ML20040A974

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Emergency Operating Procedure EP OP-2,Revision 1, Loss of Secondary Coolant. Related Correspondence
ML20040A974
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/26/1981
From:
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20040A967 List:
References
EP-OP-2, NUDOCS 8201230023
Download: ML20040A974 (28)
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Text

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,J._XHIBIT 10

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" * **" EP "-2

--Pacific Gas and Electric CampanyREVislCN i5/25/ 81

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~ G c#3 DATE PAGE 10F E3

,* DEPARTMENT OF NUC1.1 AND EAR 2 PLANT OPERATI I  ; I DI A8'.O CANYON POWER PLANT UNIT _

7g_

LOSS OF SECONDARY COOLANT

_- CA8c =

b APPROV ED . .

PLANT MAN AGER

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SCOPE taken in the event of ai Loss cy This croceoure covers tne operating steos to be s of Seconcary Ccolant. t*. at reactor trio and safety It is assumed - g inje actuations have occurrec.

Operating P rocecure No. 09-0.

d g SyMPTCM5 /k a (See OP-0 Symotoms/0iagnosticy !wgh , DAN .c..

2 51982 > 1

. . ':.mWy ve AUTOMATIC ACTIONS 9.-

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" UId- b (See OP-0) c ,y team gener concitiene CEJEC'!VE5'

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1.

Tc estaolisn stabli:ec reactor coolant system anc s criar oc plant cooldewn. isolation of the break 2.

To minimize tne energy release due to th'e -

-3 break by wnere possible. --

lifting by diroing steam the 3.4T5%E'tnep@ressurter safety. valves.QomiieVaff b iaT Fiteimat=ostinere from the unaffected steam genera 4

To isolate the auxiliary feecwater ficw to the athe intact st to maximize auxiliary feecwater ficw to to minimi:e the er.ergy release. i in reactor shutdcwn

5. To borate tne reactor coolant to establish a margi n.

f IW EDIATE OPERATOR ACTIONS i ns in the reacter trip with Sa ety 1 the imediate operator act o

1. Perfor:

In.iection E.mrcency Procedure OP-0.

f$jljjgK2305000275 020114 -

C PDR l

NUMBER EP OP-2 OlABLO CANYON POWER PLANT UNIT NO(S1 1 AND 2 ggvision 3 oATE 5/25/81 TrTLg LOSS OF SECONCARY CCOLANT PAGE 2 OF ?Q SUBSEOUENT OPERATOR ACTICNS ,

ACTIONS COMMENTS

1. Initiate tne site EmergencJ. alam.

cr .

2. If tne pressuri:er PORV's open at any time curing this prmcecure, ^ verify 7 reclosure wnen the RCS pressure falls below the PORV set:ofht. Isolste the PORV if the valve fails to close.

If the valve remains ocen and cinnot be isolated, go to OP-1. ,

3. Verify main steam line isolation. If 3. Closing the valves helps main steam line isolation has not' tify tne f aulted steam ger occured, close tne following valve's ,

tor.

Steam Generator No. I t FCV 41 Steam line: isolation valve FCV-25 Isolation valve bypas's FCV-760 IC bicwdewn valve 1

Steam Generator No. 2 FCV 42 Steam line isolation valve FC/-Za Isolation valve bypass FCV-761 IC blowdcnn valve Steam Generstar No. 3 FCV 43 Steam line isolation valve FCV-23 Isolation valve bypass FCV-762 IC blowdown valve Steam Generator No. A FCV 44 ' Steam line isolation valve FCV-22 Isolation valve bypass FCV 63 LC blowdown valve

MJMBER i? OP-d 1 440 2 PEVislCN I DIABLO CANYON PdWEH PLANT UNIT NOISI 3/26/8l DATE PAGE 3 op 2 3 7 tite LOSE OF SECON017Y COOLANT COMMENTS ACTIONS

4. Verify 10% atmosoneric steam cumos coen to hold s eam generator pressures below :ne safety valves.
5. CAUTION: 1) Automatic reinitia'
5. If the RCS pressure stacilizes above tion of safety injection will
nc shutoff neac of the RHR pu=os, not occur after this step j reset safety injection and shutcown since the reactor trip breakeg botn RHR pu=os. Continue to menitor are coen. If tne orcrator hae the RCS pressure and restart these indicaric ' that an SI is pumos if tne RCS oressure arcos recuired t iter tnis step, he to tne snutoff head of the pumas. must initiate it manually.

CAUTION: 2) If loss of off-sil power occurs after resetting safety injection, it will be necessary to load the safe-guares ecuipment onto the vital busses manually. If safety injection is reinitiatt manually ifter the loss of

' ~ off-site power, thi vital busses will automatically secuentially load the safe-guard ecuipment. If loss of off-site power occurs, go to Accendix E (Blackout with SI Emergency Leading of Diesel Generators).

6. NOTE: The conditions for
6. If W.R. RCS pressure decays below stopping RCP must be contin-1220 psig or is below 1220 psig and uously monitv"d througnout stacle. One transient.
a. Again verify a =inimum of one cnarsing pump delivering flow and one 51 pur.) delivering flow to tne RCS,
b. THEN STOP_ all four reactor coolant pumes.

