ML20199G520

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Rev 11 to AP-961, Earthquake
ML20199G520
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 01/15/1999
From:
FLORIDA POWER CORP.
To:
References
AP-961, NUDOCS 9901220319
Download: ML20199G520 (30)
v • d • e


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, j Docum:nt Transmitt,al #; 110389 ' Date: 1/15/99 i To: NRC (DC DESK) MAC: N/A Holder #: 1242 Destination:

Description:

Copy Totals Document: Revision: 11 IC# Comment: INF CTL MST AP0961 11 MINOR CHANGE 1 0 0 l

instructions to the Addressee: Please verify the document (s) received agrees with the above inf:rmation. Notify Document Control if changes are required to addressee information, or mark th] transmittal and return as indicated below.

Engineering managers are required by NEP-121 to determine if new, revised, or temporary changes to procedures affect job functions of their personnel. Managers will communicate change information appropriately and provide documentation of any training conducted to the ingineering Training Coordinator.

Operations department must attach old document (s) or portions of document (s) superseded by the above to this transmittal.

The signature indicotes ackrsowledgment of receipt of the above document (s) and that documents have been updated. Return signed and dated transmittal to Document Control within 15 working days of transmittal date to mall code:

l SA2A i

l Florida Power Corporation Document Control, SA2A Crystal River Energy Complex 16760 W. Power Line St.

Crystal River, FL 34428 6708

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220001 1 Signature of Addressee: Date:

9901220319 990115  % ,

PDR e

ADOCK 0500 3 2a \ l l

n EQ REV 11 (MC) AP-961 l

EARTHOUAKE l 1.0 ENTRY CONDITIONS JF an earthquake is suspected.

AND seismic recorder indicates a seismic event has taken place.

THEN use this procedure. l 2.0 IMMEDIATE ACTIONS l

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NOTE  !

l There are no immediate actions for this procedure. 1 i

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On Approved by MNPO . N/ FMkDate'////f[97 SIGRATURE ON FILE)

AP-961 PAGE 1 of 29 E0 l

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~c 3.0 FOLLOW UP ACTIONS *

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Gi ACTIONS DETAILS 3.1 Notify personnel of plant . STA conditions.

. Plant Operators

. NSM (evaluate plant conditions for potential entry into the Emergency Plan) 3.2 E the Rx is NOT critical. I THEN GO TO Step 3.7 in this procedure.

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3.3 IF,> 1 asymmetric control rod exists.

THEN trip the Rx and ,

CONCURRENTLY PERFORM l

rx E0P-2. Vital System Status

(), Verification. beginning with Step 2.1 3.4 Verify q;adrant power tilt is within limits See COLR.

E quadrant power tilt is tj01 within limits, THEN trip the Rx and CONCUFRENTLY PERFORM E0P-2. Vital System Status Verification, beginning with Step 2.1 1

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A l AP-961 REV 11 (MC) f%0E 3 of 29 E0 l

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l E0 REV 11 (MC) AP-961 l

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'v) EARTHOUAKE 1.0 ENTRY CONDITIONS JE an earthquake is suspected.

AND seismic recorder indicates a seismic event has taken place.

THEN use this procedure.

2.0 IMMEDIATE ACTIONS NOTE There are no immediate actions for this procedure.

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Apn.oved by MNPO . N V ~(SIGRATURE ON FILE)

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AP-961 PAGE 1 of 29 E0 1

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3.0 FOLLOW UP ACTIONS ACTIONS DETAILS 3.1 Notify personnel of plant . STA' conditions.

. Plant Operators

. NSM (evaluate plant conditions for potential entry into the Emergency Plan) i 3.2 E the Rx is NOT critical.

THEN GO TO Step 3.7 in this procedure.

3.3 E > 1 asymmetric control rod exists.

THEN trip the Rx and CONCURRENTLY PERFORM

'O E0P-2. Vital System StctJs
s Verification. beginning i

with Step 2.1 i l

3.4 Verify quadrant power tilt is within limits.

l See COLR.

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l E quadrant power tilt is

! NOT w'ithin limits, THEN tri) the Rx and

l. CONCURREfILY PERFORM l E0P-2. Vital System Status i

Verification. beginning with Step 2.1 O

! AP-967. REV 11 (MC) PAGE 3 of 29 E0 i

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.3.0 FOLLOW UP ACTIONS (CONT'D) ,

ACTIONS DETAILS l

3.5 Verify imbalance within l limits.

See OP-103D Withdrawal  !

l Limit Curves.  !

l IE imbalance is NOT within i i

limits. I THEN trip the Rx and CONCURRENTLY PERFORM l E0P-2. Vital System Status  ;

I Verification, beginning '

with Step 2.1 l L l 3.6 IE vibration was.NOT due e CONCURRENTLY PERFORM AP-510. Rapid i to )lant equipment. Power Reduction, beginning with  ;

'THE 9 start a controlled Step 3.1 plant shutdown.  !

