AOP'S

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AOP'S
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2016-06-22 14:09:57
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AOP questions
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  1. AOP-2 "Excessive Load" Symptoms/Entry conditions
    • Symptoms of excessive load (eg, Pressurizer pressure lowering, Pressurizer level lowering, audible noise) in conjunction with any of the following:
    •  EK-0968, "LOOP 1 T AVE /T REF GROSS DEVIATION" (5°F)
    •  EK-0969, "LOOP 2 T AVE /T REF GROSS DEVIATION" (5°F)
    •  EK-1362, "CONTAINMENT PRESSURE OFF NORMAL" with a steam leak in containment
    •  Turbine Governor Valve Control Malfunction (open)
  2. AOP-3 " Main Feedwater Transients" Immediate actions
    • USER ALERT A failed Feedwater flow input results in HP_PWR being inoperable. Use highest of NI/ΔT power for monitoring reactor power.
    • 1. TAKE manual control of the following, as necessary, to restore/stabilize Steam Generator level(s):
    •  CV-0701, E-50A Feed Regulating Valve
    •  CV-0703, E-50B Feed Regulating Valve
    •  CV-0735, E-50B Feed Reg Bypass
    •  CV-0734, E-50B Feed Reg Bypass
    •  HIC-0525, Combined Feed Pump Speed Control
    •  HIC-0526, P-1A Turbine Driver K-7A Speed Control
    •  HIC-0529, P-1B Turbine Driver K-7B Speed Control
    •       RNO 1.1 IF either Steam Generator level is less than or equal to 30%, THEN TRIP the Reactor.   
    •        a. GO TO EOP-1.0. "Standard Post-Trip Actions."
    •       1.2 IF either Steam Generator level is greater than or equal to 95% AND Reactor Power is greater than or equal to 15%, THEN TRIP the Reactor.
    •       a. GO TO EOP-1.0. "Standard Post-Trip Actions."
    •       1.3 IF either Steam Generator level is greater than or equal to 95% AND Reactor Power is less than 15%, THEN TRIP the Turbine. 
    • 2. IF either of the following are in alarm:
    •  EK-0961, "STEAM GENERATOR E-50A HIGH LEVEL"
    •  EK-0963, "STEAM GENERATOR E-50B HIGH LEVEL"
    • THEN VERIFY the high level override is maintaining Steam Generator level(s):
    • a. Greater than or equal to 60%.
    •  RNO a.1 TRIP the Reactor.
    •         1) GO TO EOP-1.0, "Standard Post-Trip Actions."
    •  b. Less than or equal to 90%.
    •   RNO b.1 IF Reactor Power is greater than or equal to 15%, THEN TRIP the Reactor
    •           1) GO TO EOP-1.0, "Standard Post-Trip Actions."
    •          b.2 IF Reactor Power is less than 15%, THEN TRIP the Turbine.
  3. AOP-3 "Main Feedwater Transients" Rx Trip criteria
    • Reactor Trip
    •  Either Steam Generator level lowers to 30%
    •  No Main Feedwater Pump operating
    •  EK-0961, STEAM GENERATOR E-50A HIGH LEVEL is alarming, AND Steam Generator level(s) are less than 60% and lowering (eg, fault in high level override circuit)
    •  EK-0963, STEAM GENERATOR E-50B HIGH LEVEL is alarming, AND Steam Generator level(s) are less than 60% and lowering (eg, fault in high level override circuit)

    •  Reactor power greater than 80%:
    •  Any operating Main Feedwater Pump trips
    •  CV-0711, Feed Pump P-1A Recirculation Valve fails open
    •  CV-0710, Feed Pump P-1B Recirculation Valve fails open

    •  Reactor power greater than or equal to 15%:
    •  Either Steam Generator level is greater than 90% AND the high level override has not lowered feedwater flow
    •  Either Steam Generator level is greater than 95%

    • Turbine Trip
    •  Reactor power less than 15%:
    •  Either Steam Generator level is greater than 90% AND the high level override has not lowered feedwater flow
    •  Either Steam Generator level is greater than 95%
  4. AOP-3 "Main Feedwater Transients" Entry conditions
    • EK-0143, "FW PUMP P1A TURBINE K7A TRIP"
    •  EK-0146, "FW PUMP LO SUCTION PRESS CHANNEL TRIP" (250 psig)
    •  EK-0148, "FW PUMP P1A LO SUCTION FLOW OR LO DISCH PRESS" (2500 gpm or 800 psig)
    •  EK-0149, "FW PUMP P1B TURBINE K7B TRIP"
    •  EK-0154, "FW PUMP P1B LO SUCTION FLOW OR LO DISCH PRESS" (2500 gpm or 800 psig)
    •  EK-0155, "CONDENSATE PUMP TRIP"
    •  EK-0157, "CONDENSATE PUMP P2A DISCHARGE LO PRESS" (390 psig)
    •  EK-0160, "FDWTR PUMP LO SUCTION" (305 psig)
    •  EK-0163, "CONDENSATE PUMP P2B DISCHARGE LO PRESS" (390 psig)
    •  EK-0170, "HEATER DRAIN PUMP TRIP"
    •  EK-0961, "STEAM GENERATOR E-50A HI LEVEL" (84.7%)
    •  EK-0962, "STEAM GENERATOR E-50A LO LEVEL" (55%)
    •  EK-0963, "STEAM GENERATOR E-50B HI LEVEL" (84.7%)
    •  EK-0964, "STEAM GENERATOR E-50B LO LEVEL" (55%)
    •  Indications of a Main Feedwater transient in progress
    •  Condensate Cleanup System Leak
    •  Main Feedwater Piping Rupture
    •  Heater Drain Pump Malfunction
  5. AOP-3 "Main Feedwater Transients" Automatic Actions?
    • CV-0608, Moisture Separator Drain Tank T-5 Level Control fully opens (Low Feedwater suction pressure 270 psig)
    •  Main Feed Pumps, trips (Low Feedwater Pump suction pressure 250 psig after a 3 second time delay).
    •  AFAS initiation (Steam Generator level of 30%)
    •  Reactor trip (Steam Generator level of 28%)
    •  CV-0701, E-50A Feed Regulating Valve, closes by high level override (84.7%).
    •  CV-0703, E-50B Feed Regulating Valve, closes by high level override (84.7%).
  6. AOP-1 "Loss of Load"  Reactor and Turbine trip criteria
    • Reactor Trip
    •  Reactor Power greater than or equal to 15% AND Turbine Governor Valve control in manual and not controlling

