ML20199E431

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Rev 8 to AP-961, Earthquake
ML20199E431
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 01/23/1998
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20199E419 List:
References
AP-961, NUDOCS 9802020153
Download: ML20199E431 (29)
v • d • e


Text

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EQ REV 08 AP-961 n

EARTHQUAKE INFO RV ATION 1.0 ENTRY CONDITIONS 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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Approved by MNP0 h#

TA/ Date / /22/96

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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

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conditions.

Plant Operators e

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

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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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I 3-0 FOLLOW-UP ACTIONS (CONT'D)

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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-

_ MUT level RB Sump level-.

RCS level Notify PPO to monitor AB Sump

-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,

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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,

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e SF pool 3.11 Verify-SF pool integrity, o

_0bserve SF pool _ level Notify PP0 to inspect SF pool e

liner telltale drains (95 ft AB MVP cubicles).

IE SF pool leakage has increased, IHEN contact TSC for guidance.

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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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o 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.

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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:

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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.

A 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)~

Walk down primary plant e

structures and equipment to t.etermine if damage inhibits the safe operation of plant equipment.

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Applicable carry-ever steps:

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3.13' If it becomes necessary to manually energize an electrical bus..,

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4 3.0 FOLLOW-UP ACTIONS (CONT'D)

ACTIONS DETAILS 3.17-Notify SP0 to perform a e

Observe H, tank for possible 4

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 Walk down secondary plant e

structures and equipment to determine if damage inhibits the safe ' eration' of plant' eqv *.e,

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Applicable carry over steps:

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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.-

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activities for any-actions that may have caused the vibrations.

3.19 _._ - Evaluate _ results of plant E FST-1A is HQI available, e

' 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 _-

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receivers.

-J1 control room temperature-is e

HQI being maintained between-

-70'F and 80'F, IBEll initiate action to operate CHHE-1A or CHHE-1B as required.

IE power is HQI available to a e

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:

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3.13 11 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 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

-the Triaxial Time-History i

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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l 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 ESMCC[BBREAKER3361 0677 LOSS OF DC POWER O

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5'. 0 ENCLQSURE 11 POTEN11AL SPURIOUS ALARMS (CCNT'D)

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U 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

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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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