ML073030386

Tech Spec Pages for Amendment 225 Regarding Nuclear Services Closed Cycle Cooling Water System

ML073030386
Person / Time
Site:	Crystal River
Issue date:	10/23/2007
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Bailey S, NRR/ADRO/DORL, 415-1321
Shared Package
ML072851381	List: ML073030386
References
TAC MD3227
Download: ML073030386 (2)

Text

of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

2.C.(1) Maximum Power Level Florida Power Corporation is authorized to operate the facility at a steady state reactor core power level not in excess of 2568 Megawatts (100 percent of rated core power level).

2. C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 225, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment 149. The Surveillance Requirements shall be successfully demonstrated prior to the time and condition specified below for each.

a) SR 3.3.8.2.b shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.

b) SR 3.3.11.2, Function 2, shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.

c) SR3.3.17.1, Functions 1, 2, 6, 10, 14, & 17 shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.

d) SR3.3.17.2, Function 10 shall be successfully demonstrated prior to entering MODE 3 on the first plant start-up following Refuel Outage 9.

e) SR 3.6.1.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

f) SR 3.7.12.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

g) SR 3.8.1.10 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

h) SR 3.8.3.3 shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.

Amendment No. 3. 41. 149. 205. 223 224, 225

SW SYSTEM LCO 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Nuclear Services Closed Cycle Cooling Water (SW) System LCO 3.7.7 The SW System shall be OPERABLE with:

a. Two OPERABLE emergency SW pumps; and

b. Three OPERABLE SW heat exchangers APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One emergency SW pump A.1 Restore SW system to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status B. One required SW heat B.1 Restore SW system to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> exchanger 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 not met. AND 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 /> Crystal River Unit 3 3.7-15 Amendment No. 225