ML20129J265
| ML20129J265 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/17/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20129J258 | List: |
| References | |
| NUDOCS 8507220397 | |
| Download: ML20129J265 (17) | |
Text
,
T Unit 2 Table 3.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No.
Modes in which Number of of Operable Function Must be Instrument Instrument Trip Level Operable Channels Action Channels
. Trip Function Setting Provided (1) per Trip (1)
Refuel Startup Run by Design System (7) 2 High Water. Level 150 Gallons X(2)
X X
4 Instrument A
in Scram Discharge Channels Instrument Volume 2
Turbine Condenser
>23 in. Hg.
X 4 Instrument A or C Low Vacuum Vacuum Channels da T
2 Main Steam Line 13 X Normal Full X X
X 4 Instrument A
High Radiation Power Background Channels 4
$10% Valve X(6) 8 Instrument A
Isolation Valve Closure Channels Closure 2
Turbine Control 500<P<850 psig X(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid and Disc Dump Valve 4
Turbine Stop 310% Valve X(4) 8 Instrument A or.D Valve Closure Closure Channels hf P
h j
Unit 3 l
Table:3.1.1 (Cont'd)
REACTOR PROTECTION ' SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No.-
Modes in which Number of of Operable Function Must be Instrument Instrument Trip Level Operable Channels Action Channels Trip Function Setting Provided (1) per Trip )
Refuel Startup Run by Design System (1 (7) 2 High Water Level 150 Gallons X(2)
X X
4 Instrument A
in Scram Discharge Channels Instrument Volume 2
Turbine Condenser
>23 in. Hg.
X 4 Instrument A or C y
g Low Vacuum Vacuum Channels 1
2 Main Steam Line 13 X Normal Full X X
X(14) 4 Instrument A
High Radiation Power Background Channels 4
$10% Valve X(6) 8 Instrument A
Isolation Valve Closure Channels Closure 2
Turbine Control 500<P<850 psig X(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid and Disc Dump Valve 4
Turbine Stop 110% Valve X(4) 8 Instrument A or D Valve Closure Closure Channels i
Unit 2 PBAPS 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 af fected 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 turbine first stage pressure is less than 220 psig or less than 30% of rated.
5.
IRM's are bypassed when APRM's are onscale 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 reacter is subcritical 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. -
Unit 3 PBAPS
~
NOTES FOR TABLE 3.1.1 1
I 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 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 turbine first stage pressure is less than 220 psig or less than 30% of rated.
5.
IRM's are bypassed when APRM's are onscale 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 subcritical 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. a
Unit,2 TABLE 4.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2)
Functional Test Minimum Frequenc'y (3)
High Water Level in Scram A
Trip Channel and Alarm Every 1 month.
Discharge Instrument Volume l
Turbine Condenser Low Vacuum (6)
B2 Trip Channel and Alarm (4)
Every 1 month (1).
Main Steam Line High Radiation B1 Trip Channel and Alarm (4)
Once/ week.
i Main Steam Line Isolation A
Trip Channel and Alarm Every 1 month (1).
y Valve Closure Turbine Control Valve A
Trip Channel and Alarm Every l' month.
EHC Oil Pressure Turbine First Stage Pressure A
Trip Channel and Alarm Every 3 months (1).
Permissive Turbine Stop Valve Closure A
Trip Channel and Alarm Every 1 month (1)..
Unit 3 TABLE 4.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL' TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2)
Functional Test Minimum Frequency (3)
High Water Level in Scram A
Trip Channel and Alarm Every 1 month.
Discharge Instrument Volume Turbine Condenser Low Vacuum (6)
B2 Trip Channel and Alarm (4)
Every 1 month (1).
Main Steam Line High Radiation B1 Trip Channel and Alarm (4)
Once/ week.
Main Steam Line Isolation A
Trip Channel and Alarm Every 1 month (1).
,g Valve Closure I
Turbine Control Valve A
Trip Channel and Alarm Every 1 month.
EHC Oil Pressure Turbine First Stage Pressure A
Trip Channel and Alarm Every 3 months (1).
Permissive Turbine Stop Valve Closure A
Trip Channel and Alarm Every 1 month (1).
