Attachment ZZ

PACIFIC GAS AND ELECTRIC COt:PAt!YDEPART!1Et;T OF i!UCLFAP. PLAt!T OPERATIONS

DIABLO CANYON POKER PLAN!T UN!IT NOS. 1 AND 2EtlERGENCY OPERATING PROCEDURE NO. OP-1

TITLE: LOSS OF COOLANT ACC IDEtlT

SCOPE

This procedur e covers the operating steps to be taken in the event of a Lossof Coolant Accident. It is assumed that reactor trip and safety injectionactuations have occurred. The operator should have already performed theimmediate operator actions and diagnostics of Emergency Operating ProcedureNlo. OP-O.

SYP.PTO'1S

(See OP-0 Symptoms/Diagnostics)

AUTOMATIC ACTIONS

(See OP-O)

OBJECT IVES

I'REI.IMIhtAPY

l. Verify and establish short term core cooling to'revent or minimizedamage to the fuel cladding and release of radioactivity.

2. tlaintain long term shutdown and cooling of the reactor by recirculation o,spilled reactor coolant, injected water and containment spray drainage.

3. In the case of the small break LOCA, to reduce plant conditions to the coldshutdown condition for repairs.

It1HED TATE OPERATOR ACTIONS

1. Perform the immediate opera or actions and diagnostics in the reactor tripwith S fety Injection Emer"ency Procedure OP-O.

SUBSEQUENT OPERATOR ACTIOt!S

ACTION

l. Initiate the site Emergency alarm.2. Declare this event a SITE EtlERGENCY.

Carry out the instructions given inthe E'mergency Procedures GeneralAppendix 2 (Notification of Off-SitePersonnel IN THE EVENT OF EtlERGENCY).

COt1NlENTS

PAGE 1 OF 34

APPROVAL

REVISION 2

PLAttT SUPERINTENDENT

4/22/BO

DIABLO CAhYO'f POKER PLA.'iT Ul'lIT tlOS. 1 AiiD 2EilERCiEtlCY OPERATIt,'6 PROCEDURE it0. OP-1

LOSS OF COOLAilT ACC IDENT

ACTrO;~ C$4HEi/TS

3. Honitor the R';,'ST level closely~throughout this procedure . Ir,RHST level is decreasing rapidly,such that the low level RHR pumptrip setpoint 35,'opears imminent,go directly to App ndix A, LOCAInjection/Recirculation ChangeoverProcedure, attached. l'hen AppendixA is completed, return to thisprocedure and continue.

Verify containment sump level in-creasing. If no increase isevident, r eturn to OP-0 diagnos-tics, steps 3, 4 and 5, toreevaluate the accident.

3. In the worse case, with PCS near0 psig and minimum Tech. Spec.level in R!IST with all ECCSequipment discharging includingcontainment spray, the Operator ~has 14 min. from time of breakto RHST lo level.

4. In the case of the small break,the sump may rise slowly.

5.

6.

Verify steam generator levels beingmaintained and flow approximatelyequal to all stean generators. Ifany steam generator level increasesin an unexpected manner, go to OP-3(Steam Generator Tube Rupture).

tlonitor the condensate storage tankand upon reaching 7.5': level, per-form a. or b. below.

a. If this accident is associatedwith a seismic event, go toAppendix C (AF'ump SuctionSupply from Fire later TankProcedure).

b. If this accident is l'OT asso-ciated with a seismic event,verify a level in the raw waterstorage reservoir; then openFCV 436 and 437 (reservoir supplyto AFs'l pumps) ~

5. Steam generator tube rupturesmay be indicated.

6. Lo lo level alarm at 24" in theCST gives the operator 20minutes to perform items a. or b.

a. Allow the AFH pumps to runduring the transfer. Honitorthe AFH pumps until the trans-fer is complete then restartthe pumps.

b. If.a seismic event occurs sub- ~sequent to step b. and AFHp fl i 1,~i:.ditrip all three AF'H pumps andirmediately proceed to AppendixC to supply FH pump suctionfrom the fire water tank.

7. Monitor wide range RCS hot leg temp-atures. If any temperature approaches700'F, assign an operator to performAppendix F (Determination of AdequateCore Cooling.)

7. Also moni tor P-250 point U0091,average core thermocouplereading 'F.

PAGE 2 OF 34 REYISIOZ DATE 4/22/80

~ DIABLO CANYON POWER PLANT UNIT NOS. 1 AtlD 2Et1ERGENCY OPERATING PROCEDURE NO. OP-1

LOSS OF COOLANT ACCIDENT

ACTIOi'I COt 1f

DIABLO CAHYOll POa>ER PLA.'aT UHIT tlOS, 1 AfIQ

EHERG l'ICY OPERATIllG PROCEDURE ilO. OP-1

LOSS OF COOLAilT ACCIDENT

ACTION

c. Close the BIT inlet and outletvalves 8803A and B, 8801A.andB. '„

d. Verify AC turbine bearing oilbackup pump and Hi pressureseal oil pump running after oilpressure decays to 11 psig andturbine bearing lift "„'..-.p startsat 600 RPH turbine s„-. eed.

e. Establish normal char,ing.

1) Open instrument air valvesFCV-584 and 682.

2) Check open or oo n normalcharging valve 8146.

3) Close or check closed chargingto auxiliary spray valve 8145and alt. charging valve 8147.

4) Open charging line isolationvalves 8107 and 8108.

COililEi)TS

equipment, onto the vital bussesmanually. If safety injectionis reinitiated manually afterthe loss of off-site power, thevital busses will automaticallysequential ly load the safeguardequipment.

If off-site power is lostafter'he SI signal is reset,go to Appendix G (Blackou with ~SI Emergency Loading of VitalBusses).

