ML17250B227
| ML17250B227 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/26/1991 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250B228 | List: |
| References | |
| E-3, NUDOCS 9109030065 | |
| Download: ML17250B227 (88) | |
Text
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E-3 STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 1 of 40 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY.1.0 REVIEWED BY:
('i09030065 9i082i PDR ADOCK 05000244 P
C Y
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 2 of 40 A.
PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in'ne S/G and a fault in the other S/G.
B.
ENTRY CONDITIONS/SYMPTOMS l.
ENTRY CONDITIONS This procedure is entered from:
a
~
b.
c ~
E-O, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or E
0 ~
REACTOR TRIP OR SAFETY INJECTION ~
E 1 ~
LOSS OF REACTOR OR SECONDARY COOLANT/
E-2, FAULTED STEAM GENERATOR ISOLATION, and FR H 3 g RES PONS E TO STEAM GENERATOR HIGH LEVELg when secondary radiation is abnormal, or E
0 ~
REACTOR TRIP OR SAFETY INJECTION
/
E 1 ~
LOSS OF REACTOR OR SECONDARY COOLANTg ES 1 ~ 2 g POST LOCA COOLDOWN AND DEPRESSURI ZATION g ECA 3 ~ 3 ~
SGTR WITHOUT PRESSURI ZER PRESSURE CONTROL/
when an intact S/G narrow range level increases in an uncontrolled manner.
d.
e.
ECA 3
~ 3 ~
SGTR WITHOUT PRESSURIZER PRESSURE CONTROL/
when pressurizer pressure control is restored.
E-1 series FOLDOUT page whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.
T
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 3 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o FOLDOUT page should be open AND monitored periodically.
o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).
o Personnel should be available for sampling during this procedure.
o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10-
~ R/hr.
1 Check If RCPs Should Be Stopped:
a.
RCP status
- ANY RCP RUNNING
- b. SI pumps
- AT LEAST TVO RUNNING c.
RCS pressure minus maximum S/G pressure
- LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs a.
Go to Step 2.
b.
Go to Step 2.
c.
Go to Step 2.
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 4 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2 Identify Ruptured S/G(s):
o Unexpected increase in either S/G narrow range level
-OR-Continue with Steps 5 through 10.
WHEN ruptured S/G(s) identified, THEN do Steps 3 and 4.
o High radiation indication on main steamline radiation monitor
~ R-31 for S/G A
~ R-32 for S/G B
-OR-o AO reports local indication of high steamline radiation
-OR-o HP reports high radiation from S/G activity sample
f C
l1, 4
MIN Wn
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TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 5 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION o
IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OP PEED
- FLOW, STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
o AT LEAST ONE S/G MUST BE MAINTAINEDAVAILABLEPOR RCS COOLDOWN.
k * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 3 Isolate Flow From Ruptured S/G (s):
- a. Adjust ruptured S/G ARV controller to 1050 psig in AUTO
- b. Check ruptured S/G ARV - CLOSED b.
WHEN ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed.
IF NOT closed, TNNN place controller in MANUAL and close S/G ARV.
IF S/G ARV can NOT be closed, THEN dispatch AO to locally isolate.
- c. Close ruptured S/G TDAFW, pump steam supply valve'nd place in PULL STOP
~ S/G A, MOV-3505A
~ S/G B, MOV-3504A
- d. Verify ruptured S/G blowdown valve - CLOSED
~ S/G A, AOV-5738
~ S/G B, AOV-5737 This Step continued on the next page.
- c. IP at least one MDAFW pump
- running, THEN dispatch AO with locked valve key to locally isolate steam from ruptured S/G to TDAFW pump.
~ S/G A, V-3505
~ S/G B, V-3504
- d. Place S/G blowdown and sample valve isolation switch to CLOSE.
IF blowdown can NOT be isolated
- manually, THEN dispatch AO to locally isolate blowdown.
~ S/G A, V-5701
~ S/G B, V-5702
~
~
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 6 of 40 STEP ACTION/EXPECTED RESPONSE t
(Step 3 continued from previous page) e.
