Attachment lX

TliLE:

PACIFIC GAS At]D ELECTP,IC CO'1. AllYDEPARTt1EtlT OF NUCLEAR PLAtiT OPERATIONS

DIABLO CANYON POWER PLANT UNIT NOS. 1 AtlD 2

EtiiERGENCY OPERATING PROCEDURE NO- OP-0

REACT3R TRIP WITH SAFETY INJECTION

SCOPE

This procedure covers the initial operating steps to be taken in the event ofa reactor trip with safety injection signal. The safety injection signal mayoccur at some time after the reactor trip has taken place. If this is thecase, the operator w',ll cease using EOP-5 (Reactor Trip without Safety Injection)procedure and will use this procedure to control and analvze the olant condit'ion.

'

S Yil?TO!!S

7~e fo".ic ing symptoms are typical of those which may arise in a plant whichis undergoing a loss of reactor coolant, loss of secondary coolant or steamgenerator tube rupture (one or more symptoms in each category may appear inany order):

LOSS OF REACTOR COOLANT

Lo Pressurizer Pressure

Lo Pressurizer Water Level

Hi Pressurizer Mater Level

Letdown Isol ati on Ipressurizer Heater Cutnu „

Increased Charging Flow

Hi Containment PressureHi Containment Temoerature

Hi Containment i isirnw rl w +s jiivs~ ~ ~ 4 ~ i g

PRELIMINARYHi Con".ainment RadiationHi Containment Recirc. SumpWater Level

The process variables re erred to in this Instruction are typicallymonitored by more than one instru... ntation channel. The redundantchannels should be checked for consistency while performing the ste~sof thi s Instruction.

2. The pressurizer water level indication should always be used in con-junction with other specified reactor coolant system indications toevaluate system response and to initiate manual operator actions.

PAGE ~ OF 21

APPROVAL

REVISION

PLANT SUPERINTENDENT DATE

AE~

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2Et'lERGENCY OPERATING PROCEDURE NO 0? 0

TITLE: REACTOR TRIP MITH SAFETY INJECTION

LOSS OF SECONDARY COOLANT

Lo Pressurizer Pressure

Lo Pressurizer Mater Level

Letdown Isolation/PressurizerHeater CutoutLo-Lo Reactor Coolant Tavg

Hi Containment Pressure

Hi Containment Temperature

Hi Containment Recirc. Sump Level

Steam Flow/Feedwater Flow f'.ismatch

Lo Steam Line Pressure(one or all Steam Lines)Lo Steam Generator Mater Level

Hi Steam Flow(one or all Steam Lines)Lo Feedwater Pump Discharge Pressure

AUTOMAT IC ACTIONS

STER> GEN RATOR TUBE RUPTURE

Hi Air.Ejector Padi a tion

Lo Pressurizer Pressure

Lo Pressurizer Mater Level

Increasing Charging Flow

Letdown Isolation/PressurizerHeater Cutout

Steam Flow/Feed Flow llismatch

Hi Steam Generator Blowdown RadiationIncreasing Steam Generator Mater Level

1. Reactor trip and turbine trip.2. Safety injection initiateu.

OBJECTIVES

1. To verify the reactor trip and safety injection.

PAGE 2 OF 21 REVISION DATE 4/19/80

t

DIABLO CANYON POWER PLANT UNIT NOS 1 AND 2

0, Et1ERGENCY OPERATING PROCEDURE NO. OP-0

TITLE: REACTOR TRIP WITH SAFETY INJECTION

2.

3.

NOTE: If the plant is in a condition which warrants a reactor tripand safety injection and an automatic reactor trip and safetyinjection has not yet occurred, it is the reactor operatorsresponsibility to manually initiate the reactor trip ands fety injection.

To verify all SI equipment is operating and performing the intendedfunction.

To monitor plant parameters and diagnose the initiating SI signal.

4. To mitigate the cons que..ces of a valid SI signal by providing directiononce the initiating signal is identified.

It1VEDIATE OPERATOR ACTIONS

ACTIONS

1. Verify the following automatic actions.

COf~iflENTS

l. If the action has notoccurred, use manualcontrol to satisfy therequirement.

a ~

b.

