ML20154E516
| ML20154E516 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/01/1998 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20154E508 | List: |
| References | |
| AP-961, NUDOCS 9810080217 | |
| Download: ML20154E516 (29) | |
Text
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E0 REV 10 AP-961 LO
-e-l\\ FORMATION 1.0 ENTRY CONDITIONS Holder # MM IE an earthquake is suspected.
_J AND seismic recorder indicates a seismic event has taken place.
THEN use this procedure.
2.0 IMMEDIATE ACTIONS HOIE There are no immediate actions for this procedure.
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3.0 FOLLOW-UP ACTIONS
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ACTIONS DETAILS v
3.1 Notify personnel of plant STA conditions.
Plant Operators NSM (evaluate plant conditions for potential entry into the Emergency Plan) 3.2 IE the Rx is NOT critical.
THEN GO TO Step 3.7 in this procedure.
3.3 1E > 1 asymmetric control rod exists.
THEN trip the Rx and CONCURRENTLY PERFORM
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E0P-2 Vital System Status
\\ _J Verification, beginning with Step 2.1 3.4 Verify quadrant power tilt is within limits See COLR.
IE quadrant power tilt is NOT within limits.
THEN trip the Rx and CONCURRENTLY PERFORM E0P-2. Vital System Status Verification, beginning with Step 2.1
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l 3.0 FOLLOW-UP ACTIONS (CONT'D)
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ACTIONS DETAILS 3.5 Verify imbalance within limits.
See OP-103D. Withdrawal l
Limit Curves.
E imbalance is NOT within limits.
THEN trip the Rx and CONCURRENTLY PERFORM E0P-2. Vital System Status Verification, beginning with Step 2.1 3.6 E vibration was NOT due o CONCURRENTLY PERFORM AP-510. Rapid to plant equipment.
Power Reduction, beginning with THEN start a controlled Step 3.1 plant shutdown.
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3.0 FOLLOW UP ACTIONS (CONT'D) i (
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ACTIONS DETAILS 1
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3.7 Verify RCS integrity.
- Monitor available parameters:
RCS PRESS i
PZR level MUT level RB Sump level RCS level Notify PPO to monitor WD-29-LI
" AUX. BLDG. SUMP" level (95 ft AB on "RADWASTE CONTROL PANEL")
THEN CONCURRENTLY PERFORM AP-520. Loss of RCS Coolant or Pressure.
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3.0 FOLLOW UP ACTIONS (CONT'D)
ACTIONS DETAILS CAUTION Explosive conditions may be present in the TB if main generator H, containment has been lost.
3.8 Verify main generator H 1
Review main generator H 2
2 containment.
pressure.
2 Determine if Non-1E batter-charger is unavailable.
IE main generator H 1
lE TB evacuation is required.
2 containment is degraded or THEN perform the following:
- lost, AND the following exist:
Notify plant personnel over PA.
O Main generator H 2 V
pressure exists Repeat PA announcement.
Main generator is not 2
Notify SP0 to CONCURRENTLY on line PERFORM E0P-14. Enclosure 14 Station Blackout Main Generator THEN purge the main Purging.
generator.
3.9 Verify BWST is not in recirculation with SF pumps.
IE the BWST is in 1
Stop recirculation.
recirculation with SF pumps.
2 Notify PPO to ensure SFV-13 THEJ stop recirculation.
"BWST Supply Iso" is closed (119 ft AB by SFPs).
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3.0 FOLLOW UP ACTIONS (CONT'Di l
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ACTIONS DETAILS
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3.10 Notify Chemistry to sample RCS for fuel failure.
e SF pool 3.11 Verify SF pool integrity.
Observe SF pool level Notify PPO to inspect SF pool e
liner telltale drains (95 ft AB MUP cubicles).
lE SF pool leakage has increased, THEN contact TSC for guidance.
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3.12 1E refueling canal level
(..)
is lowering.
THEN CONCURRENTLY PERFORM AP-1080 Refueling Canal Level Decrease, beginning with Step 3.1
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3.0 FOLLOW UP ACTIONS (CONT'D) s l{ }
ACTIONS DETAILS 3.13 IE at any time, it becomes Notify Maintenance to inspect necessary to manually switchgear and internals for energize an electrical damage.
bus.
THEN ensure bus is capable Ensure DC power and protective of being energized.
relaying is available.
NOTE Seismic activity may result in spurious operation of the sudden pressure relays for the Off-Site Power Transformer or the BEST resulting in a loss of off site power.
3.14 Verify ES 4160V buses are energized.
IE either ES 4160V bus is NOT energized.
N.
THEN CONCURRENTLY PERFORM
(.,)
AP-770. Diesel Generator Actuation, beginning with Step 3.1
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Applicable carry-over steps:
3.13 1E it becomes necessary to manually energize an electrical bus.
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a 3.0 F0!. LOW-UP ACTIONS (CONT'D)
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ACTIONS DETAILS 1
NOTE Consider spurious actuation due to seismic activity when evaluating plant alarms.
3.15 Review available plant Review sump levels, radiation parameters.
monitors and tank levels for possible leaks.
e Observe Control Room TEMP.
e Review system status relative to alarms. lockouts and configurations that may result from relay chatter.