Close ruptured S/G MSIV
RESPONSE
NOT OBTAINED e.
Perform the following:
- 1) Close intact S/G MSIV.
- 2) Place intact S/G ARV controller at 1005 psig in AUTO.
- 3) Place condenser steam dump mode selector switch to MANUAL.
- 4) Adjust reheat steam supply controller cam to close reheat steam supply valves.
- 5) Ensure turbine stop valves-CLOSED.
- f. Dispatch AO to complete ruptured S/G isolation (Refer to appropriate sections of Attachment RUPTURED S/G)
- 6) Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G, parts A and B).
IF the ruptured S/G can NOT be isolated from the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 7 of 40 STEP
. ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING 'SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
4 Check Ruptured S/G Level:
- a. Narrow range level - GREATER THAN 5%
[25% adverse CNMTJ
- b. Close MDAFW pump discharge valve to ruptured S/G
~ S/G A, MOV-4007
~ S/G B, MOV-4008
- c. Pull stop MDAFW pump for
'ruptured S/G
- d. Close TDAFW pump flow control valve to ruptured S/G
~ S/G A, AOV-4297
~ S/G B, AOV-4298
- e. Verify MDAFW pump crosstie valves
- CLOSED
- a. IF ruptured S/G NOT faulted, THEN perform the following:
- 1) Maintain feed flow to ruptured S/G until level greater than 5%
[25% adverse CNMT].
') Continue with Step 5.
WHEN ruptured S/G level greater than 5%
[25% adverse CNMT],
THEN do Steps 4b through e.
- b. Dispatch AO to locally close valve.
- d. Dispatch AO with locked valve key to locally close TDAFW pump manual feedwater isolation valve to ruptured S/G.
~ S/G A, V-4005
~ S/G B, V-4006
- e. Manually close valves.
~ MOV-4000A
~ MOV-4000B
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E-3 TITLE:
STEAN GENERATOR TUBE RUPTURE REV:
12 PAGE 8 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSUREi IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).
5 Check PRZR PORVs And Block Valves:
a.
Power to PORV block valves-AVAILABLE b.
PORVs -
CLOSED
- a. Restore power to block valves unless block valve was closed to isolate an open PORV:
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
- b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
- c. Block valves
- AT LEAST ONE OPEN IF any PORV can NOT be closed, THEN manually close its block valve.
IF block valve can NOT be closed, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step l.
c.
Open one block valve unless it was closed to isolate an open PORV.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 9 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6
Check If S/G Secondary Side Is Intact:
o Pressure in both S/Gs STABLE OR INCREASING o
Pressure in both S/Gs
- GREATER THAN 100 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown:
~ Steamlines
~ Feedlines IF faulted S/G NOT isolated, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
- * * * * * * * * * * * * *
- 4' 4'
CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR-AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
7 Check Intact S/G Level:
a.
Narrow range level - GREATER THAN 5%
[25% adverse CNMT]
- b. Control feed flow to maintain narrow range level between 17%
[25% adverse CNMTJ and 50%
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%
[25%
adverse CNMT] in at least one S/G.
- b. IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
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E-3 TITLE:
STEAN GENERATOR TUBE RUPTURE REV:
12 PAGE 10 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET>
SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
8 Reset SI 9
Reset CI:
a.
Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED
- b. Perform the following:
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
$L s.
I b
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 11 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT'BTAINED CAUTION RCS PRESSURE SHOULD BE MONITORED.
XF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMTJ THE RHR PUMPS MUST BE MANUALLYRESTARTED TO SUPPLY WATER TO THE RCS.
10 Check Xf RHR Pumps Should Be Stopped:
a.
Check RCS pressure:
o Pressure
- GREATER THAN 250 psig [465 psig adverse CNMT]
o Pressure
- STABLE OR INCREASING a.
Go to Step 11.
- b. Stop RHR pumps and place both in AUTO NOTE: If ruptured S/G needed for cooldown, isolation is not necessary.
ll Verify Ruptured S/G Isolated:
a.