CAUTIOH: Stop one CC pump at atime and evaluate RCS pressure.If RCS pressure drops below 1975 ~psig or PZR level drops b low23K; or RCS subcooling dropsbelow 35'F, reinstate SI andreturn to step 1 of the diag-nostics in OP-0. If chargingpumps are restarted after this ~step, add 15'F of subcooling tothe SI termination criteria ofstep 9.c.

d. Verify the unit goes on turrainggear at 0 RPil.

PAGE 4 OF aa REVISIOn 2 DATE 4/22/80

DIABLO CANYON PO'nER PLANT UNIT NOS. 1 ANDBiERGEHCY OPERATING PROCEDURE NO. OP-1

LOSS OF COOLANT ACCIDENT

ACT'tOtl

5) Adjust HCV-142 and FCV-128 orreciprocal charging pump speedto achieve RCP seal flow andcharging flow as required tomaintain pressurizer levelgreater than 25/.

6) Open RCP seal return valves,ll0 8100 and 8112. Check seal'flow normal.

f. Establish normal letdown.

1) Yer ify containment area r adi-ation monitor reading approxi-mately post accident level.

2) Open letdown valves LCV-459and 460.

3) Open letdown isolation valve. 8152.

4) Open one 75 gpm letdown orificevalve.

5) Verify PCY-135 op ..ing byobserving letdown flow.

g. Establish VCT makeup and transfercharging pumps suction to YCT.

1) Adjust VCT makeup blend to theno-load concentration.

2) Open YCT outlet valves LCV-112Band C after VCT level normal.

3) Close RHST to charging pump suctionvalves 8805A and B.

4) Yerify divert valve LCV-112A inAUTO.

COY'IENTS

5) Automatic PZR level control maynot be possible at this time dueto the TAYG signal inaccuraciesor TAVG being out of the normalcontrol band.

1) Containment area hi radiationmay mean fuel damage. Ifcont. hi radiation exists, donot establish letdown outsidecontainment. Establish let-down to the PRT if letdown isrequired.

PAGE 5 OF REY I5 ION 2 DATE 4//22 80

DIABLO CANYON PO';lER PLAr,'T u;iIT HOS. 1 AriD 2BlERGEtlCY OPERATIiiG PROCEDURE HO. OP-1

LOSS OF COOLl'ilT ACCIOEtlT

ACTION

h. Verify at least one RCP runningI'r verify a bubble in the PZRand establish conditiors orstarting at least one RCP.If conditions for starting anPCP exist, start at least oneRCP.

COI ii~lEhTS

h. The criteria given in OP-0 forstopping the RCP's on lowpressure still applies: CheckSI pump flow and stop pumpsat. PZR pressure 1365 psig.

i. Stop both PHR and SI pumps.j. Stop all 3 diesel generators if

off-site oower is available andplace diesel generator controlswitches in AUTO.

k. With pressurizer level greaterthan 20/, verify pressurizerheaters controlling pressure.

12. Verify using the RCS subcoolingmonitor that 35'F subcooling ispresent.

13. If 35'F subcooling is present and canbe maintained, proceed with a normalcooldown using Operating ProcedureL-5, if required, to perform

repairs'f

reapirs are not required, maintainhot standby conditions until authorizedto proceed by the Plant Superintendent.

If 35'F subcooling is no indicated,attempt to establish 35=F subconlingby steam dump from the steam generatorsto the condenser or atmosphere.

a. If steam dump is necessary, reducethe steam generator pressure to840 psig and maintain a RCS cool-down rate of less than 50'F/HR,consistent with the CVCS makeupcapability.

14. If 35'F RCS indicated subcooling can-not be verified and maintained, reini-tiate safet'y injection and return toOP-0 Diagnostics, step l.

13. The criteria for trippingreactor coolant pumps on lowpressure will not apply if acooldown using OperatingProcedure L-5 is performed.

a. If steam dump at the reducedpressure setting is used tomaintain subcooling, proceed tocooldown the plant usingOperating Procedure L-5.

PAGE 6 OF 34 REVISION ~ DATE 4 L22/~

DIABLO CANYON POklER PLAIIT Ui'VIT LOS. 1 A"D 2EtiERGEHCY OPERATIIVG PROCEDUPE NO. OP-1

LOSS OF COOLANT ACCIDEllT

ACT IOi'l CQI'ji'IEllTS

15. If closing the PORV and backupvalves in step 8 failed to re-cover the RCS pressure, maintainMAX SI flow and proceed to step16.

15 ~ If this is the case, then weprobably have an unisolatablebreak in the primary sys em.

16.

17.

If SI termination criteria instep 9 could not be met, main-tain t'iAX SI flow and proceed tostep 16.

If any SI equipment has failed,attempt to operate the equipmentlocally or from the control room.Effect repairs if necessary.If the RCP's are operating, stop 17.all 4 RCP's after

a. Verifying at least onecharging and SI pumps aredelivering flow

and

If CCll is lost to tho RCP's,stop all pumps within 5 minutesand maintain seal water flow.tlonitor the conditions forstopping PCP's throughout thisprocedure.

18.

19.

20.

b. PZR pressure decreases toless than 1365 psig.

If widerange RCS is above 485psig, stable or increasing,reset safety injection'nd stopboth RHR pumps.

If RCS pressure quickly decreasesbelow the steam c n rators press-ure, go to step 2'..

