ML20065H723
| ML20065H723 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/30/1982 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20065H692 | List: |
| References | |
| TAC-48929, TAC-48930, NUDOCS 8210050231 | |
| Download: ML20065H723 (3) | |
Text
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3.
Pressuriser Safsty Valve 3 a.
At least one pressuriser safety valve shall be operable whenever the reactor head is on the vessel.
b.
Both pressuriser safety valves shall be operable whenever the reactor is critical.
4.
Pressuriser Power Operated Relief Valves (PORV) and PORV Block Valves a.
Two PORVs and their associated block valves shall be operable.
1.
If a PORV is inoperable due to leakage in excess of that allowed in specification 15.3.1.D, the PORV shall be restored to an operable condPion within one hour or the associated block valve shall be closed.
2.
If a PORV is inoperable due to a channel functional test failure, the associated PORV control switch shall be placed in the closed position or the associated block valve shall be closed within one hour.
3.
If a PORV block valve is inoperable, the block valve shall be restored to an operable condition within one hour or the block valve shall be clor,ed with power removed from the block valve, otherwise the unit shall be shut down and in l
hot shutdown within the next six hours.
l 5.
The pressurizer shall be operable with at least 100 EM of pressurizer heaters available and a water level greater than lot and less than 954 during steady-state power operation. At least one bank of pressurizer heaters shall be supplied by an emergency bus power supply.
Basis:
When the boron concentration of the reactor cioolant system is to be reduced, the process must be uniform to prevent sudden reactivity changes in the reactor. Mixing of the reactor coolant. will be sufficient to maintain a m iform boron concentration if at least one reactor coolant pump or one residual heat removal pep is running while the change is taking place. The residual heat removal pimp will circulate the primary system volme in l
,y.- h tely one half hour. The pressurizer is of little concern 15.3.1-2 s
h0h[0 P
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a
TABLE 15.3.5-5 INSTRIMENT OPERATING CONDITIONS FO'3 INDICATIONS 1
2 3
MINIMtM NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS CHANNELS CHANNEL OF COLUtel 2 CANNOT BE MET NO.
FUNCTIONAL UNIT l
1.
PORY Position Indicator 1/ Valve 1/ Valve If the operability of the PORY position indicator cannot be restored within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> place the l
associated PORV control switch in the closed position or shut the associated PORV Block Valve.
2.
PORV Block Valve Position 1/ Valve 1/ Valve If the operability of the POPV Block Valve Position Indicator cannot be restored within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, l
Indicator shut and verify the Block Valve shut by direct observation or declare the Block Valve inoperable.
l 3.
Safet'y Valve Position Indicator 1/ Valva 1/ Valve If the operability of the Safety Valve Position Indicator cannot be restored within seven days, be in at least Not Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
.I 4.
Reactor coolant System Subcooling 1
1 If the operability of a subcooling monitor cannot be restored or a backup sonitor made functional within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 1
If the operability of the auxiliary feedwater 5.
Auxiliary Feedwater Flow Rate
- flow rate indicator cannot be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
6.
Control Rod Misalignment as Monitored 1
1 Ing individual rod positions once/hr., after a load change '
t or after >30 inches of control by On-Line Cosputer rod motion.
l
- Applies to precently installed combination of auxiliary feedwater pusp discharge flow indicators and auxiliary feedwa flow to steam generator indicators.
l
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i e
4
i 15.5.4 FUEL STORAGE Applicability F
2 Applies to the capacity and storage arrays of new and spent fuel.
l f
objective To define those aspects of fuel storage relating to prevention of criticality in fuel storage areas.
Specification 1.
The new fuel storage and spent fuel pool structures are designed to l
i i
1' withstand the anticipated earthquake loadings as Class I structures.
t t
The spent fuel pool has a stainless steel liner to ensure against j
4 loss of water.
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2.
The new and spent fuel storage racks are designed so that it is impossible to store assemblies in other than the prescribed storage locations. The fuel is stored vertically in an array with sufficient i
i center-to-center distance between assemblies to assure Keff <0.95 with i
4 l
{
the storage pool filled with unborated water and with the fuel loading 4
in the assemblies limited to 44.8 grams of U-235 per axial centimeter of fuel assembly. An inspection area shall allow rotation of fuel l
l assemblies for visual inspection, but shall not be used for storage.
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i l
3.
The spent fuel storage pool shall be filled with borated water at a i
i concentration of at least 1800 p;mi boron whenever there are spent I
i fuel assemblies in the storage pool.
4.
Except for the two storage locations adjacent to the designated
[
i slot for the spent fuel storage rack neutron absorbing material surveil-
[
f lance specimen irradiation, spent fuel assembly storage locations i
issnediately adjacent to the spent fuel pool perimeter or divider walls shall not be occupied by fuel assemblies which have been subcritical
~
t for less than one year.
f i
References:
FSAR Section 9.3 15.5.4-1
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