    • Turbine Trip
    •  Reactor Power less than 15% AND Turbine Governor Valve control in manual and not controlling
  7. AOP-1 "Loss of Load" symptoms/entry conditions
    • Symptoms of a Loss of Load (eg, Pressurizer pressure rising, Pressurizer level rising) in conjunction with any of the following:
    •    EK-0968, "LOOP 1 T AVE /T REF GROSS DEVIATION" (5°F)
    •    EK-0969, "LOOP 2 T AVE /T REF GROSS DEVIATION" (5°F)
    •    Turbine Control Valve Malfunction (close)
  8. AOP-17 "Loss of 125 V DC Panel(s)" indications/immediate actions for loss of D21-2
    • indications
    • -EK-0542 "Annunciator DC failure" in alarm AND
    • -K-7B, MFP trip power light is extinguished THEN
    • Actions
    • -ensure Rx tripped
    • -ensure turbine is tripped
    • -refer to ONP-6.1 "Loss of SW" and ARP-33 "auxiliary systems scheme EK-02(C-11A)"
  9. AOP-17 "Loss of 125V DC Panel(s)" indications/immediate actions for loss of D-20R
    • indications
    • -EK-0542"annunciator DC failure" AND
    • -K-7B, MFP trip power light is off AND
    • -CV-0501, E-50B MSIV position ind. lights off
    • Actions
    • -ensure Rx tripped
    • -close MSIVs using HS-0510A to ensure turbine is tripped
  10. AOP-17 "Loss of DC Power" Rx trip criteria
    • if CV-1359 is failed closed as indicated by both of the following (loss of D20R or D21-2)
    • -K-7B trip power light off
    • -CV-1359 position indication lights off
  11. When does AOP-8(9) "Loss of Bus 1C (1D) Power" require tripping the emergency diesel generators?
    • Jacket water temperature verified >/= to 195F on TI-1482/1483
    • Lube oil temperature verified >/= to 200F on TI-1478/1479
  12. What are the AOP-9 "Loss of Bus 1D" entry conditions?
    • Symptoms of loss of Bus 1D (eg, loss of power to all Bus 1D powered components) in conjunction with one or more of the following:
    •   EK-0515, "2400V BUS 1C AND/OR 1D HI/LO VOLTAGE/ UNDERVOLTAGE" (< 2375V, 18 sec time delay)
    •   EK-0522, "BUS FAIL TO TRANSFER"
    •   EK-0521, "2400V STANDBY POWER NOT AVAILABLE"
    •   EK-0510, "2400V BUS 1D BKR 152-202 TRIP" (if closed)
    •   EK-0504, "2400V BUS 1D BKR 152-203 TRIP" (if closed)
    •   EK-0532, "BUS 1C OR 1D OVERCURRENT LOCKOUT"
  13. AOP-8 "Loss of Bus 1C" symptoms/entry conditions
    • Symptoms of loss of Bus 1C (eg, loss of power to all Bus 1C powered components) in conjunction with one or more of the following:
    •    EK-0515, "2400V BUS 1C AND/OR 1D HI/LO VOLTAGE UNDERVOLTAGE" (< 2375 V, 18 sec time delay)
    •   EK-0522, "BUS FAIL TO TRANSFER"
    •   EK-0521, "2400V STANDBY POWER NOT AVAILABLE"
    •   EK-0503, "2400V BUS 1C BKR 152-105 TRIP" (if closed)
    •   EK-0509, "2400V BUS 1C BKR 152-106 TRIP" (if closed)
    •   EK-0532, "BUS 1C OR 1D OVERCURRENT LOCKOUT"
  14. What are the entry criteria for AOP-10 "Loss of Bus 1E"?
    • Symptoms of loss of Bus 1E (eg, loss of power to all Bus 1E powered components) in conjunction with one or more of the following:
    •    EK-0517, "2400V BUS 1E UNDERVOLTAGE" (90V Secondary or 1860V Primary)
    •    EK-0522, "BUS FAIL TO TRANSFER"
    •    EK-0521, "2400V STANDBY POWER NOT AVAILABLE" (85V Secondary or 1700V Primary)
    •    EK-0505, "2400V BUS 1E BKR 152-302 TRIP" (if closed)
    •    EK-0511, "2400V BUS 1E BKR 152-303 TRIP" (if closed)
  15. What is the reactor trip criteria of AOP-10 "Loss of Bus 1E"?
    Loss of Heater Drain Pumps results in Feedwater Pump(s) trip
  16. Entry criteria for AOP-17 "Loss of 125VDC Panel(s)"?
    Loss of status light indications may be the most likely method to determine if power has been lost to a DC panel. A few indications for each panel are provided to aid in determining which panel has been affected. Component effects listed in the attachments of this procedure may also be used to identify the affected panel.