Check ruptured MSIV - CLOSED
- b. Ruptured S/G pressure
- GREATER THAN 300 PSIG
- a. IF only intact S/G MSIV can be
- closed, THEN ensure air ejector/gland steam supply and flange heating steam isolated.
(Refer to ATTACHMENT RUPTURED S/G, part B).
.IF neither S/G MSIV can be closed THEN go to ECA-3.1, SGTR WXTH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESXRED, Step 1
b.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT.-
SUBCOOLED RECOVERY DESIRED, Step l.
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 12 of 4O STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 12 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available:
o Intact S/G MSIV -
OPEN o
Annunciator G-15, STEAM DUMP LIT
- b. Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO
- a. Ad]ust S/G ARV controllers to maintain intact S/G pressure in AUTO and go to Step 13.
- c. Place steam dump mode selector switch to MANUAL
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 13 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.
13 Initiate RCS Cooldown:
- a. Determine required core exit temperature from below table RUPTURED SG PRESSURE 1100 PSIG 1000 PSIG 900 PSIG 800 PSIG 700 PSIG 600 PSIG 500 PSIG 400 PSIG 300 PSIG
- b. Initiate dumping steam to condenser from intact S/G at maximum rate REQUIRED CORE EXIT TEMPERATURE ('F) 525 [505 adverse CNMT]
510 [490 adverse CNMT]
500 [475 adverse CNMT]
485 [460 adverse CNMT]
465 [440 adverse CNMT]
450 [420 adverse CNMT]
425
[395 adverse CNMT]
405 [370 adverse CNMT]
375
[330 adverse CNMT]
- b. Manually or locally initiate steam dump from intact S/G at maximum rate using S/G ARV.
IF no intact S/G available, THEN perform the following:
o Use faulted S/G.
-OR-
- c. Core exit T/Cs - LESS THAN REQUIRED TEMPERATURE
IF both S/Gs ruptured, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1
- c. Continue with Step 14.
WHEN core exit T/Cs less than
- required, THEN do Step 13d.
c;.
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E-3 STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 14 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Verify All AC Busses ENERGIZED BY OFFSITE POWER o
Normal feed breakers to all 480 volt busses CLOSED o
480 volt bus voltage - GREATER THAN 420 VOLTS o
Emergency D/G output breakers-OPEN Perform the following:
- a. IF any AC emergency bus normal feed breaker
- open, THEN ensure associated D/G breaker closed.
- b. Perform the following as necessary:
- 1) Close non-safeguards bus tie breakers:
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 2) Place the following pumps in PULL STOP:
~ EH pumps
~ Turning gear oil pump
~ HP seal oil backup pump
- 3) Restore power to MCCs.
~ A from Bus 13
~ B from Bus 15
~ E from Bus 15 F from Bus 15
- 4) Start CNMT RECIRC fans as necessary.
5)
WHEN bus 15 restored, THEN reset control room lighting.
- c. Try to restore offsite power to all AC busses (Refer to.
ER-ELEC.1, RESTORATION OF OFFSITE POWER).
QygC
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 15 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 15 Verify Adequate SW Flow:
a.
Check at least two SW pumps-RUNNING
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- a. Manually start SW pumps as power supply permits (258 kw each).
IF less than two SW pumps
- running, THEN:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1) 3)
Go to Step 17.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 16 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 16 Establish IA to CNMT:-
- a. Verify non-safeguards busses energized o
Bus 13 normal feed -
CLOSED
- a. Perform the folloving:
- 1) Close non-safeguards bus tie breakers:
-OR-o Bus 15 normal feed -
CLOSED
- b. Verify turbine building SV isolation valves -
OPEN
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 2) Verify adequate emergency D/G capacity to run air compressors (75 kv each).
IR NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC PANS).
- b. Manually align valves.
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify at least two air compressors
-, RUNNING d.
Check IA supply:
o Pressure
- GREATER THAN 60 PSIG o
Pressure
- STABLE OR INCREASING
- c. Manually start air compressors as pover supply permits (75 kw each).
IP air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- d. Perform the following:
- 1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OP INSTRUMENT AIR).
- 2) Continue vith Step 17.
