ML031120008

Technical Specifications, Reduce Minimum Reactor Coolant System Flow

ML031120008
Person / Time
Site:	Saint Lucie
Issue date:	04/18/2003
From:	NRC/NRR/DLPM/LPD2
To:
Moroney B, NRR/DLPM, 415-3974
References
TAC MB6526
Download: ML031120008 (2)

Text

TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

9. Local Power Density - High(5) Trip setpoint adjusted to Tnp setpoint adjusted to Operating not exceed the limit lines not exceed the limit lines of Figures 2 2-1 and 2.2-2 of Figures 2.2-1 and 2 2-2.

10 Loss of Component Cooling Water > 636 gpm** > 636 gpm to Reactor Coolant Pumps - Low

11. Reactor Protection System Logic Not Applicable Not Applicable

12. Reactor Trip Breakers Not Applicable Not Applicable 13 Rate of Change of Power- High(4) < 2.49 decades per minute < 2.49 decades per minute

14. Reactor Coolant Flow - Low(1) > 95 4% of design Reactor > 94.9% of design Reactor Coolant flow with four Coolant flow with four pumps operating* pumps operating' 15 Loss of Load (Turbine) > 800 psig > 800 psig Hydraulic Fluid Pressure - Low(5)

• Design reactor coolant flow with four pumps operating is 355,000 gpm I

.* 10-minute time delay after relay actuation.

ST LUCIE - UNIT 2 2-5 Amendment No 8, 60, 13i

TABLE 3.2-2 DNB MARGIN LIMITS FOUR REACTOR COOLANT PUMPS PARAMETER OPERATING Cold Leg Temperature (Narrow Range) 535 0F* < T < 5490 F Pressurizer Pressure 2225 psia** < PPZR < 2350 psia*

Reactor Coolant Flow Rate > 355,000 gpm I AXIAL SHAPE INDEX COLR Figure 3.2-4

• Applicable only if power level > 70% RATED THERMAL POWER.

• • Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

ST. LUCIE - UNIT 2 3/4 2-15 Amendment No. 8, 82, 131