ML20204J733

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Rev 4 to Emergency Operating Procedure E-3, Steam Generator Tube Rupture
ML20204J733
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/03/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
E-3, NUDOCS 8810250229
Download: ML20204J733 (27)
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Text

JUN 0 31988 MGM N

REV. ISSUE /DATE E3 STEAM GENERATOR TUBE RUMURE Rev. 4 j

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A.

PURPOSE I

I This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture.

B.

SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from:

1.

E-0, REACTOR TRIP OR SAFETY INJECTION, Step 22, l

when condenser air ejector radiation or SG blowdown radiation is abnormal.

2.

E-0, REACTOR TRIP OR S AFETY INJECTION, Step 28, f

E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 4, E 2, FAULTED STEAM GENERATOR ISOLATION, Step 6, FR H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, Step 7, when secondary radiation is abnormal.

3.

E 0, REACTOR TRIP OR SAFETY INJECT ON, Step 28 E 1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 3, ES 1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 5, ES 3.1, POST-SGTR COOLDOWN USING B ACKFILL, Step 4, ES 3.2, POST SGTR COOLDOWN USING BLOWDOWN Step 4, ES-3.3, POST SGTR COOLDOWN USING STEAM DUMP, Step 4, ECA-3.1, SGTR WITH LOSS OF REACTOR COOL /.hT - SUBCOOLED RECOVERY !

DESIRED, Step 8, l

ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY !

DESIRED, Step 4 ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 5, i

when an intact SG wide range level increases in an uncontrolled manner.

4.

ECA 3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 2,3, and 4, i

when pressurizer pressure control is restored.

5.

E 1 series foldout page whenever any SG levelincreases in an uncontrolled manner or any SG has abnormal radiation, i

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Page 1 of 27 8010250229 001007 PDR ADOCK 05000213 P

pon l

O JUN O 31988 NtJMBER 7TTI.E REV. ISSlIE/DAE l

E3 STEAM GENERATOR TUBE RUVfUKE Rev. 4 i

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STEP ACTION / EXPECT 1ED RESPO', Sc.

RESPONSE NOT OBTAINED NOTE:

o FOLDOUT PAGE SHOULD BE OPEN.

o PERSONNEL SHOULD BE >1VAILABLE FOR SAbfPLING DUdlNG THE PROCEDURE.

o SEAL INJECTION FLOW SHOULD BE AfAINTAINED TO ALL 3

RCPs.

o IN THE EVENT A SGTR AND A LEAK YO ATbf0 SPHERE OCCUR IN THE SAbfE STEAbi GENERATOR AND RCS PRESSURE IS WITHIN 400 PSIG OF SG PRESSURE, THE AFFECTED LOOP ISOLATION VALVES CAN BE CLOSED, PROVIDED THE St Af0V TO THAT LOOP IS Al2O CLOSED.

(SEE ATTACHbfENT B FOR LOOPISOLATIONPROCEDURE).

1 CHECK IF RCPs SHOULD BE STOPPED:

a. Check liPSI QR charging pumps-
u. QQ IQ Step 2.

AT LEAST ONE RUNh1NG

b. Check RCS pressure-
b. QQ IQ Step 2.

l LESS TIIAN 1150 PSIG I

(1380 PSIG FOR ADVERSE j

CONTAINMENT) l

c. Stop all RCPs
d. Close all four seal water return MOVs
c. IEcontainment pressure is greater than 5 PSIG, TIIEN perforn the follwing:
1. Close Cil TV 240, Cil TV 241 (Sed water return trip valves).
2. Close CC TV-1411 (CCW retum from RCP oil coolers)

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JUN 0 31988 NUhGER TTRE REV. ISSUE /DATE E3 STEAM GENERATOR TUBE RUPTURE Rev. 4 STEP ACT10N/EXPECIED RESPONSE l

RESPONSE NOT OBTAINED 2

IDENTIFY RUPTURED SG(s):

CONTINUE WIm STEPS 5 THROUGH 10, o Unexpected increase in any WHEN RUPTURED SG(s)IS SG wide range level IDENTIFIED.

THEN DO STEPS 3 AND 4.

2 o High activity from any SG blowdown hne sample M

o High radiation from any SG steamline 2

o High radiation from any SG blowdown line Page 3 of 27

JUN03 le8s NLTMBER TTTLE REV. ISSt.*E/DATE l

E?

STEAM GENERATOR TUBE RUITURE Rev. 4 j

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STEP ACMON/ EXPECTED RESPONSE RESPONSENOT OBTAINED i

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CAUTION:

o IF THE TURBINE DRIVEN AFW PUhfPS ARE THE ONLY AVAILABLE SOURCE OF AUX /UARY FEEDWATER, STEAbf SUPPLY TO THE TURBINE DRIVEN AFW PUbfPS biUST BE AfAINTAINED FROh! AT LEAST ONE SG.

o AT LEAST ONE SG AfUST BE SfAINTAINED AVAILABLE FOR RCS COOLDOWN.