    • ED-11A
    •  P-8A, Motor Driven Auxiliary Feedwater Pump, Bkr Indication
    •  Bus 1C Control Power Available indication

    • ED-11-1
    •  CV-0510, S/G E-50A MSIV, position indication
    •  Bus 1A Control Power Available indication

    • ED-11-2
    •  K-7A, Feedwater Pump P-1A Turbine Driver, Trip Power
    •  CV-0847, SW Supply to Containment, position indication

    • ED-21A
    •  P-8C, Motor Driven Auxiliary Feedwater Pump, Bkr indication
    •  Bus 1D Control Power Available

    • ED-21-1
    •  CV-0501, S/G E-50B MSIV, position indication
    •  Bus 1B Control Power Available indication
    •  Bus 1E Control Power Available indication

    • ED-21-2
    •  K-7B, Feedwater Pump P-1B Turbine Driver, Trip Power indication
    •  CV-1359, Non-Critical SW Header Isol, position indication
    •  EK-0542, "ANNUNCIATOR DC FAILURE"
  17. What is the mitigating strategy of AOP-17 "Loss of 125VDC Panel(s)"?
    • 1. Determine which DC buses are affected.
    • 2. If ED-11A, ED-11-1, ED-11-2, ED-21A, or ED-21-1 is deenergized, perform prompt compensatory actions.
    • 3. Review equipment fed from affected DC buses to determine affected equipment and alternate components available.
    • 4. Determine and correct cause of loss of DC.
    • 5. Restore affected DC buses.
    • 6. Restore affected AC buses, if applicable.
  18. What is the Reactor Trip criteria of AOP-17 "Loss of 125VDC Panels(s)"?
    • Loss of ED-20R or ED-21-2
    • CV-1359, Non-critical SW Header Isol, fails closed on loss of ED-20R or ED-21-2 as indicated by BOTH of the following:
    •  K-7B, Feedwater Pump P-1B Turbine Driver, "Trip Power" light is extinguished
    •  CV-1359 position indication lights are extinguished
  19. What are the automatic actions of AOP-17 "Loss of 125VDC Panels(s)"?
    • Deenergizing Bus ED-10R results in the loss of EY-10, Preferred AC Bus No 1, and the following actions will occur:
    •  P-8A/P-8B AFW control circuitry transfers to EY-30 power.
    •  Main Feedwater control for 'A' S/G transfers to EY-30 power.
    •  P-8B, Steam Driven Auxiliary Feedwater Pump, starts.

    Deenergizing Bus ED-20R results in the loss of EY-20, Preferred AC Bus No 2, and the Main Feedwater control for 'B' S/G transferring to EY-40 power.

     Deenergizing Panel ED11-1 results in P-8B, Steam Driven Auxiliary Feedwater Pump, starting.
  20. What are the entry conditions for AOP-18 "Loss of Left Train DC Power"?
    • EK-0548, "125V DC BUS UNDERVOLTAGE" AND
    • EK-0541, "BATTERY CHARGERS TROUBLE" AND
    • EK-0543, "PREFERRED AC BUS NO 1 TROUBLE" AND
    • EK-0544, "PREFERRED AC BUS NO 3 TROUBLE"
  21. What are the automatic actions of AOP-18 "Loss of Left Train DC Power"?
    P-8B, Steam Driven Auxiliary Feedwater Pump, starts.
  22. What are the immediate actions of AOP-17 "Loss of 125V DC Panel(s)"?
    • 1. VERIFY the following conditions exist (loss of Bus ED-20R):
    •  "ANNUNCIATOR DC FAILURE," (EK-0542) is in alarm
    •  K-7B, Feedwater Pump P-1B Turbine Driver, "Trip Power" light is extinguished
    •  CV-0501, S/G E-50B MSIV (MZ-3), position indication lights are extinguished
    •   a. ENSURE the Reactor is tripped.
    •   b. PLACE HS-0510A, Main Steam from Steam Generator E-50A, to CLOSE. (to ensure the Turbine is tripped)

    RNO

    1.1 GO TO Step 2.


    • 2. VERIFY the following conditions exist: (loss of Panel ED-21-2)
    •  "ANNUNCIATOR DC FAILURE" (EK-0542) is in alarm
    •  K-7B, Feedwater Pump P-1B Turbine Driver, "Trip Power" light is extinguished
    •   a. ENSURE the Reactor is tripped.
    •   b. ENSURE the Turbine is tripped.

    • RNO
    • 2.1 GO TO Section 6.0, "Operator Actions."
  23. What are the immediate actions of AOP-18 "Loss of Left Train DC Power"?
    • 1. VERIFY the Reactor tripped, if reset.
    • RNO
    •   1.1 TRIP the Reactor, if reset.
    • 2. VERIFY the Turbine tripped.
    • RNO
    •   2.1 TRIP the turbine using one of the following:
    •    PUSH PB20AST, Main Turbine Emergency Trip
    •    PLACE HS-0501A, Main Steam from Steam Generator 'B' to CLOSE
    •    manually at turbine front standard

    • 3. TRIP 25F7 and 25H9, Main Generator Output breakers as follows:
    •   a. CONNECT jumper between terminals 1 and 10 on Relay 487U, Diff Relay-Unit Differential, trips Gen (Y phase)
  24. Entry conditions for AOP-19 "Loss of Right Train DC Power"?
    • EK-0542, "ANNUNCIATOR DC FAILURE"
    • AND
    • K-7B Trip Power Available light extinguished
    • AND
    • PY-0102B and PY-0102D, TMM Channels loss of power
    • AND
    • CV-0501, S/G E-50B MSIV Position Indication lights extinguished
  25. What are the immediate actions for AOP-19 "Loss of Right Train DC Power"?
    1. VERIFY the Reactor tripped, if reset.

    • RNO
    • 1.1 TRIP the Reactor, if reset.

    2. VERIFY the Turbine tripped.

    • RNO
    • 2.1 TRIP the turbine using one of the following:
    •  PLACE HS-0510A, Main Steam from Steam Generator 'A' to CLOSE
    •  manually at the front standard
  26. AOP-36 "Loss of Component Cooling" Reactor trip criteria?
    • CCW flow to Containment lost for greater than 10 minutes
    • Failure to restore a Component Cooling Water Pump to service
  27. AOP-36 "Loss of Component Cooling" symptoms/entry conditions
    • T-3, CCW Surge Tank level lowering and not being recovered
    • CCW cooled components indicate degraded cooling
    • EK-1169, "COMPONENT CLG PUMP DISCHARGE LO PRESS" (80 psig)
  28. AOP-36 "Loss of Component Cooling" automatic actions?
    Standby CCW Pump starts @ 80 psig
  29. AOP-35 "Loss of Service Water" entry conditions
    • EK-1124, "TRAVELING SCREEN HI DP" (9"H 2 O)
    • EK-1129, "SERVICE WATER PUMP BAY LO LEVEL" (Elevation 574'3")
    • EK-1163, "CRITICAL SERV WATER HEADER "B" LO PRESSURE" (45 psig)
    • EK-1164, "CRITICAL SERV WATER HEADER "A" LO PRESSURE" (45 psig)
    • EK-1165, "NON-CRITICAL SERV WATER LO PRESS" (45 psig)
  30. AOP-35 "Loss of Service Water" Rx trip criteria
    Service Water Bay level lowers to 572’

