ML20064K305
| ML20064K305 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/11/1994 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20064K302 | List: |
| References | |
| NUDOCS 9403230063 | |
| Download: ML20064K305 (4) | |
Text
.
Unit 2 PBAPS NOTES FOR TABLE 3.1.1 1.
Thero shall be two operable or tripped trip systems for each function.
If the minimum number of operable sensor channels for a trip system cannot be mot, the affected trip system shall be placed in the safe (tripped) condition, or the appropriate actions listed below shall be taken.
A.
Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
B.
Reduce power level to IRM range and place mode switch in the start up position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30% rated.
2.
Permissible to bypass, in refuel and shutdown positions of the reactor mode switch.
3.
Deleted.
4.
Bypassed when reactor thermal power is less than 30% of rated,
as indicated by turbine first stage pressure.
5.
IRMs are bypassed when APRMs are onseale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
7.
When the reactor is suberitical and the reactor water temperature is less than 212 degrees F, only the following trip functions need to be operable.
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge instrument volume high level 8.
Not required to be operable when primary containment integrity is not required.
9.
Not required to be operable when the reactor pressure vessel head is not bolted to the vessel. 9403230063 940311 PDR ADOCK 05000277 P
PDR m
l Unit 3 PBAPS l
NOTES FOR TABLE 3.1.1 1.
There shall be two operable or tripped trip systems for each function.
If the minimum number of operable sensor channels for a trip system cannot be met, the affected trip system shall be placed 'n the safe (tripped) condition, or the t
approp.tiate actions listed below shall be taken.
A.
Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
B.
Reduce power level to IRM range and place mode switch in the start up position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Re. duce power to less than 30% rated.
2.
Permissible to bypass, in refuel and shutdown positions of the reactor modo switch.
3.
Deleted.
4.
Bypassed when reactor thermal power is less than 30% of rated as indicated by turbine first stage pressure.
5.
IRMs are bypassed when APRMs are onseale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
7.
When the reactor is suberitical and the reactor water temperature is less than 212 degrees F, only the following trip functions need to be operable.
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge instrument volume high level 8.
Not required to be operable when primary containment integrity is not required.
j 9.
Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.
l
~ Unit '-3 '
TABLE 3.2.F fCont'd1 - SURVEILLANCE'INSTRUMENTATIOil Minimum No.
of Operable Type Instrument Indication Item Channels Parameter Instrument and Range Action
- 11 2
Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.
(10)(11)
Water Level (wide range) 12 1
Control Rod Position N/A 28 Volt Indicating )
Lights
)
(1)(2)(3)(4)-
)
13 1
Neutron Monitoring N/A SRM, IRM, LPRM
)
0-100%
}
14 1
Safety-Relief Valve POAM-2(3)-2-71A-L Acoustic or (5)
Position Indication TE-2(3)-2-113A-L Thermocouple 15 2
Drywell High RR-8(9)103A, B Recorder (7)
,' ;j Range Radiation 1-1E(+8) R/hr Monitors y.
16 1
Main Stack High Range RR-0-17-051 Recorder (7)
Radiation Monitor 10 to 1011 cp3 5
(Log scale) 17 1
Reactor Building Roof
-RR-2979 (Unit 2)
Recorder (7)
Vent High Range Radiation -
RR-3979 (Unit 3) 10 to 1013 7
CPM Monitor (Log Scale) 18 2'
Drywell Hydrogen 3AC872, 3BC872 Analyzer and Recorder (1)(2)(3)
Concentration Analyzer XR-90411A, XR-90411B 0-30% volume and Monitor
- Notes for1 Table 3.2.F appear on pages 78 and 78a.
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PBAPS-Unit 3 3.10 BASES A.
Refuelina Inter 1qq);1 The refueling interlocks are designed to back up procedural core reactivity controls during refueling operations. The interlocks prevent an inadvertent criticality during refueling operations when the reactivity potential of the core is being altered.
To minimize the possibility of loading fuci into a cell containing no control rod, it is required that all control rods are fully inserted when fuel is being loaded into the reactor core. This requirement assures that during refueling the refueling interlocks, as designed, will prevent inadvertent criticality.
The refueling interlocks reinforce operational procedui 2 that prohibit.
taking the reactor critical under certain situations encountered during the refueling operations by restricting the movement of control rods and the i
operation of refueling equipment.
The refueling interlocks include circuitry which senses the condition of th'e refueling equipment and the control rods.
Depending on the sensed condition, interlocks are actuated which prevent the movement of the refueling equipment or withdrawal of control rods (rod block).
Circuitry is provided which senses the following conditions:
1.
All rods inserted.
2.
Refueling platform positioned near or over the core.
3.
Refueling platform hoists are fuel-loaded (fuel grapple, frame mounted hoist, monorail mounted hoist).
a i
4.
Fuel grapple not full up.
5.
Deleted.
6.
One rod withdrawn.
When the mode switch is in the " Refuel" position, interlocks prevent 'the refueling platform from being moved over the core if a control rod is withdrawn and fuel is on a hoist.
Likewise, if the refueling alatform is over the core with fuel on a hoist, control. rod motion is bloc <ed by the.
interlocks.
When the mode switch is in the refuel position, only one control rod can be withdrawn. The refueling interlocks, in combination with-core nuclear design and refueling procedures, limit the probability of'an inadvertent criticality. The nuclear characteristics of the core assure j
that the reactor
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