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ISOLATE FLOW FROh! RUITUPED SG(s):

a. Close ruptured SG(s) main steamline
a. Cose mptured SG(s) main steamline trip valve (s) non return valve.

IE the non return valve FQIoperable, THEN perform the following:

1. Cose allintact SG main steamline trip valves.
2. Cose steam dump s' apply h10Vs.

hts htOV 520 and hts hiOV-553,

3. Cose reheater steam supply hiOVs, hiS hiOV 35and hts 510V 36.
4. Close AUX steam supply manual l

isolation valve, hts V 513

5. Use intact SG atmospheric vent and terry turbines for steam dump.

I JE prured SG can NQIbe iso from at least one intact SG, I

THEN GDIQ ECA 3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOED I

RECOVERY DESIRED, Step 1.

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b. Cose steam supply valve (s) from l

ruptured SG(s) to turbine driven AFW pump (s) and atmospheric vent valve l

t

c. Verify blowdown isolation valve (s)
c. Cose blowdown manualisolation from ruptured SG(s) CLOSED valve (s) from ruptured SG(s).
d. Close steamline low pint drain valves from ruptured SG(s)
e. Cose steamline trip valve drain valve from ruptured SG(s)
f. Check the bypass for the ruptured SG(s)
f. Cose bypass valve.

main steamhne trip valve - CLOSED I

Page 4 of 27

JUN 0 31998 NasEn mu REv. issue /oAn E3 STEAM GENERATOR TUBE RUMURE Rev. 4 i

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

AUTO AUX FEEDWATER FLOW WILL HAVE TO BE DEFEATED BEFORE SG LEVE12 CAN BE MANUAILY CONTROll ED WITH FEEDWATER BYPASS VALVES.

4 CHECK RUPTURED SG(s) LEVEL:

a. Check wide range level-
a. Maintain AUX feedwater flow to OREATER THAN 63 %

ruptured SG(s) until wide range level (67 % FOR ADVERSE is greater than 63 %

CONTAINMENT)

(67 % for adverse containment).

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b. Control AUX feedwater flow to maintain wide rangelevel between 63 % and 69 %

(67 % to 69 % for adverse containment)

F 7

CAUTION:

IF ANY PRZR PORY OPENS BECAUSE OF HIGH PRZR PRESSURE, STEP S b SHOUL.D BE REPEATED AFTER RCS PRESSURE DECREASES TO LESS THAN 2350 PSIG.

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CilECK PRZR PORVs AND BLOCK VALVES:

a. Check power to block valves -
a. Restere power to block valves.

AVAII.ABLE

b. Check PORVs CLOSED
b. E PRZR pressure is less than 2350 PSIG, THEN manually close PORVs.

0 E any PORY can MOIbe closed,

'IEEN nunually close its block valve.

E block valve can NOIbe closed, THEN QQ IQ ECA 3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

c. Check PORY block valves CLOSED
c. E PRZR pressure is less than 2350 PSIG, IEEE manually close PORY block valves.

Page 5 of 27

JUN 0 31988 NUMBER Tml REV. ISSUE /DATE I

E3 STEAM GENERATOR TUBE RUPTURE Rev. 4 e

i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

6 CHECK SECONDARY INTEGRITY:

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a. Check all SG pressures -
a. IE any SG pressure is decreasing in STABLE DR INCREASING an uncontrolled mant:er i

AND the SG is b'QIisolated.

l THEN GQIQ E 2, FAULTED SG ISOLATION, Step 1.

b. Check all SG pressures -

b.1E any SG is completely depresserized '

GREATER THAN 100 PSIG AER the SG is NQIisolated.

THEN ODIQ E 2, FAULTED SG ISOLATION, Step 1.

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CAUTION:

Af0NITOR DWST LEVEL. START AfAKEUP TO DWST BEFORE LEVEL DECREASES TO 54,000 Gall.ONS.

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7 CHECK lhTACT SG LEVELS:

a. Check wide range levels -
a. Maintain total AUX feedwater flow GREATER THAN 63 %

greater than 320 GPM until wide (67 % FOR ADVERSE range levelin at least one SG is l

CONTAINMENT) greater than 63 %

(67 % for adverse containment).

b. Control AUX feedwater flow to
b. E any SG wide range level continues maintain wide range levels between to increase in an uncontrolled maner, ;

63 % and 69 %

WEN RETURNIQ Step 1.

i (67 % and 69 % for cdverse l

cont:.;nment) 8 CHECK CONTAINMENT START ONE CONTAINMENT INSTRUMENT AIR PREFSURE INTRUMENT AIR COMPRESSOR GREATER THAN 118 PSIG TO ESTABLISH INSTRUMENT AIR PRESSURE.