See Enclosure 1. Potential Spurious Alarms.
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Review containment integrity.
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3.16 Notify PPO to perform a e Verify power is available to any primary plant walk down.
waste gas compressor (95 ft AB on "RADWASTE CONTROL PANEL"):
WDP-1A WDP-1B e
Walk down primary plant structures and equipment to determine if damage inhibits the safe operation of plant equipment.
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Applicable carry-over steps:
3.13 lE it becomes necessary to manually energize an electrical bus.
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3.0 FOLLOW-UP ACTIONS (CONT'D)
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ACTIONS DETAILS 3.17 Notify SPD to perform a Observe H tank for possible 2
secondary plant walk down.
leaks.
- Observe FSTs for leaks.
FST-1A FST-1B o Determine if the following equipment is accessible and manual operation is NOT inhibited:
ARV-48 "B CONDENSER VACUUM BKR" (119 ft TB Above C Waterbox)
ARV-49 "A CONDENSER VACUUM BKR" (119 ft TB Above B Waterbox)
FSV-918 "FST to CDT-1 Cross-Tie Iso" (119 ft Berm by FST-1A)
('l MSV-25 "A OTSG Atmospheric Dump"
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(119 ft IB) i.
MSV-26 "B OTSG Atmospheric Dump" (119 ft IB)
EFV-36 "EFW & AFW Suction Iso From Hotwell" (95 ft TB between C and D inlet waterboxes)
IADR-1 IADR-2 Walk down secondary plent structures and equipment to determine if damage inhibits the safe operation of plant equipment.
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Applicable carry-over steps:
3,13 lE it becomes necessary to manually energize an electrical bus..
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3.0 FOLLOW UP ACTIONS (CONT'D)
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ACTIONS DETAILS 3.18 Review current plant activities for any actions that may have caused the vibrations.
IE required equipment is NOT 3.19 Evaluate results of plant walk downs and initiate accessible or manual operation necessary actions.
is inhibited.
THEN initiate action to establish access and restore manual operation capability.
e IE an IA dryer is NOT available.
THEN initiate action to periodically blow down air receivers.
IE Control Room TEMP is NOT between 70 and 80 F.
7-s THEN initiate action to operate v)
CHHE-1A or CHHE-1B as required.
e IE power is NOT available to a waste gas compressor.
THEN consider aligning WG header to AB ventilation system based on WG header PRESS.
IF IB is NOT accessible due to high TEMP.
AND manual operation of ADVs is required.
THEN notify SPD to open IB doors to TB (119 ft TB):
H-201 H-202
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Applicable carry-over steps:
3.13 JF it becomes necessary to manually energize an electrical bus..
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3,0 FOLLOW UP ACTIONS (CONT'D)
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ACTIONS DETAILS 3.20 IE RCS cooling is by Nat JF FST-1A is NOT available.
Circ.
THEN begin cooldown within 8 IHEN ensure adequate hours to ensure adequate secondary inventory.
secondary inventory.
Notify SPO to open EFV-36 "EFW &
AFW Suction Iso From Hotwell" (95 ft TB between C and D inlet waterboxes).
IE EFV-36 cannot be opened.
THEN notify TSC.
3.21 Notify MNPO to determine subsequent actions and additional surveillance requirements based on results of plant reviews and follow-up action.
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J 3.22 Notify I&C Supervisor to perform PT-378. Functional l
Testing arid Calibration of the Triaxial Time-History Accelographs and Triaxial Seismic Switch. Section 4.2. Action Following a Seismic Event.
