ML17261A994
| ML17261A994 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/23/1990 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17261A978 | List: |
| References | |
| AP-TURB.4, NUDOCS 9003080376 | |
| Download: ML17261A994 (52) | |
Text
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AP-TURB.4 LOSS OF CONDENSER VACUUM REV:
6 PAGE 1 of 6 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P
T SUPERIN EN ENT 4 39" 0
EFFECTIVE DATE QA NON-QA~ CATEGORY 1.0 REVIEWED BY:
6 INNASTATION START:
DATE TIME 1
COMPLETED:
DATE TIME'003080376 900227 PDR ADDCK 05000244 F
PNU
l'l
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AP-TURB.4 TITLE:
,REV:
6 PAGE 2 of 6'.
PURPOSE This procedure provides the necessary actions to control the plant with decreasing condenser vacuum.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of LOSS OF CONDENSER VACUUM are; a.
Low or decreasing condenser vacuum, or b.
Annunciator J-16, MOTOR OFF CW-EH EMERG OIL SEAL OIL BU alarm, or c.
Annunciator H-7, CONDENSER HI PRESSURE, 25.5" HG alarm, or d.
Unexplained decreasing generator output.
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AP-TURB.4 TITLE)
LOSS OF CONDENSER VACUUM REV 6
PAGE 3 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION)
SHALL BE PERFORMED.
NOTE: If condenser vacuum is LESS THAN 20" Hg, condenser steam dump is not available.
S/G ARVs must be used to remove decay heat.
1 Check Condenser Vacuum GREATER THAN 20n Hg IF condenser vacuum LESS THAN 20" HG, THEN:
- a. Verify turbine trip.
b.
GO TO AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED)
OR E-O, REACTOR TRIP OR SAFETY INJECTION, as required.
2 Place 1 Priming Air Ejector-IN SERVICE a.
Open priming air ejector'root
- valve, V-3578
- b. Place 1A priming air in service
- 1) Open steam supply to lA priming air ejector (V-3581) not to exceed 200 psig on PI2019
- 2) Open 1A priming air removal valve (V-3248)
- b. IF 1A priming air ejector NOT
- operable, THEN place 1B priming air ejector in service:
- 1) Close V-3248.
- 2) Close V-3581.
- 3) Open steam supply to 1B priming air ejector (V-3580) not to exceed 200 psig on PI2020.
- 4) Open 1B priming air removal valve (V-3249).
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AP-TURB. 4 TITLE:
LOSS OF CONDENSER VACUUM REV 6
PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3
Decrease Turbine Load To Stabilize Vacuum:
o Vacuum - GREATER THAN 20" o
Vacuum - STABLE OR INCREASING IF vacuum can NOT be maintained, THEN:
- a. Decrease generator load to minimum.
- b. Trip turbine.
- c. Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
CAUTION EXCESSIVE CONDENSER BACK PRESSURE MAY RESULT IN THE LAST ROW OF TURBINE BLADES OPERATING AS A COMPRESSOR PRODUCING BLADE LOADING OPPOSITE TO THE DIRECTION OF ROTATION.
THIS MAY INDUCE SEVERE NON-SYNCHRONOUS BLADE VIBRATION.
4 Verify Turbine Back Pressure WITHIN LIMITS OF FIGURE 1
IF operating in the AVOID region, THEN ad]ust turbine load as necessary to return to the safe operating region.
IF operating in the DO NOT OPERATE
- region, THEN trip the turbine and go to AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED OR E-O, REACTOR TRIP OR SAFETY INJECTION.
5 Check Condenser For Air Inleakage:
o Condenser
- NO INLEAKAGE DETECTED IF condenser inleakage is detected, THEN:
- a. Isolate if possible.
- b. IF inleakage can NOT be
- isolated, THEN go to Step 8.
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AP-TURB. 4 TITLE:
LOSS OF CONDENSER VACUUM REV' PAGE 5 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6
Check Condenser Circulating Water System OPERATING AS REQUIRED IF a circulating water pump has
- tripped, THEN:
a.
Reduce turbine load to LESS THAN 50X.
- b. Throttle water box outlet valve (Refer to T-8C, ISOLATION OF CONDENSER WATER BOX AT POWER).
7 Check Operation Of Air Ejectors:
- a. Air ejector steam pressure-APPROXIMATELY 180 PSIG b.
Check inner and after condenser vacuums:
o Inner condenser vacuum-APPROXIMATELY 29 INCHES o
After condenser vacuum-APPROXIMATELY 27 INCHES
- a. IF air ejector steam pressure
+
- low, THEN open regulator bypass, vlv 3584 to restore pressure AND notify ISC.
