ML19347D740
| ML19347D740 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/19/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347D734 | List: |
| References | |
| NUDOCS 8103261196 | |
| Download: ML19347D740 (3) | |
Text
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Table 4.1-3 (Cont'd)
Channel Description Surveillance Function Frequency Surveillance Method 7.
Interlocks v Isolation Calibrate R
Apply known pressure to the Valves on Residual pressure sensors gg Heat Removal Line pac l8 8.
Containment Pressure a.
Check S
a.
Verify pressure indication
$4 b.
Calibrate R
b.
Known pressure applied to sensor
]
9.
RilR ltX Outlet a.
Check S
a.
Verify temperature indications gh Temperature when the system is in operation b.
Calibrate R
,~
Known resistance substituted for RTD 10.
Check M(3)(4) a.
Perform internal self checking Flow Rate test p
b.
Calibrate R
b.
Apply simulated transducer y
signal w"
11.
Check S(3)(4) a.
Comparison of monitor indicatior.
System Subcooling to existing pressure / temperature Margin Monitor relationships b.
Calibrate R
b.
Apply known pressure and g-temperature inputs into the g
processor o.
5 12.
PORV Position Indicator a.
Calibrate R
Apply known frequency to sensors N
(Acoustic Flow Sensor)
Table 4.1-3 (Cont'd)
Channel Description
' Surveillance Function Frequency Surveillance Method 13.
Safety Valve Position a.
Calibrate R
Apply known frequency to sensor Indicator (Acoustic Flow Sensor) 14.
PORV Actuation a.
Check M(3)(4) a.
Bistable trip test ircuit b.
Calibrate R
b.
Apply known pressure to sensors 15.
Pressurizer Power a.
Calibrate R
Apply known pressure to the pressure Operated Relief - Low sensor. Manual actuation of each Pressure Setpoint b.
Test R(5)
PORV to verify solenoid operation.
(1) Not required unless the reactor is in the power operating conditt'on.
(2) Not required during plant startup and shutdown periods.
~
(3) Not required when plant is in the cold shutdown condition.
(4) 'Must be performed within 30 days prior to attaining a power operating condition.
(5) Must be performed prior to cooldown below 220 F.
I 8
8 n
y
}
H.
In the event that a PORV or its associated block valve l
- becomes inoperable, either restore the PORV or block valve to operable status or close the associated block valve and remove power from the block valve; otherwise, 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 /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I.
The pressurizer shall be operable with at least one l
bank of proportional heaters and a water level during normal system operation between 28 and 60 percent whenever,F.the reactor coolant system T,y, is greater than 500 Basis:
When reactor coolant boron concentration is being reduced, the process must be uniform throughout the reactor coolant system volume to prevent stratification of reactor coolant at a lower boron concentration which could result in a reactivity insertion.
Sufficient mixing of the reactor coolant is assured by one low pressure safety injection (LPSI) pump operating in the RRR mode. When operated in this mode it will circulate the reactor coolant system volume in less than 12 minutes. The pressurizer volume is relatively inactive; therefore, it will tend to have a boron concentration higher than the rest of,the reactor coolant system during a dilution operation. Administrative procedures will require use of pressurizer spray to maintain a nominal spread between the boron concentration in the pressurizer and the reactor coolant system during the addition of boron.
Without residual heat removal, the amount of steam which could be generated at safety valve lift pressure with the i
reactor suberitical would be less than half of one valve's capacity. One valve, therefore, provides adequate defense against overpressurization when the reactor is subcritical.
t Overpressure protection is provided for all critical conditions. The safety valves are sized to relieve steam at a rate equivalent to the peak volumetric pressure surge rate.
For this purpose one safety valve is sufficient; however, a minimum of two safety valves is required by Section III of the ASME Code.
3.3-2 Amendment No. $2, 54
.