Maintain seal water flow to the RCP seals.

c. Close the Centrifugal Charging pumo
c. IftheRCSpressureisr/

stored above 2000 psig )

recirculation valves (8105 & 8106). een E105 & 8106 to pra

d. If component cooling water to the RCP's tect t.5e pumos f rom das is isolated due to a cantainment chase S isolation, stop all RCP's within 5 i

minutes and maintain seal flow as acove.

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.am NUMBER E? 0?-i OLABLO CANYON POWER PLANT UNIT !10(S) 1 AND 2 REVis10N I DATE 5/25/81 LOSS OF SECONDARY COOLANT PAGE 4 OF 2 $

Tm.E COMMENTS ACTiCNS_

7. The low pressure steam generator
7. Monitor steam generator pressures is the faulted steam generator.

to determine tne faulted steam generator.. If cne steam generator has a kw steam generator pressure, re-tinate APJ ' low to that e e=m gener3ter.

]

Steam Generator No. 1 Low Pressure _

Close LCV's 106 and 110.

- j Steam Generator No. 2 Low P ?csure I

l close LCV's 107 and 111.

_ Steam Generater No. 3 Low Prassure Close LCV's 108 and 115.

Steam Generator No. a Lew Prassura Cicse LCV's 109 and 113.

If all steam generators are depressurited or depressurizing, maintain AFW ficw to all steam generators until tne faulted steam generator is icentified.

8. If all steam generator pressures are stable.
a. APJ flow to the individuxl
a. Di match an ocerator to inspect steam generators my supply the feedwater and main steam adcitional information as to G lines for a possible break. b: sak lu:ation.

If a break is found, continue with step 'J.

9. If a break is not found, return ,to Accident Diagnostics itep 3.in OP-0.

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l sHM8ER i?-OF-2 asvision 1 DIABLO CANYCN' POWER PLANT UNIT NO(S) oATE 5/26/81 LOSS OF SECONCARY CCCLANT PAGE 5 0F 28 _

7p7te-CCMMENTS

[ ACTIONS I 10. Verify AFW flow to all nonfaulted steam generators. Maintain maximum' AFW flow until s eam cenerator narrow range level indicat=rs are reading on scale.

11. If s .eam generator water leve' increases in an unexcectec manner .n ene steem generator, go to 0F-3A l

steam generator tuce rupture. i

12. If: curs the lo lo level alarm en the CST, the Monitor the concensate storace tank 12.

and ucon reacninc accroximately 10 e;urator has aporoxi.ntely 1 level', perform a'. or b below. 25 minutes to perform iters I l

a. or b. l
a. Verify a level in the raw water  !

storage reservoir; then open FCV-436 and FCV-437 (Reservoir supply to AFW pu os). Alicw the AFW pumos to run during the transfer. Monitor the AFW flew closely. If AFW flow is lost,

_ trio all 3 AFW pumos until the transfer is complete, then restart th's pumor. -

b. If the raw water storage reservoir is not available, go to Accencix C (AFW Puma t

suction Sucply fron; Fire Water Tank Pro-cedure) . Allow :ne API pumos to run dur-Monitor tne AFV flow ing the closely. tra'nsfer.If AFW ficw is lost, trip all 3 AFW pumos until the transfer is co=clete, then res art the pumos.

13. If containment spray has been initiated and containment pressure has decreased to less I  : nan 22 psig.
a. Reset Train A and Train B containment spray actuation,
b. Verify all CFCU's running on low speed.
c. Stop both C.S. pumos.
d. Close spray additive valves.

14 If containment spray has been initiated and con-tainment pressure rer.ain,s acave 22 psig, reset containment scray signal and cancel the sprayMonitor FWST addi tive. Close valves 8994A&B.

level throughout this procecure and wnen the V.3T i low level alarm 32% is annunciated, perform l

a. to c. beicw.

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M8ER EP GP-2 DIABLO CANYON PCWER PLANT UNIT N0(S) 1 AND 2 REVis:CN }

cAn 5/26/81 TIT 1.5 LCSI 0F SECONCARY COOLANT PtGE6 OF 29

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CD.v ENTS ACTIC'.~

a. Verify RHR pu=os trio if they are running.
b. Perform Aopendix A (SI Injection /

Recirculation Changeover Procedure).

c. Cantinue to spray with the C.S.

pu=os witnout additive until the

  • RWST lo lo level alam is annun-ciated, tnen shutdown the c::nuin-ment spray pu=os.
d. After tne cnangeover to cold leg recireu}ation, use the RHR to co'ntinue to spray containment until c::ntainment pressure is less than 22 psig. Verify CFC1J's l

running on lo speec prior to tar.ninating conuinment spray.