If PZR pressure is slowly de-creasing or stable and is above

1370. psig, continue with thesteps below.

a. Reduce steam generator pressureto 840 psig using steam dumpby methods B or C below.

b. If the condenser is available,open the main steam isolationvalves and dump steam to thecondenser using the steam

18. This is the shutoff head of theRHR pumps using RCS wide rangepressure indicator with a badcontainment environment.

19. A large break LOCA is indicated.

20. A small break LOCA is indicated.The instructions given in step20 will aid i.n the cooldown anddepressurization.

a. Reducing steam pressure willlower the RCS pressure andtemperature.

b. Continue to Monitor R';!ST level,as RCS pressure decreases SIflow will increase Rt!ST leveldecrease will accelerate. I,

PAGE 7 OF 34 REVISION 2 DATE ~//22 80

DIABLO CANYON PO"E'ER PLANT UNIT ttOS. 1 Al'IU 2EMERGENCY OPEPATING PROCEDURE NO. OP-1

TITLE: LOSS OF COOI ANT ACC,~,-.,:,T

ACT!01! C0l!I'IBiTS

pressure mode. pressurizer level has beenlost, monitor PZR level in-dication for its return.

c. If the condenser is no avail-able, use the 10'tmosph ricdumps.

d. Maintain a RCS cooldown nogreater than 100'F/HR.

e. 51onitor the subcooling marginmeter, if 57 F subcooling canbe achieved with the cooldown,continue to cool ;ihile monitor-ing the cooldown rate of 100'F/HR.If PZR level is above 32/,attempt to take the plant to coldshutdown usin!g Operating Pro-cedure L-5. Continu to monitorfor the above conditions andprocede with the procedure step21.

21. If containment hi-hi pressure hasinitiated containment spray

a. Verify the additive tank levelis decreasing. and th t theentire tanks is discharged.

b. Maintain contai.-; —..ent sp~ay untilthe RUST lo lo alarm is reachedor the level indicator indicatesOK level.

c. Reset contair„".ent spray signaland shutdown containm nt spraypumps.

22. Periodically check the auxiliarybuilding radiation r.onitors forECCS leakage if Appendix A hasbeen performed. If leakage isfound, attempt to isolate theleakage; however. do not inter-rupt ECCS flow at any time.

PAGE 8 OF 34 REVISION 2 DATE 4l22'0

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2EHERCiENCY OPERATING PROCEDURE NO OP-1

LOSS OF COOLANT ACCIDENT

23.

ACT!OR

If Appendi x A, LOCA Injec tion/Recirculation Changeover Proce-dure, has not yet been performed,continue to monitor the R'HSTlevel and ~re are for Appendix Ain the following manner.

a. At the 480 volt vital loadcenters F and H, close thebreakers for the following~va ves:

8980 RHR pump supply fromR';(ST 52-1F-31.

8976 SI pump supply fromRHST 52-1H-20.

b. Reset the SI and Phase Bisol ati on s igra 1 s.

c. If off-site power is a-vailable, shutdown all 3diesel generators andleave them in auto.

d. Close (CUT IN) the seriescontactors for the follow-ing valves using the toggleswitches in the control room.

8809A and B, PH."-. pu.psInjection to cold legs.

8974A and B, SI pump Recirc.

8982A and B, PHR pumps suctionfrom containment sump.

Cour�>ENTS

a. This will allow operation ofvalves during Appendix A. DONOT make any valve operationat this time.

b. Reset only. Do not start orstop any SI equipment.

d. This will allow operation ofvalves during Appendix A. DONOT make any valve operationsat this time.

e. Yiaintain fu'll Sl flovi until '.the R!!ST lo

DIABLO CA!iYOH PO'ilER PLAllT Ut'iIT t'

DIABLO CAifYON POriER PLANT U,"iIT hOS. 1 AND 2BlERGEhCY OPERATIhG PROCEDUPE h0. OP-1TIT«: LOSS OF COOLAi T ACCIDENT

CO) li~lEtlTSACTIOi"t

c. Regulate no. 1 RHR pumpflovi using its hand controlvalve (flCV-638) to maintain-pump motor current less than57.5 amps.

32. The system" are no:v lined up forthe cold leg recirculation phase.Continue to operat in thismanner for 19-1/2 hours.

During this period, make thefolio;iing motor operated valvesavailable by closing their 480Vbreakers at the vital load centers.

8802A SI pump no. 1 discharge tohot legs 52-1F-48.

8835 SI pump common discharge tocold leos 52-1G-25.

8703 RHR pumps common dischargeto hot legs 52-1G-26.

8802S SI pump no. 2 discharge tohot legs 52-1H-26.

33. Continue to operate in the cold legrecirculation mode for 19-1/2 hours,then procede to Ap" ndix B, Cold LegRecirculation/Hot Leg RecirculationChangeover Procei" . =-.

32. DO liOT make any valv changesafter making the valves avail-able.

PAGE 11 OF 34 REVISIO'< 2 DATE 4/22/80

DIABLO CAhYO|i PQ'rlER PLAht';"IT tIOS. 1 A;.ID 2E'EMERGE|(CY OPEP>ETIf'G PROCEDUPE Op-l AP. E';NOIX ATITLE: ~SOF COOL@!iT ACCIDFiiT

APPED'lOIX A

LOCA INJECTIORECIRCULATIOi't CHAilGE OVER PROCEDURF.

SUBSEQUEsiT OPERATOR ACT IOHS

2.

3,

5.

6.

ACTION

All steps listed below must bcarried out expeditiously, in aprecise orderly sequence. Donot interrupt the oceration untilall actions are completed. Mh nboth ECCS trains are initiallyavailable and a valve fails torespond or to complete its de-manded operation, postpon anycorrective action until the sub-sequent operational steps areperformed.

honitor RHST level closely. Ifthe RHR pumps do not trip a t

%. trip them manually.

If during this operation the R'Yapproaches a 0Ã level, stop allpumps taking suction from the RHST.Restart pumps after the PHR systemis aligned to provide suction.

At the vital 480 volt load centersF and H, close the breakers for the

~erformed

8980 RHR pumps supoly from R'T52-1F-31.

8976 SI pumps supply fran PAiST52-1H-20.

Reset SI and Phase 8 isolationsignals if not alread~ reset.If off-site power is available,shutdown all 3 diesel generatorsand leave them in Auto if thishas not been erformed.

COllHENTS

CAUTIOli: If a loss of off-sitepower has occurred in coincidencewith the LOCA and all 3 dieselgenerators are running andsupplying the vital busses, con-tinue with these instructiors aswritten. If a diesel generatorhas failed, go to Appendix E{Loss of Off-site Power DuringLOCA with Loss of Dies 1 Generator)for additional guidance beforeproceeding.