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Page 6 of 27

JUN 0 31988 NUMBER l TME REV. ISSUE /DATE E3 STEAh! GENERATOR TUBE RUMURE Rev. 4 i

STEP ACT!ON/EXPEC11ED RESPONSE RESPONSE NOT 03TAINED 9

VERIFY'ALL AC BUSES ENERGIZED TRY TO RESTORE OFF S12 POWER BY OFF SITE POWER TO AC BUSES.

1 (SEE OPPOSITE PAGE) l IE OFF SITE POWER CAN b'QI BE

RESTORED, THEN LOAD THE FOLLOWING I

EQUIPh1ENT ON AC Eh1ERGENCY j

BUSES:

1. htCC 5.
2. Control air com ressors.
3. Semi vital 120 olt buses.
4. Closed cooling system pumps.

I S. Battery charger I A.

6. One component cooling water pump.
7. One semce water pump for each diesel.
8. IE service water is used for RHR HX, THEN use two service water pumps.
9. Start CARFANs as required to linut containment pressure and temperature.

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CAUTIONt RCS PRESSURE SHOULD BE of0NITORED IF RCS PRESSURE DECREASES TO LESS THAN 403 PSIG (63S PSIG FOR ADVERSE CONTAIN&fENT) THE LPSI PUhfPS AfUST BE AfANUAll.Y RESTARTED TO SUPPLY WATER TO THE RCS.

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10 CllECK IF LPSI PUhtPS SHOULD BE STOPPED:

a. Check RCS pressure -
a. QQIQ Step 11.

GREATER THAN 405 PSIG l

(635 PSIG FOR ADVERSE CONTAINhtENT)

b. Stop LPSI pamps and place in TPO i

Page 7 of 27

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JUN 0 31988 IhutBER TITLE REV. ISSLT/DATE I

E3 STEAM GENERATOR TUBE RUITURE Rev. 4 I

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTALNED

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r CAUTION:

ISOLATION OF THE RUPTURED SG(s), n'fTH THE EXCEPTION OF LOW POINT DRAINS. SHOULD BE COMPLETE BEFORE CONTINUING TO STEP 11 UNLESS A RUPTURED SG 15 g

NEEDED FOR ECS COOLDOH'N.

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l1 CHECK RUPTURED SG(s) PRESURE ODIQ ECA 3.1, GRE ATER TliAN 500 PSIG SGTR WITil LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, STEP 1.

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Page 8 of 27 i

JUN 0 31988 NUhBER TTRE REV. ISSUE /DATE E.3 STEAM GENERATOR TUBE RUMURE Rev. 4 f

STEP ACTION /EXPECIED RESPONSE RESPONSE NOT OBTAINED I

NOTEt RCPs SilOULD NOT BE TRIPPED UNLESS RCS PRESSURE DROPS TO 300 PSIG, AFTER COOLDOWN IS STAR' FED.

12 INITIATE RCS COOLDOWN:

a. Determine required core exit temperature:

Ruptured SG pressure Average Core Exit (PSIG)

Temperature (* F)

Concintrent Normal Adverse 1000 492 477 900 480 460 800 466 442 700 451 421 600 436 394 500 418 359

b. Dump stearn to condenser from
b. Manually.QR locally dump steam intact SG(s) at maximum rate from intact SG(t) at maxirr.um mte using steam dump using the following:
1. Atmospheric vent
  • alve.
2. Turbine driven A ax feedwater pumps.

IE no intact SG available, T11EN perform the following:

o Use faulted 50 08 o GQIQ ECA 3.1, SGTR Wmi LOSS OF i

REACTOR COOLAST-SUBCOOLED RECOVERY DESIRED, Step 1.

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Page 9 of 27

JUN 0 31988 NUMBER

'ITT1E REV. ISSUE /DATE i

E-3 STEAM GENERATOR TUBE RUPTURE Rev. 4 l

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 12

c. Check average core exit temperature -
c. RETURN IQ Step 12 b.

LESS TIIAN REQUIRED TEMPERATURE i

d. Stop RCS cooldown and maintain RCS temperature less than required temperatwe sc-CAUTIONt RCS COOll)OWN IN STEP 12 SHOULD BE COMPLETED BEFORE CONTINUING TO STEP 13.

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13 CIIECK RUMURED SG(s) PRESSURE IE PRESSURE CONTINUES TO STABLE OR INCREASING DECREASE.

THEN GDIQ ECA 3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, STEP 1.

l 14 CliECK RCS SUBCOOLING BASED GQ IQ ECA-3.1, ON CORE EXIT THERMOCOUPLES SGTR WTDI LOSS OF REACTOR GREATER THAN 52' F COOLAST SUBCOOLED (SEE OPPOSITE PAGE RECOVERY DESIRED, STEP 1.