15. Ter.ninate safety injection if 15. Canditicas for temination criteria A, 3 or C below can be met. should be c::ntinuously con l Manitor and suy within the Tecnni- tored thrtugncut these cal Saecifications heatup/cocidcwn instructions. If all stea

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curtes wnile trying to mecc the generators are depressuri::

or depressurizing, do NOT criteria for :eminating SI.

teminate SI until the fat steam generator is identi A. ' ,

1.) One wide range R'CS loop THOT is 1) Attemot to maintain te-

< 350*F. If possible, c::nfim .ture <350*F. If the by c::tt exit themc;oucles. criteria described in are used for teminati:

of safety injecticn ani the reactor coolant te atures increase to >25 maintain the safety ici i 'in pumps in ocerati@

until all criteria for or "C" below are satis

2) AND wide range RCS pressure >700 psig and stable or increasing,
3) AND PZR level >2": and rising, AND subcooled =argin meter reading 4) If the subcooling mar
4) monitor becomes INOP5

>35'F succ::aled, or suspect, use the saturation curie to detemine subcooling.

NUMBER O vP-d CI ABLO CANYON #CWER PLANT UNIT NO(S) R EVislON l LOSS OF SECCNCARY CCOLANT cAn 5/25/81 :

i 1T1. P.1GE 7 0F 2S ACTICNS

5) AND auxiliary feecwater flow has ceen isolatec to all depressur-1:ed steam cenerators and a) ~or b) is satis?ied below.

a) AFW flow to the unfaulted steam generators is greater than 205 gpm per steam gen-erator, b) ~0R one steam cenerator narrow range water level i ; greater

, than 10%.

i l 3.

1) ALL wide range RCS loop T are HOT

>350!F, l 2) AND W.R. RCS pressure >2000 psig -

L -- stacle or increasing, -

3) AND FZR level >22".,
4) AND succ=cled margin meter reading >35'F

, sumcoo1ed, .

5) AND auxiliary fee &ater flow has been l 1solated to all decressurized steam

, generators and a) or b) is satisfied I below, a) AF4 flow to the unfaulted steam generators is greater tnan 205 gpm per steam generator b) C_R, one steam generatcr narrcw range water level is greater than 10:

6) AND centainment pressure and containment raciation and containment recir sump CO NOT exhibit acnor nally hich or Tiicreasing raadings. If c:ntainment conditions are increasing, continue SI until criteria C can be me't.

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l NUMBER i.3 OP-2 1' DIABLO CANYCN POWER Pt ANT UNIT NO(S) g ggggy )

oAn 5/25/81 LOSS OF SECCNDARY CCOLANT PAGE SOF 28

' TITLE CCMMENTS AC IONS C.

1) All wide rance RCS loco T.,0T are n

>350*F,

2) AND W.R. RCS pressure >2000 psig stacle or increasing,
3) AND PZR level >50%,

!. ) ANO subcooled marcin reter readina

~ ~

i G 'F subccoled, -

5) AND auxiliary feedwater ficw has been i isolated to all cepressurited steam generators and a) g- b) is satisfied belcw.

a) AFW flow to the unfaulted steam l

generators is greater unan -205 g;m per steam generator 1

I b) 0R cne steam generator narrow range water level is greater than 10%

6) AND containment pressure or containment 6) If all steam generators raciation or containment recire. sura are :eoressurited or de-

. exnibit acnormally 'n ign or increasing  ::ressuriting, co NOT

! readings. teminate SI until the.

faulted s.eam gener? tor is icentified.

NUMBER F.P OP-2 DIABt.O CANYON' POWER Pt ANT UNIT NO(S) I and 2 Rems CN I TITt.5_

LOSS OF SEC0!10ARY CCOLANT 9o 2S .

CCMMENTS ACU ONS

16. If criteria A,3 or C above is met and 16. CAUTION: 1) Automatic rainiti-SI has not been reset, reset tne SI anon of safary injection will signal and stro the RHR and SI pumos. not occur afte tnis stPo St:0 one cnarging pumo at a time anc since 'he reactor trip breaker evaluated RCS pressure. Maintain are coen. If :ne coerator sufficient cnarging flow to saoply has indication tnat a SI is acequate seal injection flow.

recuired after tnis steo, he cust initiate it manually.

17. Continue to monitor he RCS conditions.
a. IF, RCS W.R. pressure decreases by I60 psig,
b. OR, PIR level decreases by 10% b. NOTE: PIR level and press a7 iTEex:ectacly frcm SI termination excected to drop wnen letcowI poi nt, is reesublisned.
c. iR,,incicated subccoling < SS*F , ,
d. THEN, manually reinitiate SI pump operation to maintain RCS pressure and

] PIR level and return to Accident

' Diagnostic Section of OP-0. -

e. Safety injection may be teminated after
  • :ne restart wnen reacer coolant pressure is being contmiled to the ncminal value wnicn exists wnen safety injection was initially teminated (Ty <350*F) or to a value greater than or ecual to 2000 psig .

(Tg >350*F) and wnen the reactor coolant

  • indicated subcooling is greater than f0'F.
18. If RCS conditions renain suble per#crm the following steos.
a. Reset containment isolation pnase A.
b. If RCP's have been st=pped, and W.R. RCS b. Start pumo 1-1 or 1-2 i '

pressure is greater than 1220 psig, associated with an un-escolish conditions for surting faul M loop so that PZR RCP's and surt at least one RCP

!cray is effective.

associated with an unfaulted steam NOTE: If the CentrifuoaE generaur. Charging puma recirc va(

c. Verify AC turoine bearing oil pumo (8105 & 8106) wereclosq and Hf pressure seal oil backup in Step 6, reccen thesel valves if RCS pressure cump mening after oil pressure nrcays t' 'l psig and turoine restored above 2000 psif bt tri n -

pumo starts at 600 RF.' tu. ; ae speed. .

