ML20080E351
| ML20080E351 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/10/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080E354 | List: |
| References | |
| NUDOCS 9501130079 | |
| Download: ML20080E351 (2) | |
Text
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3.1.1 Doerable Components (Continued) l l
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4 i
i f.
Nominal primary system operation pressure shall not exceed 2100 l
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psia.
g.
The reactor inlet temperature (indicated) shall not exceed the j
value given by the following equation at steady state power operation:
T,,i,, s 542.99 +.0580(P-2060) + 0.00001(P-2060)**2 + 1.125(W-138) -
O.0205(W-138)**2 Where: TIi.,-reactorinlettemperaturein'F
= nominal operating pressure in psia W
= total recirculating mass flow in 10' lb/h i
corrected to the operating temperature conditions.
l 1
When the ASI exceeds the limits specified in Figure 3.0, within 15 minutes, initiate corrective actions to restore the ASI to the
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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 lbnVhr, the maximum inlet temperature shall be less than or equal to the T,,i,, LC0 at 150 M lbnVhr.
i 3-Ic Amendment No. M, H, SS, M 7, +14,- M 4, 137 Corrected January 10, 1995 9501130079 950110 PDR ADOCK 05000255 P
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3.1 PRIMARY COOLANT SYSTEM (c:nt'd)
I Basis (Cont'd)
I The FSAR safety analysis was performed assuming four primary coolant i
pumps were operating for accidents that occur during reacter 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 pemitted for a limited time to allow the restart 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 i
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.
l The transient analyses were' 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. 44, H, H e, 4 M, M 4, 137 i
Corrected January 10, 1995
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