FOR ADVERSE CONTAINMENT) l I

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JUN03 US$

NUMBER Tm.E REV. ISSLTJDATE E3 STEAM GENERATOR TUBE RUMURE Rev. 4 l

3TEP ACTION / EXPECTED RESPONSE P.ES?.ONSE NOT OBTAINED 15 DEPRESSURIZE RCS TO MINIMIZE l

BREAK FLOW AND REFILL PRZR.

I

a. Check nomui PRZR spray -

a QQIQ Step 16 AVAILABLE OBSERVE CAUTION PRIOR TO i

STEP 16.

I S. Open PRZR normal spray alves l

c. Check normal PRZR spr:.y effective -
c. QQIQ Step 16 PRZR PRESSURE RAPIDLY OBSERVE CAUTION PPJOR TO DECREASING SHIP 16.
d. Spray PRZR with maximum available spray until ANY QNE of the following conditions is satisfied:

o RCS subcooling based on core exit thermocouples approaching 32' F (SEE OPPOSITE PAGE for adverse containment) 2 o PRZR level greater than 76 %

i (69 % for adverse containment) l l

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o Both of the following exist:

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1. RCS pressure less than ruptured SG pressure (s) l l
2. PRZR level greater than 10 %

(24 % for adverse containment)

e. Close spny valve (s):

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1. Normal spray valve (s)
1. Stop RCP(s) supplying failed spray valve (s).
2. Auxiliary spray valve
2. Isolate auxiliary spray valve
f. QQIQ Step 18, OBSERVE CAUTION PRIOR TO STEP 18 I

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JUN 0 31988

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NUMBER TTII.E REV. ISSLT./DATE E3 STEAM GENERATOR TUBE RUPTURE Rev. 4 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

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i CAUTION:

o THE PRT RUPTURE DISK SfAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURIZE THE RCS. THIS SfAY RESULT IN ABNORbfAL CONTAINbfENT CONDITIONS.

o CYCUNG OF THE PRZR PORY SHOULD BE hilNibf/ ZED.

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l NOTE:

THE UPPER HEAD REGION SfAY VOID DURING RCS i

DEPRESSURIZATION IF RCPs ARE NOT RUNNING. THIS l

WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

f 16 DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a. Check PRZR PORV -
a. Establish auxiliary spray flow, AT LEAST ONE AVAILABLE THEN RETURN IQ step 15 d.

IE auxiliary spray EQIestablii ut 111EN O_Q IQ ECA 3.3, SGTR WITHOUT PRESSURIZER l

PRESSURE CONTROL, Step 1.

b. Open or.e PORV and its block valve i

until m QEE of the following j

conditions is satisfied:

i o RCS subcooling based on core exit thermocouples approaching 32' F (SEE OPPOSITE PAGE i

for adverse containment)

QR l

o PRZR level greater than 76 %

(69 % for adverse containtnent) i o Both of the following nist:

1. RCS pressure less than ruptured SG pressureis)
2. PRZR level greater than 10 %

i (24 % for adverse containment)

c. Close PRZR PORV and its block valve Page 12 of 27

JUN 0 31988 NUMBER EU REY. ISSUE /DATE E3 STEAM GENERATOR TUBE RUPTURE Rev 4

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S'EP ACTION / EXPT.CTED RESPONSE RESPONSE NOT OBTAINED 17 CIIECK RCS PRESSURE INCREASINO CHECK PORV AND ELOCK VALVES CLOSED.

E PRESSURE CONTINUES TO

DECREASE, HIEN PERFORM THE FOLLOWING:
1. Monitor the followinl; for indication ofleakage from PRZ1 PORV:
a. Check PORY tail pipe temperature indication,
b. Check PORY acoustic monitor.
2. GQIQ ECA 3.1,

'GTR WITH LOSS OF REACTOR

)LANT - SUBCOOLED E

TVERY DESIRED, Step 1.

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Page 13 of 27

4 JUN 0 31988 NUMBER TTTT E REY. ISSUE /DATE E3 STEAM GENERATOR TUBE RUITCRE R e v.

4 STEP ACTION /EXPECIED RESPONSE RESPONSE NOT OBTAINED r

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CAUTlON:

51 MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVEhT OVERFILL 2NG THE RUPTURED SG(s).

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i 18 CHECK IF $1 t1.OW SHOULD BE TERMINATED:

a. Check RCS subcooling based on
a. DO NOT STOP S1 PUhiPS, cc > exit thennocouples -

EQIQ ECA 3.1, O.. DATER TliAN 32' F SGTR WTTH LOSS OF REACTOR (SEE OPPOSITE PAGE COOLANT SUBCOOLED FOR ADVERSE CONTAIN'EVO RECOVERY DESIRED, Step 1.

b. C.;eck secendary heat sink:
b. DO NOT STOP St PUhtPS, GQ IQ EC/ 4.1, o Check total AUX feedwcer flow -

SGTR WITil uOSS OF REACTOR GREATER THAN 320 GPhi COOLAST-SUBCOOMD AVAIIABE RECOVERY DESIRED, Step 1.

