ML20199E431
| ML20199E431 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/23/1998 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20199E419 | List: |
| References | |
| AP-961, NUDOCS 9802020153 | |
| Download: ML20199E431 (29) | |
Text
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EQ REV 08 AP-961 n
1.0 ENTRY CONDITIONS INFO RV ATION JE an earthquake is suspected, MQ sei:mic recorder indicates a seismic event has taken place, lH_@ use this procedure.
2,0 IMMEDIATE ACTIONS NOIE There are no immediate actions for this procedure.
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.O Approved by MNP0 h# TA/ Date / /22/96 (j
u (SIGNATynE 0)IFILE) j AP-961 PAGE 1 of 29 EQ l
l 9802020153 980123 '
PDR ADOCK 05000302
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.e 3.0 FOLLOW UP ACTION _$
ACTIONS DETAILS 3.1 Notify personnel _of plant e STA ~
conditions.
e Plant Operators
- SSOD (evaluate plant conditions for_ potential entry into the Emergency Plan) 3.2 E the Rx is @T critical, Ill@ GO TO Step 3.7 in this procedure.
3.3 _ E any asymmetric control rod exists, IBfB trip the ax and CONCURRENTLY PERFORM
{J \ E0P 2, Vital System Status Verification, beginning with Step 2.1 3.4 _ Verify-quadrant power tilt .
is within limits.
See COLR.
E quadrant power tilt is N_0_I within limits, I!i@ trip the Rx and CCTLURRENTLY PERFORM E ', Vital System Status h ./ication, beginning with Step 2.1 O
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, 3-0 FOLLOW-UP ACTIONS (CONT'D)
( ACTIONS DETAILS v
- 3.5 Verify imbalance within limits.
See OP-103D, Withdrawal Limit Curves.
-1E imbalance is @l within limits, IllEN trip the Rx and CONCURRENTLY PERFORM E0P-2, Vital System Status Verification, beginning with Step 2.1 3.6 1E vibration was NOT due e CONCURRENTLY PERFORM AP-510, Rapid to plant equipment, Power Reduction, beginning with IllEN start a controlled Step 3.1 plant shutdown.
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, - 3.0 F0LLO'l-UP - ACTIONS (CONT'D) .
ACTIONS gy
-3.7-
. Verify RCS integrity.
- Monitor available parameters: '- -
RCS PRESS 1
PZR' level-
RCS level
-level, i
If RCS integrity is lost,.
Jillh 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, I Review main generator H 2 containment, pressure.
2 Determine if Non-lE battery charger is unavailable.
_ _ _ . If main generator H, 1 Jf TB evacuation is required, containment is degraded or THEN perform the following:
lost, AND the following exist: Notify plant personnel over PA.
,Q Main generator H,
(> pressure exists Repeat PA announcement.
Main generator is not 2 Notify SP0 to CONCURRENTLY on line PERFORM E0P-14, Enclosure 14, Station Blackout Main Generatcr I!!EN purge the main Purging.
generator. .
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3.9 Verify BWST is not in recirculation with SF
- pumps.
If the BWST is in 1 Stop recirculation.
recirculation with SF pumps, 2 Notify PPO to ensure SFV-13 THEN stop recirculation. "BWST Supply Iso" is closed (119 ft AB by SFPs).
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, 3.0 FOLLOW-UP ACTIONS (CONT'D)
- [~'I ACTIONS
%J ki. TAILS 3.10 Notify Chemistry to sample e RCS ~
for fuel failure, e SF pool 3.11 Verify-SF pool integrity, o _0bserve SF pool _ level e Notify PP0 to inspect SF pool liner telltale drains (95 ft AB MVP cubicles).
IE SF pool leakage has '
increased, IHEN contact TSC for guidance.
( 3.12- IE refueling canal level-i
. is lowering,--
IHEN CONCURRENTLY PERFORM AP-1080, Refueling Canal.
