanger(s) made inoperable by SW.

Enter LCO 3.0.3. Immediately R.E. Ginna Nuclear Power Plant 3.7.8-1 Amendment 102

SW System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify screenhouse bay water level and temperature 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are within limits.

- NOTE -

SR 3.7.8.2 Isolation of SW flow to individual components does not render the SW loop header inoperable.

Verify each SW manual, power operated, and 31 days I automatic valve in the SW flow path and loop header that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.8.3 Verify all SW loop header cross-tie valves are locked 31 days in the correct position.

SR 3.7.8.4 Verify each SW automatic 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.

SR 3.7.8.5 Verify each SW pump starts automatically on an 24 months actual or simulated actuation signal.

R.E. Ginna Nuclear Power Plant 3.7.8-2 Amendment 102