    Operator actions are not maintaining either Critical Service Water Header Pressure greater than or equal to 42 psig

    • Loss of Non-Critical Service Water as indicated by the following alarms:
    •  EK-1165, "NON CRITICAL SERV WATER LO PRESS" (45 psig) AND
    •  PPC Urgent Alarm, "EXC FIELD COLD AIR RTD-31" [T_EXCITER_31] (48°C) OR
    •  PPC Urgent Alarm, "EXC DIODE COLD AIR RTD-32" [T_DIODE_32] (48°C) OR
    •  EK-0259, "EXCITER COOLER HI TEMP" (50°C)
  31. What are the immediate actions for AOP-35 "Loss of Service Water"?
    CAUTION Exciter damage may occur within 10 seconds of losing Non-Critical Service Water.

    • © 1. IF EK-1165, "NON CRITICAL SERV WATER LO PRESS" (45 psig) is in alarm, THEN VERIFY the following annunciators clear:
    •  PPC Urgent Alarm, "exc field cold air RTD-31" (48°C)
    •  PPC Urgent Alarm, "exc diode cold air RTD-32" (48°C)
    •  EK-0259, "EXCITER COOLER HI TEMP" (50°C)

    • RNO
    •  1.1 TRIP Reactor, if reset. Refer to EOP-1.0, "Standard Post-Trip Actions."
    •  1.2. IF the following occur:
    •    Non-Critical Service Water has been isolated or lost
    •    REC-C11A-01, Generator Temperature Recorder, points 33 and 34 Exciter Cold Air Temperature is greater than 80°C or rising
    •   THEN:
    •   PERFORM Attachment 1, "Break Condenser Vacuum," to slow generator rotor speed.
  32. AOP-37 "Loss of Instrument Air" symptoms/entry criteria?
    • EK-1101, "CONTAINMENT INSTR AIR LO PRESS" (85 psig)
    • EK-1102, "INSTRUMENT AIR LO PRESS" (85 psig)
    • EK-1103, "SERVICE AIR LO PRESS" (80 psig)
  33. AOP-37 "Loss of Instrument Air" Reactor Trip criteria?
    Erratic equipment behavior observed on equipment required for safe plant operation
  34. AOP-37 "Loss of Instrument Air" automatic actions?
    • Standby Instrument Air Compressor(s) starts at 92 psig
    • CV-1212, Service Air Header Isol closes at 85 psig in the Instrument Air Header
  35. Safety function hierarchy
    • reactivity control
    • maintenance of vital auxiliaries-electric
    • PCS inventory control
    • PCS pressure control
    • core heat removal
    • PCS heat removal
    • containment isolation
    • containment atmosphere
    • maintenance of vital auxiliaries-water
    • maintenance of vital auxiliaries-air
  36. Indications of a steam generator tube rupture
    • steam plant activity > alarm setpoint or rising
    • unexplained rise in S/G level in one S/G
    • unexplained feed flow mismatch between S/Gs
    • unexplained loss of PCS inventory
  37. Indications of excess steam demand event
    • containment high range monitors are not rising and do not corroborate the containment area monitors
    • PCS subcooling rise
    • S/G pressure lowering
  38. AOP-7 "Rapid Power Reduction" Rx trip criteria?
    • Reactor Trip
    •  Either Steam Generator level less than 30%
    •  Either Steam Generator level greater than 95%
    •  Pressurizer level less than 30%
    •  Pressurizer level greater than 62.8%
    •  T AVE less than 525°F
    •  Rack C, EK-0605, "TM/LO PRESSURE CHANNEL PRE-TRIP"
    •  Rack B, EK-0608, "HI PRESSURIZER PRESSURE CHANNEL PRE-TRIP"
    •  More than one control rod misaligned (8 inch deviation) after attempted realignment
    •  Plant cannot be stabilized following termination of power reduction
  39. AOP-7 "Rapid Power Reduction" Entry Conditions?
    • Use of this procedure is directed by another abnormal operating procedure.
    •  Control Room Supervisor determines that abnormal plant conditions requires immediate power reduction at a rate greater than 30%/hour and less than or equal to 300%/hour.
  40. AOP-6 " Loss of Condenser Vacuum" entry conditions
    • EK-0111, "VACUUM LO" (24" Hg)
    • EK-0110, "VACUUM PRETRIP" (21.5" Hg)
    • EK-3522, "CLG TWR PUMP P-39A TRIP"
    • EK-3523, "CLG TWR PUMP P-39B TRIP"
    • PT-0763 Turbine Backpressure (6" Hg)
  41. AOP-6 "Loss of Condenser Vacuum" Rx/Turbine trip criteria
    • Reactor Trip
    •  Reactor Power greater than or equal to 15%
    •   Main Condenser vacuum lowers to less than 22" Hg
    •   Loss of both cooling tower pumps
    • Turbine Trip
    •  Reactor Power less than 15%
    •   Main Condenser vacuum lowers to less than 22" Hg
    •   Loss of both cooling tower pumps
  42. AOP-6 "Loss of Condenser Vacuum" Automatic Actions?
    Turbine trips at 18 to 21 inches Hg Main Condenser vacuum.
  43. AOP-6 "Loss of Condenser Vacuum" Mitigating Strategy?
    • 1. Stabilize Main Condenser vacuum greater than 24" Hg (˜6" Hg Turbine backpressure).
    • 2. If a cooling tower pump has tripped, reduce power to maintain Main Condenser vacuum greater than 24" Hg.
    • 3. If a cooling tower pump has tripped, utilize water in the cooling tower basin/piping to aid in maintaining Main Condenser vacuum.
    • 4. If air in-leakage or air removal problems are affecting Main Condenser vacuum, then attempt to determine source and correct.
  44. AOP-2 "Excessive Load" trip criteria
    • Reactor Trip
    •  An un-isolable load rise which exceeds 1% change in HB Power Steady, NI or ΔT Power
    •  A plant condition requiring a power reduction at a rate greater than 30%/hour
    •  EK-1362, "CONTAINMENT PRESSURE OFF NORMAL" in alarm AND a steam leak inside containment
    •  Reactor power greater than or equal to 15% AND Turbine Governor Valve Control in manual and not controlling

