ML20204J543

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Rev 4 to Emergency Operating Procedure ES-0.1, Reactor Trip Response
ML20204J543
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
ES-.1, ES-0.1, NUDOCS 8810250173
Download: ML20204J543 (14)
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JUN 0 31988

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NUMBER TIT 12 REY. ISSUE /DATE E S.O.1 REACTOR TRIP RESPONSE Rev. 4

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PURPOSE nis procedure provides the necessary instructions to stablize and control the plant followin8 a reactor tnp without a safety injection.

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SYMPTOMS OR ENTRY CONDITIONS nis procedure is entered from E-0, REACTOR TRIP OR S AFETY INJECTION, Step 4, when Si is neither actuated nor required.

0010250173 801007 DR ADOCK 05 23 Page 1 of 14

JUN031c80 NUMBER TTILE REV. ISSUE /DATE E S - 0.1 REACTOR TRIP RESPONSE Rev.4 i

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 03 FALNED r

7 CAUTION:

IF St ACTUATION OCCURS DURING THIS PROCEDURE, E-0, REACTOR TRIP OR SAFETYINJECTION, SHOULD BE PERFORhfED.

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NOTE:

o FOLDOUT PAGE SHOULD BE OPEN.

o AFTER VERIFYING THAT.A TOTAL AFW FLOW OF GREATER THAT 320 GPhi CAN BE OBTAINED AND AfAINTAINED, AFW FLOW AfA Y BE THROITLED TO LESS THAN 320 GPhi TO AfD IN AIAINTAINING RCS TEhfPERATURE.

o AUTO AUX FEEDWATER,IF ACTUATED, AfUST BE DEFEATED BEFORE SG LEVEL 2 CAN BE CONTROLLED WITH THE FEEDWATER BYPASS AOVs.

1 CilECK RCS AVERAGE E LESS TIIAN 535' F TEh1PERATURE STABLE AT ASC DECREASING, OR TRENDING TO 535' F.

InES PERFORhi TIIE FOLLOWING:

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a. Stop dumping steam.

b.E cooldown continues, reduce total AUX feedwater flow to 320 GPhi until wide range levelin at l least one 50 is greater than 63 7c.

T11EN control AUX fet.dwater flow to maintain SG levels.

c. E cooldow n continues.

TiiEN close sieam dump isolation valves.51S h!OV 520 and 51S hiOV 553.

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d. E cmidow n continues, TiiEN close all four main steam line tnp valves.
f. E cooldown decreases TAVG 50' F below steady state TAVG ASD LOCA is SQIin progn:ss, IUliS Emergency Borate the RCS (SEE OPPOSITE PAGE) 1 Page 2 of 14

JUN 0 31988 NUMBER EH REY. ISSUE /DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4 l

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAISTD 1

E GREAT 1?R THAN 535' F AND INCREASING, THEN PERFORM THE FOLLOWING:

a. Dump steam to the main condenser.

E main condenser EQI available.

THEN dum p steam using one DH more or the following:

1. Atmos 3heric vent valve.
2. Terry "abine steam sup sly valves.
3. Hog ht steam supply va ves.

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t JUN 0 31988 NUMBER TTTU REY. ISSUE /DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2

CHECK FEEDWATER STATUS:

a. Check RCS average temperature -
a. Continue with Step 3, LESS TilAN 545 F WHEN temperature is less thw f /,5' F.

THEN do Steps 2 b, c, d arh.

b. Verify main feedwater now control b.Mam. ally close main feedwater now i

valves CLOSED control valves.

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c. Close all four motor operated feedline
c. Locally close feedline MOVs isolation valves OR manual feedline isolation valves,
d. Check one main feedwater pump -
d. Check AUTO AUX icedwater actuated.

RUNNING E b'QI actuated, IliFE perfonn the following:

1. Manually stan AUX feedwater pumps.
2. Open all four feedwater bypass AOVs.
c. Verify total AUX feedwater now -
e. Establish total AUX feedwater flow GREATER THAN 320 GPM greater than 320 GPM:

o Open feedwater bypass AOVs to each SG.

l DR o Manually stan AUX feedwater pumps.