C.

d.

e.

g.

h.

Reactor trip (all rods on bottom, DRPI-Nuclear Instruments Decreasing. )

Turbine trip (all four SV closed on EH

panel.)

Vital 4160 busses F, G and H transferredto startup power (breaker positions onVB-4.)

Vital 4160 busses F, G and H voltage normal(120 volts indicated on 480 volt vital bussesF, G and H, VB-4.)

Diesel generators running (diesel RPt'1 onVB-4.)

Verify auxiliary building ventilation systemin building and safeguards mode (mode lighton ventilation section of VB-4.)

Verify control room ventilation system in mode4 (mode light on VB-4.)

Verify both motor driven auxiliary feedwaterpumps running and all 4 auxiliary feedwaterLCV open. (Hotor breal:er position lights andLCV position indicators on VB-3.)

PAGE 3 OF REVISION DATE 4/19/80

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2

EHERGENCY OPERATING PROCEDURE NO. OP-O

REACTOR TRIP HITH SAFETY INJECTION

ACTION

Feedwater isolation (valveposition lights on VB-3).

j. Check the safeguards postagestamp monitor lights on VB-1.If 2 steam loops have Histeam flow in alarm with any2 loop Lo pressure or any 2

loop in Lo-Lo Tavg in alarm,tnen:

Verify all 4 main steam 'isolationvalves, bypass valves and all 4 steamgenerator blowdown stop valv s ICclosed (valve position indica-tion lights on VB-3).

COY(MENTS

k. Verify all safety injectionpumps have started and auto-matic,valve operations haveoccurred (all SIiFM ISQL(STHGEN LEVEL postage stamp monitorlights on VB-1 not in alarm).

l. Verify containment Phase A andcontainment ventilation isolation(all containment Phase A postagestamp monitor lights on VB-1not in alarm).

2. Verify the following minimum pump flows.

If tne minimum flows are rot occurring,attempt to operate equipmient manually orlocally to establish the flows. If minimumflosjs as indicated below are indicated,continue with Step 3 of this procedure.

a. t1inimum of one charging pump runningwith flow via BIT indicated on FI 917.(VB-1)

b. Hinimum of one safety injection pumprunning with flow indicated when PZR

pressure is less than the SI pump shutoffhead (VB-l).

b. NOTE: IF PZR Pressureis greater than the shutoffhead of the SI pump, continueon with this procedure. Con-tinue to monitor PZR pressur~and verify SI pump flow ifpressure'rops below theshutoff head of the SI pump.

PAGE 4 OF 21 REVISION O OATE a/19/80

DIABLO CANYON POWER PLAIIT UNIT HOS. 1 AND 2EMERGENCY OPERATING PROCEDURE NO. OP-0

TITLE: REACTOR TRIP HITH SAFETY INJECTION

ACTION

c. Verify 1 or 2 below:

1) Both motor driven AFPrunning and flow indi-cated to all 4 steamgenerators (VB-3).

OR

ra. J ee raC / 4I QI I I IIC OICOIII tII IVYII ref'I

and establish flow to all 4generators (VB-3).

d. Verify RCS heat removal by

1) Observing automatic steam dumpto condenser or atmosphericsteam dump via the 10K steamdump valves (VB-3).

2) RCS Tavg decreasing to no-loadtemperature (CC-l).

c ~

d.

COMlMENTS

NOTE: Allow full aux-iliary feeduater f'l autothe steam generatorsuntil the narrow rangesteam generator level in-dicators indicate alevel of 28!. This willassure the SG tubes arecovered even in a bad con-a~i a w ~

'.aaa aeulC>a I CIIV I I VriIIIYali.

Atmospheric steam dumpwill be blocked by anexisting "Turbine Tripp-ed" condition. If con-denser steam dump hasbeen blocked due to a

control malfunction orloss of the "CondenserAva ilable" condition,decay heat removal willbe effected by auto;,aticactuation of the steamgenerator lOK atmosphericsteam dump valves, or, ifthese prove ineffective,the steam generator codesafety valves. In thisevent, steam pressure willbe maintained at the 'setpressure of the controil-ing valve(s) and reactorcoolant average tempe.aturewill stabilize at approxi-mately the saturation temp-erature for the steampressure being maintained.