4. This step may be delayed untiltime permi ts.

PAGE 12 OF 34"

REV IS IOi'i DATE 4/22/80

DIABLO CANYON POWER PLANT Ui'(IT NOS. 1 AND 2EhERGENCY OPERATING PROCEDUPE NO. OP-1 APPENDIX A

LOSS OF COOLANT ACCIDENT

ACTION

APPENDIX A cont.

COP23ENTS

~ 7.

9

1O.

12.

13.

14.

15.

Close (cut in) the series contac-tors for the following valves fromthe toggle switches in the control

~if

8809 A 8 B RHR pumps injection tocold legs.

8974 A 5 B SI pumps recirculation.

8982 A 5 B RHR pumps suction fromsump.

Hith the SI, charging and possiblythe spray pumps still taking suc-tion from the RHST and the RHRpumps tripped at ~4~% in the R! ST,proceed to transfer RHR suction tothe containment sump as follows insteps 9 thru 29.

Check that the containment recirc-ulation sump level indicators readat least ~~to provide adequateNPSH to the RHR pumps.

Close the two RHR heat exchangeroutlet crosstie valves (8716A 8 B).

Close the no. 2 RHR pump normalsuction valve (87OOB).

I

Open the no. 2 RHR pump suctionvalve from the containment recirc-ulation sump (8982B).

Open the component cooling wateroutlet valve from no. 2 RFR heatexchanger (FCY-364.)

Restart no. 2 RHR pump and checkflow to the vessel.

Close the safety injection pumprecirculation valves (8974A 8 B).

8. Monitor R!!ST level, trip allpumps takino suction from theRIIST upon reaching II Slevel in the tank. Restartpumps after RHR suction supplied.

PAGE 13 OF 34 REVISION DATE aa/22/r/0

DIABLO CANYON PO'E'ER PLANT Ut'tIT NOS. 1 ANO 2

EtiERGEtlCY OPERATIilG PROCEDURE VO. OP-1 APPEttDIX ATITLE: LOSS OF COOLANT ACCIDEtiT

ACT IQn

APPENDIX A (cont.)CONNENTS

19.

20.

21.

22.

23

'4.

25.

26.

Anan +he r ~4 ~4vyw I ~ \r I ~ \ 4 ll I c I g 1 I IJ 'e'4 ~r 1 vn p

urn@

suction from RHR pumo no. 2(88048). Check for increasedsafety injection pumo flow andpressure.

Close the safety injection pumpsnormal suction valve (8976 ) fromthe RiiST.

Open the alternate suction valvesfor the centrifugal chargingpumps (8807A 8 B}.

Close the no. 1 RHR pump normalsuction valve (8?OOA).

Open the no. 1 RHR pump suctionvalve from the containment recirc-ulation sump (8982A).

Check the level in the recircu-lation sump again for adequateNPSH.

Open the compon nt cooling watero tlet va'.ve from no. 1 RHR heatexchanger (FCY-365).

Restart tho no. 1 PHR pump an"check for flow to the vessel.

Open the centri fugal chargingpumps alternate suction val ve fromRHR pump no. 1 (8804A). Check forincreased charging pump flow andpressure.

Close the charging pumps normalsuction valves from the R';IST{8805A 8 8).

Close the RHR pumps normal supplyvalve from the RltST (8980).

17. This step may be delayed ifbreakers in step 4. have notbeen racked in.

26. This step may be delayed ifbreakers in step 4. have notbeen racked in.

PAGE 14 OF REVISION DATE 4/22/GG

DIABLO CANYON PO"EP, PLANT UNIT NOS. 1 AND 2ENERGENCY OPERATING PROCEDURE NO. OP-1 APPENDIX A

LOSS OF COOLANT ACCIDENT

ACTION

APPENDIX A cont.

COivit lEfITS

27 llhan tt a lo lo le -1 p---<reached in the RMST, trip bothcontainment spray pumps.

28. If step 4, 17 and 26 were delayed,perform tnese steps at this time.

29. If either RHP, pump failed, eithercontairsnent sump to RHR suctionvalve failed to ope (valves8982A or B) or either RHR Trainto centrifugal charging pumps orSI pumps suction valves 88OCA orB failed to open, go to AppendixD (RHR Train Failure).

30. Return to the LOCA procedure stepthat was left to perform thisAppendix.

27. Trip any other engineeredsafeguard pumps that arestill taking suction fromthe RHST. This will onlybe necessary if the pre-ceding steps have not beencompleted prior to reachingthe lo lo level set point.

PAGE ~ OF 34 REVISION ~ DATE ~~

DIABLO CAIIYON,PQ'ii'ER PLAIIT UtlIT jiOS. 1 AlloBlERGL'jlCY OPERATlliG PROCEOL|RE HO. OP-1 APPE'lDIX B

TITLE: LOSS OF COOLPllT ACCIOEjlT

APPEjiOIX B

COLO LEG RECIRCULATIQ"l/ljOT LEG RECIRCULATIOjl CHAi'lGE OVER PROCEOURE

Hot

2.

3.

4.

5.

6.

7.

8.

9.

10.

ACTl0"'eg

Recirculation Phase

Approximately 19-1/2 hours afterthe injection pha"e, the recirc-ulation flow path is changed rromthe cold legs to the hot legs.

It is important during this phasto insure that two separate andredundant trains of both RHR andsafety injection pumps are estab-lished.

Close the no. 1 RiiR pump cold Ieginjecti on val ve (8809A) .

Close the PHR pump no. 1 valve tothe containment spray header (9003A) ifit is open.Check open the RHR pump no. 1 valveto the safety injectior. pimps andcentrifugal charging pumps (88040).

Shut down both centrifugal chargingpuIIIps and close both BIT '.r.letvalves (8803A and B).

Shutdown no. 1 safety iniection pump..

Close no. 1 safety injection pumpdischarge cr osstie val v (8821A).

Open the no. 1 safety ir,„'ectionpump hot leg injection valve. (8802A).