M BER E? OP-2 Ol ABLO C/.NYCN PCWER Pt. ANT UNIT NO(S) 1 AND 2 REVisiCN l D^n 5/25/81 TITLg LOSS OF SECCNCARY CCOLNiT PAGE 10 0F 27 AC~ IONS COMMENTS

d. Es'uolish nor nal cnarging.
1) 'Open inst.m ment air valves ECV-584 & 682.

l 2) Check open normal enarging valve 8146

3) Close or check " closed charging to -

auxiliary spray valve 8145.

4) Ooen enarging line isolation valves MO-8107 & 81C8.
5) Adjust HCV-142 & FCV-128 or reciprocal '

cnarging pumo speed to achieve RCP seal flow and enarging ficw as recuired to main-tain pressuri:er level greater than 225.

6) Ocen RCP seal return valves, MO-8100 & 8112.

Check seal flow normal.

7) Check open or ocen centrifugal charging puma recirculation valves.
e. Establish normal' letdown.
1) Open letcown valves LCV-459 & 460.
2) Open letcown isolation valve 8152.
3) Open one 75 gpm ietdown orifica valve.
4) Verify pCV-135 opening by observing letdown ficw.
f. C'ose the BIT inlet and outlet valves MO 8802A & B, and MO 8801 A & B.
g. Establish VCT makeup and transfer charging pumos suction to VCT.
1) Adius: VCT makeup blend to tne no-load cer. centration.
2) Open VCT outlet valves LCV-1123 and C.
3) Close RWST to charging pump suction valves 8805A & B.

NUM3ER 5? OP-2 DIABLO CANYCN PCWER PLANT UNIT NOIS) 1 AND 2 REVislCN I LOSS OF SECCNDARY CLCLANT cATE 5/25M TITLE '-

PACE ll_CF 2,g ._

ACTIONS COMMENTS

4) Verify divert valve LCV-Il2A in AtJTO.
h. Verify or esno!!sa nori:L cnarging to maintain FZR level at 22: anc W.R. RCS pressure at tne value reached

{ wnen SI was ter:nnated or 2000 psig.

, Reesaclisn PIR heaters and return to aut:=atic level and pressure control only after containment c:nditions are sucn :nat procer oceration of the centrol systems can be verified.

1. Stco all 3 diesel generators if off-site ;cwer available and place diesei generator c:ntrol swittnes in AUTO.
j. Place tne main and fe=cet.mo turbines an turning gear at 0 RPM sgeed.

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'9. Borate the RCS to the cold Xe free l c:ndition, if recuired.

20. If :ne nonfaulted steam generator levels nave returned to tne narrow range regulate AF4 flow to :.aintain levels in the narrow range.
21. Verify 50*F subccoling on the RCS sub-c: cling meter. If 50*F subccoling is present, go to step 24.
22. If 50*F subccoling is not present, attempt to establish 50*F succ cling vitn merned a. or b. below.
a. Dumo Stear. to the condenser. a. This is the preferred if tne creax is ins 1ce t:.c MSIV's method.  !

or if a feecwater line break was found, open the M.S. isolation valves from the Safety injection pu:ra unfaulted steam generators. Reset the operation should be q steam cump c:ntrol to the steam header initiated if an uncon<

pressure control mode. l.ower the trolled drop in RCS l control setooint to establish 50*F sub- pressure or pressuriz; cooling wnile maintaining less than 50*F level uc urs durino tn

~

HR RCS c:olcown rate. c:oldcwn pmcass.

NW8ER EP OP-2 DIABLO CANYCN PCWhR PLANT UNIT NO(S) 1 AND 2 REvtston 1

' nee n cer"*m 2 0v can' W.

ATE 5/25/81 TITLE PAGE 12cF 23 AC ICNS COMMENTS During tne controlled coolcown the low RCS pressure criteria for tricoino RCP's will not acoly.

b. Dumo Steam to the At=csoner*. b. The steam generator blow-If tne creax is cuts 1ce tne :.ain do n radioactive levels steam isolation valves, icwer the snould be cnecked prior to setooint on the 10~. atmos::neric cu.: ping steam to tne atmos-steam cur:o valves imm tne enere. If hi radiation is unfaul ad steam generators to found in a steam generator es colisn 50*F succooling wnile use the remaining un-maintaining <50*F/HR RCS cool- faulted naam generators ccwn rate. to cool the plint. How-ever, if no otner method of cooldown is possible, dtrao steam to the at:::cs-pnere regardless of the

- radiation levels in the steam generator bicwacwn.

22. If 50*F succousing cannot be achieved, reinitiate safety injection and go to CP-0 Diagnost cs and reevaluate the iccicent
24. If RCP's are not mnning, establish 24.. Tne la RCS pressure RCP trip c::nditions for starting the pu=cs and criteria will not acply during:

start at least one reactor ccolant tre coolcown. 7 art RCP's pumo not asscciated with the faulted 1 cr 2 if cossidie, so tnat steara gener ttors. pressur1::er spray is possible.

