ML20140D709
| ML20140D709 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/14/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20140D705 | List: |
| References | |
| NUDOCS 9704240060 | |
| Download: ML20140D709 (2) | |
Text
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15.3 I_IMITING CONDITIONS FOR OPERATION 15.3.1 REACTOR COOLANT SYSTEM Aonlicability Applies to the operating status of the Reactor Coolant System.
e Ob_iective To specify those limiting conditions for operation of the Reactor Coolant System which must be met to ensure safe reactor operatin.
Snecification A.
OPERATIONAL COMPONENTS I
1.
Coolant Pumps
- 1 When the reactor is critical, =c:p: for :=::. 2: ! =: cne both reactor coolant pumps shall a.
be in operation.
(!)
Rece rr pc :: d " :c* 5: r. :: !ned en 3.5 e rated pr :::
- !=- MS 1
rene:cr ece!:n: pr.nps ar: i : epere:!ce (2)
!f:!Ser receter ace' -: in.np :== cperating, media: p;.er redwti "" '
initiated under ad ::!::ratiwemtre! = ne :=ar;:c reduce pc.e Y !=
han W.f::::d pc.:
(M) If one or.both reactor coolant pump (s) cease operating and pcu er E. greater San 3.5% af :::d pcuer,5": !:= San !0Y cra::d pcuer, the_ reactor shall be niaced in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.duide;.
"! c men :i mediately and ver#y Se rea;:cr trip 're:i :: ::: cpened * : one hour b.
When the reactor is subcritical and the average reactor coolant temperature is greater than 350*F, except for tests, at least one reactor coolant pump shall be in operation.
(1)
Both reactor coolant pumps may be deenergized provided:
a.
No operations are permitted that would cause dilution of the reactor coolant system boron concentration, b.
Core outlet temperature is maintained at least 10 F below saturation temperature, and The reactor trip breakers are open.
c.
At least one reactor coolant pump or residual heat removal system shall be in operation c.
when a reduction is made in the boron concentration of the reactor coolant.
2.
- One steam generator shall be operable whenever the average reactor coolant temperature is a.
above 350 F.
3.
Components Required for Redundant Decay Heat Removal Capability
- Reactor coolant temperature less than 350 F and greater than 140 F.
a.
(1)
At least two of the decay heat removal methods listed shall be operable.
(a)
Reactor Coolant Loop A, its associated steam generator and either reactor coolant pump (b)
Reactor Coolant Loop B, its associated steam generator and either reactor coolant pump
- Applicable only when one or more fuel assemblies are in the reactor vessel.
. Unit 1 - Amendment-46 15.3.1-1 Jrly 23, ""
Unit 2 - Amendment 4M 9704240060 970414 PDR ADOCK 05000266 P
Items 15.3.1.A.1.a.(-2-) permits an orderly reduction in power if a reactor coolant pump is lost during operation betwe= 3.5% =d at less than or equal to 50% of rated power.
Above 50% power, an automatic reactor trip will occur if either pump is lost. The power-to-flow ratio will be ma ntained equal to or less than 1.0, which ensures that the minimum DNB ratio increases at lower flow since the maximum enthalpy rise does not increase above its normal full-flow maximum value.*
Specification 15.3.1.A.3 provides limiting conditions for operation to ensure that redundancy in decay heat removal methods is provided. A single reactor coolant loop with its associated steam generator and a reactor coolant pump or a single residual heat removal loop provides sufficient heat removal capacity for removing the reactor core decay heat; however, single failure considerations require that at least two decay heat removal methods be available. Operability of a steam generator for decay heat removal includes two sources of water, water level indication in the j
steam generator, a vent path to atmosphere, and the Reactor Coolant System filled and vented so thermal convection cooling of the core is possible. If the steam generators are not available for t
decay heat removal, this Specification requires both residual heat removal loops to be operable unless the reactor system is in the refueling shutdown condition with the refueling cavity flooded and no operations in progress which could cause an increase in reactor decay heat load or a decrease in boron concentration. In this condition, the reactor vessel is essentially a fuel storage pool and removing a RHR loop from service provides conservative conditions should operability problems j
develop in the other RHR loop. Also, one residual heat removal loop may be temporarily out of s
service due to surveillance testing, calibration, or inspection requirements. The surveillance procedures follow administrative controls which allow for timely restoration of the residual heat removal loop to service ifrequired.
l Additionally, with reactor coolant temperature between 350 F and 140 F, all operating decay heat removal pumps (either reactor coolant pumps or residual heat removal pumps) are allowed to be deenergized for a short time (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) with the stipulation that boron dilution activities are not allowed and that core outlet temperature remain 10 F below saturation.
Unit 1 - Amendment No.4M S q W M 4cG4 Unit 2 - Amendment No.4M 15.3.1-3c