3. Monitor containment pressure (VB-1), ifcontainment pressure reaches or exceeds22 psig, verify the following:

a. Main steam isolation valves and bypassvalves closed (VB-3).

b. Steam generator blowdown valves ICclose (VB-3).

PAGE 5 OF 21 REVISION 0 DATE 4/1 glsO

DIABLO CANYON POWF R PLANT UiNIT NOS. 1 AND 2EttERGEisCY OPERATIiNG PROCEDURE NO. OP-0

TITS E: REACTOR TRIP WITH SAFETY Ii'UECTION

ACTI0>l CollllENTS

4.

c. Containment spray initiated (phase 8isolation postage stamp monitor lightsnot in alarm VB-l).

d. Phase 8 isolation (phase 8 isolationpostage stamp monitor lights not inalarm VB-l).

e. Manual ly trip a 1 1 4 RCP '.

ltonitor wide range RCS hot leg temperatures.If any temperature approaches 700'F, assignan operator to perform Appendix 8 (Deter-mination of Adequate Core Cooling) ~

c. If actions a through ddo not occur automaticallywhen containment pressurereaches 22 psig, initiatethe action manual'ly.

e. CCW to the lube oil coolerswill be lost on the phase 8 %isolation.

Also monitor P-250 pointU0091, average core thermo-couple reading F.

Af'CTDcl>T DI AP's>AS&TlS

l. Evaluate RCS pressure:

a. If PZR pressure is below 1950 psig ordecreasing, close or veri y closedthe following valves:

Pressurizer Spray Valve PCV 455A

Pressurizer Spray Valve PCV 4558

Auxiliary Spray Valve 3145

Pressurizer Power Relief Valve PCV 474

P> cssur >zer Po'viei R=l >as Va ive PCV 436

Pressurizer Power Relief Valve PCV 455C

a. Verify closed by observingposition indication lightsand discharge pipe tempera-ture indica ors.

The diagnostic chart attach>edto this procedure is pre-sented to clarify the diag-nostics. It is not to beused in lieu of the pro-cedure.

b. If PZR pressure is grea er than 1950 psigand stable or increasing, go to Step 1 ofSubsequent Operator Actions.

b. If RCS pressure has previ-ously decreased below 1850psig and is now increasingunder the influence of thecharging pumps, the operatoris cautioned that these aresmall Loca ~sm toms.

2. If PZR pressure continues to decay below1365 psig or is below 1365 psig and stable.

2. NOTE: The condi tions for stop-ping RCP must be continuous'lymonitored throughout the tran-sient.

PAGE ~ OF" 21 REV IS IO>l DATE 4/19/80

DIABLO CANYON POWER PLANT UNIT HOS. 1 AND 2Et1ERGENCY OPERATING PROCEDURE NO. OP-0

TITLE- REACTOR TRIP 'HITH SAFETY INJECTION

ACTION COHtlENTS

a. Again verify a minimum of one chargingpump delivering flow and one SI pumpdelivering flow to the RCS

THEN

b. STOP all four reactor coolant pumps. tlain-tain seal water flow to the RCP seals byadjusting the reciprocal charging pump speedrr ~ u a nrsol I 'Lrv I co ~

c. If component cooling water to the RCP'sis isolated due to a containment phase B

isolation, stop all RCP's within 5 minutesand maintain seal flow as above.

3. If condenser air ejector radiation monitoris reading abnormally ~hi h radiation

OR

One steam generator level is increasingabnormally fast

AND

containment pressure, containm nt arearadiation monitor, and containment recii C.sump level exhibit NORi'lAL readi..gs, dis-continue this procedure and beginprocedure OP-3, Steam Generator TubeRupture.

4. If steam g nerator pressure is ABNORMALLY LO>1

in one steam generator as compared to theother steam generators, discontinue thisprocedure and begin proce:~ re OP-2, Loss ofSecondary Coolant.