2 o Check wide range levelin at I

least one intxt SG -

I GREATER THAN 63 %

(67 % FOR ADVERSE CONTAINhtENT) l

c. Check RCS pressure-
c. DO NOT JTOP SI PUhiPS, STABLE Q1 INCREASING EQIQ ECA 3.1, SGTR WITH LOSS OF REACTOR COOLAST SUBCOOLED RECOVERY DESIRED, Step 1.
d. Check PRZR level-
d. DO NOT STOP SI PUhiPS, i

GREATER THAN 10 %

RETURN IQ Step 11.

(24 % FC" ADVERSE CONTAi

' OM l

l 19 STOP St Pi oth A D PLAC': B TPO:

I o llP'il Pi a i

l o LPSIPtt i l

o All but a s*

at t

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JUN 0 31985 NUMBER TTTLE REV. ISSLTJDATE i

E3 STEAM GENERATOR TUBE RUPTURE Rey, 4 i

(

STEP ACT10N/ EXPECTED RESPON5E RESPONSE NOT OBTAlhTD r

7 CAUTION:

o IF OFF SITE POWER IS LOST AFTER RESETTING SI, AfANUAL ACTION AfAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPEI!ENT.

o IF CONTROL SWITCH FOR ANY SHUTDOWN CHARGING l

PUhfP WAS TAKEN TO THE TRIP POSITION, THE PUhfP(S)

AfAY AUTO START WHEN BOTH Si WL RELAYS ARE RESET.

\\

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20 RESET SI AND CONTAIh3 TEST ISOLAT10N:

a. Check containment pressure -
a. Perform the following-LESS TifAN 5 PSIO
1. Open CKTs A13 and B13 in DC panels A and B.
2. Reset SI WL Relays.
3. IE charging pump control switch (es) are NQIin TPO, 111EN restore low discharge pressure a sto start for shutdown charging pump (s) by taking pu control switch (es) to the

'T

" position then reles ing swit h(es) to the "Auto" position.

4. QQIQ Step 21.
b. Ret.et Si and containment isolation (SEE OPPOSTTE PAGE) 21 PLACE SI SYSTEM IN STANDBY:
a. Place SI pumps in standby
b. Close loop St MOVs and Core Deluge MOVs l

22 CONTROL CHARGING FLOW TO MAINTAEURZR LEVEL l

Page 15 of 27

JUN 0 31985 NUMBER 1TIU REV. ISSUE /DATE E3 STEAM GENERATOR TUBE RUPTURE Rev.4 f

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STEP ACTION /E) TCTED RESPONSE RESPONSE NOT OBTAINED l

23 VERIFY St FLOW NOT REQUIRED:

f

a. Check RCS subcooling based on
a. Manually operate SI pumps as l

core exit thermocouples -

necessary.

GREATER THAN 32' F GQIQ ECA 7,1, l

(SEE OPPOSITE PAGE SGTR WITH LOSS OF REACTOR FOR ADVERSE CONTAINMENT)

COOLAST SUBCOOLED RECOVERY DESIRED, Step 1.

l

b. Check PRZR level-
b. Manually operate SI pumps as I

GREATER THAN 10 %

necessary, (24 % FOR ADVERSE lE level can b'QIbe maintained.

l 1

CONTAINMENT)

THEN QQ IQ ECA 3.1, SGTR WITH LOSS OF REACTOR COOLAST SUBCOOLED RECOVERY DESIRED, Step 1.

24 CHECK VCT MAKEUP CON'IROL SYSTEM:

a. Check VCT makeup blender ratio-
a. Adjust makeup blender ratio to SET FOR GREATER "TIAN RCS greater than RCS boron concentration. t BORON CONCENTPATION l
b. Check VCT makeup controls -
b. Place makeup controls in automatic.

l IN AUTOMATIC I

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JUN 0 31988 NUMBER TTILE REY. ISSUESATE E.3 STEAM GENERATOR TUBE RUPTURE Rev. 4 l

STEP ACTION /EXP:CTED RESPONSE RESPONSE NOT OBTAINED 25 CHECK IF LETDOWN CAN BE ESTABLISHED:

a. Check PRZR level-
a. Continue with step 26, GREATER THAN 15 %

WHEN PRZR levelis (35 % FOR ADVERSE greater than 15%

CONTAINMENT)

(35 % for adverse containment)

IllES do step 25 b.

b. Establish letdown
b. IE containment pressure is (SEE OPPOSITE PAGE) less than 5 PSIG, THEN establish alternate letdown by performing the following:
1. Reset Containment HCP WL Relays.
2. Open DH TV 1841, drain header tnp valve.
3. Reset solenoid in blowdown room for drain header trip valve, DH TV 1847,
4. Line up drain header to VCT:
a. Cose DH.V-408, drain header to PDT.
b. Open CH V 383, drain header to VCr.
5. Cose breaker for DH MOV-310.
6. Open one loop drain MOV.
7. Throttle DH MOV 310 to maintain PRZR level.
8. Cose CH MOV-292B and CH-MOV 292C.