I THEN open FW MOV 35 to feed all SGs simultaneously.

  • E FW MOV 35 fails to open,

111EN perfonn the followmg:

1. Stop AFW pumps
2. Open FW MOV 35.
3. Restart AFW pumps. *2 E AUX feedwater now greater than 320 GPM h'0I established.

111EN QQ IQ FR II.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

Page 4 of 14

i JUN03138.'

NUMBER TT M REV. lSSUE/D ATE ES.O.i REACTOR TRIP RESPONSE Rev.4 i

STEP ACTION / EXPECTED RESPONSE AESPONSE NOT OBTAINED 3

VERIFY ALL COh'IROL RODS IETWO OR MORECONTROLRODS FULLY INSERTED EOI FULLY INSERTED, lifEN EMERGENCY BORATE 200 PPM FOR EACH CONTROL ROD EQI FULLY INSERTED (SEE OPPOSITE PAGE).

4 VERIFY GENERATOR OUTPUT MANUALLY OPEN GENERATOR BREAKERS,14B 3T 2 AND OUTPUT BREAKERS 14B 3T 2 14B 4T-2, OPEN AFTER AND 14B 4T 2.

52 SECOND TIME DELAY

( OUTPUT BREAKERS TRIP IMMEDIATELY ON ELECIRICAL FAULT) l Page 5 of 14

t JUN O 31988 NUMBER TTTIE REV.If"*E' * ""

ES 0,1 REACTOR TRIP RESPONSE R-4 STEP ACTION /EXPEC1ED RESPONSE RESPONSE NOT OBTAINED 5

VERIFY ALL AC BUSES ENERGIZED VERIFY EhtERGEF"! BUSES BY OFFSITE POWER ENERGIZED BY DIESEL GENERATORS THEN PERFORM THE FOLLOWING:

o Verify MCC 5 enerr!:cd.

E EQIenergized.

THEN energize MCC-5 E MCC-5 can EQIbe energized, THEN GQIQ EOP 3.150, LOSS OF MCC 5, Step 1.

o Start CARFANS a q2 ired.

o Stop all radiologic.u and chemical releases.

o Isolate steam to the Air Ejectors.

o Check RCP cooling status:

1. Elower bearinE temperature is less than 170 F, i

THEN perform the following:

a. Start one CCW pump.

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b. Start one charging pump.
c. Initiate RCP seal water flow.
2. Elower bearing temperature is greater than 170' F.

THEN perform the following:

a. Close RCP thermal barrier manual return isolation valve (CC V 841).
b. Close RCP seal supply valves (CH V 345A thmugh D).
c. Start one CCW pump,
d. Start one charging pump.
c. Slowly open RCP thermal barrier manual rerum valve (CC V 841).

f, WHEN lower hearing temperature b uss than 170' F, THEN slo a n.itiate RCP seal watt! Itv.

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o Try to restore ottsite power I

(SEE OPPOSITE PAGE).

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JUN 0 31986 o

NUMBER TITLE REY. lSSUE/DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4

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STEP ACT10N/ EXPECTED RESPONSE RESPONSE NOT OBTAlhTD 6

CHECK PRZR LEVEL CONTROL:

a. Check PRZR level-
a. Perfonn the following:

GREATER TIIAN 11.5 %

1. Verify letdown orifice isolation valves closed.
2. Place orifice isolation valve control switches in the closed position.
3. Venf all PRZR heaters are off.

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off.

THEN manually turn off all heaters.

4. Control charging flow to increase PRZR level to greater than 11.5 %.
b. Verifyletdown IN SERVICE
b. Manually place letdown in senice (SEE OPPOSITE PAGE)
c. Verify charging -IN SERVICE
c. Manually place charging in senice,
d. Check PRZR level-
d. Control charging and letdown flow to TRENDING TO 25 %

maintain PRZR.evel at approximately 25 %.

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JUN 0 31985 NUMBER TTHE REV. ISSUE /DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4 i

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAISTD 7

CIIECK PRZR PRESSURE CONTROL:

a. Check PRZR pressure -
a. Verify Si actuation.