PAGE 7 OF 21 REVISION DATE 4/19/80

DIABLO CANYON PO'h R PLANT UNIT NOS. '1 AND 2EtlERGENCY OPERATING PROCEDURE NO. OP-0

TITLE: REACTOR TRIP MITH SAFETY INJECTION

ACTION CONi'IENTS

5. If containmenit pressure, containment arearadiation moni tor, or containment r ecirc.sump level exhibit ABNORINLLY HIGH orINCREASING levels, discontinue thisprocedure and begin procedure OP-1, Lossof Reactor Coolant.

5. NOTE: For very smal 1

coolant breaks insidethe containment, thecontainment pressure andcontainment recirc. sump ~level may increase veryslowly and possibly notrecognizable by thoperator immediately.Therefore, the operatorshould monitor theseparameters throughout thetransient.

6. If containment pressure, contai'nment arearadiation monitor and containment recirc.sump 'level remains stable in the Ere-event~ran e, discontinue this procedure and beginprocedure OP-2, Loss of Second ry Coolant.

SUBSE(}UENT OPERATOR ACTIONS

ACTION COYii~lENTS

1. Assume the event is NOi'I SPURIOUS safetyinjection until all of the ollowing itemsare verified.

a. Containment pressure normal.

b. Containment temperature r. rmlal.

c. Containment recirc. sump level normal.

d. Containment area radiat'.en monitor normal.

e. Condenser air ejector radiation normal.

f. Auxiliary Bldg. control board area radiationnormal.

g. Reciprocal charging pump room area radiationnormal.

h. Plant ventilation particulate monitor normal.

Plant ventilation radio gas monitor normal.

PAGE 8 OF 21 REVISION DATE e//o an

DIABLO CANYON POMER PLANT UiNIT NOS. 1 Ai80 2EfiERGENCY OPERATING PROCEDURE NO. OP-0

REACTOR TRIP l/ITH SAFETY INJECTION

ACTIOil COhHENTS

If the above symptoms a through iare normal, and when

j. Pressurizer pressure greaterthan 2025 psig.

k. Pressurizer narrow range waterlevel greater than 25>.

1. RCS indicated subcooling greaterthan 35'F.

m. At least one steam generator widerange water level indication indi-cates a stable and increasingwater level and AFW flow is evi-dent to that steam generator.

THEN

j. CAUTION: If Step 1 items a tom cannot be verified, returnto Diagnostics Step l.

l. If the RCS subcooling meter isinoperable or is suspected tobe incorrect, use wide rangeRCS pressure and the highestwide range Thot in conjunctionwith the attached RCS saturationcurve (graph) to determine PCS

subcooling.

m. NOTE: AF';l flow to all steamgenerators should be greaterthan 155 gpm per steam oeneratoruntil level returns to thenarrow range level ins ruments.If both motor driven AFH pumpsare running and delivering ow,the steam driven AFl'ump maybe shutdown when the steamgenerators narrow range levelindicators indicate 33'.

2. Reset safety injection. 2.'AUTION: 1) Automatic reinitiationennea ety injection will no'ccurafter this step since the reactortrip breakers are open. If theoperator has indication that an SIis required after this step, hemust initiate it manually.

CAUTION: 2) If loss of off-sitepower 'occurs after rese ting sa;etyinjection, it will be necessary toload %he safeguards equipment ontothe vital busses manually. Ifsafety injection is reinitiatedmanually after the loss of off-sitepower, the vital busses will auto-matically sequentially load thesaf guard equioment.