    • Turbine Trip
    •  Reactor power less than 15% AND Turbine Governor Valve Control in manual and not controlling
  45. AOP-12 "Loss of preferred AC bus Y-10" entry conditions?
    • EK-0543, "PREFERRED AC BUS NUMBER 1 TROUBLE"
    • AND
    • Channel 'A' RPS Trip Ladder Logic Lights Illuminated
  46. AOP-12 "Loss of preferred AC bus Y-10" Rx Trip Criteria?
    CV-0711, Feed Pump P-1A Recirculation Valve, fails open with Reactor power greater than 80%
  47. AOP-12 "Loss of preferred AC bus Y-10" auto actions?
    • P-8A, Motor Driven Auxiliary Feedwater Pump, control circuitry transfers to EY-30, Preferred AC Bus No 3.
    • P-8B, Steam Driven Auxiliary Feedwater Pump, control circuitry transfers to EY-30, Preferred AC Bus No 3.
    • Main Feedwater control for E-50A, 'A' S/G, transfers to EY-30, Preferred AC Bus No 3.
  48. AOP-13 "Loss of Preferred AC bus Y-20" entry criteria?
    • EK-0545, "PREFERRED AC BUS NO 2 TROUBLE"
    • AND
    • Channel 'B' RPS Trip Ladder Logic Lights Illuminated
  49. AOP-13 "Loss of preferred AC bus Y-20" automatic actions?
    Main feedwater control for 'B' S/G transfers to Y-40, preferred AC bus No 4.
  50. AOP-13 "Loss of Preferred AC bus Y-20" Rx trip criteria?
    CV-0710, Feed Pump P-1B Recirculation Valve, fails open with Reactor power greater than 80%
  51. What do you have to do if you lose Y-10 on a CHR or CHP?
    • On CHR (left channel)
    • -close CIAS CV's
    • -trip left channel ESS room sump pumps

    • On CHP (left channel)
    • -activate SIS
    • -close CIAS CV's
    • -manually initiate left channel containment spray
  52. What do you have to do if you lose Y-20 on a CHP or SIAS?
    • On SIAS
    • -manually align right channel

    • On CHP
    • -start P-54A spray pump
  53. What do you have to do if you lose Y-30 on a CHP or SIAS?
    • On SIAS
    • -manually align left channel

    • On CHP
    • -start P-54B/C spray pumps
  54. What do you have to do if you lose Y-40 on a CHR or CHP?
    • on CHR (right channel)
    • -close CIAS CV's
    • -trip right channel ESS room sump pumps

    • On CHP (right channel)
    • -activate SIS
    • -close CIAS CV's
    • -manually initiate right channel containment spray
  55. AOP-14 "Loss of Preferred AC Bus Y-30" entry criteria?
    • EK-0544, "PREFERRED AC BUS NUMBER 3 TROUBLE"
    • AND
    • Channel 'C' RPS Trip Ladder Logic Lights illuminated
  56. AOP-14 "Loss of Preferred AC bus Y-30" Automatic actions?
    Rx Trip if power is greater than or equal to 1E-4% and less than or equal to 15% RTP
  57. AOP-15 "Loss of Preferred AC bus Y-40" entry criteria?
    • EK-0546, "PREFERRED AC BUS NUMBER 4 TROUBLE"
    • AND
    • Channel 'D' RPS Trip Ladder Logic Lights illuminated
  58. AOP-15 "Loss of Preferred AC bus Y-40" Auto actions?
    Rx trip if power is greater than or equal to 1E-4% and less than or equal to 15% RTP
  59. AOP-16 "Loss of Instrument AC bus Y-01" entry criteria?
    • Loss of Control Rod Matrix lights (EC-12)
    • AND
    • Loss of Control Rod LED Position Indication (EC-02)
  60. AOP-16 "Loss of instrument AC bus Y-01" automatic actions?
    • Main Feedwater Pumps slow to minimum speed
    • Maximum Charging
    • CV-2001, Letdown Stop, closes when HS-2001 is in AUTO
    • Charging Pump suction shifts to SIRW Tank
    • MO-2087, VCT T-54 Outlet, closes
    • MO-2160, SIRWT T-58 Outlet to Charging Pp P-55A, B, C, opens
  61. Why do we trip the RX if it is reset and we lose Y-01?
    • MFPs slow to minimum speed 3250 RPM if they haven't tripped due to low suction pressure
    • Charging aligned to SIRWT
    • -due to VCT lo-lo level 7.9%
    • Core matrix lights extinguished
  62. What happens to charging/letdown on loss of Y-01?
    • max charging/minimum letdown
    • -due to failure impact on PZR level backup control program
  63. Why do we close CV-2001, Letdown Stop Valve, on a loss of Y-01?
    • PIC-0202 fails closed
    • CV-2001 only closes in Auto
    • prevents lifting RV-2006
  64. What must be done if PZR level lowers to 36% and you have lost Y-01?
    • Relay that trips PZR heaters is lost
    • -operator must trip PZR heaters on lo-lo level (36%)
  65. When do you secure PCPs on loss of Y-01? Why?
    • if loss of Y-01 is sustained for >10 minutes, stop PCPs as necessary to maintain 1 PCP operating in each loop
    • trip them because you lose indications for them and letdown HX outlet fails open and you might not have enough CCW cooling if only 1 CCW pump is operating
  66. AOP-31  "Spurious Containment Isolation" entry conditions?
    EK-1126, "CIS INITIATED" with Containment pressure and radiation levels normal.
  67. AOP-31 "Spurious Containment Isolation" automatic actions?
    • Containment Isolation Valves close
    • Safety Injection initiated (CHP only)
    • Containment Spray initiated (CHP only)
    • Reactor trip (CHP only)
  68. AOP-31 "Spurious Containment Isolation" Rx trip criteria?
    Containment Isolation caused by Containment High Pressure signal (CHP)
  69. AOP-31 "Spurious Containment Isolation" mitigating actions?
    • 1. Eliminate leakage path via RV-2006, Letdown Heat Exch E-58 Inlet Safety Relief.
    • 2. Restore CCW to Containment if flow was isolated for less than 10 minutes.
    • 3. Reset Containment High Pressure circuits.
    • 4. Reset Safety Injection Actuation System circuits.
    • 5. Position Containment Isolation Valves to desired position.
  70. AOP-31 "Spurious Containment Isolation" Immediate actions?
    1. VERIFY Containment Isolation is caused by a CHP signal.