Level Decrease, beginning i with Step.3.1-1 A
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. 3.0 FOLLOW-UP ACTIONS (CONT'D)
ACTIONS DETAILS 3.13 1E at any time, it becomes
- Notify maintenance to inspect necessary to manually- switchgear and internals for energize an electrical damage, bus, Iti@ ensure bus'is capable e __ Ensure DC power and protective of being energized, relaying available.
RQlE 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. ~
9 3.14 Verify ES 4160V buses are energized.
IE either ES 4160V bus is NOT energized,
[. lt!G CONCURRENTLY PERFORN
's AP-770, Diesel Generator Actuation, beginning with Step 3.1 O
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Applicable carry-over steps:
'v(] 3.13 lE it becomes necessary to manually energize an electrical bus...
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_, 3.0 FOLLOW-UP ACTIONS-(CONT'D)
ACllQM D.fl&I.LI M
t Evaluatien of plant alarms shcald consider spurious actuation due to seismic activity.
3.15- Review available plant e Review sump levels, radiation parameters, monitors and tank levels for possible leaks.
e Observe control room temperature. ,
o Review system status relative to alarms, lockouts and configuration that may be a result of relay chatter.
See Enclosure 1, Potential Spurious Alarms.
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- Review containment integrity.
=3.16 Notify PPO to perform a e Verify' power is av'ailable to any walk down of the primary .
waste gas compressor:
plant.
WDP-1A (95 ft AB Rad Waste
?anel)
( WDP-1B (95 ft AB Rad Waste-Panel)~
e Walk down primary plant structures and equipment to t.etermine if damage inhibits the safe operation of plant equipment.
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Applicable carry-ever steps:
( 3.13' If it becomes necessary to manually energize an electrical bus..,
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, 3.0 FOLLOW-UP ACTIONS (CONT'D)
ACTIONS DETAILS 4
3.17- Notify SP0 to perform a e Observe H, tank for possible - -
Walk down of the secondary leaks.
plant, e Observe FSTs for leak (s),
o Determine if the following equipment is accessible and manual operation is N_QI inhibited:
_ ARV-48 "B Condenser Vacuum Bkr" (119 ft TB Above C Waterbox)
ARV-49 "A-Condenser Vacuum Pkr"
'(119 ft TB Above B Waterbox)'
FSV-918 "FST to CDT-1. Cross-Tie-Iso" (119 ft Berm by FST-1A)
MSV-25 "A OTSG Atmospheric Dump" (119 ft IB)
MSV-26 "B OTSG Atmospheric Dump" (119 ft IB)
EFV-36 "EFW & AFW Suction Iso from Hotwell"'(95 ft TB between ;
B&C. inlet waterboxes) e Verify proper operation of the in-service IA dryer .(95 ft TB):
IADR IADR-2 e Walk down secondary plant structures and equipment to determine if damage inhibits the ;
safe ' eration' of plant' '
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Applicable carry over steps:
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LJ 3.13 jf it becomes necessary to manually energize an electrical bus...
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. ),,0 FOLLOW-UP ACTIONS ~-fCONT'D)-
ACTIONS'- DETAILS 3.18 Review current plant .- ~
activities for any-actions that may have caused the vibrations.
3.19 _._ - Evaluate _ results of plant e E FST-1A is HQI available,
' walk downs and initiate IRB time to begin cooldown necessary actions, based on available water inventory is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- IE required equipment is @I accessible.or manual- operatten is inhibited, IBffi initiate action to establish access and restore manual operation capability.
- _ _ IE an-IA dryer is HQ1 available, IBEtt initiate action to
),. periodically blow down air _-
receivers. ,
e -J1 control room temperature-is HQI being maintained between-
-70'F and 80'F, IBEll initiate action to operate .
CHHE-1A or CHHE-1B as required.
e IE power is HQI available to a waste gas compressor, Ih@ consider aligning the WG-header to the AB. ventilation system based'on WG header PRESS.
.1E-1B is HQI accessible due to high temperature, NiQ manual operation of ADVs-is required, IRB notify SP0 to open !B doors to TB:-
H201 (119 ft TB)
__._ H202 (119 ft TB)
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Applicable carry-over steps:
( 3.13 11 it becomes necessary to manually energize an electrical bus...