PAGE"g OF 21 REV I SION 0 DATE 4I 1 9/80

O'.ABl 0 CAtiYOtl POMER Pl ANT UNIT HOS. 1 AND 2EtlERGENCY OPERATING PROCEDURE tl0. OP-0

TITLE: REACTOR TRIP MITH SA. ETY ItlJECTION

ACTION

a. Reset containment isolationphase A, train A and train B.

b. Stop all but OHE charging pumpand maintain RCP se~I floiq, rfa centrifugal charging pump isleft in service, open the cen-trifugal charging pump recirc.valves MO 8105 and 8106.

c. If RCP's have been stopped, establishconditions for starting PCP's andstart at least one RCP.

d. Close the BIT inlet and outletvalves 8803A and B, 8801A and B.

e. Verify AC turhine hearinn nil ns

and Hi pressure seal oil backuppump running after oil pressuredecays to 11 psig and turbinebearing lift pump starts at 600 RPM

turbine speed.

f. Establish normal charging.

1) Open instrument a;r ; ivesFCY-584 and 682.

2) Check open or open normalcharging valve 8146.

3) Check close .or 'close c"argingto auxiliary spray val;e 8145and alter nate spray valve 8147.

4) Open charging line isolation valvesMO 8107 and 8108.

5) Adjust HCV-142 and FCV-128 orreciprocal charging pump speed toachieve RCP seal flow and chargingflow as required to maintainpressurizer level greater than 224.

COMflEt i'TS

If manual loading or automaticloading is performed, verify theequipment given in Appendix A isloaded onto the vital buses.

b. CAUTION: Stop one CC pump at+im4 anil uaea

1 > a+n Dl S p ersuif RCS pressure drops below1850 psig, reinitiate SI andreturn to Step 1 of the. diag-nostics and consider a smallbreak Loca.

PAGE 10 OF 21 REVISION DATE 4/1 9/80

DIA"LO CANYON POWER* PLANT UNIT NOS. '1 AND 2Eh1ERGENCY OPERATING PROCEDURE NO OP-0

TITLE:*

R ACTOR TRIP 1IITH SAFETY INJECTION

ACTION COt'ii'1ENTS

6) Open RCP seal return valves, tl0 8100and 8112. Check seal flow normal.

Establ ish normal 1 etdown.1) Check open or open letdown valves

LCV-459 and 460.

2) Open letdown isolation valve 8152.

3) Open one 75 gpm letdown orifice valve.

4) Verify PCV-135 opening by observingletdown flow.

Establish VCT makeup and transfer chargingpumps suction to VCT.

1) Adjust VCT makeup blend to the no-loadconcentration.

2) Open VCT outlet valves LCV-1128 and C,

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

4) Verify divert valve LCV-li2A in AUTO.

With pressurizer leve; a=proximately 22;.',verify pressurizer pressi.r control inAUTO and pressurizer sprays and heaterscontrolling pressure .

Stop both RHR and SI pumps.

Stop all 3 diesel generators, place dieselgenerator control switches in AUTO.

Insure the main an'd feedpump turbines onturning gear once 0 RPI'1 speed is reached.

PAGE 11 OF 21 REVISIO'I DATE 4/19/80

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2EiIERGENCY OPERATIl'IG PPOCEDURE NO. OP-0

TITLE: REACTOR TRIP WITH SAFETY INJECTION

ACTIDi'I COilMENTS

3. Verify the following:

a. With normal RCS charging, letdown andVCT makeup, the pressurizer water levelremains above 17'X.

b. With pressurizer heaters in service, thepressurizer pressure remains above 1850psig.

c. RCS indicated subcooling greater than35

If i tern a., b., or c. above cannot beverified itANUALLY REIl'!ITIATE SAFETYINJECTION an return to dsagnosticStep 1 of this procedure.

4. IF after securing safety injection andtransferring the plant to normal pressur-izer pressure and level control, the reactorcoolant pressure does not drop below thelow pressurizer pressure setpoint forsafety injection actua ion ~.'iD the pressuri-zer water level remains abov 17„span, ANOthe reactor coolant indica.ed subcooling >sgreater than ~F, then'onsider 'theevent a s urious safet inJection.

CAUTION: Stoppingand starting of theECCS pumps can cause pumpmotor overheating orreduced motor lift. Hencif the pumps are restarteconce after termination anadditional 15'F of sub-coolinq should be added t

'herequired subcooling por to the second terminatof the charqing pumps..