Unit 2 TABLE 4.1.2 (Cont'd.)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES.FOR REACTOR PROTECTION INSTRUMENT. CHANNELS Instrument Channel Group (1)
Calibration (4)
Minimum Frequency (2),
Turbine Control Valve Fast A
Standard Pressure Source Once per operating Closure Oil Pressure Trip cycle.
Turbine Stop Valve Closure A
Note (5)
Note (5)
Unit 3 TABLv. 4.1.2 (Cont'd.)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUf!ENT CIIANNELS Instrument Channel Group (1)
Calibration (4)
Minimum Frequency (2)
Turbine Control Valve Fast A
Standard Pressure Source Once per operating Closure Oil Pressure Trip cycle.
Turbine Stop Valve Closure A
Note (5)
Note (5)
l PBAPS 3:1 BASES (Cont'd) the amount of water which must be accommodated during a scram.
During normal operation the discharge volume is empty; however, should it fill with water, the water discharged to the piping from the reactor could not be accommodated which would result in slow scram times or partial control rod insertion.
To preclude this occurrence, level switches have been provided in the instrument volume which alarm and scram the reactor when the volume of water reaches 50 gallons.
As indicated above, there is sufficient volume in the piping to accommodate the scram without impairment of the scram times or amount of insertion of the control rods.
This function shuts the reactor down while sufficient volume remains to accommodate the discharged water and precludes the situation in which a scram would be required but not be able to perform its function adequately.
A source range monitor (SRM) system is also provided to supply additional neutron level information during start-up but has no scram functions (reference paragraph 7.5.4 FSAR).
Thus, the IRM and APRM are required in the " Refuel" and
" Start / Hot Standby" modes.
In the power range the APRM system provides required protection (reference paragraph 7.5.7 FSAR).
Thus the IRM System is not required in the "Run" mode.
The APRM's cover only the power range.
The IRM's and APRM's provide adequate coverage in the start-up and intermediate range.
The high reactor pressure, high drywell pressure, reactor low water level and scram discharge volume high level scrams are required for Startup and Run modes of plant operation.
They are, therefore, required to be operational for these modes of reactor operation.
The requirement to have the scram functions indicated in Table 3.1.1 operable in the Refuel mode assures that shifting to the Refuel mode during reactor power operation does not diminish the protection provided by the reactor protection system.
The turbine condenser low vacuum scram is only required during power operation and must be bypassed to start up the unit.
The main condenser low vacuum trip is bypassed except in the run position of the mode switch.
Turbine stop valve closure occurs at 10% of valve closure.
Below 220 psig turbine first stage pressure (30% of rated),
the scram signal due to turbine stop valve closure is bypassed because the flux and pressure scrams are adequate to protect the reactor.
Unit 2-TABLE 3.2.A
~
INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No.
of Operable Number of Instrument Instrument Instrument Trip Level Setting Channels Provided Action.
Channels per By Design (2)
Trip System (1)
~
2 Main Steam Line f 200 Deg. F 4 Inst. Channels B
Leak Detection High Temperature 1
Reactor Cleanup
< 300% of Rated 2 Inst. Channels C
System High Flow Flow
&y 1
Reactor Cleanup f 200 Deg.
F.
1 Inst. Channels E
System High Temperature 2
Reactor Pressure f 600 psig 4 Inst. Channels F
(Feedwater Flush System Interlock)
Unit 3 TABLE 3.2.A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No.
of Operable Number of Instrument Instrument Instrument Trip Level Setting Channels Provided Action' Channels per By Design (2)-
Trip System (1) 2 Main Steam Line
< 200 Deg. F 4 Inst. Channels B
Leak Detection High Temperature 1
Reactor Cleanup
< 300% of Rated 2 Inst. Channels C
3 System High Flow FTow i
1 Reactor Cleanup
< 200 Deg.
F.
1 Inst. Channels E
System High Temperature 2
Reactor Pressure
< 600 psig 4 Inst. Channels F
(Feedwater Flush System Interlock)
PBAPS e
Unit 2 9
NOTES FOR TABLE 3.2.A 1.
Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken:
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shutdown Cooling.
E.
Isolate Reactor Water Cleanup Filter Demineralizers unless the following provision is satisifed.
The RWCU Filter Demineralizer may be used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank, with the high temperature trip inoperable for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degreef F.
F.
Isolate Feedwater Flush System l
3.
Instrument setpoint corresponds to 177.7" above top of active fuel.
4.