GREATER THAN 1700 PSIG E NQIactuated, manually actuate SI, IllEN GQIQ E 0, REACTOR TRIP OR SAFETY INJECTION, Step 5.

b. Place spray valve control switch (es)in closed for loop (s) with stopped RCP(s)
c. Check PRZR pressure -
c. E pressure is less than 2000 PSIL STABLE AT QR TRENDINO LN'D decreasing, TO 2000 PSIO DiEN pe-form the following:
1. Venf PRZR PORV(s) closed.

E'

closed, THEN manually close PORV(s).

E PORV(s) can b'QI be closed,

'niEN close PORY block valve (s).

2. Verify PRZR spray valves closed.

E b'QIclosed, DIEN manually close spray valves.

E spray valves can b'QI be closed, THEN stop RCP(s) supplying failed spray valve (s).

3. Verify PRZR heaters on.

E h'0I on, j

THEN manually turn on heaters.

E pressure greater than 2000 PSIG ASI! increasing THEN perform the fo!!owing:

1. Verify PRZR heaters off I

E h'DI off, THEN manually tum heaters off.

2. Control pressure with normal spray, j

E normal spray b'QIavailable Ab'D letdown is in senice, TliEN use auxiliary spray.

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E auxiliary spray b'QIavailable, THEN use one PORV.

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Page 8 of 14

JUN O 31988 NUMBER TT!1E REY. ISSUE /DATE

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ES 0.1 REACTOR TRIP RESPONSE Rev.4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

8 CilECK SG LEVELS:

a. Check wide range levels -
a. hiaintain total AUX feedwater flow I

4 GREATER THAN 63 %

peater than 320 GPhi until wide range i

.evelin at least one SG is greater than 63 %

b. Control AUX feedwater flow to
b. IE any SG wide range level continues maintain wide range levels between to increase, 63 % to 69 %

THEN stop Aux feedwater flow to that SG.

9 INSURE lilGH PRESSURE STEAh!

DUhtP STEAh! USING ONE DUh1P OPERATES TO htAINTAIN QR h1 ORE OF THE FOLLOWING:

1 TAVG AT535' F l

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a. Atmos 3heric vent valve.

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b. Terry "urbine steam sup aly valves.

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c. Hog Jet steam supply va ves.

1 10 CliECK THE STATUS OF THE FOLLOWING SYSTEhtS:

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a. Check MCC a. QQIQ EOP 3.150, l

J ENERGIZED LOSS OF MCC 5, Step 1.

b. Check Semi vital buses -
b. GQ IQ EOP 3.1-46, ENERGlZED TOTAL LOSS OF SEMI VTTAL i

l POWER, Step 1.

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c. Check Control Air pressure -
c. GQ IQ EOP 3.134, GREATER THAN 50 PSIG CONtPLETE LOSS OF CONTROL l

3 AIR SUPPLY, Step 1.

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d. Check Circulating Water System -
d. GD IQ EOP 3.123, OPERATING LOSS OF CIRCULATING WATER, t

Step 1.

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c. Check condenser vaccum -
c. GQ IQ EOP 3.18, GREATER THAN 21.5" Hg CONtPLETE LOSS OF CONDEFSER VACCUht, Step 1.

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JUN 0 31986 NUMBER 1TTIE REV. ISSUE /DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTEt RCPs SHOULD BE RUN IN ORDER OF PRIORTY TO PROWDE NORMAL PRZR SPRAY.

11 CliECK RCP STATUS:

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

AT LEAST ONE RUNNING

1. Establish conditions for starting an RCP:
a. Close1 Tc isolation valve.
b. Open loo bypass valve.
c. Start oil 1 t pump.
d. Insure seal water and component cooling water supplied to RCP.
e. Insure lower bearing temperature is less than 170 F.
f. Check RCS pressure greater than 300 PSIG.
g. Open CH TV 240, CH TV 241 and CH TV 334.

(seal water return trip valves)

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

THEN perform the following:

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

IE RCP can NQI be started, THEN perform the following:

a. Open loop Te isolation valve,
b. Close loop bypass valve.
c. Verify natural circulation (SEE A1TACHMENT A).