CAUTION: Do not reset thereactor trip breakers untiauthorized by the PlantSuperintend nt. 0

a. Whenever the ECCS are activated, the plantis in a condition designated as an unusualevent. Carry out the instruction givenin Emergency Procedures General Appendix 2(Notification of Off-Site Personnel in theEvent of Emergency).

PAGE 12 OF 21 REVISION DATE <I I g/DD

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2EYERGENCY OPERATING PROCEDURE NO OP 0

TITLE-'EACTOR TRIP tJITH SAFETY INJECTIOh

ACTION COt~i!ENTS

SPURIOUS SI SIGNAL RECOVERY

1. Proceed to a normal Hot Standby conditionas follows.

a. If steam line isolation has occurred:

1) Close or check closed all 35 and40K steam dump valves.

2) Prepare or verify main condenseravailable for service.

3) Equalize and open all 4 NSIV's

4) Establish steam dump to condenserusing steam pressure mode set at1005 psig.

5) Verify all atmosphe. ic steam dumpvalves closed.

CAUTION: Monitor steamgenerator pressure closelyduring this operation.Imiediately close all NSIV'sif steam pressure decays duringth":s operation.

b. Open the main generator motor operateddisconnect switch and reenergize theunit auxiliary transformers by back-feeding from the 500 KV vard. Transferall station auxilia. y busses (12 and 4KV busses) to the unit auxiliary trans-formers.

c. Return the auxiliary building ventilationsystem to normal by resetting the "S"

signal on both POV cabinets and selectingbuilding only mode on VB-3.

d. Reset both Units 1 and 2 control roomventilation systems on Unit 2 radiationcontrol board and verify both Units 1

and 2 venti lation systems return to thenormal mode of operation.

e. Mhen directed by.,the SFN, shutdown thefollowing:

1) One auxiliary saltwater pump.

PAGE 13 OF 21 REVISION 0 DATE 4/19/80

DIABLO CANYO 2 PO'riER PLAIA2T UNIT NOS. 1 Ai2P 2EilERGENCY OPERATIl!G PPOCEOURE i<0. OP-0

TITLE:,,EACTOR TRIP WITH SAFETY INJECTION

ACTION

2) Steam driven auxiliary feedwaterpump after stean generator levelsare greater than 33K and motordriven oumps are controlling level.

3 ) Close CFCU maxi flow valves thenshutdown 1 CC!l pump.

4) Remove 2 CFCU 's from service and placetne running CFCU 's on fasr. speed.

f. Verify a BA transfer pump is running andopen the BIT recirc. valves to begin in-creasing BIT concentration. Call Chemicaland Radiation Department to begin samIplingthe BIT and BAT.

g. Reset containment ventilation isolationtrains A and train B.

1) Open containment rad. Gas monitorvalves FCV-681, 678 and 679.

2) Verify normal readings on containmentair particulate and radio g~s monitorson RNS board.

h. Reset radwaste isolation valves resetswitches.

1) Have the auxiliary operator verify thefollowing valves are in the desiredposition. (Use the phase A isolationmonitor lights test s ',tch to powerthe monitor light bo" to verifypositions.) FCV's 253, 255, 258, 500,254, 256, 257, 260 a"d 501.

i; Open fire water valve FCV-633 and primarywater to containment valve 8029.

COi I(2EI 2TS

j. Open valve 8045 N2 to PRT.

k. If the incore chiller has been in serviceprior to the SI, open incore chiller valvesFCV 655, 657, 654 and 656.

PAGE 14 OF 21 REYISIOI1 0 DATE 4//19 A

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2EMERGENCY OPERATING PROCEDURE NO. OP-0

TITLE: REACTOR TRIP WITH SAFETY INJECTIOll

ACTIOt<

l. If the gross failed fuel detector hasbeen in service prior to the SI, openHot Leg sample valves 9356A and B.

1) Verify flow returns on the GFFDflowmeter.

2) Verify the GFFD countrate returnson scale and stabilizes at a valuebelow the post SI countrate on therecorder.

m. Open the pressurizer steam space samplevalves 9354A and B.

n. Open pressurizer relief tank gasanalyzer valve 803%A.