26 ALIGN CHARGING PUMP SUCrlON TO VCT:

a. Open CH MOV 257
b. Cose DA MOV 373
c. Check BA MOV 32 CLOSED
c. Cose BA MOV 32 Page 17 of 27 1

JUN 0 31988 NUMBER Tm2 REV. ISSUE /DATE E.3 STEAM GENERATOR TUBE RUITURE Rev 4 l

(

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED r

7 CAUTION:

RCS AND RUPTURED SG(s) PRESSURES AfUST BE AfAINTAlNED LESS THAN THE RUPTURED EG(s) SAFETY VALVE SETPOINT.

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27 CONTROL RCS PRESSURE AND hiAKEUP FLOW TO MINIhil7E RCS TO SECONDARY LEAKAGE.

a. Perform appropriate action (s) form table below:

i PRZR LEVEL RUPTURED SG(s) LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 15 %

o increase RCS Increase RCS o increase RCS

( 35 % FOR makeup now makeup flow makeup flow ADVERSE CONTAINMENT) o Depressurize RCS o Maintain RCS and using Step 27 b.

ruptured SG(s) pressures equal BEDVEEN 15 %

Depressurize RCS Turn on PRZR Maintain RCS AND 50 %

using Step 27 b.

heaters and ruptured

( 35 % AND 50 %

SG(s) pressures FOR ADVERSE equal CONTAINMENT) bEDVEEN 50 %

o Depressurize RCS Tum on PRZR Maintain RCS AND 76 %

using Step 27 b.

heaters and ruptured

( 50 % AND 69 %

SG(s) pressures FOR ADVERSE e DsTease RCS equal CONTAINMENT) raakeup now GREADER DIAN Decrease RCS Turn on PRZR Maintain RCS 76 %

makeup flow heaters and ruptured

( 69 % FOR SG(s) pressures ADVERSE eqt'al CONTAINMENT)

b. Use normal PRZR spray to
b. IE letdown is in service, accomplish action specified in THEN use ausiliary spray.

l table for s'ep 27 a l

IEletdown FQIin service, THEN use one PRZR PORV.

t Page 18 of 27

JUN 0 31988 NUMBER Trn.E REV. ISSt1E/DATE j

E.3 STEAM GENERATOR TUBE RUITURE Rev. 4 I

9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

28 CHECK IF DIFSEL GENERATORS SHOULD bu STOPPED:

1. Verify ac emergency buses energized -
a. Try to restore off site power to BOTliTRAINS BY OFF SITE both trains.

POWER (SEE OPPOSITE PAGE) 1 BUSES 8,4 and 5 IE NQIrestored.

AND

'niEN load the following equipement t

BUSES 9,6 and 7 on the ac emergency buses:

1.MCC 5.

l

2. Control air compressors.
3. Semi vital 120 V buses.
4. Closed cooling system pumps.
5. Battery charger I A.
6. One component coeling water pump.
7. One service water pump for each diesel gene.c..or.

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8. IE service wates is supplied to RHR heat exchangers.

I T11EN use at least two service water pumps.

9. Start CARFANS as required to limit containment pressure and temperature.
b. Stop any unloaded diesel

'l generator and place itin standby (SEE OPPOSITE PAGE)

I 29 MINIMlZE SECONDARY SYSTEM l

l CONTAMINA'I1ON:

j

a. Check for leakage from ruptured SG(s)
b. Close CD V 634 conder.ser high leveldump isolation valve 30 RJPN ON PRZR IIENIT.RS AS NECESSARY TO HEAT PRZR

)

WATER TO RUPTURE SG(s)

SARJRATIO" TEMPERATURE i

)

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Page 19 of 27

JUN 0 31988 NUMBER TTn2 REY. ISSUE /DATE i

E3 STEAM GENERATOR TUBE RUPTURE Rev. 4 i

STEP ACTION / EXPECTED RESPONEE RESPONSE NOT OBTANID I

31 CHECK RCP COOLING SYSTEMS:

ESTABLISH NORMAL COOLING FLOW TO RCPs, o RCP CCW System flow NORMAL IN ACCORDANCE WITH, o RCP sealinjection flow NORMAL NOP 2.81.

