ML18064A462

Proposed Tech Specs Pages 3-1b,3-1c & 3-2,deleting Item 3.1.11e & Associated Basis Inadvertently Restored by Amend 137

ML18064A462
Person / Time
Site:	Palisades
Issue date:	10/31/1994
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18064A461	List: ML18064A460 ML18064A462
References
NUDOCS 9411100248
Download: ML18064A462 (4)

Text

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ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 PALISADES TECHNICAL SPECIFICATIONS CORRECTED PAGES 3 Pages

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1 ~411100248 94l0-.,.1 ___ \

pDR ADOCK 05000255 I PDR

• 3.r PRIMARY cooul SYSTEM Applicability Applies to the operable status of the primary coolant system.

Objective To specify certain conditions of the primary coolant system which must be met to assure safe reactor operation.

Speci fi cations 3.1.1 Operable Components

a. At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or equal to 2810 gpm shall be in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during an emergency loss of coolant flow situation.

Under these circumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running.

b. Four primary coolant pumps shall be in operation whenever the reactor is operated above hot shutdown, with the following exception:

Before removi~g a pump from service, thermal power shall be reduced as specified in Table 2.3.1 and appropriate corrective action implemented. With one pump out of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four-pump operation) or be in hot shutdown (or below) with the reactor tripped (from the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Start-up (above hot shutdown) with less than four pumps is not permitted and power operation with less than three pumps is not permitted.

c. The measured four primari coolant pumps operating reactor vessel flow shall be 140.7 x 10 lb/hr or greater, when corrected to 532°F.

d. Both steam generators shall be capable of performing their heat transfer function whenever the average temperature of the primary coolant is above 300°F.

e. Deleted 3-lb Amendment No. 3-1-, ~' -l-18, -l-l-9, -!-34, 3-7, 161

~ 3.Ll. Operable Comlents (Continued.)

f. Nominal primary system operation pressure shall not exceed 2100 psi a.

g. The reactor inlet temperature (indicated) shall not exceed the value given by the following equation at steady state power operation:

Tinlet ~ 542.99 + .0580(P-2060) + O.OOOOl(P-2060)**2 + 1.125(W-138) -

0.0205(W-138)**2 Where: T*nlet = reactor inlet temperature in ° F

~ = nominal operating pressure in psia W = total recirculating mass flow in 106 lb/h corrected to the operating temperature cond it i ans.

When the ASI exceeds the limits specified in Figure 3.0, within 15 minutes, initiate corrective actions to restore the ASI to the acceptable region. Restore the ASI to acceptable values within one hour or be at less than 70% of rated power within the following two hours.

If the measured primary coolant system flow rate is greater than 150 M lbm/hr, the maximum inlet temperature shall be less than or equal to the T1nlet LCO at 150 Ml bm/hr.

3-lc Amendment No. 3-l, .§.!., 8&, -H+, -H-8, +/-34, 137

PRIMARY lo LANT SYSTEM (cont'd)

Basis (Cont'd)

The FSAR safety analysis was performed assuming four primary coolant pumps were operating for accidents that occur during reactor operation.

Therefore, reactor startup above hot shutdown is not permitted unless all four primary coolant pumps are operating. Operation with three primary coolant pumps is permitted for a limited time to allow the rest~rt of a stopped pump or for reactor internals vibration monitoring and testing.

Requiring the plant to be in hot shutdown with the reactor tripped from the C-06 panel, opening the 42-01 and 42-02 circuit breakers, assures an inadvertent rod bank withdrawal will not be initiated by the control room operator. Both steam generators are required to be operable whenever the temperature of the primary coolant is greater than the design temperature of the shutdown cooling system to assure a redundant heat removal system for the reactor.

The transient analyses were 6 performed assuming a vessel flow at hot zero power (532°F) of 140.7 x 10 lb/hr minus 6% to account for flow measurement uncertainty and core flow bypass. A DNB analysis was performed in a parametric fashion to determine the core inlet temperature as a function of pressure and flow for which the minimum DNBR is equal to the DNB correlation safety limit. This analysis includes the following uncertainties and allowances: 2% of rated power for power 3-2 Amendment No. -2{), .§.I-, 18, -l-3-1-, -l-34, 137