VHEN IA restored, THEN do Steps 16e and f.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 17 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAIN"::,
17 Est:ablish Charging Flow:
a, Charging pumps
- ANY RUNNING a,
Perform the following:
- 1) IF CCW flow is lost to any RGP <iIcrmal barrier 0R any RCP $ 1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally close seal injection needle valves to affected RCP.
- b. Align charging pump suction to RWST:
o 'CV-112B -
OPEN o
LCV-112C -
CLOSED
- c. Start charging pumps as necessary and establish 75 gpm total charging flow
~ Charging line flow
~ Seal in5ection
~ V-300A for RCP A
~ V-300B for RCP B
- 2) Ensure HCV-142 demand at OX.
- b. IF LCV-112B can NOT be opened, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging'pump room).
- 3) WHEN'V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
J C IP
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 18 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION RCS COOLDOWN IN STEP 13 SHOULD BE COMPLETED BEFORE CONTINUING TO STEP 18.
18 Check Ruptured S/G Pressure STABLE OR INCREASING IF pressure continues to decrease to less than 250 psi above the pressure of the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
19 Check RCS Subcooling Based On Core Exit T/Cs GREATER THAN 20'F USING FIGURE MIN SUBCOOLING Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1
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TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 19 of 40 STEP ACTION/EXPECTED RESPONSE R,"'PONSE NOT OBTAII"-.TI NOTE:
SI ACCUMs may in)ect during RCS depressurization.
20 Depressurize RCS To Minimize Break Flow And Refill PRZRI a.
Check the following:
o Ruptured S/G level - LESS THAN 90%
[85% adverse CNMT]
o Any RCP - RUNNING o
- b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:
o PRZR level - GREATER THAN 75%
[65% adverse CNMT]
-OR-o RCS pressure
- LESS THAN SATURATION USING PIGURE MIN SUBCOOLING
-OR-o BOTH of the following:
1)
RCS pressure
- LESS THAN RUPTURED S/G PRESSURE 2)
PRZR level - GREATER THAN 5% [30% adverse CNMT]
- c. Close normal PRZR spray valves:
- 1) Ad)ust normal spray valve controller to OP.'EMAND
- 2) Verify RCS pressure-INCREASING
- d. Verify auxiliary spray valve (AOV-296).- CLOSED e.
Go to Step 23 a.
Go to Step 21.
- c. Stop RCPs.
- d. Decrease charging speed to minimum and ensure charging valve to loop B cold leg open (AOV-294).
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E-3 TITLE:
STEAM GENERATOR TUBE RUpm"T E REV:
12 PAGE 20 of, 40 IJJ CIP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
~ * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 0AUT10N o
THE PRT MAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURI"."
~T!E RCS.
THIS MAY RESULT IN ABRI~>M".T CNMT CONDITIONS.
o CYCLING OR THE PRZR PORV SHOULD BE MINIMIZED.
o THE UPPER HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IR RCPS ARE NOT RUNNING.
THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE:
o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
o When using a PRZR PORV select one with an operable block valve.
21 Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR:
PRZR PORVs - AT LEAST ONE AVAILABLE
- a. Refer to Attachment N2 PORVS to operate PORVs.
- b. IR auxiliary spray available, THEN return to Step 20b.
IR auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step l.
This Step continued on the next page.
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E-3 TITLE:
STEAN GENERATOR TUBE RUPTURE
,I REV 12 PAI I, 21 of 40 STEP ACTION/EXPECTED RESPONSE R:"'"-":NSE NOT OBTAINED (Step 9~ "ontinued from previous page)
Open one PRZR PORV until ANY of the folloving conditions satisfied:
o PRZR level - GREATER THAN 75%
[65% adverse CNMT]
-OR-o RCS pressure
- LESS THAN SATURATION USING FIGURE MIN SUBCOOLING
-OR-o BOTH of the folloving:
1)
RCS pressure
- LESS THAN RUPTURED S/G PRESSURE 2)
PRZR level - GREATER THAN 5%
[30% adverse CNMT]
- d. Close PRZR PORVs
- d. IR either PRZR PORV can NOT be
- closed, THEN close associated block valve.