       RNO  1.1 GO TO Operator Actions Step 1.

    • a. ENSURE the Reactor is tripped.
    • b. REFER TO EOP-1.0, "Standard Post-Trip Actions."
  71. How do you tell if the loss of a Preferred AC bus is due to an inverter failure or a bus fault?
    NOTE: Loss of the Preferred AC bus due to the Inverter Output breaker opening indicates it is likely that there is a fault on the Preferred AC bus.

    NOTE: Loss of the Preferred AC bus due a tripped DC Input breaker when the AC Output breaker remains closed indicates that the Preferred AC bus is likely free of a fault.
  72. Why do we close CV-2003,2004,2005 letdown orifice stop valves on an inadvertent containment isolation signal?
    CV-2009, letdown to containment isolation valve, closes and you would lift RV-2006 @ 600 psig letdown pressure
  73. Which containment isolation valves do not have latching circuits?
    • CCW supply and return valves
    • -CV-0910, CV-0911, CV-0940
    • FRVs
    • -CV-0701/0703
    • MFR bypass valves
    • -CV-0734/0735
  74. AOP-32 "Loss of Containment Integrity" entry conditions?
    • Obvious breach in Containment
    • Inoperable Containment Isolation valve(s)
    • Failed interlock mechanism on a Containment Air Lock
    • Inoperable Containment Air Lock door(s)
  75. AOP-23 "Primary Coolant Leak" Reactor trip criteria?
    • Unidentified PCS leak rate greater than 10 gpm
    • Non-isolable intersystem leak identified
  76. AOP-23 "Primary Coolant Leak" entry conditions?
    PCS leak rate greater than 0.15 gpm unidentified calculated in accordance with DWO-1, "Operator's Daily/Weekly Items Modes 1, 2, 3, and 4"

    • Symptom of PCS leak in conjunction with any of the following:
    •   Unexplained drop in VCT level 
    •   Unexplained rise in Containment pressure, temperature, humidity, radiation and/or sump level
    •   Unexplained Charging and Letdown Flow Mismatch
    •   EK-0201, "CONT GAMMA RIA-2321 HIGH"
    • (400 R/hr) 
    •   EK-0202, "CONT GAMMA RIA-2322 HIGH" (400 R/hr)
    •   EK-0213, "CONT GAMMA RIA-2321 ALERT" (40 R/hr)
    •   EK-0214, "CONT GAMMA RIA-2322 ALERT" (40 R/hr)
    •   EK-0702, "RELIEF VALVE 2006 DISCH HI TEMP" (200°F)
    •   EK-0731, "QUENCH TANK HI TEMP" (150°F)
    •   EK-0732, "QUENCH TANK HI PRESS" (10 psig)
    •   EK-0733, "QUENCH TANK HI-LO LEVEL" (HI-79%, LO-67%)
    •   EK-0743 "PRESSURIZER PWR OPERATED RELIEF VALVE DISCHARGE HI TEMP" (180°F)
    •   EK-0744, "PRESSURIZER SAFETY VALVE RV-1039 DISCH HI TEMP" (180°F)
    •   EK-0745, "PRESSURIZER SAFETY VALVE RV-1040 DISCH HI TEMP" (180°F)
    •   EK-0746, "PRESSURIZER SAFETY VALVE RV-1041 DISCH HI TEMP" (180°F)
    •   EK-1172, "COMPONENT CLG SURGE TANK T-3 HI-LO LEVEL" (HI-93%, LO-35%)
    •   EK-1350, "CONTAINMENT SUMP HI-HI LEVEL"  (12" or 10% from the bottom)
    •   EK-1351, "CONTAINMENT SUMP HI LEVEL"  (5" from the bottom, Elevation 585.41')
    •   EK-1362, "CONTAINMENT PRESSURE OFF NORMAL"  (0.8 psig)
    •   EK-1373, "SV AND/OR PORV OPEN"
    •   EK-1509, "PRI SYSTEM DRAIN TANK T-74 HIGH PRESSURE" (7 psig)
  77. AOP-23 "Primary Coolant Leak" automatic actions?
    • P-55A Charging Pump speed rises
    • Charging Pumps P-55B and/or P-55C start
  78. AOP-24 " Steam Generator Tube Leak" entry conditions?
    • Primary to Secondary leakrate greater than or equal to 0.003 gpm as calculated per one of the following:
    •   Chemistry Procedure CH 3.31 “Primary to Secondary Leak Rate Determination.”
    •   PPC page 540, “Primary to Secondary Leakrate.”

