ML20148F194
| ML20148F194 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/21/1988 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20148F111 | List: |
| References | |
| NUDOCS 8803280088 | |
| Download: ML20148F194 (5) | |
Text
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a Units 2 and 3 PBAPS 1.2 BASES The reactor coolant system integrity is an important barrier in the prevention of uncontrolled release of fission products.
It is essential that the integrity of this system be protected by establishing a pressure limit to be observed for all operating conditions and whenever there is irradiated fuel in the reactor vessel.
The pressure safety limit of 1325 psig as measured by the vessel steam space pressure indicator assures not exceeding 1375 psig at the lowest elevation of the reactor coolant system.
The 1375 psig value is derived from the limiting design pressures of the reactor pressure vessel (1250 psig at 575 degrees F) and recirculation system piping (suction piping:
1250 psig at 575 degrees F).
The pressure safety limit is set in accordance with the ASME Boiler and Pressure Vessel Code Section III to limit the maximum pressure to less than 110% of the design pressures for the reactor vessel (110% x 1250 = 1375 psig) and the recirculation system piping (suction: 110% x 1250
= 1375 psig).
A safety limit is applied to the Residual Heat Removal System (RHRS) when it is operating in the shutdown cooling mode.
At this time it is included in the reactor coolant system. f$h kDO
[7 P
Unit 3 a
TABLE 4.2.A 4
MINIMUM TF;T 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-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) Reactor Water Cleanup (1)
Once/3 months Once/ day High Flow
- 7) Reactor Water Cleanup (1)
Once/3 months None High Temp.
- 8) Reactor Pressure (1)(3)
Once/ operating cycle Once/ day ooj' (Feedwater Flush Permissive) 4 Logic System Functiona'i 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.
- 3) Reactor Water Cleanup Isolation Once/6 months
- 4) Drywell Isolation Vvs.
Once/6 months TIP Withdrawal Atmospheric Control Vvs.
Sump Drain Valves 3
- 5) Standby Gas Treatment System Once/6 months Reactor Building Isolation
f PBAPS Units 2 and 3 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps 4.6.E Jet Pumps
- 1. Whenever the reactor is in
- 1. Whenever there is recirculation the startup or run moaes, flow with the reactor in the all jet pumps shall be startup or run modes, jet operable. If it is determined pump operability shall be that a jet pump is inoperable, checked daily by verifying an orderly shutdown shall be that the following initiated and the reactor shall conditions do not occur be in a Cold Shutdown within simultaneously:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Flow indications from each of a) The two recirculation loops have the 20 jet pumps during two a flow imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single loop operation operated at the same speed.
shall be verified prior to initiation of reactor startup b) The indicated value of core flow from a cold shutdown condition.
rate varies from the value derived from loop flow measure-ments by more than 10%.
- 3. The indicated core flow is the sum of the flow indication from each of the 20 jet pumps.
If c) The diffuser to lower plenum flow indication failure occurs differential pressure reading for two or more jet pumps on an individual jet pump immediate corrective action varies from the mean of all shall be taken.
If flow jet pump differential pressures indication fot-all but 1 jet by more than 10%.
pump cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an orderly shutdown
- 2. Additionally when operating shall be initiated, and the one recirculation pump, the l
reactor shall be in cold diffuser to lower plenum shutdown condition within differential oressure shall be
~
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
checked daily and the differential pressure of any jet pump in the idle loop shall not vary by more than 10% from established pattern.
- 3. The baseline data recrired to evaluate the conditions in specification 4.6.E.1 and 4.6.E.2 will be obtained each operating cycle.
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Unit 3 TABLE 3.7.1 (Cont'd.)
o PRIMARY CONTAINMENi ISOLATION VALVES Number of Power Maximum Action en Operated Valves Operating Normal Initiating Group Valve Identification Inboard Outboard Time (sec.)
Position Signal NA feedwater check valves 2*
2*
NA 0
Process 3
Radioactive gas sample isolation 4
If NA C
SC valves 3
Instrument nitrogen compressor If 1
5 0
GC suction line isolation valves 3
0xygen Analyzer System 14 NA 0
GC NA Standby liquid control system 1*
1*
NA C
Process check valves i 2B RHRS shutdown cooling suction 1
1 32 C
SC m
isolation valves 2B RHRS shutdown cooling 1
24 C
SC injection isolation valves 2C Feedwater flush Valves 2
50 C
SC 4
IIPCIS steam line isolatten 1
1 20 0
GC valves 5
RCICS steam line isolation 1
1 15 0
GC valves 2A Reactor water cleanup system 1
1 30 0
GC isolation valves 2A Reactor water cleanup system 1
20 0
GC return isolation valve
- Valves not power operated.
( __ _ _ _ _ _ - _ _ _ _ _. __
e a c PBAPS Unit 3 TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
NOTES 7A AO-2-80A; AO-2-86A MSIV (1) (2) (3) (5) (9) 7B AO-2-80B; AO-2-86B 7C AO-2-80C; AO-2-86C 7D AO-2-80D; AO-2-86D 8
MO-2-74; MO-2-77 (1) (2) (4) (5) (9) 9A MO-23-19; MO-23-20; MO-23-21 9A MO-2-38A; MO-3663 9B MO-13-21; MO-13-20; MO-13-30; MO-12-68; 9B MO-2-38B; MO-3663 10 MO-13-15; MO-13-16 11 MO-23-15; MO-23-16; AO-5807*
12 MO-10-17; MO-10-18 13A.
MO-10-25B; MO-10-154B; SV-5222 13B MO-10-25A; MO-10-154A; SV-5221 14 MO-12-15; MO-12-18
)
16A MO-14-12B; MO-14-llB; SV-5224 16B MO-14-12A; MO-14-11A; SV-5225 18 AO-20-82; AO-20-83 19 AO-20-94; AO-20-95 Effective upon completion of the modification authorized by Amendment No. 46
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