2. Maintain Hot Standby conditions untilauthorized to proceed with a normalstartup or inform the plant superintendentthat the unit is proceeding to ColdShutdown.

COl~ll lENTS

PAGE 15 OF 21 REUISIOII~ OAiE ~4/I9 80

DIABLO CAI'lYOil POWER PLANT UNIT NOS. 1 A"lD 2EliERGENCY OPERATI "lG PROCEDURE NO. OP-0TITLE: REACTOP, TRIP ';lITH SAFETY INJECTION

SI EquipmentOperationVerified

or decreasing

0 slg

Yes No

Verify closed all PORVand

Backup Isolat',on.Val;esGo to Step 1 of

SubsequentOperator Actions

Pressure (1365 psig andSI flow indicated or CCHto RCP lost

No

P r. Level remains >17>

Pzr. Press remains >2070 psigRCS subcooling >35'F

Y s

Trip all 0 RCP's

Yes

Go to Step 2of subsequentOoerator Actionsfor SI Termination

Cont. Press Hi orCont. Rad Hi orCont. Recirc Sump Hi

A.E. Rad. Level Hi orOne SG Level increasing fastwith Containment Conditions

Normal

One Stm Gen. PressureLower than other Stm

Generators

Go to OP-1LOCA

Go to OP-3St-i. Gen. Tube Rup ure

Go to OP-2Loss of Secon'ary

Coolant

PAGE 16 OF 21 REVISION 0 DATE 4/19/80

DIABLO CANYON POWER PLA"lT UNIT NOS. 1 AND 2EliERGEi'lCY OPERATING PROCEDURE NO. OP-0TITLE: REACTOR TRIP WITH SAFETY INJECTION

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PAGE 17 OF 21 REVISION 0 DATE 4/19/80

DIABLO CANYON POWER PLANT UNIT NOS. 1 ANO 2EMERGENCY OPERATING PROCEDURE NO. OP-0

TITLE: REACTOR TRIP WITH SAFETY INJECTION

APPE1NDIX A

BLACKOUT WITH SAFETY IMECTION EMERGENCY LOADIElG OF VITAL BUSSES

1. If the vital busses loose voltage prior to resetting the safety injectionsignal, the vital busses will automatically load the vital equipment

-given below. Verify the quipment has been loaded by observing breakerlights on the control board.

2. If the vital busses loose voltage after the safety injection signal hasbeen reset, load or verify loaded the equipment given below onto the

n ~ ~ ~ e ~

1 1 J ~ IlI I vvv sapjas vA I IIIQ t t iy 4 SeeendS be fPleen 1 03 dl ng OTeach piece of equipment onto a given vital bus.

YITAL BUS

NOTES F NOTES

VITAL BUS

NOTES

VITAL BUS

2 D/G 1-3

2&3 MCC 1-F

2 CC Pp l-lSI Pp 1-1

1&2 CFCU 1-2

1&2 CFCU 1-1

2 CCW Pp l-l2 ASW Pp 1-1

2 AFW Pp 1-1

ilOTES:

2 D/G 1-2

2&3 MCC-1-G

2 CC Pp 1-2

4 Cont Spray Pp 1-1

RHR Pp 1-1

1&2 CFCU, 1-3

1&2 CFCU 1-5

2 CCW Pp 1-2

2 ASW Pp 1-2

2 D/G 1-1

2813 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 ofvol tage signal.

3. The vital 480 volt MCC will not strip from the bus; however, it should beverified on the bus.

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

PAGE 18 OF 21 REVISION DATE 4/19/80

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2'HERGEVCY OPERATING PROCEDURE NO. OP-0

TITLE: REACTOR TRIP WITH SAFETY INJECTIO

APPENDIX S

DETERMINATION OF ADEQUATE CORE COOLING

This appendix provides the guidance to determine adequate core cooling ifinadequate core cooling is suspected. Further, the instructions for regainingadequate core cooling is presented.