Instrument setpoint corresponds to 129.7" above top of active fuel.
5.
Two required for each steam line.
6.
These signals also start SBGTS and initiate secondary containment isolation.
7.
Only required in Run Mode (interlocked with Mode Switch).
8.
At a radiation level of 1.5 times the normal rated power background, an alarm will be tripped in the control room to alert the control room operators to an increase in the main steam line tunnel radiation level.
I PBAPS Unit 3 NOTES FOR TABLE 3.2.A 1.
Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken:
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shutdown Cooling.
E.
Isolate Reactor Water Cleanup Filter Demineralizers unless the following provision is satisifed.
The RWCU Filter Demineralizer may be used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank, with the high temperature trip inoperable for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degreef F.
F.
Isolate Feedwater Flush System l
3.
Instrument setpoint corresponds to 177.7" above top of active fuel.
4.
Instrument setpoint corresponds to 129.7" above top of active fuel.
5.
Two required for each steam line.
6.
These signals also start SBGTS and initiate secondary containment isolation.
7.
Only required in Run Mode (interlocked with Mode Switch).
8 At a radiation level of 1.5 times the normal rated power background, an alarm will be tripped in the control room to alert the control room operators to an increase in the main steam line tunnel radiation level.
l L
l i
PBAPS i
Unit 3 NOTES FOR TABLE 3.2.A (Continued) 9.
In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 250 degrees F for a period not to exceed 30 minutes to permit restoration of the ventilation flow.
During the 30 minute period, an operator shall observe control room indications of the duct temperature so in the event of rapid increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.
- 10. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation level and associated trip setpoints may be adjusted during the test prgram based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing nornal radiation levels after completion of the test program, and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power.
-63a-a
m-PBAPS Unit 2 NOTES FOR TABLE 3.2.A (Continued) 9.
In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 250 degrees F for a period not to exceed 30 minutes to permit restoration of the ventilation flow.
During the 30 minute period, an operator shall observe control room indications of the duct temperature so in the event of rapid increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.
-63a-l
TABLE 4.2.A MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (5)
Instrument Functional Test Calibration Frequency-Instrument Check 1)
Reactor High Pressure (1)
Once/3 months None (Shutdown Cooling Permissive) 2)
Reactor Low-Low (1)(3)
Once/ operating cycle Once/ day' Water Level (7) 3)
Main Steam High Temp.
(1)(3)
Once/ operating cycle Once/ day 4)
Main Steam High Flow (7)
(1)(3)
Once/ operating cycle Once/ day 5)
Main Steam Low Pressure (1)
Once/3 months None 6)
Once/3 months Once/ day l
High Flow l
7)
Once/3 months None High Temp.
(
8)
Reactor Pressure (Feedwater (1)(3)
Once/ operating cycle Once/ day ~l 1
Flush Permissive)
Logic System Functional Test (4) (6)
Frequency 1)
Main Steam Line Isolation Vvs.
Once/6 months Main Steam Line Drain Vvs.
Reactor Water Sample Vvs.
2)
RHR - Isolation Vv. Control Once/6 months Shutdown Cooling Vvs.
Head Spray 3)
Reactor Water Cleanup Isolation Once/6 months l
4)
Drywell Isolation Vvs.
Once/6 months TIP Withdrawal Atmospheric Control Vvs.
Sump Drain Valves 5)
Standby Gas Treatment System Once/6 months Reactor Building Isolation i
SIMPLIFIED SCHEMATIC-CONDENSER LOW VACUUM /
M,SIV CLOSURE-BYPASS TYPICAL OF FOUR TRIP LOGIC.
3
==
CLOSED WITH MODE SWITCH I
IN SHUTDOWN. REFUEL. OR START-UP K27E
==
CLOSED WITH REACTOR PRESSURE BELOW 600 PSI (THIS CONTACT WILL BE JUMPERED BY PROPOSED MODIFICATIONS)
CONDENSER LOW VACUUM AND
(---
MS IV CLOSbRE BYPASS KISA
/
]
l l
l l
l u
l 3
i CLOSED WHEN l
- K2A CONDENSER VACUUM i
K2A GREATER THAN SETPOINT l
~ K16 A ----i
==
s l
== K I S A --- J
== K3 A
== K3E CLOSED WHEN MSIV FULLY
> OPEN
== K3 A
== K3E,