    • Adverse trends in any of the following:
    •   RIA-0631, Off Gas Monitor Radiation Indicator
    •   RIA-0707, Steam Generator Blowdown Process Monitor
    •   RIA-2323, Main Steam Safety and Dump Valve Discharge
    •   RIA-2324, Main Steam Safety and Dump Valve Discharge
    •   RIA-2325, Particulate Stack Monitor Remote Readout
    •   RIA-2326, Normal Range Noble Gas Stack Monitor
    •   RIA-2327, High Range Noble Gas Stack Monitor
  79. AOP-24 "Steam Generator Tube Leak" automatic actions?
    • P-55A, Charging Pump speed rises
    • P-55B and/or P-55C, Charging Pumps start (if tube leakage plus letdown flow exceeds the capacity of P-55A)
    • Steam Generator Blowdown Valves close (if RIA-0707, Steam Generator Blowdown Monitor setpoint is exceeded)
  80. AOP-24 "Steam Generator Tube Leak" Reactor trip criteria?
    A sustained rise in the CVCS charging rate is needed to maintain Pressurizer level at program level 

    PCS makeup requirements exceed those expected for the rate of power reduction in progress

    Radiation monitor response exceeds those expected for the rate of power reduction in progress
  81. What common effect does the loss of Y-10 or Y-20 have on the main feedwater system?
    FWP recirc valves fail to open causing power and S/G water level transient
  82. What common effect does a loss of Y-10 or Y-20 have on the selected loop Tave?
    Loss of TYT-0100 or TYT-0200 respectively will cause it to fail high, which will affect Tave and ADV input and displays. This will affect the input to the PZR level controller.
  83. Loss of what preferred AC bus will cause the ADVs to be inoperable?
    Y-10
  84. What alternate action is necessary following a loss of Y-10 to compensate for the loss of RIA-0631?
    Local sampling per the ODCM
  85. Following a loss of Y-10 or Y-40 will both channels of safety injection automatically initiate on containment high pressure?
    No, left or right (respectively) channel SIS must be manually initiated on a valid CHP
  86. Following a loss of Y-10, will both channels of safety injection automatically initiate on pressurizer low pressure?
    Yes, both channels will operate normally with Y-10 lost and a low pressurizer pressure (1605 psia) signal, manual initiation is not necessary.
  87. Loss of which preferred AC bus causes us to manually sequence rods?
    Y-20
  88. Following loss of Y-10 or Y-40 will both channels of CIS automatically initiate on Containment High Pressure (CHP)?
    No, the right or left channel of CIS and SIAS must be manually initiated on a valid CHP.
  89. On a loss of Y-10, Y-20, Y-30, or Y-40 will the containment spray pumps all start with a valid CHP condition?
    • No, some of the spray pumps will not auto start with the loss of any preferred AC bus.
    • For a loss of Y-20 and Y-30 this is due to the SIS signal being necessary to enable the spray pumps to start.
  90. If the PCS must be placed on shutdown cooling with either Y-30 or Y-40 not available, what interlocks must be defeated to allow entry into the S/D cooling mode?
    • I and C must install a jumper around PS--104A or PS-0104B to allow opening of MO-3015 and MO-3016 respectively.
    • Also electrical maintenance must provide alternate power to the SIAS left channel block circuit.
  91. Following the loss of any preferred AC bus, explain the reason for disarming LTOP prior to restoring power to the bus?
    By closing the PRV and ensuring LTOP is in the defeat position, we can be sure the PORV will not open due to a false signal.
  92. Loss of which preferred AC bus would cause the P-8C AFW pump to trip?
    Loss of Y-20 will cause the low suction pressure trip to actuate for P-8C.
  93. Assuming an all rods out initial condition with a loss of Y-20, what is available to monitor control rod position following a trip?
    • SPI on the PPC
    • Lose PIP and LED displays
    • Matrix will indicate rods at an intermediate position
  94. Following a loss of Y-20, what means are available to monitor control rod PDIL and PPDIL?
    SPI on the PPC and PPC alarms
  95. How does the loss of Y-20 or Y-30 affect the operability of 1-1 or 1-2 diesel generator with the plant at power?
    The diesels will be inoperable due to the loss of the normal shutdown sequencers.
  96. Following the loss of Y-20 or Y-30, will associated channel of Safety Injection equipment automatically initiate on pressurizer low pressure or CHP?
    • No, loss of Y-20 will prevent right channel SIAS equipment from starting automatically.
    • Loss of Y-30 will prevent the left channel equipment from starting automatically.
  97. Loss of what will cause the turbine bypass valve to be inoperable?
    Y-01
  98. What effect does a loss of Y-01 have on the operating main feedwater pumps?
    Feed pumps ramp to minimum speed, could trip on low S/G water level.
  99. Following a loss of Y-01, explain why it is necessary to direct PCP controlled bleed off to the containment sump?
    VCT outlet is closed, so you would overfill the VCT.
  100. Following a loss of Y-01, what action is necessary when pressurizer level lowers to 36%?
    Deenergize PZR heaters.
  101. Following a loss of Y-01, why may it become necessary to secure PCPs?
    Lose indications and if only 1 CCW pump is operating you might not have enough cooling due to letdown CCW flow increasing.
  102. Why is it necessary to test the control room alarm panels every 15 minutes following a loss of Y-01?
    Because you lost your "DC failure alarm"
  103. Following a loss of Y-01, how can you determine charging flow?
    Must send an AO to FI-0212A in the aux building hallway.
  104. If shutdown cooling were in service and we have a loss of Y-01, what is the appropriate procedure to enter?
    AOP-30 "Loss of Shutdown Cooling"
  105. Following a loss of Y-01, what source is supplying suction to the charging pumps?
    SIRWT is supplying due to VCT level failing low and you swap suctions at 7.9% level in the VCT.
  106. What are the 2 functions of the containment building?
    • Provide ample biological shielding during both normal and accident conditions
    • Minimizes the release of radioactive material to the public in the event of an accident.
  107. When is containment required to be operable?
    Modes 1,2,3,4
  108. Why does AOP-32 "Loss of Containment Integrity" direct you to close the letdown orifice stop valves CV-2003,CV-2004, CV-2005?
    When we have a CIS to prevent lifting letdown relief RV-2006 at 600 psig due to letdown being isolated.
  109. On a loss of power to the controllers for CV-3006/CV-3025, what happens to the controllers when power is restored?
    • If power is lost to the controllers at C-02 for < 2 seconds
    • -controllers return to pre-loss of power state
    • If power lost to controllers at C-02 for > 2 seconds
    • -controllers fail to manual
    • -CV-3025 fails closed
    • -CV-3006 fails open
    • If power lost to controllers at C-33, and then restored
    • -controllers return to auto and the valves reposition to the position specified by the control room controllers
    • -initially CV-3025 fails closed
    • -initially CV-3006 fails open
  110. AOP-30 "Loss of Shutdown Cooling" Equipment trip criteria?
    • Emergency Diesel Generator 1-1(1-2), using the overspeed trip /reset
    •   Jacket water temperature greater than or equal to 195°F on TI-1482(1492)
    •   Lube oil temperature greater than or equal to 200°F on TI-1478(1488) 