ACTION

1. If 1 or more RCS hot leg wideWmnren DTA I r ~ ~~ ~ ~ t 'gnAO I.~ ~ o~u ~ i ~ v u upas vuu>s S Vvproceed as follows.

2. If P-250 point U0091 isavailable, proceed with Step 3.If the P-250 point U0091is oot available go to Step S

immediately.

3. Determine the core outletaverage thermocouple reading.If the average core outletreading is less than 1200'F,ADEQUATE CORE COOLING EXISTS.Notify tne control operatoradequate core cooling ex'.sts.

4. If the core outlet averagetherooouple r adirg is greaterthan 1200 F, INADEOUATE CORE

LIN X S . Notify tcontrol operator and immedia.elygo to Step 11

'.

If the core outlet therr»ocoup;ereadings are available at th™incore board in the controlroom, proceed with Step 6. Ifthe therocouples are not available,go to Step 9.

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

COtNENTS

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

6. Continue to take average readingsas long as the wide range hot legloop temperatures are grea el than700'F.

PAGE 19 OF 21 REYISION DATE 4/19/80

DIABLO CAtlYO"l POWER'PLANT UNIT NOS. 1 AtlD 2EtiERGEt'CY OPERATII'lG PROCEDURE tl0. OP-0

TITLE: REACTOR TRIP WITH SAFETY IriJECTION

ACTION

APPEtlOIX 8 (Cont. )

COt 1HEH TS

7.

8.

9.

10.

If the average of the thermocouplesis greater than 700'F (all peggedhi), INADEQUATE CORE COOLING mayexist. Notify the control operatorand go to Step 10.

If both the P-250 incore thermocouple7 Oah llln >nrl f'ha l nr n| n ~n~A~ n~r it

~ \ &4 & ~ ~ ~ J&tl.e incore board in the control roomare unavailable, proceed with Step 9.

Proceed to the control board anddetermine if all hot leg wide rangeloop RTD's are pegged hi. If thehot leg temperature are not peggedhi, AOEOUATE CORE COOLING EXISTS.If the hot leg temperature arepegged hi, ItlAOEgUATE CORE COOLINGtlAY EXIST. Notify the controloperator and go to Step 10.

If SI f Iow to the RCS or auxiliaryfeedwater flow is being deliv redto the steam generators, ADEQUATECORE COOLING EXISTS, If neitherSI flow to the RCS nor AFW flow tothe steam generators can not beverified, Ii'lAOEqUATE Col= CUOLIt'GEXISTS. Notify the control operatorand proceed to Step 11.

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

10. Continue to moni tor SI and AF';Iflow.

ItlAOE UATE CORE COOLING INSTRUCTIONS

E

Carry out the instructions givenin the Emergency Procedures GeneraIAppendix 2 (Notification of Off-sitePersonnel in the Event of an Emergency).

12. Attempt to establish SI flow tothe RCS or AFM flow to the steamgenerators.

'PAGE 20 OF 21'EYISION 0 DATE 4/19/80

OIAf5$0 CANYON POVER PLANT UNIT NOS. 1 AND 2~ Eb)ERbENCY OPERATING PROCEDUREI fl0. OP-0

TITLF.: REACTOR TRIP llITH SAFETY INJEC'I ION

ACTION

APPENDIX 8 (Cont.)

COh lENTS

13. Continue monitoring core outlettemperature to determine theeffectiveness of the remainingactions.

14. DEPRESSORIZE THE RCS by methoda or b below.

a. Oump steam to the condenseror atmosphere if the steamgenerator levels are in thenarrow range and AF';,'low isevident.

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

THEN

Open the pressurizer PORV's.

15. If no means of depressurization areavailable, or if the depressurizationdid not result in decreasing coreexit thermocouple or side rangehot leg temperature,

THEN

START A RCP if possible.

~ "14, tlonitor Rl!ST.level and per'formAppendix-A when the RUST lolevel alarm is reach d.

a. This is th pre erredmethod.

b. Opening the PORV willreduce the RCS oressure toallow SI flow to cool thecore.

15. Start one RCP. No conditiorsare imposed on starting thpump. The pump must be startedto move coolant through thecore.

PAGE 21 OF 21 REVISION DAiE ~aasnn