ML20127B018
| ML20127B018 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/18/1985 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20127B004 | List: |
| References | |
| NUDOCS 8506210329 | |
| Download: ML20127B018 (4) | |
Text
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LIMITING CONIDITIONS FOR OPERATION I
ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION 3.3.3.5 The Essential Parameters Manitoring Instrtsnentation shall be OPERABLE in accordance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN.
APPLICABILITY: RECOVERY MODE ACTION:
a.
With the exception of the Reactor Vessel Water Level monitoring instrumentation, the Spent Fuel Storage Pool "A" Water Level monitoring instrumentation, and the Fuel Transfer Canal (Deep End) Water Level j
monitoring instrumentation, for instrumentation not in accordance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN, restore i
the inoperable instrument (s) to the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
b.
The operaollity requirements for the Reactor Vessel Water Level
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monitoring instrumentation shall be as specified in specification 3.4.2.
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c.
The operacility requirements for the Spent Fuel Storage Pool "A" Water Level monitoring instrumentation shall be as specified in specification
.l 3.9.1.
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d.
The operability requirements for the Fuel Transfer Canal (Deep End) Water Level monitoring instrumentation shall be as specified in specification i
3.9.3.
POST-ACCIDENT INSTRUENTATION 4
j 3.3.3.6 Deleted.
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Cil.ORINE DETECTION SYSTEMS l
3.3.3.7 Two chlorine detection systems, with their alarm / trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 j
ppm, shall be OPERABLE:
a.
One at the air intake tunnel, and 1
b.
One at the Control Room air supply duct.
i APPLICA81LIH: RECOVERY MODE i
i ACTION:
With one or more chlorine detection systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation; restore the inoperable detection system to l
OPERAdLE status within 30 days.
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THREE MILE ISLAND - UNIT 2 3.3-6 TSCR NO. 50 l
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LIMITING CONIDITIONS FOR OPERATIO4 m
3.5 COMJNICATIONS 3.5.1 Control Room i
Direct communication shall be maintained between the Control Room or the Command Ce6ter and personnel in the Reactor Building. As stated in Table 6.2-1, the additional SOL or SQL Limited to Fuel Handling, notwithstanding location, will have direct communications with personnel in the Reactor Building performing CORE ALTERATIONS.
l APPLICABILITY: During CORE ALTERATIONS ACTION:
4 When direct communication between the Control Room or the Comnand Center and l
personnel in the Reactor Building, as stated in the above specification,-
l cannot be maintained, suspend all operations involving CORE ALTERATIONS and restore comunications to OPERABLE status, a
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T M MILE ISLAND - UNIT 2 3.5-1 TSCR NO. 50
s LIMITING CONIDITIONS FOR OPERATION i
3.9 RADI0 ACTIVE WASTE STORAGE I
SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING l
3.9.1 Two independent Spent Fuel Storage Pool "A" Water Level monitoring
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instruments shall be OPERA 8LE.
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APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".
i ACTION:
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a.
With only one Spent Fuel Storage Pool "A" water level monitoring i
instrument OPERABLE, immediately verify that the water level is within limits, re-verify the level at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore a j
second instrument to OPERABLE status within 7 days.
b.
With no Spent Fuel Storage Pool "A" Water Level monitoring instruments OPERABLE, terminate all activities involving any Canister containing core material in or over Spent Fuel Storage Pool "A" and all operations 1
involving changes in Spent Fuel Storage Pool "A" water inventory and j
restore at least one instrum9nt to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
t SPENT FUEL STORAGE POOL "A" WATER LEVEL 3.9.2 The water level in Spent Fuel Storacje Pool "A" shall De maintained as j
specified per mc approved procedures.
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APPLICABILITY: Whenever any Canister containing core material is in the Spent I
s Fuel Storage Pool "A".
I ACTION:
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With Spent Fuel Storage Pool "A" Water Level not in accordance with approved-i procedures, terminate all activities involving any Canister containing core l
material in or over Spent Fuel Storage Pool "A" and restore the water level to I
within specification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING
'3.9.3 Two indp endent Fuel Transfer Canal (Deep End) Water Level monitoring instrunents shall be OPERABLE.
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APPLICAdILITY: Whenever any Canister containing core material and/or the plenum assembly is in the Fuel Transfer Canal (Deep End).
l ACTION:
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With only one Fuel Transfer Canal (Deep End) Water Level monitoring a.
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instrunent OPERABLE, immediately verify tnat the water level is within limits, re-verify the level at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore a second instrunent to OPERABLE status within seven (7) days, i
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'fMREE MILE ISLAND - UNIT 2 3.9-1 TSCR NO. 50 f
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TABLE 4.3-7 1
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ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i
E MINIMUM E
CHANNEL CHANNEL*
READOUT OPERABLE E
INSTRUMENT CHECK CALIBRATION LOCATION (S)
CHANNELS l
E 1.
Reactor Building Pressure S
R Control Room 2
2.
Reactor Vessel Water Level S/W
SA Control Room < 2 >
2
3.
Reactor Coolant System Temperature S
R CAB 217 &
1/ Loop Control Room 4.
Incore Thermocouples S
R Control Room or 2
Cable Room 5.
NI Intermediate Range Level Log N M
R CAB 217 &
1 Control Room
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6.
NI Source Range Level M
R CAB 217 &
2 L
Control Room O
7.
Reactor Building Water Level NA SA Control B1dg.
1 Area West d
8.
Borated Water Storage Tank Level S
R Control Room 1
9.
Steam Generator Level NA NA NA 1/ Generator 10.
Decay Heat Removal Flow M
R CAB 217 1/ Loop 11.
Spent fuel Storace Pool S /d' ' '
SA Control Room or 2
g "A" hater Level fuel Handling Bldg.
l 12.
Fuel Transfer Canal S/H
SA Control Room or 2':>
g (Deep End) Hater Level Reactor Bldg.
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(See following page for notes)