7i', l l, 4%
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E-3 TITLE:
STEAN GENERATOR TUBE RUPTURE REV 12 PAGE 22 of 40
.N/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 22
( "Iit cL raiS Pressure INCREASING Close block valve for the PRZR PORV that was opened.
IP pressure continues to decrease, THEN perform the following:
- a. Monitor the following conditions for indication of leakage from PRZR PORV:
o PORV outlet temp (TI-438)
NOT decreasing.
o PRT pressure, level or temperature continue to increase.
b.
Go to ECA-3.1, SGTR PITH LOSS OP REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
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STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 23 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFlLLING OF THE RUPTURED S/G.
23 Check If SI Flow Should Be Terminated:
a.
RCS subcooling based on core exit T/Cs--
GREATER THAN O' USING FIGURE MIN SUBCOOLING
- b. Secondary heat sink:
o Total feed flow to S/G(s)-
GREATER THAN 200 GPM AVAILABLE
-OR-a.
Do NOT stop SI pumps.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
- b. IF neither condition satisfied, THEN do NOT stop SI pumps.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
o Narrow range level in at least one intact S/G-GREATER THAN 5%
[25% adverse CNMT]
c.
RCS pressure
- STABLE OR INCREASING d.
PRZR level - GREATER THAN 5%
[30% adverse CNMT]
c.
Do NOT stop SI pumps.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step l.
d.
Do NOT stop SI pumps.
Return to Step 11.
24 Stop SI Pumps And Place In AUTO
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 24 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION ALIGNING SI PUMP SUCTION TO RWST BEFORE ISOLATING BAST MAY RESULT IN BACKFLOW FROM RWST TO BASTS.-
25 Verify SI Pump Suction Aligned To RWST:
- a. SI pump suction valves from BASTs -
CLOSED
~ MOV-826A
~ MOV-826B
~ MOV-826C
~ MOV-826D a.
Ensure at least one valve in each flow path closed.
~ MOV-826A or MOV-826B
~ MOV-826C or MOV-826D
~ MOV-825A
~ MOV-8258
- b. Ensure at least one valve is open.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 25 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 26 Establish Required Charging Line Flow:
- a. Charging pumps - ANY RUNNING
- a. Perform the folloving:
- 1) IF CCW flov is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally isolate seal injection to affected RCP:
- b. Establish 20 gpm charging line flov
~ RCP A, V-300A
~ RCP B, V-300B
- 2) Ensure HCV-142 open.
- 3) Start one charging pump.
27 Verify SI Flow Not Required:
a.
RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING b.
PRZR level - GREATER THAN 5%
[30% adverse CNMT]
- a. Manually operate SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
- b. Manually operate SI pumps as necessary.
IF PRZR level can NOT be maintained, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 26 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 28 Check If CNMT Spray Should Be Stopped:
a.
CNMT spray pumps - ANY RUNNING
- b. Verify CNMT pressure
- LESS THAN 4 PSIG
- c. Reset CNMT spray d.
Check NaOH tank outlet valves-CLOSED
~ AOV-836A
~ AOV-836B a.
Go to Step 29.
- b. Continue vith Step 29.
WHEN CNMT pressure less than 4 psig, THEN do Steps 28c through f.
- d. Place NaOH tank outlet valve controllers to MANUAL and close valves.
e.
Stop CNMT spray pumps and place in AUTO Close CNMT spray pump discharge valves
~ MOV-860A
~ MOV-860B
~ MOV-860C
~ MOV-860D
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 27 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 29 Check If SI ACCUMs Should Be Isolated:
a.
Check the following:
o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o
PRZR level - GREATER THAN 5X
[30X adverse CNMT]
t
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves
~ MOV-841 4 MOV-865
- a. Manually operate SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
- c. Vent any unisolated ACCUMs:
- 1) Open vent valves for unisolated SI ACCUMs.
- d. Locally reopen breakers for MOV-841 and MOV-865
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 28 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 30 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least three SW pumps-RUNNING
- b. Verify AUX BLDG SW isolation valves - AT LEAST ONE SET OPEN
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735
- c. Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED
- a. Manually start pumps as power supply permits (258 kw each).