- b. IF vacuums are low, THEN close inner condenser loop seal isolation valve, vlv 3228.
IF vacuum increase results, THEN leave vlv 3228 shut for a short period to restore loop seal.
8 Check Condenser 'Vacuum STABLE OR INCREASING IF condenser vacuum can NOT be restored at power,.THEN shutdown the plant (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN) ~
9 Establish Stable Plant Conditions:
o Tavg - AT PROGRAM o
S/G level - AT PROGRAM
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AP-TURB.4 TITLE:
LOSS OF CONDENSER VACUUM REV 6
PAGE 6 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Complete HIGHER SUPERVISION NOTIFICATION 11 Establish Further Guidance:
o Go to - APPROPRIATE PLANT PROCEDURE
>>END-
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AP-TURB.4 TITLE:
6 PAGE 1 of 1 BACK PRESSURE (inches Hg) 7 INCREMENTS 0.2 inches Hg FIGURE 1
DO NOT OPERATE IN THIS REGION COMPUTER ADDRESS BAROMETRIC PRESS.
- P-3200 CONDENSER VACUUM - P-3201 BACK PRESSURE - PBACK OR USE AUX. OPERATOR CALC.
AVOID OPERATION IN THIS REGION SATISFACTORY OPERATING REGION INCREMENTS 20 MV 100 200 300 400 GROSS ELECTRIC (MV) 500 600
II g
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E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 1 of 15 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE LA T SUPERINTENDE T EF ECT VE DATE CATEGORY 1.0 REVIEWED BY:
I
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV:
10 PAGE 2 of 15 A-PURPOSE This procedure provides actions to recover from a loss of reactor or secondary coolant.
B.
ENTRY CONDITXONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from:
a.
E-O, REACTOR TRXP OR SAFETY XNJECTION, and FR H 1g
RESPONSE
TO LOSS OF SECONDARY HEAT SINK/
when a
PRZR PORV is stuck open and its block valve can not be closed.
b.
E-O, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms:
high containment radiation,,
high containment pressure, or high containment recirculation sump level.
c.
E-O, REACTOR TRIP OR SAFETY INJECTION, and ECA-2.1, UNCONTROLLED DEPRESSURIZATXON OF BOTH STEAM GENERATORS, when RCS pressure is less than the shutoff head pressure of the RHR pumps.
d.
ES-1.1, SI TERMXNATION, and FR-I.2,
RESPONSE
TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
e.
E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.
f.
ECA-0.2, LOSS OF ALL AC'OWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.
g.
ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a'OCA outside containment is isolated.
h.
FR-C.l,
RESPONSE
TO INADEQUATE CORE COOLING, and FR-C.2,
RESPONSE
TO DEGRADED CORE COOLING, after core cooling has been reestablished.
i ~
FR H 1 g
RESPONSE
TO LOSS OF SECONDARY HEAT SINK/
if RCS pressure is less than all non-faulted S/G(s) pressure.
j ~
FR H 1 g
RESPONSE
TO LOSS OF SECONDARY HEAT S INK~
after secondary heat sink has been reestablished and all PRZR PORVs are closed.
p~E
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E-l, TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 3 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28Fo~
THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP l.
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 Conditions should be evaluated for Site Contingency Reporting (Refer to 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 TWO 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.
E
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV,:
10 PAGE 4 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2
Check If S/G Secondary= Side Is Intact:
o Pressure in both S/Gs - STABLE OR INCREASING I
o Pressure in both S/Gs
- GREATER THAN 100 PSIG IP any S/G pressure decreasing in an uncontrolled manner OR completely depressurized,'HEN verify faulted S/G isolated unless needed for RCS cooldown:
~ Steamlines
~ Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER.SOURCES FOR
'FW PUMPS VILL BE NECESSARY (REFER TO ER-APV.1)
ALTERNATE VATER SUPPLY TO APV PUMPS).
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
3 Check Intact S/G Levels:
- a. Narrow range level - GREATER THAN '5X [25X adverse CNMT]
- b. Control feed flow to maintain narrow range level between 17X
[25X adverse CNMT] and 50X
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5X [25X adverse CNMT] in at least one S/G.
li
- b. IF narrow range level in any S/G continues to increase in an uncontrolled
- manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
5p tp
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 5 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 4
Check Secondary Radiat.ion Levels NORMAL o
Steamline radiation monitor (R-31 and R-32) o Request HP sample S/Gs for activity IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation.