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3.0 FOLLOW UP ACTIONS (CONT *D)

, /O ACTIONS DETAILS t/

3.7 Verify RCS integrity. . Monitor available parameters:

1 RCS PRESS PZR level l 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")

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l JF RCS integrity is lost.

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 H2 containment has been lost.

3.8 Verify main generator H z 1 Review main generator Hz containment. pressure.

2 Determine if Non-1E battery charger is unavailable.

E main generator H 2 1 E TB evacuation is required.

containment is degraded or THEN perform the following:

lost.

AND the following exist: Notify plant personnel over PA.

p Main generator H 2 y, pressure exists Repeat PA announcement.

Main generator is not 2 Notify SPO 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.

E the BWST is in 1 Stop recirculation.

recirculation with SF pumas. 2 Notify PPO to ensure SFV-13 THE1 stop recirculation. "BWST Sup)1y Iso" is closed (119 ft A3 by SFPs).

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3.0 FOLLOW UP ACTIONS (CONT'D)

ACTIONS DETAILS 3.10 Notify Chemistry to sample e RCS for fuel failtire.

  • SF pool- -

3.11 Verify SF pool integrity. . Observe SF pool level e Notify PPO to inspect SF pool liner telltale drains (95 ft AB ,

MVP cubicles). i

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IE SF pool leakage has I increased. I THEN contact TSC for I guidance.

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3.12 JE refueling canal level O 1s lowering.

THEN CONCURRENTLY PERFORM

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AP-1080. Refueling Canal  :

Level Decrease, beginning with Step 3.1 i

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~AP-961 REV 11-(MC) PAGE 11 of 29 EQ

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3.0 FOLLOW UP ACTIONS (CONT'DJ

'/'~^, ACTIONS DETAILS

'w) 3.13 IE at any time, it becomes . Notify Maintenance to inspect l necessary to manually switchgear and internals for energize an electrical damage.

bus. .

THEN ensure bus is capable . Ensure DC power and protective l of being energized. relaying is available. '

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NOTE Seismic activity may result in spurious operation of the sudden pressure relays for the Off Site Power Transformer or the BEST I resulting in a loss of off site power. 1 I

3.14 Verify ES 4160V buses are l

energized.

IF either ES 4160V bus is  !

TidT energized.

,e 3 l' THEN CONCURRENTLY PERFORH

(',) AP-770. Diesel Generator Actuation, beginning with Step 3.1 l

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AP-961 REV 11 (MC) PAGE 13 of 29 E0

Applicable carry-over steps: . .

3.13 IE it becomes necessary to manually energize an electrical bus.. g O

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3.0 FOLLOW UP ACTIONS (CONT'D)

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u ACTIONS DETAILS NOTE Considw spucious 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.

. Observe Control Room TEMP.

. Review system status relative to alarms, lockouts and configurations that may result from relay chatter.

See Enclosure 1. Potential Spurious Alarms.

. Review containment integrity.

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3.16 Notify PPO to perform a . Verify power is available to any primary plant walk down. waste gas compressor (95 ft AB on "RADWASTE CONTROL PANEL"):

WDP-1A WDP-1B

. 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)

A_CTIONS DETAILS 3.17 _. . Notify SP0 to perform a . Observe Hz tank for possible secondary plant walk down. leaks.

. Observe FSTs for leaks.

FST-1A FST-1B e 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)

O 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 C & D inlet waterboxes) e Verify proper operation of the in-  !

service IA dryer (95 ft TB): l IADR-1  !

IADR-2 I

e Walk down secondary plant i structures and equipment to l determine if damage inhibits the safe operation of plant  ;

equipment.

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Applicable carry-over steps: .

3.13 JE it becomes necessary to manually energize an electrical bus... g O

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-3.0 FOLLOW UP ACTIONS (CONT'D)

ACTIONS DETAILS 3.18 Review current plant-activities for any actions that may have caused the

!. ivibrations.

l-l 3.19 Evaluate results of plant . Jf required equipment is NOT walk downs and initiate accessible or manual operation necessary actions. is inhibited.

THEN initiate action to establish access and restore manual operation capability.

. [F an IA dryer is NOT available.

~ HEN initiate action to

'perTodically blow down air receivers.