25 If. 50*F succ::aling is pnsent and can be maintained, pmceed with a normal c::ol-down using Operating Pmcedure L-5.

25 Reinitiate SI if an uncontrolled RCS depressurizat;an or PIR level decreases during the plant c:aldown.

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NUMBER EP OP-2 DIABLO CANYON POWER PLANT UNIT NC(S) 1 AND 2 REvtstCN I DATE 5/25/8l

' Oes or gEc0NOApv Cont:NT ' PAGE 130F 23 17TLE -

APPENDIX A S; INJECTION / RECIRCULATION CHANGE OVER PROCEDURE SUBSEOUENT OPERATOR ACTIONS ACTIONF CCMMENTS

1. All stecs listed below must be 1. ' CAUTION: If a loss of off-site carriec out exceditiously, :n a cower nas cccurred in coincicence precise orcerly secuence. Jo witn this precedure and all 3 not interruct the cceration until diesei generators are running and all actions are cc=cleted. When supplying tae vital besses, born ECOS trains are initially continue with :nese instruc icns availaole and a valve fails to as written. If a diesel generator has failed, cc to Accendix B resconc or to ccmolete its ce-mancec operation, postcone any (Loss of Off-site Pcwer with Loss corrective action until the sub- of Diesel Generator) for additional secuent operational stecs are guidance before preceeding. _.

performed.

2. Monitor RWST level closely. If

- :ne RHR pumps co not trip at aoprcx.

33t, trip :nem manually. _ . _ , _ __ _, __

3. If curing :nis cceration the RWST accreacnes a Ot level, stco all pumos taking suction frem the RWST.

Restart pumps after the RHR system l-is aligned to provide suctica.

4. This step may be delayed until -f
4. At the vital 180 valt load centers time permits.

F and H, ciese the breakers for the follcwing valves if not already_

cerferrec.

8980 RHR pu.:ps su:: ply frem RWST ~

52-l F-31.

8976 SI pumcs supply frem RWST >

52-lH-20.

5. Reset SI and Phase B isolatien signals if not alreacy reset.
6. If off-site pcwer is available, shutdown all 3 diesel generators ,

and leave them in AUTO if this has not bean cert:r -ed.

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NUM8sR 5E VEM DIABLO Ct:NYCN POWET, PLANT UNIT NOIS1 1 AND 2 REvts CN I cATE 3/26/31 I_055 nc (70?t0;.;;V C00f_ ANT gg ._

37tc APPENDIX A (cont)

COP.MENTS AC IONS

7. Close (cut in) tne series contac-ters for tne following valves frcm the taggle switenes in tne control room if not alreadv CUT IN.

8809 A & S RHR pumps injecticn to cold legs.

8974 A & S SI pumps recirculatien.

8982 A & 5 RHR pu=cs suction from su=c.

8'. Monitor RWST level, trip all

8. With the SI, charging and possibly pumos taking sucticn from the tne spray pu=cs still taking suc- RWST ucen reacning 0 % level tion from the RWST and the RHR in the tank. Restart pu=cs pu=cs tripced at 33% in the RWST, after RHR suction supplied.

proceed to transfer RHR suction to tne containment su c as follows ir steos 9 thru 29. - - - _ ..

9. Check that tne containment recircu-lation st c level indicaters read at least a0". to provide adecuate NPSH to tne RHR pu=cs. . , , ,.
10. Close th'e two RHR heat exchanger outlet crosstie valves (3716A & B).
11. Close the No. 2 RHR pur:c nor :al suction valve (87003).
12. Ocen the No. 2 RHR pu=c suction valve frem %e containment recircu-lation su=c (S9823).

I3. Open the ce=cenent cooling water outlet valve frem No. 2 RHR heat exchanger (FCV-364).

14. Restart No. 2 RHR pt=c and check flow to the vessel .
15. Close the safety injection pu=c

( recirculation valves (8974A & B).

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. NUM8ER E? OP-2 l OIABLO CANYON PCWE.9 PLANT UNIT NOISI 1 AND 2 l REVisICN I-oA'" ~/25/S1 Tine 1.055 CF SECONDARY COOLANT PAGE15 cF 23 APPENDIX A ; cont)

ACTIONS CD.U.MENTS

16. Open ?.he safety injection pu :p -

suction frem RHR pe=a No. I (88040). Chcck for increased safety injection pu.:o flow and pressure.

17. Close tne safety injection pum::s 17. This step may be delayed if breakert nomal suction valve (8976) frem in steo a nave not been racked in.

tne RWIT.

18. Ocen tne alternate suction vales for tne centrifugal cnarging pc=s (8807A & 3).
19. Close the No.1 F3R p'r.t nomal suction valve (870CA).
20. Ocen the No. 1 RHR pumo suction valve frem tr e containment recircu-lation su== (8982A). ._ _
21. Check the level in the recircu-lation sumo again for acecuate NPSH. .

l

22. Open tne component cooling water outle: valve frem No.1 RHR heat excnanger (FC7-365). -
22. Restart the No. 1 RHR pumo and ,

cneck for flow to the vessel. i I

'24. Open the centrifugal charging pumos altan ate suction valve frem RHR pir.o No. 1 (6804A). Check for ,

increased charging pu=o flow and pressure.