Start no. 1 safety iniection pump andcheck for rated flow of approximatelySSO gpm.

Close the no. 1 safety injection pu pnormal suction valve (8923A).

CO"'0E'lTS

PAGE 16 OF '4 REY IS IOII DATE IIEE/00

DIABLO CAttYON POWER PLANT UNIT NOS. 1 AtlD 2

EYERGENCY OPERATIi'G PROCEDURE NO. OP-1 APPENDIX 8

TITLE: LOSS OF COOLANT ACCIDEttT

ACTION

APPEt}DIX Bg cont+

COiMENTS

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

Close tile no. 2 RHR pump cold leginjection valve (88098).

Check closed the no. 2 RHR pumpvalve to the containment sprayheader (90038).

Check open the no. 2 RHR pumpto the safety injection pumpsalternate suction valve (88048).

Shutdown no. 2 safety injectionPl ll.iTl,

Close the no. 2 safety injectionpump discharge ci osstic valve(8821B).

Close the safety injection pumpscommon discharge valve (8835) tothe coid legs.

Open the no. 2 safety injectionpump hot leg injection valve(8802B).

Start the no. 2 safety injectionpump and check for rated flow ofapproximately 650 gpm.

Close the no. 2 safety injec ionpump normlal suction valve (89238).

The systems are now set up in twocompletely separate and redundanttrains with each RHR pump supplyinga separate SI pump. No containmentspray or direct RHR recirculationare utilized.

If desi red, direct RHR recir cul a-tion to the hot legs may be usedsimultaneously as follows:

a. Open the No. 1 RHR traindischarge crosstie valve(8716A).

PAGE 17 OF 34 . REY I5 IOIN 2 DATE i~wlpn

DIABLO CAllYO'i PO'rlER PLAtlT UlIl'lOS. 1 AilD 2ENERGEilCY OPEPATIilG PROCEDURE il0. OP-1 APPED lDIX 8

TITLE: LOSS OF COOLAilT ACCIDE'lT

ACT IQII

APPEilDIX 8 cont.

COMVEi'

DIABLO CANYON POVER PLANT UNIT tlOS. 1 AflD 2EH RGEHCY OPERATING PROCEDURE tl0. OP-1 APPEtlDIX CTITLE: LOSS OF COOLAtlT ACCIDENT

APPEti'DIX C

AUXILIARYFEED PUtiP SUCTIOtl SUPPLY FROtl FIRE HATER TAtlK

The operator has 20 minutes to perform this operation after the Lo Lolevel alarm on the condensate storage tank and before the AFlt pumps losesuction. This provides sufficient time; however, the operator must notdelay and must carry out the valve line up in order as ivritten.

If tho AF'll numns aro beinn sunpl iod from +ho raw water roservoir andseismic event occur with res'tan+ loss of A.. H suet.on and aux.llaryfeedwater flow to the steam generators, the steam generators will boildry in about 30 minutes. Under these conditions, it is especially importantto expedite this procedure and reestablish AF'H flow to the steam gen ratorsprior to the reactor losing its heat sink.

ACTIOtl COt'IHENTS

Using the attached draw'.ng, proceed tosupply the AFH pumps suction Idiom thefire water tank.1. Close or verify closed hU-0-284

and NU-0-286.1. Closing these valves prevents

losing fire water out a possiblebreak in the reservoir supplyline.

2. Close or check closed t',U-l-298.

3. Close or check closed tlU-0-325.

4. Close or check closed l1U-0-427.

5. Open FP-0-306 and FP-0-307.

6. Notify the control room tha thesuction for the AFW pumps is nowavailable from the fire water tank.

7. From the control room open FCY 436and 437.

8. Proceed to the auxiliary feedwaterpumps and vent the pump casings ifrequired to remove air .

PAGE 19 OF 3h REV IS IO"l DATE 4/22/80

To FirePumps

Suction

From Raw}/ater Reservoir ~

CloseSTIY

MU-0-284

Fire WaterTank

FP-0-3 6

Open

Open

F -0- 07

Raw Water Hea cClose 'U-1-29]

Seal ed FP-0-4OpenValve

To M.U.

Fi1 ters

Close

VU-0-427

MU-0-325

l Wl ID-t.rilI Xl LOmnr-~ ~ fn

A AIC>Vl Ol/l 0 g)

OOcD C'>I

0Q IH bA

IvlO O

CQnmrn

Ol/lOaI

Cl oseSTR ~!

MU-0-286

AFW

Ppl-1

FCV-436 p<

Open

PackageBoi 1 I.r

Ol owdownM.U. Filter

Bypass

]-207 SealedOpenValve

Open

FCV-437M

AFW

Pp 1-2 ~!1-3

Fire Hater Tank toAFW Pump Suction

0

DIABLO CANYOt< POMER PLANT UNIT NOS. 1 AND 2Ef1ERGENCY OPERATING PROCEDURE f~0. OP-1

LOSS OF COOLANT ACCIDENT

ACTION

APPENDIX 0

RHR TRAIN/COHPONEfi'T FAILURE

A. FAILURE IN RHP, TRAIN NO. 2

Core ENT

1. If RHR pump No. 2 failed, con-tainmert sump to RHR valve8982B or RHR p»mp No. 2 to SIsuction valve 8804B failed toopen proceed w',th steps a.toe. to provide charging and SIpump suction from RHR pumpNo. 1

verify RHR nIImn No. 1crosstie valves to SIpump suction 8807A or.,B open.

b. Close or verify closedTrain No. 2 to SI pumpsuction valve 8804B.

c. Throttle HCV 638 to ersureadequate suction for the SIand c ntrifugal chargingpumps (approximately 20psig above containmentpressure) while maintainingRHR pump motor current lessthan 57.5 amps.

d. Return to the LOCA proceduresteo that was left to performAppendix A.

1. Monitor Ri|ST level, whenthe level reaches thelo lo alarm setpoint,trip all safeguards pumpstaking suction from thetank.