IF abnormal radiation levels detected in any S/G, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR
5 Check PRZR PORVs And Block Valves:
a.
Power to PORV block valves-AVAILABLE b.
PORVs - CLOSED
- c. Block valves
- AT LEAST ONE OPEN
- 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.
IF any PORV can NOT be closed, THEN manually close its block valve.
IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C c.
Open one block valve unless it was closed to isolate an open PORV.
gs"
'f e
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 6 of 15 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.
6 Reset SI 7
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.
8 Verify Adequate SN Flow:
I 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 perform the following:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1) 3)
Go to Step 10.
tf f,
a~t e
A,
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV'0 PAGE 7 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 9 Establish IA to CNMT:
- a. Verify non-safeguards busses energized from offsite power o
Bus 13 normal feed - CLOSED
-OR-o Bus 15 normal feed -
CLOSED
- b. Verify turbine building SW isolation valves - OPEN
~ 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
- a. Perform the following:
- 1) Close non-safeguards bus tie breakers:
F
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).
IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC PANS).
3)
WHEN bus 15 restored, THEN reset control room lighting.
- b. Manually align valves.
- c. Manually start air compressors as power supply permits (75 kw each).
IF 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 OF INSTRUMENT AIR).
- 2) Continue with Step 10.
WHEN IA restored, THEN do Steps 9e and f.
'k 1
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E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 8 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Check Normal Power Available To Charging Pumps:
o Bus 14 normal feed breaker-CLOSED o
Bus 16 normal feed breaker-CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).
IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).
AJAR
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E-1 LOSS OF REACTOR OR. SECONDARY COOLANT REV:
10 PAGE 9 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED ll Check If Charging Flow Has Been Established:
- a. Charging pumps
- ANY RUNNING
- a. Perform the following:
- 1) IF CCW flow 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 close seal injection needle valve(s) to affected RCP:
- b. Charging pump suction aligned to RWST:
o LCV-112B -
OPEN o
LCV-112C - CLOSED
- c. Start charging pumps as necessary and ad)ust charging flow to restore PRZR level
~ V-300A for RCP A
~ V-300B for RCP B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Manually align valves as necessary.
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).
l
't A
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV:. 10 PAGE 10 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 12 Check If SI Should Be Terminated:
a.
RCS pressure:
o Pressure
- GREATER THAN 1625 psig
[1825 psig adverse CNMT]
o Pressure
- STABLE OR INCREASING a.
Do NOT stop SI pumps.
Go to Step 14.
b.
RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING b.
Do NOT stop SI pumps.
Go to Step 14.
- c. Secondary heat sink:
o Total feed flow to intact S/Gs - GREATER THAN 200 GPM
- c. IF neither condition satisfied, THEN do NOT stop SI pumps.
Go to Step 14.
-OR-o Narrow range level in at least one intact S/G-GREATER THAN 5X [25K adverse CNMT]
d.
PRZR level - GREATER THAN 5X
[30X adverse CNMT]
d.
Do NOT stop SI pumps.
Perform the following:
- 1) IF normal PRZR spray available, THEN try to
'stabilize RCS pressure with PRZR spray.
2)
Go to Step 14.
II I
EOP:
E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT 1
REV 10 PAGE 11 of 15 STEP ACTION/EXPECTED RESPONSE'ESPONSE NOT OBTAINED 13 Go To ES-1.1, SI TERMINATION, Step 1
14 Check If CNMT Spray Should Be Stopped:
a.
CNMT spray pumps
- RUNNING
- b. Check 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 15.
- b. Continue with Step 15.
WHEN CNMT pressure less than 4 psig, THEN do Steps 14c through f.
- d. Place NaOH tank outlet valve controllers to MANUAL and close valves.
e.
Stop CNMT spray pumps and place in AUTO
- f. Close CNMT spray pump discharge valves
~ MOV-860A
~ MOV-860B
~ MOV-860C
~ MOV-860D
p A
4
EOP:
E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 12 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION o
IF OFFSITE POWER IS LOST AFTER SI RESET, SELECTED SV PUMPS AND ONE CCW PUMP VILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION VILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
o RCS PRESSURE SHOULD BE MONITORED.
IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG
[465 PSIG ADVERSE CNMT], THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
15 Check If RHR Pumps Should Be Stopped:
a.
Check RCS pressure:
- 1) Pressure
- GREATER THAN 250 psig [465 psig adverse CNMT]
2)
RCS pressure
- STABLE OR INCREASING
- b. Stop RHR pumps and place in AUTO 1)
Go to Step 17.
2)
Go to Step 16.