25. Close tN2 charging ou=os nomal suction valves frem the RWST '

(8805A & B).

25. Close the FF.R pumos normal supply 25. Tnis step may be delayed if br-sked in step 4 have not been racked in. i valve frem the RWST (8980).

a

NuM;ER *F

. VF-4 OIABLO CANYON PCWER PLANT didT NO(S1 1 AND 2 REvtslON 1 TITL- LOSS OF'iECONCARY COOLANT El6 0F APPENDIX A (cont)

ACTI0 tis CCt'MENTS

27. When the la lo level point is 27. Trip any other engineered reached in the RWST, trip both safeguard Sumas that are containment spray pumos, still taking suction from -

the RWST. This will only -

be necessary if tne preceding steps hav3 not been comoleted prior to reacning the lo lo -

level set;oint.

23. If stems 4, 17 and 26 were delayed, perform these steps '

at tnis time.

29. If either RHR pumo failed, eitner c:ntainment suma to l RHR suction valve fatted to open (valves 8962A or 8) or l eitner RHR Train to centrifugal H cnarging :cmos or SI pumos suction .!

valves 880?A or B failed to ~ ~ ~ -'

open, go to Accendix 0 (RHR -

Train Failure).

30. Return to tne procecure step tnat was left to perform this Accendix.

t

NUMBEa E? OP-2 CIABLO CANYCN POWER PLANT UNIT NOLSI 1 AND 2 REvis:CN I I  !

TITLE 10FF of CEESiCs:V COOLANT PAGE 170F ES APPENDIX B LOSS OF OFF-STTE POWER CURING LOCA WITH LOSS OF OIESEL GENERATOR ACTIONS CCMMENT3 A. If a diesel generster fails during nis procacure, continue with the procecure as written until Accendix A (SI Injectien/ Recirculation Change Over Procecure) is to ce cerfer=ed.

Then follow :ne guicance given below for the align =ent for cold leg and ,

het leg recirculation.

B. Diesel Generst:r Failure Diesel Gener ater 1-1 Failure

1. If d';asel generator 1-1 has failed, the folicwing steps -

should be used to align the system for cold leg recircu-latien.

a. Verify the folloxing pL=tt are running. 1 AEW Pu=os 1 and 2 ~

AFW Pumo 3 Charging Pumas 1 and 2 CCW Pu==s I and 2 SI Pu=o 1 C.S. Pu=o 1 RHR Pu=0 1

b. With diesel generatcr 1-1 failed, do the following i staps in the order given l b:-icw in Aapendix A (SI it;ection/Recirculatien

-Change Over Procedure).

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

1 i

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NUMBER E? Ch- 2 DIABLO CANYCN POWER PLANT UNIT NO(S) 1 AND 2 REvistoN I

' net nf e f.*

  • y ry v t*mnt 37 cATE 5/25/81 TlT(
  • pace 18 OF 78 ,

APPENDIX B (cont)

ACTICNS CD:4MENTS

c. Throttle HCV-638 to provide aceouate suctior for the SI ano cnarging pumos (approx-imatoly 20 psig acove con-tsinment pressure wnile uinuining RHR pumo motor current less tnan 57.5 amps).
d. Tne cold leg recirculation flow patn would bc as folicws.

RHR pumo 1 from conuinment sumo to cold legs 1 and 2, 51 puns I frcm RHR oumo 1 to all cold legs, c.:.arging pumo 1 and 2 from RHR pu=o 1 to all cold legs via the BIT.

Centainment spray pu=o .1 ,,,

from RWST to spray headers.

Diesel Generator 1-2 Fail ara

1. :f diesel generator I-2 has failed the followi :g steps snould be used to align the system for cold leg recircu-lation.
a. Verify ti.e following pumps are running.

ASW Pu:r.,7 1 AF4 Pur:ps 2 and 3 Charging Pump 1 CCW Puras 1 and 3 SI Pumas 1 and 2 C.S. Pumo 2 RF" Pu=p 2 f

-,: , - e c. i - , -- , - - - -

, .r . ,

NUMBER E? OP-2

. DIABLO CANYCN PCWER PLAMT UNIT NO(Sl 1 AND 2 REVislCN i DATE 5/25/81 TrrLE , LOSS OF SECCMCARY CCOLU,7 pace 19 OF E8 APPENDIX S (cont)

ACTICNS CCMMENTS

b. With ciesel generator 1-2_ \

failed, do tne following steps in :ne orcer given below in Accendix A (SI Injection /pecirculation Change. Oser Procecure).

Steos: 2,3,4,5,7,3,9,10,11,12, 13,14,15,15,17,18,25,25,27,23.

c. Throttle HCV-637 to provice acequate suction for the SI and cnarging pu=os (accroxi-mately 20 psig acove con-tain=ent pr-ssure wro le dain-taining RHR pumo motor current less than 57.5 amps).
d. The cold leg recirculation flow cath wou;c be as follows.

Contiinment scraran=a 2 frc= ~

RWST to spray heacers. RHR pu=c 2 from contain=cnt sumo to cold legs 3 and 4, SI pu=cs 1 and 2 frcm RHR pumo 2 to all cold legs, enarging pu=c 1 frem RHR pumo 2 to all cold legs via the BII.