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, ,,- ~3.0 FOLLOW-UP' ACTIONS'(CONT'D)
() ACTIONS DETAILS 3'.20 Notify MNP0 to determine 1 -
subsequent actions and additional survefilance requirements based on results of plant reviews
- and follow-up action.
- 3.21- Notify.I&C Supervisor to
' - perform PT-378, Functional Testing and Calibration of i
-the Triaxial Time-History Accelographs and. Triaxial
- Seismic Switch,-Section 4.2, Action Following a Seismic Event.-
3.22 EXIT-this procedure.
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6.0 ENCLOSUR1_1 EDTENTIAL SPURIOUS ALARMS O
ALARM POINT EQUIPMENT DESCRIPTION CONDITION -
0003 EMERG NUCLEAR SERVICE SEA WATER PP A LOSS OF DC POWER 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 P OVERLOAD 0059 REACTOR BUILDING SPRAY PUMP A OVL'RLOAD 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 0117 CORE FLOOD TANK B LEVEL HIGH 0137 CIRCULATING 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 REH0 VAL PUMP B OVERLOAD 0242 DECAY HEAi 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 08 PAGE 23 of 29 EQ
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5.0 ENCLOSURE 1 PJ1LWT1AL SPURIOUS ALARMS (CONT'DJ O ALARM "I POINT EQUIPMENT DESCRIPTION CONDiil0N - -
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
-057B UNIT 1 BREAKER 3212 LOSS Or DC POWER 4
0588 ES AUX XFMR B FEEDER BREAKER 3220-- LOSS OF DC POWER 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 0650 4160V-ES BUS A P0T 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 B'JS '3 P0T XFMR TROUBLE 0672 480V HEATING AUX BUS 3 POT XFMR TROUBLE 0673 ES MCC 3B FREAKER 3340 LOSS OF DC POWER 0674 ES MCC Al BREAKER 3341 LOSS OF DC POWER 0677 ESMCC[BBREAKER3361 LOSS OF DC POWER O
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,._ 5'. 0 ENCLQSURE 11 POTEN11AL SPURIOUS ALARMS (CCNT'D)
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ALARM POINT EQUIPMENT DESCRIPTION CONDITION -
0679- ES MCC AB BREAKER 3360 LOSS OF DC POWER 0713 GEN HEUT GND LOCK OUT RELAY LOSS OF OC POWER 0714 STEP-UP XFMR/ GEN DIFF LOCK OUT RELAY LOSS OF DC POWER 3
0715 GN DIFF LOCK OUT RELAY LOSS OF DC POWER 0730 BACKUP ES XFMR MASTER TRIP LK\0T RLY LOSS OF DC POWER 0897- STf. TION 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 1033 MAKEUP PUMP 1A OVERLOAD 1039 MAKEUP PUMP IB '0VERLOAD !
1044 MAKEUP PUMP IC LOSS OF DC POWER 3045 MAKEUP PUMP IC OVERLOAD 1098 MAKEUP PUMP IB-LOSS OF DC POWER i 1099- MA4EUP PUNP IB OVERLOAD 1175 REACTOR TRIP LOCK 0UT 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 OC POWER 1189 4160V ES BUS B CROSS TIE CIRCUIT LOSS OF DC POWER i A
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6.0 ENCLOSURE 1 POTENTIAL $PUR1005 ALARMS (CONT'D)
O ALARM P0lNT EQUIPMENT UESCRIPTION CONDITION - -
1259 MOTOR DRIVEN EF PUh.' A
__ LOSS OF DC POWER 1260 MOTOR DRIVEN EF PUMP A OVERLOAD 1554 CNTRL COMP!X WATER ClilLLER A CHHE-1A 1055 0F DC POWER 1555 CNTRL COMPLX WATER CHILLER 8 CHHE-18 LOSS OF DC POWER 1824 EMERGNUCSERVCCCPUMPA(SWP1A) 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 O
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