16 Check RCS And S/G Pressures a.
Check pressures in both S/Gs-STABLE OR INCRBASING
- a. Return to Step l.
b.
Check pressures in both S/Gs-GREATBR THAN 100 PSIG
- c. Check RCS pressure
- STABLE OR DECREASING
- b. Monitor RCS pressure.
IF RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.
- c. Return to Step l.
yD
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E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 13 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 17 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by offsite power:
o Emergency D/G output breakers OPEN o
AC emergency bus voltage-GREATER THAN 420 VOLTS o
AC emergency bus normal feed breakers
- CLOSED
- a. Perform the following:
- 1) Close non-safeguards bus tie breakers as necessary:
~ 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) Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
~ A from Bus 13
~ B from Bus 15
~ E from Bus 15
~ F from Bus 15 5)
WHEN bus 15 restored, THEN reset control room lighting breaker.
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
- 6) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- 7) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
fr~
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I0 etl
'F4%
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E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV 10 PAGE 14 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 18 Evaluate Plant Status:
- a. Verify sump B recirculation capability:
'nd valves
- a. IF at least one train of cold leg recirculation capability can NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step l.
o Bus 14 and MCC C-ENERGIZED o
Bus 16 and MCC D-ENERGIZED 2)
RHR pumps
- OPERABLE
- b. Dispatch AO to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key required)
- c. Check auxiliary building radiation - NORMAL
~ Plant vent iodine (R-10B)
~ Plant vent particulate (R-13)
~ Plant vent gas (R-14)
~
CCW liquid monitor (R-17)
~ LTDN line monitor (R-9)
~
CHG pump room (R-4)
- d. Direct HP to obtain following samples:
~ RCS activity
~ BASTs boron
- b. IF any RHR pump seal leakage indicated, THEN leakage should be evaluated and isolated if necessary.
- c. Notify HP and refer to appropriate AR-RMS procedure.
IF the cause is a loss of RCS inventory outside CNMT, THEN 'go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
This Step continued on the next page.
'I
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E-1 TiTLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV:
10 PAGE 15 of 15 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED (Step 18 continued from previous page)
- e. Verify adequate Rx head cooling:
- 2) Verify at least one control rod shroud fan -
RUNNING')
Verify one Rx compartment cooling fan - RUNNING 1)
Go to Step 19.
- 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) 19 Check If RCS Cooldown And Depressurization Is Required:
a.
RCS pressure
- GREATER THAN 250 psig [465 psig adverse CNMT]
b.
Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1
- a. IR RHR pump flow greater than 475 gpm, THEN go to Step 20.
20 Check If Transfer To Cold Leg Recirculation Is Required:
a.
RUST level - LESS THAN 28X b.
Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1
- a. Return to Step 18.
r.r I
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TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV:
10 PAGE 1 of 1 E-1 APPENDIX LIST TITLE 1)
RED PATH
SUMMARY
2)
FIGURE MIN SUBCOOLING 3)
ATTACHMENT CNMT RECIRC 4)
ATTACHMENT D/G STOP 5)
ATTACHMENT SD-1 6)
ATTACHMENT SI/UV 7)
FOLDOUT PAGES
i 4
l+,,
0
EOP:
E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV:
10 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 434
[464 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
I f
V
+'1
EOP:
TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV'0 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 I
1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
20 RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION INADEQUATE SUBCOOLING REGION RS E CNMT TEMPERATURE INCREMENTS 10'R NORMAL CNMT 0
250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
~ ~
1 I".
~ ~~
EOP:
E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV:
10 PAGE 1 of 1 FOLDOUT PAGE 1.
SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:
o RCS subcooling based on core exit T/Cs LESS THAN O'F USING FIGURE MIN SUBCOOLING OR o
PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%
[304 adverse CNMT]
2.
SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:
a.
RCS subcooling based on core exit T/Cs GREATER THAN O'F USING FIGURE MIN SUBCOOLING
- b. Total feed flow to intact S/Gs GREATER THAN 240 gpm OR-Narrow range level in at least one intact S/G GREATER THAN 5%
[25% adverse CNMT]
c.
RCS pressure:
o GREATER THAN 1625 psig
[1825 psig adverse CNMT]
o STABLE OR INCREASING d.
PRZR level GREATER THAN 5%
[30% adverse CNMT]
3.
SECONDARY INTEGRITY CRITERIA 1F 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 1.
4.
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.
5.
AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
6.
E-3 TRANSITION CRITERIA IF any S/G level increases in an uncontrolled manner or. any S/G has abnormal radiation, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
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