IR less than two SW pumps can be
- operated, THEN go to Step 37.
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 29 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 31 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored:
OPEN o
IA pressure
- GREATER THAN 60 PSIG
- b. Verify instrument bus D-ENERGIZED c.
CCW pumps ANY RUNNING
- d. Charging pump - ANY RUNNING
- a. Continue with Step 37.
WHEN IA
- restored, THEN do Steps 31 through 36.
- b. Energize MCC B.
IF MCC B NOT available, THEN perform the following:
- 1) Verify MCC A energized.
- 2) Place instrument bus D on maintenance supply.
- c. Perform the following:
- 1) IF any RCP gl seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).
~ RCP A, MOV-749A and MOV-759A RCP B, MOV-749B and MOV-759B
- 2) Manually start one CCW pump.
- d. Continue with Step 37.
WHEN any charging pump running, THEN do Steps 32 through 36.
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E-3 TITLE STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 30 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 32 Check If Seal Return Flow Should Be Established:
- a. Verify RCP $ 1 seal outlet temperature
- LESS THAN 235'F
- b. Verify RCP seal outlet valves-OPEN
~ AOV-270A
~ AOV-270B
- c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313 a.
Go to Step 33.
- b. Manually open valves as
, necessary.
d.
Open RCP seal return isolation valve MOV-313
- e. Verify RCP gl seal leakoff flow LESS THAN 5.5 GPM
- f. Veri'fy RCP gl seal leakoff flow
- GREATER THAN 0.25 GPM
- d. Perform the following:
- 1) Place MOV-313 switch to OPEN.
- e. IR any RCP seal leakoff flow greater than 5.5 gpm, THEN:
o Close the affected RCP seal discharge valve
~ RCP A) AOV-270A
~ RCP B, AOV-270B o
Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step'3.
- f. Refer to AP-RCP.1, RCP SEAL MALFUNCTION.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 31 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 33 Verify PRZR Level GREATER THAN 134
[40~o adverse CNMT]
Continue with Step 35.
WHEN PRZR level increases to greater than 13%
[40% adverse CNMT], THEN do Step 34.
34 Establish Normal Letdown:
- a. Establish charging line flow to REGEN Hx - GREATER THAN 20 GPM
- b. Place the following switches to CLOSE:
~ Letdown orifice valves (AOV-200A, AOV-200B; and AOV-202)
~ Letdown isolation valve AOV-371
~ Loop B cold leg to REGEN Hx AOV-427
- c. Place letdown controllers in
-MANUAL at 25% open-
~ TCV-130
~ PCV-135
- d. Reset both trains of XY relays for AOV-371 and AOV-427 e.
Open AOV-371 and AOV-427
- f. Open letdown orifice valves as necessary
- g. Place TCV-130 in AUTO at 105'F
- h. Place PCV-135 in AUTO at 250 psig
- i. Adieu'st charging pump speed and HCV-142 as necessary IP RCP seal return has been established',
THEN establish excess letdown as follows:
o Place excess letdown divert
- valve, AOV-312, to NORMAL.
o Ensure CCW from excess letdown'pen, (AOV-745).
o Open excess letdown isolation valve AOV-310.
o Slowly open HCV-123 to maintain
=
excess letdown temperature less than 195'P and pressure less than 100 psig.
o Adjust charging pump speed as necessary.
IP RCP seal return NOT established, THEN consult TSC to determine if excess letdown should be placed in service.
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STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 32 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 35 Check VCT Makeup System:
a.
BAST levels - ANY GREATER THAN 5X
- b. Check Annunciator B-23, BORIC ACID TANK LO LO LEVEL-EXTINGUISHED a.
Go to Step 36.
- b. Perform the following:
- 1) Adjust boric acid flow control valve to required flow from table.
BAST LEVEL
<10%
10-15X 15-20%
>20%
BORIC ACID FLOW (GPM) 4.5 6.7 8.9 10.0
- c. Adjust boric acid flow control valve in AUTO to 4.5 gpm
- d. Verify the following:
1)
RMW mode selector switch in AUTO 2)
Go to Step 35d.