PAGE 21 OF 34 REV IS! ON DATE 4/22/BP

DIABLO CANYON PO'rlER PLANT UNIT NOS. 1 AND 2BiERGENCY OPERATING PROCEDURE NO. OP-1

TITLE: LOSS OF COOLANT ACC IDENT

ACTIQii

APPEIIDIX D

8. FAILURE It) RHR TRAIN NO. 1

COhHENTS

1. If RHR pump No. 1 failed, containmentsump to RHR valve 8982A or RHR pumpNo. 1 to charging pumps suction valve8QOLQ fp i 1 ed +o nnan nrnr aaAsteps a to e to provide chargingand SI pump suc ion froriI RHR pumpNo. 2.

a. Verify RHR pump No. 2 crosstievalves to SI pump suction 880?Aor B open.

b. Close or verify closed TrainNo. 1 to SI pump suction valve8804A.

c. Throttle HCV 63? to ensure ade-quate suction for the SI andcentrifugal charging pumps(approximately 20 psig abovecontainmen't pressure) whilemaintaining RHP, p mp motorcurrent less than 57.5 amps.

'.

Return to the LOCA procedu. estep that was left to performAppendix A.

1. Monitor R!tST level,when the level reachesthe lo lo alarm set-

guards pumps takingsuction from the tank.

PAGE 22 OF 34 REVISION DATE ~

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2EMERGENCY OPERATING PROCEDURE NO. OP-1 APPENDIX E

TITLE: LOSS OF COOLANT ACCIDENT

APPENDIX E

LOSS OF OFF-SITE POWEP. DUPING LOCA WITH LOSS OF DIESEL GENEPATOR

yr~ mes

A. If a diesel generator fails duringthe LOCA procedure, continue withthe LOCA procedure as written untilAppendix A (LOCA Injection/Pecircu-lation Change Over Procedure) is tobe performed. Then follow the guidancegiven below for the alignment forcold leg and hot leg recirculation.

B. Diesel Generator Failure

COhrl NIS

Diesel Generator 1-1 Failure

l. If diesel generator 1-1 hasfailed, the following ste =should be used to align thesystem for cold leg recircu-lation.

a. Verify the followingpumps are running.

ASM Pumps 1 and 2AFW Pump 3Charging Pumps 1 and 2CCW Pumps 1 and 2S I Pump 1C.S. Pump 1RHR Pump 1

b. With diesel generator1-1 failed, do thefollowing steps in theordel given below inAppendix A (LOCA Injec-tion/Recirculation ChangeOver Procedure).

Steps: 2,3,4,5,7,8,9,10,15,18,19,20,21,22,23,24,25~26,27,28,then do step 17.

PAGE 23 OF 34 REVISION DATE ~422/80

DIABLO CAtlYOi't POMER PLAf'IT Ut/IT tlOS. 1 AND 2EhERGEtlCY OPERATING PROCEDUPE t(0. OP-1 APPENDIX E

TITLE: LOSS OF COOLANT ACCIDENT

ACTIOi"

APPEHDIX E (Cont.)

COVHEi'ITS

Throttle HCV-638 to provi deadequate suction for the SIand charg>ng pumps (approx-imately 20 psig above con-tainment pressure whilemaintaining RHR pump motorcurrent less than 57.5 amps).

d. Th cold leg recirculationflow path would be asfollows.

RHR pump 1 from containmentsump to cold legs 1 and 2,SI pump 1 from PHR pu,.p 1to all cold legs, chargingpumps 1 and 2 from RHR pump1 to all cold legs via theBIT.

Containment spray pump 1from R';/ST to spray headers.

2. Proceed as follows after 19 1/2hours for hot leg recirculation.

a. Per, orm the fol 1 ow ng s iepsin t'e order given below inAppendix 8 (Cold Leg Recircu-lation/Hot Leg RecirculationChange Over Proc=dure).

Steps: 1,3,4,5,6,7,8,9,10,11.

b. Close HC'/-638 RHR dischargevalve. U

c. Open 8716A RHR pump crosstievalve.

d. Open 8703 RHR to hot legs1 and 2.

e. Throttle open 638 to holdon RHR pressure greater than20 psig above cantainmentpressure or less than 57.5amps on RHR pumps.

PAGE 24 OF 34 REYISIOH . Dip 4'/22)80

. DIABLO CANYON POWER PLANT uNIT NOS. 1 AND 2El'1ERGENCY OPERATING PROCEDURE NO. OP"1 APPENDIX E

TITLE: LOSS OF COOLANT ACCIDENT

ACT IQll

APPENDIX E (Cont.)

COI"lt1ENTS

f. The hot leg recirculationflow path would be asfollows.

RHR pump 1'rom containmentsump to SI pump 1 suctionvia valves 8804A, 8807A andB and to hot legs 1 and 2 viavalve 8703.

SI pump 1 from RHR pump 1to RCS hot legs 1 and 2

Diesel Generator 1-2 Fai lur

l. I diesel generator 1-2 hasfailed the following stepsshould be used to align thesystem or col d 1 cg i ec i i cu-lation.

a. Verify the following pumpsare running.

ASH Pumps 1AFW Pumps 2,and 3Charging Pump 1CCLI Pumps 1 and 3SI Pumps 1 and 2C.S. Pump 2RHR Pump 2

b. 1lith diesel generator 1-2failed, do the following stepsin the order gi ven belowin Appendix A (LOCA Iniection/Recirculation Change OverProcedure).

Steps: 2,3,4,5,7,8,9,10,11,12,13,14,15,16,17,18,25,26,27, 28.

PAGE 25 OF REVISION 2 DATE ~~dhoti

DIABLO CANYON POWER PLANT UNIT NOS.Et'l RGEI>CY OPERATING PROCEDURE NO OP 1 APPENDIX E

TITLE: LOSS OF COOLANT ACCIDENT

ACTION

APPENDIX E (Cont.)

