ML19318D246
| ML19318D246 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/12/1980 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19318D229 | List: |
| References | |
| FNP-2-EOP-16.0, NUDOCS 8007080250 | |
| Download: ML19318D246 (4) | |
Text
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's h VOLUME S FNP-2-EOP-16.0
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June 12, 1980 Revision 0 FARLEY NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE FNP-2-EOP-16.0 S
A F
E T
Y INADEQUATE CORE COOLING I
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DUE TO A SMALL LOSS OF COOLANT ACCIDENT R
E L
A T
E D
UNCOMTROLLED COPY CAUTION: This copy '* " '
maintained Current. Do not use m Approved:
Safety Related Activity.
D operations superint ent Diskette EOP-2 8 00708o 2@
LIST OF E 5_CTIVEPAdES
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FNP-2-EOP-16.0 i..
REVISION NO.
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VOL. 5 FNP-2-EOP-16.0 FARLEY NUCLEAR PLANT C
UNIT 2 EMERGENCY OPERATING PROCEDURE EOP-16.C INADEQUATE CORE COOLING DUE TO A I
SMALL LOSS OF COOLANT ACCIDENT 1.0 Purpose The purpose of this procedure is to specify precautions and operator actions required to restore a condition of adequate core cooling during a small Loss of Coolant
- Accident.
2.0 Symptoms 0
Any five (5) core exit thermocouples indicating >,1200 F on the core subcooling monitor panel.
3.0 Automatic Actions None 4.0 Immediate Operator Actions l~(
None n
5.0 Subsecuent Operator Actions CAUTION: If during the conduct of this procedure, RWST level decreases to 150,000 gallons establish cold leg recirculation per FNP-2-EOP-1.0.
NOTE: Throughout this procedure, continue efforts to provide safety injection flow to the RCS, and auxiliary feedwater flow to the steam generators, including operating equipment locally, if necessary.
NOTE: Continue monitoring core exit thermocouples on the core subcooling monitor panel per FNP-2-SOP-44.2.
5.1 Cooldown the RCS by:
5.1.1 Dumping steam to the condenser by using steam dumps in the steam pressure mode QR 5.1.2 If the condenser is not available, by dumping steam through the atmospheric
.. (,
steam reliefs.
A 1
Rev. 0
VOL. 5 FNP-2-EOP-16.0 CAUTION:
Cooldown through use of the C:
steam generators should only be attempted if there is an effective steam generater water level as indicated by core thermocouple temperatures decreasing and auxiliary feedwater is available.
NOTE:
If the Condensate Storage Tank level decreases to 4 ft.,
shift auxiliary feedwater pump suction to the service water system per FNP-2-SOP-22.0.
5.1.3 If the steam generators do not provide core heat removal, proceed as follows:
5.1.3.1 Verify that High Head and/or Low Head safety injection system is delivering flow to j
the RCS.
5.1.3.2 Open the pressurizer power operated relief valves, k
CAUTION:
Do not pump down the PRT.
5.1.4 If the above means of RCS cooldown are unavailable, or if the cooldown did not result in decreasing core exit thermocouple temperatures, start a RCP to establish forced flow through the core, per FNP-2-SOP-1.1.
C 2
Rev. 0
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