IE natural circulation NOI verified,

'lliEN increase dumping steam.

d. Attempt to start another RCP.

Page 10 of 14

JUN 0 31988 NUMBER 1TTLE REV. ISSUE /DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4

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STEP ACT10N/EXPEC11ED RESPONSE RESPONSE NOT OBTAISID 12 CITECK SOURCE RANGE DEHCTORS ENERGIZED:

a. Check intermediate range flux -
a. Continue with step 13, LESS TIIAN 5 x 1010 Ah1PS WHEN less than 5 x 1010 Ah1PS, THEN do steps 12 b, e and d.
b. Verify source range detectors -
b. hianually energize source range ENERGlZED detectors.
c. Transfer nuclear flux recorders to source range scale
d. TranS,

>R meters to source rar,20 13 SHUTit,'

NECESSARY PLAhT F u.

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a. Stop one main feedwater pump
b. Stop one condensate pump i
c. Place standby heater drain pump in TPO
d. Place running heater drain pump in TPO 14 h1AthTAIN STABLE PLANT CONDmONS:

o PRZR pressure - AT 2000 PSIG o PRZR level APPROXIhtATELY 25 %

o SG wide range levels -

BEDVEEN 63 % AND 69 %

o RCS awrage temperature -

BEDVEEN 533' F AND 535' F 15 DETERht!NE IF NATURAL CIRCULATION COOLDOWW IS REQUIRED:

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a. RCPs available
a. GQIQ ES 0.2, NATURAL CIRCULATION I

COOLDOWN, Step 1.

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JUN 0 31988 NUMBER TTT U REV. ISSLTJDATE E S.0.1 REACTOR TRIP RESPONSE Rev.4 i

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 PERFORM THE FOLLOWING ACTIONS:

o Place 32012R 5 control switch in TPO o Place exciter field breaker control switch in TPO o Place voltage regulator control switch in manual o Open turbine drain valves o Stan idle RCPs as necessary to control RCS temperature:

a. Stan RCPs one at a time by performing the following:
1. Close loop Tc isolation valve
2. Open loop bypass valve
3. Start oil hft pump
4. Insure seal water and com mnent cooling v'4ter supplied to TCP
5. Insure lo' ver bearing tem;<rature is less thta 170' F
6. Check RCS pressure greater than 300 PSIG
7. Check open CH TV 240,
7. Oxn CH TW240, CH T%241 and Cll T%241 and CH T%334.

C i T%334.

(scal water return trip valves)

8. Check oyn CC TW1411
8. Open CC TW1411 (RCP oil cooler CCW rerum trip valve)
9. Open seal water return MOV
10. Stan selected RCP
11. Oxn loop Tc isolation valve
12. C ose loop bypass valve Page 12 of 14

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JUN 0 31988 l

NUMBER 1TTLE REV. ISSUE /DATE ES 0.1 REACTOR TRIP RESPONSE Rev.4 STEP ACTION /EXPECAD RESTCNSE RESPONSE NOT OBTAINED NOTE:

o WHEN PLANT CONDITIONS ARE STABLE, REVIEW THE i

STATUS OF ANNUNICATORS AND SYSTEM PARAMETERS.

COMPARE OBSERVATIONS WITH EXPECTED INDICATIONS.

j IMMEDIATELY REPORT OFF NORMAL OR UNEXPLAINED CONDITIONS TO THE SHIFT SUPERVISOR.

o NOTIFY DUTY OFFICER AND FILE A PIR.

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l 17 GQ IQ NOP 2.14, I

RECOVERY FROM A REACTOR TRIP, STEP 1 1

I END

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JUN 0 31988 NUMBER TTHE REV. ISSUE /DATE ES.0.1 REACTOR TRIP RESPONSE

.Rev.4 i

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ATTACIBTENT A J

'Ihe following conditions support or indicate natural circulation flow:

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

o SO pressures are stable or decreasing.

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

o RCS cold leg temperatur:s are at saturation temperature for SG pressures.

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