- d. Adjust controls as necessary.
2)
RMV control armed
- RED LIGHT LIT e.
Check VCT level:
o Level - GREATER THAN 20%
-OR-o Level - STABLE OR INCREASING
- e. Manually increase VCT makeup flow as follows:
- 1) Ensure BA transfer pumps and RMV pumps running.
IF NOT, THEN reset MCC C and MCC D UV lockouts as necessary.
- 2) Place RMW flow control valve HCV-ill in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
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E-3 STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 33 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 36 Check Charging Pump Suet:ion Aligned To VCT:
a.
VCT level - GREATER THAN 20%
- a. IP VCT level can NOT be maintained greater than 5%,
THEN perform the following:
- 1) Ensure charging pump suction aligned to RWST o
LCV-112B open o
LCV-112C closed
- b. Verify charging pumps aligned to VCT o
LCV-112C -
OPEN o
LCV-112B -
CLOSED
- 2) Continue with Step 37.
WHEN VCT level greater than 40%,
THEN do Step 36b.
- b. Manually align valves as necessary.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 34 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.
37 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage:
a.
Perform appropriate action(s) from table:
PRZR LEVEL RUPTURED S/G NARROW RANGE LEVEL 1'. 8 THAN 13%
[40% ADVERSE CNMT]
INCREASING o Increase RCS makeup flov o Depressurize RCS using Step 37b DECREASING Increase RCS makeup flov OFFSCALE HIGH o Increase RCS makeup flov o Maintain RCS and ruptured S/G pressure equal BETWEEN 13%
[40% ADVERSE CNMT]
AND 50%
Depressurize RCS Energize using Step 37b PRZR heaters Maintain RCS and ruptured S/G pressure equal BETWEEN 50X AND 75X
[65X ADVERSE CNMT]
GREATER THAN 75X
[65% ADVERSE CNMT]
o Depressurize RCS using Step 37b o Decrease RCS makeup flow o Decrease RCS makeup flow Energize PRZR heaters Energize PRZR heater~
Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal
- b. Control prIT sure using normal PRZR spray, if av~ilab:
, to obtain desired results for Step 37a
- b. IF'letdovn is in service, THEN use auxiliary spray (AOV-296).
IR NOT, TURN use one PRRR PORV.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 35 of 4O STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by offsite power:
o Emergency D/G output breakers OPEN
- a. Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
o AC emergency bus voltage-GREATER THAN 420 VOLTS o
AC emergency bus normal feed breakers
- CLOSED b.
Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 39 Minimize Secondary System Contamination:
- a. Isolate reject from hotwell to CST:
o Place hotwell level controller (LC-107) in MANUAL at 50%
- a. IF hotwell level increasing, THEN direct HP to sample hotwells for activity.
o Verify hotwell level -
STABLE b.
Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 36 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling:
a.
o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED
- b. Check RCP seal injection:
o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER
-OR-o RCP seal injection flow to each RCP - GREATER THAN 6 GPM
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E-3 roric:
STEAM GENERATOR TUBE RUPTURE REV 12, PAGE 37 of 40 STEP
.ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
42 Check RCP Status:
a.
- AT LEAST ONE RUNNING
- b. Stop all but one RCP
- a. Perform the following:
- 1) Try to start one RCP:
a) Ensure conditions for starting an RCP.
o Bus llA or 11B energized.
o Refer to Attachment RCP START.
b) IF RVLIS level (no RCPs) less than 95%,
THEN perform 'the following:
o Increase PRZR level to greater than 65%
f80%
adverse CNMTJ.
o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.
c) Start one RCP.
- 2) IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation can NOT be verified, THEN increase dumping steam.
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E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 38 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
43 Check If Source Range Detectors Should Be Energized:
a.
Source range channels-DEENERGIZED a.
Go to Step 43e.
- b. Check intermediate range flux-EITHER CHANNEL LESS THAN 10-~~
AMPS
- b. Perform the following:
- 1) IF neither intermediate range channel is decreasing, THEN initiate boration.