Diesal Generator 1-3 Failure

1. If di-sel generator 1-3 has failed, the following steps snould be used tn align tne system for cold leg recirculation.
a. "crify the following pumps are running.  ;

ASW Pu=c 2 AFW Pumo 2 Charging Pumo 2 CCW Pu=cs 2 and 3 SI Pums 2 ,

C.S. Pumas 1 and 2 RHR Pumos I and 2 D

=

.+e.

. NUMBER EP OP-2 DIABLO CANYCN PCWER PLANT UNIT NO(S) 1 AND '?

R EVISION I UA" TIT 1.E LOSS OF SECCNCARY COOLANT [/26/8I Pace 20 cF 6 APPENDIX 3 (cont)

ACTIONS COMMENTS

b. With tne diesel generattr 1-3 failed, co the following steps in :ne order g1ven below in Accandix A (SI Injection / Recirculation Change

. Over Procecure).

t

Steps: 2,3,4,5,7,8,9,10,.11,12,13, 14,15,16,17,18,19,20,21,22,23,24, 27,23.
c. Tnrottle HCV-638 and 537 to provide acecuate suction for the SI anc cnarging pu:::o (approxi-mtely 20 psig aoove containment pressure wnile maintaining RHR our o motor current less than -

57.5 amos).

--f- The cold leg recirculatien - -- -

flow path would be as follows.

Centainment scray pumos 1 and 2 from RWST to spray headers.

RHR pumo No. 2 from gentainment su=p to cold legs 3 and a and to SI pu:::p No. 2.

SI puma No. 2 frem RHR No. 2 to cold legs 3 and A.

RHR puro No.1 from containcent sumo to cold leg 1 and 2 and to No. 2 centrifugal charging pu :o.

CentrifJgal charging pumo No. 2 frem RHR Pu.:o No. 2 to all cold

- legs via the BIT.

M BER E? OP-2 DI ABLO CANYON PCWER PL/.NT UNIT NOIS) 1 AND 2 REVistoN 1 LOSS OF SECONDARY CCOLANT UA" I/20/8I

' 1TL:- PAGE 210F 2S APPENDIX C AUXILIARY r::9 PUMP SUC~ ION SUPDLY ORCM FIRE WATER TANK The coerator has 20 minutes to perfonn this aceration after the lo lo level alann en tne concensate storage tank anc before tne AP4 pumas lose suction.

This provices sufficient time; nowever,tne coerator must not delay and must carry out the valve line up in orcer as written.

If the AFW cumos are being sucolied frem the raw water reservoir and a seismic i event occurs with resultant loss of AF4 suction and auxiliary feecwater flow to tne steam generators, the steam generators will boil cry in acout 30 minutes.

Uncer nese concitions, it is especially imer: ant to excedite this procedure anc raestaclisn AF4 flow to the steam generators prior to one reac:cr losing its he.it sink.

ACTIONS COMMENTS I

Using the attached drawing, proceed to su: ply the AF4 pu:=s suction frem the fire water tank. -

1. Cicse or verify closed MU-0-234 'l. Closing these vahes prevents and MU-0-286, losing fire water out a possible break in :ne reservoir supply line.

2 '~ Close' cr check closed.MU-t 298.

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

4 Cicse or check closed MU-0-427.

5. Open FP-0-306 and FP-0-307.
6. Notify the centrol recm that the

, suction for the AF4 pumps is now available frcm the fire water tank.

7. Frcm the c:ntrol recm open FCV-436 and 437.

~

8. Proceed to tne auxiliary feecwater pumps and vent the puro casings if required- to remve air.

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1 NUMBER :D OP 2-DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ggy,ggy y OATE *i26/81 TITLS '"FS O' 5 ~0NOARY T OLAN7 - pacg23 op h APPENDIX D RHR TRAIN /CCMPONENT FAILURE A. FAILURE IN Rha TRAIN NO. 2 ACTIONS COMMENTS

1. If RHR pu..:o No. 2 failed, 1. Monitor RWST level, unen containment sumo to RHR valve the level reaches the lo 10 89823 or RHR puro No. 2 to SI alarm set::oint, trip all suction valve 88048 failed to safeguarcs ou=os taking suction open proceed witn steos a. to from the tank.
e. to provide cnarging and SI pumo suction from RHR pumo No. 1.
a. Verify RHR pu=D No. I crosstie valves to SI pu=D suction 8807A or 3 open. ,

~

b. Close or verify closed ~

Train No. 2 to SI puma suction valve 88048.

c. Tnrot:le HCV-638 to ensure acecuate suction for the SI anc centrifuctI cnarging pu=os (acproximately 20 psig cbove . containment .

pressure) wnile maintaining RMR puma motor current iess than 57.5 a.ms.

d. Rerum to the OP-2 procedure stem that was left to perform Acpendix A.

