ML20115H661
| ML20115H661 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/18/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20115H632 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8504230216 | |
| Download: ML20115H661 (5) | |
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TABLE 3.2.F SURVEILLANCE INSTRUIIENTATION llinimum No.
of Operable Type Instrument Indication Channels Instrument and Range Action ***
2 Reactor Water Level Recorder 0-60" (12) (13)
(narrow range)
Indicator 0-60" 2
Reactor Water Level Recorder -165" to +50" (5)
(wide range) 2 Reactor Unter Level Recorder -325" to 0" (5)
(fuel range) 4 2
Reactor Pressure Recorder 0-1500 psig (1) (2) (3) y Indicator 0-1200 psig i
2 Drywell Pressure Recorder 0-70 psig (1) (2) (3) 2 Drywell Pressure Recorder 0-225 psig (8) (9)
(wide range) 2 Drywell Pressure Recorder 5-25 psia (8) (9)
(subatmospheric range) 2 Drywell Temperature Recorder 0-400 degrees F (1) (2) (3)
Indicator 0-400 degrees F 2
Suppression Chamber Water Recorder 30-230 degrees F (1) (2) (3) (G)
Temperature
- Indicator 30-230 degrees F 2
Suppression Chamber Water Recorder 0-600 degrees F (1) (2) (3)
Temperature **
Indicator 0-400 degrees F 2
Suppression Chamber Water Recorder 0-2 ft.
(1) (2) (3) 1 Level (narrow range)
Indicator 0-2 ft.
8504230216 850418 PDR ADOCK 05000277 P
PBAPS NOTES FOR TABLE 3.2.F (Con t ' d )
9)
If no channels are operable, continued operation is permissible during the succeeding 7 days, provided both Drywell Pressure instruments (0-70 psig) are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 />.
10)
With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, continued operation is permissible during the succeeding 30 days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel to operable status within 7 days or 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 />.
11)
If no channels are operable, continued operation is permissible during the succeeding seven days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 />.
12)
With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, either restore the inoperable channel to an operable status within 7 days, or 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 />.
13)
If this parameter is not indicated in the control room, either restore at least one inoperable channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 />.
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TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Cneck 1)
Reactor Water Level Once/ operating cycle Once.Each Shift (narrow range) 2)
Reactor Water Level Once/ operating cycle Once/ day (wide range) 3)
Reactor Water Level Once/ operating cycle Once/ day (fuel zone) 4)
Reactor Pressure Once/6 months Once Each Shift 5)
Drywell Pressure Once/G months Once Each shift 6)
Wide Range Drywell Pressure Once/ operating cycle Once/ day 7)
Subatmospheric Drywell Pressure Or.ca/ operating cycle Once/ day 8)
Drywell Temperature Once/6 months Once Eacn Shift i
9)
Suppression Chamber Temperature Once/ operating cycle Once Each Day
- 10) Suppression Chamber Water Level Once/6 months Once Each Shift
- 11) Wide Range Suppression Chamber Once/ operating cycle Once/ day Water Level 12)
Control Rod Position NA Once Each Shift 13)
Neutron Monitoring (APRM)
Twice Per Week Once Each Shift 14)
Safety / Relief Valve Position Once/ operating cycle Once/ month Indicator (acoustics)
- 15) Safety / Relief Valve Position NA*
Once/ month Indicator (thermocouple)
- 16) Safety Valve Position Indicator Once/ operating cycle Once/ month (acoustics)
- 17) Safety valve Position Indicator NA*
Once/ month (thermocouple) l
r PDAPS 3.2 DASES (Con t ' d )
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.
Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.
Each set of instrument channels is arranged in a 1 out of 2 4
twice trip logic.
Trip settings of less than 16 mr/hr for the monitors in the refueling aren ventilation exhaust ducts are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
3 Flow integrators are used to record the integrated flow of 11guld from the drywell sumps.
The alarm unit in each integrator is set to annunciata before the values specified in Specification 3.6.c are exceeded.
An air sampling system is also provided to detect leakage inside the primary containment.
Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.
The instrumentation and the applicable NUREG-0737 requirements are:
1.
Uide range drywell pressure (II. F.1. 4 )
2.
Subatmospheric drywell pressure (II.F.1.4) 3.
Uide range suppression chamber water level (II. F.1. 5) 4.
Main stack high range radiation monitor (II.F.1.1) 5.
Reactor building roof vent high range radiation monitor (II.F.1.1) 6.
Drywell hydrogen concentration analyzer and monitor (II.F.1.G) 7.
Drywell high range radiation monitors (II. F.1. 3) 8.
Reactor Water Level - wide and fuel range (II.F.2) 9.
Reactor pressure (I.D.2) 10.
Safety-Relief Valve position indication (II.D.3)
F-PBAPS 3.2 BASES (Cont'd.)
The recirculation pump trip has been added at the suggestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.
The response of the plant to this postulated event fall within the envelope of study events given in General Electric Company Topical Report, NEDO-10439, dated March, 1971.
In the event of a loss of the reactor building ventilation system, radiant heating in the vicinity of the main steam lines raises the ambient temperature above 200 degrees F.
Restoration of the main steam line tunnel ventilation flow momentarily exposes the temperature sensors to high gas temperatures.
The momentary temperature increase can cause an unnecessary main steam line isolation and reactor scram.
Permission is provided to increase the temperature trip setpoint 5
to 250 degrees F for 30 minutes during restoration of ventilation system to avoid an unnecessary plant transient.
The Emergency Aux. Power Source Degraded Voltage trip function prevents damage to safety-related equipment in the event of a sustained period of low voltage.
The voltage supply to each of the 4kV buses will be monitored by undervoltage relaying.
With a degraded voltage condition on the off-site source, the undervoltage sensing relays operate to initiate a timing sequence.
The timing sequence provides constant and inverse time voltage characteristics.
Degraded voltage protection includes:
(1) An instantaneous relay (ITE) initiated at 90% voltage which initiates a 60-second time delay relay and a G second time delay relay.
The G-second time delay relay requires the presence of a safety injection signal to initiate transfer; (2) An inverse time voltage relay (CV-6) initiated at 87% voltage with a maximum 60 second delay and operates at 70% voltage in 30 seconds; and (3)
An inverse time voltage relay (IAV) initiated at approximately 60% voltage and operates at 1.8 seconds at zero volts.
When the timing sequence is completed, the corresponding 4kV emergency circuit breakers are tripped and the emergency buses are transferred to the alternate source.
The GO-second timing sequences were selected to prevent unnecessary transfers during motor starts and to allow the automatic tapchanger on the startup transformer to respond to the voltage condition.
The G-second timing sequence is necessary to prevent separation of the emergency buses from the off-site source during motor starting transients, yet still be contained within the time envelope in FSAR Table 8.5.1.
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