OPERATION OF COMPONENT COOLING SYSTEM, Ab32 NOP 2.61.

SEAL WATER STARTUP NORMAL OPERATION.

l 32 CHECK IF RCP SEAL WATER STOP AFFECTED RCP(s).

RETURN FLOW (s)IS GREATER 'IllAN 0.2 GPM e

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Page 20 of 27 l

JUN 0 31988 SUU1ER TTTLE REV. ISSUE /DATE E3 STEAM GENERATOR TUBE RUPTURE Rev. 4 I

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STEP ACI10N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED r

7 l CAUTIONt IF RCP SEAL COOUNG HAD PREV lOUSLY BEEN LOST, THE i

AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO AV h

ENGINEER!NG EVALUATION.

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NOTE:

RCPs SHOULD BE RUN IN ORDER OF PRIORITY TO PROVIDF NORMAL PRZR SPRAY.

I 33 CHECK RCP STATUS:

a. Check RCPs -
a. Try to start one RCP:

AT LEAST ONE RUNNING

1. IE RVLIS head indicates less than 100 %,

THEN perform the following:

o Increase PRZR level to greater than 75 %,

(90 % for adverse containment),

o increar,e RCS subcooling based l on core exit thermocouples to i

greater than 60' F l

(SEF OPPOSITE PAGE for adverse containment).

2. Establish conditions for starting an RCP:
a. Close loop Tc isolation valve.
b. Open loop bypass valve,
c. Start oil lift pump,
d. Insure seal water and component cooling ' vater supplied to RCP. l
e. Insure lower Naring temperature !

is less than 170: F.

f. Check RCS pressure j

greater than 300 PSIG.

g. Open CH TV 240, CH TV 241 and CH TV 334.

(scal water return trip valves)

I

h. Open CC-TV-1411 (RCP oil cooler CCW rerum trip valve)
1. Open seal water retum MOV.

I Page 21 of 27 1

JUN 0 31988 NUMBER TTI12 REV. lSSUE/DATE 3

E.3 STEAM GENERATOR TUBE RUPTURE Rev. 4

(

STEP ACT10N/EXPECIED RESPONSE RESPONSE NOT OBTAlhTD 33

2. Start selected RCP.

3 THEN perform the following:

a. Oxn loop Tc isolation valve,
b. C ose loop bypass valve.

l E RCP can EQIbe started, THEN perform the following:

a. :. en loop Tc isolation valve.
b. Cfore loop bypass valve.
c. Verify natural circulation (SEE ATTACHMENT A).

E natural circulation EQIverified, 11IEN inacase dum ping steam.

d. Attempt to start another RCP.
b. Stop all but one RCP i

34 CHECK SOURCE RANGE i

DETI!CI' ORS ENERGIZED:

a. Check intermediate range flux -
a. Continue with step 35, LESS THAN 5 x 10'10 AMPS WHEN less thsn 5 x 1010 AMPS, IllES do steps 34 b, e and d.
b. Verify source range detectors -
b. Manually energize source range ENERG12ED detectors,
c. Transfer nuclear flux recorders to source range scale
d. Transfer SUR meters to source range 35 SHUT DOWN UNNECESSARY PLANT EQUIPMENT
a. Stop one main feedwater pump
b. Stop one condensate pump
c. Place standby heater drain pump in TPO
d. Place running heater drain pump in TPO l

Page 22 of 27

JUN 0 31988 NUMBER TTIM REV. ISSUE /DATE E.3 STEAM GENERATOR TUBE RUFTURE Rev. 4 i

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 QQ IQ APPROPRIA~E POST SGTR COOLDOWN METHOD:

o CtQIQ ES 3.1 POST SGTR COOLDOWN USING B ACKFILL, Step 1 2

i o QQIQ ES 3.2, POST SGTR COOLDOWN USING BLOWDOWN, Step 1 o GQIQ ES 3.3, l

POST SGTR COOLDOWN USING STEAM DUMP, Step 1 o Isolate affected loop (SEE ATTACHMENT B) e END l

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f Page 23 of 27

JUN 0 31988 NUMBER mu REV. ISSUE /DATE E.3 STEAM GENERATOR TUBE RUPTURE Rev. 4 1

STEP AC110N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A De following conditions support or indicate natural circulation flow:

l o

RCS subcooling based on core exit thermocouples is greater than 32' F.

o SG pressures are stable or decreasing, o

RCS temperature based on core exit thermocouples and average temperatuas indications is stable or decreasing.

o RCS c,ld leg temperatures are at saturation temperature for 50 pressures.