CO!~r

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2EtlERGENCY OPERATING PROCEDURE OP-1 APPENDIX E

TITLE: LOSS OF COOLANT ACCIDENT

ACTION

APPENDIX E.(Cont.)

COMMENTS

f. Throttle open HCV-637 tohold an RHR pressure greaterthan 20 psig above contain-ment pressure or less than57.5 amps on the RHR pumos.

g. The hot leg recirculationflow path would be as follows:

PHP. pump 2 from containmentsump to SI pumps 1 and 2suction, via valve 88048 andto hot legs 1 and 2 via 8?03.

SI pumps 1 and 2 rom RHRpump 2 to all RCS ho legs.

Diesel Generator 1-3 Failure

l. If diesel generator 1-3 has failed,the following steps should beused to align the system forcold leg recirculation.

a. Verify the followirig pumpsare running.

ASW Pump 2AFW Pump 2Charging Pump 2CCW Pumos 2 and 3SI Pump 2C.S. Pumps 1 and 2RHR Pumps 1 and 2

b. With the diesel generator1-3 failed,do the followingsteps in the order givenbelow in Appendix A (LOCAInjection/Recirculation ChangeOver Procedure).

Steps: 2,3,4,5,7,8,9,10,11,12,13,14,15,16,17,18,19,20,21,22,23,24,27, 28.

PAGE 27 OF 34 REVISION 2 DATE ~//22 SO

DIABLO CANYON PO'nE PLANT UiiIT 1'S, 1 AiAl0 29'tERGEHCY OPFRATIi'6 PROCEDURE OP-1 APPEitOIX E.

TITLE: LOSS OF COOLANT ACCIDKi'IT

c ~

ACTTOiV

APPEi30IX E (Cont. )

Throttle HC'l-538 and 637 toprovide adequate suction forthe SI and charging pump(approximately 20 psig abovecontainment pressure whilemaintaining RHR pump motorcurrent less than 57.5 amps).

The cold leg recirculationflow path wo ld be as follows.

Containment spray pumps 1 and 2from R~lST to spray headers.RHR pump Ho. 2 from containmentsump to cold legs 3 and 4 andto SI pump No. 2.

SI pump iuo. 2 from RHP too. 2 toall cold legs.RHR pump No. 1 from containmentsump to cold leg 1 and 2 andto t

DIABLO CANYON POWER PLANT UNIT'OS. 1 AND 2EhERGENCY OPERATING PROCEDURE OP-1 APPENDIX E

TITLE: LOSS OF COOLANT ACCIDENT

ACTION

APPENDIX E (Cont.)

COt'f

DIAB~ 0 CANYON POMER PLANT UNIT NOS. 1 AND 2EhERGEi'iCY OPERATING PROCEDURE NO. OP-1 APPENDIX F

TITLE: LOSS OF COOLANT ACCIDENT

APPENDIX F

DETERNIflATIOtV OF ADEQUATE CORE COOLING

This appendix provides the guidance to determ.'ne adecuate core cooling ifinadequate core cooling is suspected. Further, the instructions for regainingadequate core cooling is presented.

ACTiON

l. If 1 or more RCS hot leg widerange RTD's approach 700'Fproceed as follows.

'I

2 ~ If P-250 point U0091 isavailable, proceed withstep 3. If the P-250 pointUO091 is not available go tostep 5 immediately.

3. Determine the core outletaverage thermocouple reading.If the average core outletreading is less than 1200'F,ADEQUA

"-CORE COOLING EXISTS.

Noti fy the control operatoradequate core cooling exists.

4. If the core outlet averagetberocouple reading is oreatertl,an l2OOoF iivnOE nTE CORECOOLING EXISTS. flotify th controloperator and immediately go tostep 11.

5. If the core outlet thermlocouplereadings are available at thincore board in the control room,proceed with step 6. If thetherocouples are not availablego to step 9.

6. Determine the average of allavailable thermocouple readings.If the average is less than 700'F,ADEQUATE CORE COOLING EXISTS .Notify the control operator.

COt'o'iENTS

3. Continue to monitor the P-250core outlet average temperature.

6. Continue to take av rage readingsas long as the wide range hot legloop temperatures are greater ti an700'F.

PAGE 30 OF 34 REYISION 2 DATE ~//22 80

DIA8LO CANYON POHER PLAtlT UNIT NOS. 1 AND 2EthERG NCY OPERATItlG PROCEDURE NO. OP-1 APPEt'DIX F

LOSS OF COQLAtlT ACCIDEtlT

7.

8.

APPENDIX F (Cont.)

ACTION

If the average of the thermocouples isgreater than 700'F (all pegged. hi),INADEQUATE CORE COOLING may exist.Notify the control operator and go tostep 10.IT both the P 250 1 ilcoi e thieriisl oup ILreading and the incore readings at theincore board in the control room areunavailable, proceed with step 9.

COtAi lENTS

10.

Proceed to the co'ntrol board anddetermine if all hot leg wide rangeloop RTD's are pegged hi. If the hotleg temperature are not pegged hi,ADEQUATE CORE COOLING EXISTS. Ifthe hot leg temnerature are peggedhi INADEQUATE CORE COOLItlG mayEXIST. Notify the control operatorand go to step 10.

If SI flow to the RCS or auxiliaryfeedwater flow is being deliveredto the steam generators, ADEQUATECORE COOLING EXISTS. If neitherSI flow to the RCS nor AFH flowto the steam generators can beverified, INADEQUATE CORE COOLINGEXISTS. Notify the controloperator and proceed to step 11.

9. Continue to monitor RCS hotleg temperature if they are hibut not pegged hi.

10. Continue to monitor SI and AF'.lflow.

INADE UATE CORE COOLItlG INSTRUCTIO.",S

Declare a General Emer enc".Carry out the instructions oi venin the Emergency ProceduresGeneral Appendix 2 (Notificationof Off-site Personnel in theEvent of an Emergency).