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O NUMBER EP C/.2 DI ABLO CANYON POWER PLANT UNIT NOIS) 1 AND 2 REVislCN 1 oATE 3/26/81 TITLE ' "IE OFl30W" '*00' ANI PAGE 240F 28 APPENDIX 0

3. FAILURE IN RHR TRAIN NO.1 ACTIONS COMMENTS i
1. If RHR puma No.1 failed, containment 1. Monitor RWST level, wnen the su=a to RHR valve 8982A cr RHR pu=o level reaches the lo lo alarm No.1 to charging ou=os suction valve setooint, trio all safeguards ESO4A failed to coen, proceed with pu=os taking suction frem the steos a. to e. to provice cnarging tan k, and SI pu=c suction frem RHR pu=c No. 2.
a. Verify RHR pe=a No.' 2 crosstle valves to SI pu. o suction 8807A or 6 coen.
b. Close or verify closed Tetin No. I to SI pu=o sucticn valve 8804A. .,
c. . Throttle HCV-637 to ensure adecuate suction for the SI and - - -

centrifugal cnarging pur:as (accroximately 20 psig acove containment pressure) wnile maintaining RHR pt=:0 motor current 1ess tnan 57.5 a=cs.

d. Return to the CP-2 precedure step that was left to perform Appendix A.

1 e

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, i NUMBER E? OP-2 DIABLO CAMYCW PCWER PLANT UNIT MO(S) I anc 2 l REV!sION I LCSS OF SECCNCARY CCCLANT DATE 3/26/8l 7;7g, PAGE 230F 28 l APCENDIX E

1. If the vitai busses lose voltage criar to resetting me safety injection signal, the vital cusses will aut:matically loac :ne vital ecui=ent giver. below. Verify tne ecuic ent has been loaced by ocserving breaker lignts on =e c:ntrol boarc.
2. If the vital busses lose voltage after tne safety injection signal has been reset, loac or verify loacec :ne ecuignent given below onto the vital busses manually. Allow accroximately 4 seconcs between loading of ear.n piece of ecuits:ent onto a given vital bus. Load or verify that the CFCU are running in low sceed.

VITAL 505 VITAL SUS VITAL SUS F G H 0/G l-3 D/G l-2 0/G l-1 MCC 1-F MCC 1-G MCC 1-H CC Pp 1-1 CC Pp 1-2 SI Pp l-2 SI Pp l-1 l CFCU 1-2 RHR Pp l-1 RHR Pp l-2 CFCU 1-1 CFCU 1-3 CFCU 1 4

~

C Q Pp 1-1 CFCU 1-5 CQ % l-3 ASW Pp 1-1 CCW Pp 1-2 AN Pp 1-2 i AFW Pp l-1 ASW Pp 1-2 i

3. Load the Contain=ent Spray Pumas only if tney wen running rior to tne blackout.- -

l VITAL SUS _

VITAL SUL G H l

i l

I Cont Spray Pp 1-1 Cont Scray Pp 1-2 y

o -. .

NUMBER Ep Op.2 l DI ABLO CANYCN PCWER Pt. ANT UNIT NCISI I and 2 R Evts!ON 1 LOSS OF SECCNCARY CCOLANT DAR - 2MI

. 1TL:- pacs 45cp 8 APPENDIX E EMERGENCY PROCECURE NOTIFICATION INSTRUCTIONS

1. When nis eiergency procecure has been activated and upon direction frem the Shift Forman proceec as follows.
t. Designate this event an Unusual Event. Notify Personnel as ::er Emergency Procedure G-2 (Estaolishment of On-Site Emergency Organization)
b. If a rajor steam line break is accomoanied with primary to secondary leakage >10 g;:m designate this event as an Alert. Notify tnose agencies given in Emargency Procecure G-3 (Notification of Off-Site Organization) .
c. If the primary to secondary leakage progresses to >50 gpm with fuel damage evicent, designate this event as a Site Area Emergency.
e. Within one hour notify tne NRC Ooerations Center using the red phone in the Control Roem. Gather sufficient infor .ation frem all sources prior to calling so mat tne ::none ~

call is meaninciul . Notify the ..

NRC that your call is ;:ursuant to 10 CFR Part 50.72. , (Notification of Significant Events) .

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NUMBER d E-d DIABLO CANYCN POWER PLANT UNIT NO(S) I AND 2 REVISICN I T1',U, inee ne ere~_s.n_.s v can_t_ n47 DATE 5/26/83 PAGE27_ce ?S 2 3 .. ._

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0 NUMBER :D QP-2

~

DI ABLO CANYCN PCWER PLANT UNIT NOIS) I AND 2 REVtsICN I LOSS OF SECONDARY COOLANT oAn S/26/81

.UL-Pacz 23 oF 2S APPENDIX Z EMERGENCY PROCEOURE NOTIFICATICN INSTRUCTIONS

1. When :nis emergency procedure has been activated and ucen cirection from the Shift Foreman, proceed as follows:
a. Designate this event an Unusual Event. Notify Personnel as per Erergency Precedure G-2 (Estaolishment of On-Site Emergency Organization) and tne agencies given in Emergency Procacure G-3 (Notification of Off-Site Organ 1:atica).
b. If a major steam line break is ac: maanied with crimary to seconcary leakage >10 gpm designate this event as an Alert. Imolement Notifica-tien Prececures E? G-2 and G-3.
c. If the primary to sec:ndary leaktge progresses to 250 gpm with fuel darage evicent, designate this esent as a Site Area Emergency. Imole-ment Not'1icaricn Prececures E? G-2 and G-3.

e 6

1 -

.

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