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.lUN 0 31988 NUMBER TTT12 REY. ISSUESATE E3 STEAM GENERATOR TUBE RUMURE Rev. 4 I

STEP AC110N/EXPF.CTED RESPONSE RESPONSE NOT OBTAINED ATTACIBiENT B i

When the decision has been rnade to isolate a loop (s) with a rupture $G, use the fo'Jowing l

procedure.

l 1.

Check ruptured SG(s) isolated:

o Steamlinesisolated o feedwaterlinesisolated 2.

Stop RCP in loop (s) with ruptured SG r

7 CAUTION:

IF CONTROL SH' ITCH FOR ANY SHUTDOH'N CHARGING PUMP %'AS TAKEN TO THE TRIP POSITION, THE PUMP (S)

MAY AUTO START %' HEN BOTH Si %'L REl.AYS ARE RESET.

L J

3.

Reset SI and containment isolation:

a. Check containment pressure -
a. Perform the fo'Jowing:

LESS THAN 5 PSIG

1. Open CKTs A13 and B13 in DC panels A and B.
2. Reset SI WL Relays.
3. E charging pump control switch (es) are h'QIin TPO, THEN restore low discharge pressure auto start for shutdowTt charging pump (s) by taking pump control switch (es) to the 7ttp" position then releasing switch (es) to the "Auto" position.
4. G.Q IQ Step 4.

l

b. Reset Si and containment isolation (SEE OPPOSIE PAGE) 4.

Close ruptured loop (s) SI MOV 5.

Check IF RCS depressurization is required:

I

a. Check RCS pressure -
a. QQIQ Step 8.

GREAHR THAN RUI'RJRED SG(s)

PRESSURE BY 400 PSIG, (180 PSIG FOR ADVERSE CONTAINMEST)

Page 25 of 27

JUN031986 NUMBER TTTU REV. ISSUE /DATE l

E.3 STEAM GENERATOR TUBE RUPTURE Rev. 4 I'

(

STEP ACT10N/ EXPECTED RESPONSE RESPONSE NOT OBTANED l

ATTACHMENT B l

1 6.

Depressurize RCS to minimize RCS to SG differential pressure

a. Use normal PRZR spray a Eletdownin service, THEN use auxiliary spray valve.

E letdown b'QIin service, j

THEN use one PRZR PORV.

i E no PORY available, THEN use auxiliary spray,

b. Depressurize RCS untilone of the i

following conditions is satisfied:

o FRZR level-GREATER THAN 76 %

(69 % FOR ADVERSE I

CONTAINMENT) 6 i

o RCS subcooling based on core thermocouples -

APPROACIENG 32' F l

7.

Check RCS to SG A P-Continue RCS cooldown and WITHIN 400 PSIG depressurization, i

(180 PSIG FOR ADVERSE CONTAINMENT)

WHEN RCS to SG A P is within 400 PSIG (180 PSIG FOR ADVERSE CONTAINMENT),

j THEN QQIQ Step 8.

8.

Close HOT and COI D Leg loop Eloop isolation valves b'QIclosed, Isolanon valves for loop (s) with Ab'D a leak to atrr mohere from the ruptured SG ruptured SG(s) is,. ~ progress, THEN QQIQ ECA 3.1.

l 1

E loop isola' ion valves b'QI closax!.

1 Ab'D a leak to atmosphere from the t

]

ruptured SG(s) is b'QIin progress.

F THEN QQIQ appro 3riate post SGTR j

recovery procedure, ES 3.1, ES 3.'

QR ES 3.3.

i Page 26 of 27 I

JUN 0 31988 NUMBER TME REV. ISSUE /DATE j

E.3 STEAM GENERATOR TUBE RUITURE Rtv, 4

(

STEP ACTION / EXPECTED RESK)NSE RESPONSE NOT OBTAD*ED ATTACHMENT B l

1 I

9.

Close RCP seal water suppy and return isolation valves on isolated loop (s) i 10.

Open isolated loop (s) drain header MOV 11.

Open isolated loep(s) bypass valve

{

12.

Verify loop (s) with ruptured SG is Eloop isolation valves d'QIclosed, isolated:

Ab'D a leak to atmosphere from the ruptured SG(s) is in progress, o Check isolated loop (s) and isolated THEN QQIQ ECA 3.1.

SG(s) pressures -

APPROXIMATELY EQUAL Eloop isolation valves b'QIclosed, Ab'Q a leak to atmosphere from the ruptured SG(s)is h'0Iin progress.

TliEN QQIQ appropriate post SGTR recovery procedure, l

ES 3.1 ES 3.2 l

QR ES 3.3.

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l NOTE:

AN ISOLATED LOOP (s) MUST REMAIN ISOLATED. FURTHER I

RECOVERY ACTIONS MUST BE CONDUCTED AS DIRECTED BY l

PLANT ENGINEERING STAFF.

13.

QQIQ E 1, LOSS OF REACIOR OR SECONDARY COOLANT, Step 1, l

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