- c. Check the following:
o Both intermediate range channels LESS THAN 10-'MPS
- 2) Continue with Step 44.
WHEN flux is LESS THAN 10-'mps on any operable
- channel, THEN do Steps 43c through e.
- c. Continue with Step 44.
WHEN either condition met, THEN do Steps 43d and e.
-OR-o Greater than 20 minutes since reactor trip
- d. Verify source range detectors-ENERGIZED
- d. Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2
of 2).
- e. Transfer Rl;-45 recorder to one source range and one intermediate range channel IF source ranges can NOT be
- restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 44.
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E-3 TITLE:
STEAN GENERATOR TUBE RUPTURE REV 12 PAGE 39 of 40 STEP ACTION/EZPECTED RESPONSE
RESPONSE
NOT OBTAINED 44 Establish Normal Shutdown Alignment:
a.
Check condenser
- AVAILABLE
- a. Dispatch AO to perform Attachment SD-2.
- b. Perform the following:
o Open generator disconnects
~ 1G13A71
~ 9Z13A73 o
Place voltage regulator to OFF o
Open turbine drain valves o
Rotate reheater steam supply controller cam to close valves o
Place reheater dump valve switches to HAND o
Stop all but one condensate pump
- c. Verify adequate Rx head cooling:
- 2) Verify at least one control rod shroud fan - RUNNING
- 3) Verify one Rx compartment cooling fan - RUNNING
- d. Verify Attachment SD COMPLETE
-1)
Go to Step 45.
- 2) Manually start one fan as power supply permits (45 kw)
- 3) Perform the following:
o Dispatch AO to reset UV relays at MCC C and MCC D.
o Manually start one fan as power supply permits (23 kw)
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E-3
'STEAN'ENERATOR TUBE RUPTURE REV 12 PAGE 40 of 40 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 45 Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:
o Go to ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1
-OR-o Go to ES-3.2, POST-SGTR COOLDOW USING BLOVDOVN, Step 1
-OR-o Go to ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1
-END-
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STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 1 of 1 E-3 APPENDIX LIST TLTLE 1)
RED PATH
SUMMARY
2)
FIGURE MIN SUBCOOLING 3)
ATTACHMENT CNMT RECIRC FANS 4)
ATTACHMENT D/G STOP 5)
ATTACHMENT N2 PORVS 6)
ATTACHMENT NC 7)
ATTACHMENT SEAL COOLING 8)
ATTACHMENT RCP START 9)
ATTACHMENT RUPTURED S/G 10)
ATTACHMENT SD-1 ll)
ATTACHMENT SD-2 12)
ATTACHMENT SI FLUSH 14)
FOLDOUT PAGES
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E-3 STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 1 of 1 RED PATH
SUMMARY
a.
SUBCRITICALITY Nuclear power greater than 54 b.
CORE COOLING Core exit T/Cs greater than 1200'F
-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43%
[46%
adverse CNMT]
c.
HEAT SINK Narrow range level in all S/Gs less than 54,
[254 adverse CNMT] AND total feedwater flow less than 200 gpm d.
INTEGRITY Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.
CONTAINMENT CNMT pressure greater than 60 psig
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E-3 TITLE:
t STEAM GENERATOR TUBE RUPTURE REV 12 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication S
PRESSURE (PSIG)
RC 2500 2400 2300 2200 2100 2000 1900 1800
- 1700, 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
20 RCS PRESSURE INCREMENTS 20 PSIG
+~
SUBCOOLED REGION
~-~
t INADEQUATE SUBCOOLING REGION ADVERSE CNMT T
~
TEMPERATURE INCREMENTS 10'F NORMAL CNMT 0
250 300 350
.400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
1 tt d,C 4
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E-3 LITLE:
STEAM GENERATOR TUBE RUPTURE REV:
12 PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1:
o RCS subcooling based on core exit T/Cs
LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR 2.
o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%
[304 adverse CNMT]
SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been
- isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step l.
3.
I COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than'
- feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
4 ygr