12. Attempt to establish SI flowto the RCS 'or AFIrl flow to thesteam generators.

PAGE 31 OF 34 REVISION 2 DATE 4/22/80

DIABLO CMYON PO'AER PLANT Ul)IT NOS.EtlERG NCY OPERATING PROCEUDRE NO. OP-1 APPENDIX F

TITLE: LOSS OF COOLANT ACCID NT

ACTION

APPENDIX F (Cont.)

COf NENTS

13. Continu moni toring core outlettemperature to determine theeffectiveness of the remainingactions.

14. DEPRESSURIZE THE RCS by ™e.hod.A or 8 hei ow.

a. Dump steam to the condenseror atmosphere if the steamgenerator levels are in thenarrow range and AF!I flow isevident.

b. Verify the SIS or chargingpumps are running and availableto deliver water to the RCS

THEN

Open the pressurizer PORV's.

14. Monitor R';(ST level and performAppendix A when the RI;EST lo 1 evelaIarm is reached.

a. This is the preferred m thod.

b. Opening the PORV's uill providea drop in RCS pressure sufficientto allow the SI flow required tocool the core.

15. If no means of depressuriz"t.'o.". "". " 15.available, or if the depressur.'zationdid not result in decreasing coreexit therocouple or wide.hot leg temperature,

THEN

START A RCP if possible.

S art one PCP. Yo conditio Is aleimposed on starting. The pump mustbe started to move coolant throughthe cove.

PAGE 32 OF 34 IIEl/IS ION DATE 4/22/80'

DIABLO CANYON POWER PLAiiT UNIT HOS. 1 AHD 2EMERGENCY OPERATING PROCEDURE NO. OP-1

TITLE: LOSS pF COOLANT ACCIDENT

APPENDIX G

BLACKOUT WITH SAFETY IN3ECTION EMERGENCY LOADING OF VITAL BUSSES

l. If the vital busses loose voltage ~iior to resetting the safety injectionsignal, the vital busses will automatically load the vital equipmentgiven below. Verify the equipment has been loaded by observing breaker1ights on the control board.

2. If the vital busses 'loose vnltaue after the safety injection signa'I hasbeen reset l,oad or verify loaded the. equipment given below onto thevital busses manually. Allow approximately 4 seconds between loading ofeach piece of equipment onto a given vital bus.

VITAL BUS

NOTES F

2 0/G 1-3

2&3 MCC 1-F

2 CC Pp 1-1

SI Pp 1-1

1&2 CFCU 1-2

1&2 CFCU 1-1

2 CCW Pp 1-1

2 ASW Pp 1-1

2 AFW Pp 1-1

NOTES:

NOTES

2

2&3

2

1&2

1&2

2

2

VITAL BUS

0/G 1-2

MCC-1-G

CC Pp 1-2

Cont Spray Pp 1-1

RHR Pp 1-1

CFCU 1-3

CFCU 1-5

CCW Pp 1-2

ASl Pp 1-2

VITAl BUS

NOTES H

2 0/G l-l2&3 MCC 1-H

SI Pp 1-2

4 Cont Spray Pp 1-2

RHR Pp 1-2

1&2 CFCU 1-4

1&2 CCW Pp 1-3

2 AFW Pp 1-2

l. If these loads are on the bus, verify they are running in low speed.2. These loads should already be loaded on the vital bus due to the loss of

voltage signal.

3. The vital 480 volt MCC will not st. ip from the bus; h wever, it should boverified on the bus.

4. Load the cont. spray pumps only if they were running prior to the blackout.

PAGE 33 PF 34 REY IS ION 2 BATE a/22/80

DIABLO CAI'lYOH PO~ER PLAi~lT UjIIT >lOS. 1 AHO 2EtlERGEHCV OPERATING PROCEDURE tlO. OP-1

TITLE: LOSS OF COOLAI'lT ACCIDEjllT

2300

~ I

„1 '.Satgra'tion curve iiith not i'nstrument errors.'

3 2:1.-'.!

I

I

Saturation curve 'ijith conservative.inst;rural:.en'rrors'for use vn th

CS; pressure and 'ilR'CS'cahot:..:.-'.'.—..j—,'.:,-'.—tb.e~sQd j,l'it.t no~=.:.con'd.i ions'..-'gi

~oniasnp.-,.'-,l—-, r.-..;...T.—,=.j

".:', i:

~Q—bu t-'v.ja j

,TT.,

.:i.'- )'. "l

t 'con~asnmen~ pre~sJr and,tern 'i rat'ure 'high.,': .'.:.'::

l~ i

h

2 I'', ~..j

'00(? - "- '-' o'-::::::f:-'.. -:'-' —,.'::j-,jIjeR

—"3-QQaj",e~ th md'.ti on~l: -: .I

~ I

r:::ft

~ ~ ~

~ '.x: .; j

Pressure(ps jg) .::.f.."- - j--, „:

.... 'L:-: ' f .'.gLC.C.EP.TABLE

~ ~ ~~ ~ ~ ~ + ~

~ ~ljREA

~ I ~ ~ ~

RCS " !'.':: .'.j'::-: f"::: - ': ! i'-::."': '. ~~ ~ ~

~ ~ l: ~ '--'. Ui~QCCEPTABLE.:.:- .::. AREA

1000 ~ ~ ~ - ~ ~

~ ~

t —:..::f:;:l-:.'--::-- --*

600

500

. l:il-.:-.:.- ~ -- ~ -F-~—

:'.. "-:*.. j-5: SECluRBTLOJ, I

~ ~

400i' ~ i- -)

~ ~ ~ j. ~ : ~ ~ ~

i..::: 2,;::;.-:.I:.: ':.: ~ . ~::: ,J.-: ...:,: ..~ ~ ..~ ~ ~ t

~ ~ ~I

~ ~ ~

300

2000

"j.':::(

~-

':p RCS Temperature { F)

100 200, 300 400 500 600 700

PAGE 34 OF 34 REV I5 ION 2 DAT" 4/22/80