3.23 EXIT this procedure.
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5.0 ENCLOSURE ; POTENTIAL SPURIOUS ALARMS
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ALARM POINT EQUIPMENT DESCRIPTION CONDITION 0003 EMERG NUCLEAR SERVICE SEA WATER PP A LOSS OF DC POWER l
0008 EMERG NUCLEAR SERVICE SEA WATER PP B LOSS OF DC POWER 0012 DECAY HEAT SEA WATER PP A LOSS OF DC POWER 0013 DECAY HEAT SEA WATER PP A OVERLOAD 0016 DECAY HEAT SEA WATER PP B LOSS OF DC POWER 0017 DECAY HEAT SEA WATER PP B OVERLOAD 0059 REACTOR BUILDING SPRAY PUMP A OVERLOAD 0060 REACTOR BUILDING SPRAY PUMP B OVERLOAD 0061 REACTOR BUILDING SPRAY PUMP A LOSS OF DC POWER 0062 REACTOR BUILDING SPRAY PUMP B LOSS OF DC POWER
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0117 CORE FLOOD TANK B LEVEL HIGH U
0137 ClimdLATING WATER PUMP A DISCH PRESS HIGH 0212 DECAY HEAT CLOSED CYCLE PUMP A LOSS OF DC POWER 0213 DECAY HEAT CLOSED CYCLE PUMP B LOSS OF DC POWER 0223 DECAY HEAT REMOVAL PUMP A OVERLOAD 0224 DECAY HEAT REMOVAL PUMP B OVERLOAD 0242 DECAY HEAT REMOVAL PUMP A LOSS OF DC POWER 0556 4160V ES BUS A PARALLEL FEED 0559 BREAKER 3206 LOSS OF DC POWER 0563 UNIT AUX XFMR 3 BREAKER 3207 LOSS OF DC POWER 0566 UNIT AUX XFMR 3 BREAKER 3208 LOSS OF DC POWER AP-961 REV 10 PAGE 23 of 29 EQ
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.i 5.0 ENCLOSURE 1 POTENTIAL SPURIOUS ALARMS (CONT'D)
O ALARM i
POINT-
. EQUIPMENT DESCRIPTION CONDITION 0569 DIESEL GENERATOR A BREAKER 3209 LOSS OF DC POWER 0572 DIESEL GENERATOR.B BREAKER 3210 LOSS OF DC POWER 0575 UNIT-1 BREAKER 3211 LOSS OF DC POWER q
0578 UNIT 1 BREAKER 3212 LOSS OF DC POWER
.0588 ES AUX XFMR B FEEDER BREAKER 3220 LOSS OF DC POWER 1
0590 ES AUX XFMR A FEEDER BREAKER 3221 LOSS OF DC POWER 0592 PLANT AUX XFMR 3 FEEDER BREAKER 3222 LOSS OF DC POWER 0609 ES BUS B BREAKER 3310 LOSS OF DC POWER 0612 ES BUS A BREAKER 3311 LOSS OF DC POWER 0646 4160V UNIT BUS A POT XFMR TROUBLE i
0650 4160V ES BUS A POT XFMR TROUBLE 0652 4160V ES BUS B POT XFMR TROUBLE 0654 480V ES BUS A POT XFMR TROUBLE 0656 480V ES B POT XFMR TROUBLE 0664 480V TURB AUX BUS B POT XFMR TROUBLE 0670 480V PLANT AUX BUS 3 POT XFMR TROUBLE 0672 480V HEATING AUX BUS 3 POT XFMR TROUBLE 0673 ES MCC 3B BREAKER 3340 LOSS OF DC POWER 0674 ES MCC Al BREAKER 3341 LOSS OF DC POWER 0677 ES MCC AB BREAKER 3361 LOSS OF DC POWER O
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5.0 ENCLOSURE 1 POTENTIAL SPURIOUS ALARMS (CONT'D) q V
ALARM POINT EQUIPMENT DESCRIPTION CONDITION 0679 ES MCC AB BREAKER 3360 LOSS OF DC POWER 0713 GEN NEUT GND LOCK OUT RELAY LOSS OF DC POWER 0714 STEP-UP XFMR/ GEN DIFF LOCK OUT RELAY LOSS OF DC POWER 0715 GEN DIFF LOCK OUT RELAY LOSS OF DC POWER 0730 BACKUP ES XFMR MASTER TRIP LK\\0T RLY LOSS OF DC POWER 0897 STATION AIR COMPRESSOR A OVERLOAD 0903 STATION AIR COMPRESSOR B OVERLOAD 0909 INSTRUMENT AIR COMPRESSOR A OVERLOAD 0915 INSTRUMENT AIR COMPRESSOR B OVERLOAD 1032 MAKEUP PUMP 1A LOSS OF DC POWER g
1033 MAKEUP PUMP 1A OVERLOAD 1039 MAKEUP PUMP 1B OVERLOAD 1044 MAKEUP PUMP 1C LOSS OF DC POWER 1045 MAKEUP PUMP 1C OVERLOAD 1098 MAKEUP PUMP 1B LOSS OF OC POWER 1099 MAKEUP PUMP 1B OVERLOAD 1175 REACTOR TRIP LOCKOUT RELAY LOSS OF DC POWER 1184 4160V ES BUS A CROSS TIE LOCK 0UT RLY LOSS OF DC POWER 1185 4160V ES BUS A CROSS TIE CIRCUIT LOSS OF DC POWER 1188 4160V ES BUS B CROSS TIE LOCK 0UT RLY LOSS OF DC POWER 1189 4160V ES BUS B CROSS TIE CIRCUIT LOSS OF DC POWER AP-961 REV 10 PAGE 27 of 29 E0 1
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5.0 ENCLOSURE 1 P0TENTIAL SPURIOUS ALARMS (CONT'D) m
,iV; ALARM POINT EQUIPMENT DESCRIPTION CONDITION 1259 MOTOR DRIVEN EF PUMP A LOSS OF OC POWER 1260 MOTOR DRIVEN EF PUMP A OVERLOAD 1554 CNTRL COMPLX WATER CHILLER A CHHE-1A LOSS OF DC POWER 1555 CNTRL COMPLX WATER CHILLER B CHHE-1B LOSS OF DC POWER 1824 EMERG NUC SERV CCC PUMP A (SWP-1A)
OVERLOAD 1827 EMERG NUC SERV CCC PUMP B (SWP-1B)
OVERLOAD 1853 EMERG NUC SERV CCC PUMP A LOSS OF DC POWER 1854 EMERG NUC SERV CCC PUMP B LOSS OF DC POWER 1991 4160V RX AUX BUS POT XFMR TROUBLE k
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