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J_F Control Room TEMP is NOT between 70 and 80 F, g initiate 1A or action CHHE-1Btoasoperate required.

. Jf power is NOT available to a waste gas compressor,  !

THEN consider aligning WG header 1

-to AB ventilation system based .

on WG header PRESS.  !

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. IF IB is NOT accessible due to l

h. TEMP, AN manual operation of ADVs is required, THEN notify SP0 to open IB doors l to TB (119 ft TB):

H-201 i

-H-202 L

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Applicable carry-over steps: .

3.13 JE it becomes necessary to manually energize an electrical bus. g  ;

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3.0 FOLLOW UP ACTIONS (CONT'Dj_

(D ACTIONS DETAILS

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3.20 E RCS cooling is by Nat .

E FST-1A is NOT available.

Circ, THEN begin cooldown within 8 THEN ensure adequate hours to ensure adequate secondary inventory. secondary inventory.

. Notify SPD to open EFV-36 "EFW &

AFW Suction Iso From Hotwell" >

(95 ft TB between C and D inlet waterboxes). ,

. E EFV-36 cannot be opened.

THEN notify TSC.

3.21 Notify MNP0 to determine i subsequent actions and '

additional surveillance requirements based on results of plant reviews and follow-up action. i L_./

3.22 Notify I&C Supervisor to perform PT-378. Functional Testing and 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 1 P0TENTIAL 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 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 0117- CORE FLOOD TANK B LEVEL HIGH 0137 CIRCULATING WATER PUMP A DISCH PCESS HIGH 0212' DECAY HEAT CLOSED CYCLE PUMP A LOSS OF DC POWER 0213 DECAY HEAT CLOSED CYCLE PUMP B LOSS OF DC POWER 1 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 3REAKER 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 O

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5.0 ENCLOSURE 1 POTENTIAL SPURIOUS' ALARMS (CONT'D)

ALARM 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 0578 UNIT 1 BREAKER 3212 LOSS OF DC POWER 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 POT XFMR TROUBLE 0652 4160V ES BUS B POT XFMR TROUBLE i 0654 480V ES BUS A POT XFMR TROUBLE 0656 480V ES B POT XFMR TROUBLE I

0664 480V TURB AUX BUS B POT XFMR TROUBLE 0670 480V PLANT AUX BUS 3 POT XFMR TROUBLE l  ;

0672 480V HEATING AUX BUS 3 POT XFMR TP0UBLE 0673 ES MCC 3B BREAKER 3340 LOSS .)F DC POWER 0674 ES MCC Al BREAKER 3341 LOS[0FDCPOWER l 0677 ES MCC AB BREAKER 3361 LOSS OF DC POWER l AP-961 REV 11 (MC) PAGE 25 of 29 E0 l

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5.0 ENCLOSURE 1 POTENTIAL SPURIOU$ ALARMS (CONT'D) rw 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 LOS5 0F DC POWER 0715 GEN DIFF LOCK OUT RELAY LCSS OF DC POWER 0730 8ACKUP ES XFMR MASTER TRIP LK\0T RLY LOSS OF DC POWER 1

0897 STATION AIR COMPRESSOR A OVERLOAD l 0903 STATION AIR COMPRESSOR B OVERLOAD 0909 INSTRUMENT AIR COMPRESSOR A OVERLOAD l

0915 INSTRUMENT AIR COMPRESSOR B OVERLOAD 1032 MAKEUP PUMP 1A LOSS OF OC POK R

(' 1033 MAKEUP PUMP 1A OVLRLOAD l y _._.

I 1039 t%KEUP PUMP IB OVERLOAD 1 l

1044 MAKEUP PUMP 1C LOSS OF DC POWER l 1045 MAKEUP PUMP 1C OVERLOAD 1098 MAKEUP PUMP 1B LOSS OF DC POWER 1

1099 NAKEUP PUMP 1B OVERLOAD l 1175 REACTOR TRIP LOCK 0UT RELAY LO'sS 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 0VT RLY LOSS OF DC POWER 1189 4160V ES BUS B CROSS TIE CIRCUIT LOSS OF DC POWER I k

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5.0 ENCLOSURE 1 POTENTIAL SPURIOUS ALARMS (CONT'D)

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\J ALARM POINT EQUIPMENT DESCRIPTION CONDITION 1259 MOTOR DRIVEN EF PUMP A LOSS OF DC 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-18) OVERLOAD 1853 EMERG NUC SERV CCC PUMP A LOSS OF DC POWER 1854 EMERG NUC SERV CCC PUMP B LOSS OF DC POWER 1991 1160V RX AUX BUS POT XFMR TROUBLE u

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