    • Operating LPSI pump P-67A OR P-67B
    •   Severe LPSI Pump cavitation not corrected by throttling Shutdown Cooling flow
    •   Shutdown Cooling flow less than 170 gpm
  111. What is reduced inventory?
    < 623' elevation
  112. Why are the LPSI injection MOVs, in conjunction with CV-3006, used to throttle flow instead of just throttling CV-3006?
    Throttling the loop injection valves prevents LPSI pump runout due to CV-3006 failing open on a loss of Y-01. Throttling CV-3006 provides the differential pressure required to force flow through the SDC heat exchangers.
  113. AOP-30 "Loss of Shutdown Cooling" entry conditions?
    • Shutdown Cooling System initially in service and any of the following:
    •   Unexpected EK-1162 "LPSI Pump Low Discharge Pressure Alarm" (120 psig)
    •   Unexpected LPSI pump trip
    •   Uncontrolled PCS temperature rise
    •   Entry has been directed by another procedure
  114. AOP-5 "Control Rod Drop" immediate actions/Rx trip criteria?
    • IF any of the following conditions exist, THEN TRIP the Reactor:
    •  One or more dropped or misaligned Control Rod occurring while the Reactor is critical and less than 15% power
    •  Two or more dropped or misaligned Control Rods with Reactor greater than or equal to 15% power
    •  More than one uncoupled Control Rod
    •  Unanticipated or anomalous Reactor behavior
  115. AOP-5 "Control Rod Drop" auto actions?
    Possible TM/LP or Variable High Power trip
  116. AOP-5 "Control Rod Drop" entry conditions?
    • EK-0948, "DROPPED ROD"
    • AND
    • Any rod bottom limit switch
    • OR
    • Dropped rod indication on PPC page 410

    • Misaligned control rod (greater than 19 inches)
    • Uncoupled control rod
    • Reactor Engineering discretion
  117. What is required by AOP-5 "Control Rod Drop" when quadrant power tilt is > 15%?
    REDUCE Reactor power to less than or equal to 25% by boration within 4 hours. Refer to Technical Specifications LCO 3.2.3.
  118. What is required by AOP-5 "Control Rod Drop" when quadrant power tilt is > 10% but </= 15%?
    REDUCE Reactor power to less than or equal to 50% by boration within 4 hours. Refer to Technical Specifications LCO 3.2.3.
  119. What is required by AOP-5 "Control Rod Drop" when quadrant power tilt is > 5% but </= 10%?
    NOTIFY Reactor Engineering to verify Total Radial Peaking Factors are within the limits of Technical Specifications LCO 3.2.2 within 2 hours and once per 8 hours thereafter.
  120. AOP-11 "Loss of 480V Buses" entry criteria?
    • EK-0506, "STA PWR TRANSF 13 BKR 152-108 TRIP OR UV"
    • EK-0531, "STA PWR TRANS NO 11 & 19 152-115 TRIP OR UV"
    • EK-0533, "STA PWR TRANS NO 12 & 20 152-201 TRIP OR UV"
    • EK-0536, "STA PWR TRANS NO 14, BKR 152-304 TRIP OR UV"
    • EK-0537, "MCC 1/21-23/25 BKR 52-1906 BKR 52-1112 BKR 52-1901 TRIP"
    • EK-0538, "MCC NO 7 BREAKER 52-1103 TRIP"
    • EK-0539, "MCC 2/22-24/26 BKR 52-2006 BKR 52-1214 BKR 52-2001 TRIP"
    • EK-0540, "MCC NO 8 BKR 52-1201 TRIP"
  121. AOP-11 "Loss of 480V Buses" mitigating strategy?
    • 1. Start opposite train equipment on a loss of power.
    • 2. Reenergize bus when fault has been isolated.
    • 3. Protect opposite train equipment.
  122. When do you get the spent fuel pool low level alarm?
    • 646" elevation
    • This is 1 foot above SFP pump suction piping
  123. AOP-26 "Loss of Spent Fuel Pool Cooling" entry conditions?
    • EK-1307, "FUEL POOL CLG PUMPS P-51A AND/OR P-51B TRIP"
    • AND
    • P-51A or P-51B aligned to spent fuel pool cooling

    EK1309, "SPENT FUEL POOL HI/LO LEVEL" (LO-Elevation 646')

    • Spent Fuel Pool Level lowering as indicated on:
    •  LI-2141, Channel A, SFP Level
    •  OR
    •  LI-2142, Channel B, SFP Level

    TIA_0925_D, "PPC Urgent Alarm, SFP HIGH TEMPERATURE" (140°F)

    TIA_0926_D, "PPC Urgent Alarm, SFP NORTH TILT PIT HIGH TEMPERATURE" (140°F)
  124. AOP-26 "Loss of Spent Fuel Pool Cooling" immediate actions?
    • PERFORM the following:
    • a. PLACE irradiated fuel bundles that are in hoist boxes in one of the following locations:
    •  Bundle's previous location
    •  Bundle's future location
    •  Tilt Machine then tilt horizontal
    •  Reactor Engineer specified location

    • b. LOWER SFP Elevator to Lower Limit.
    • c. MOVE irradiated fuel bundles in Ultrasonic Test Rig or Ultrasonic Fuel Cleaning Rig to their fuel storage rack location.
  125. What must you do to ventilation if you get any of the following:
    SFP area high radiation alarms clear (RIA-5709 or RIA-2313)
    3.1 ENSURE at least one train of Control Room HVAC in EMERGENCY MODE within 20 minutes. Refer to SOP-24, "Ventilation and Air Conditioning System."

    • 3.2 ENSURE CLOSED the following:
    •  a. SFP Hatch Covers OR Track Alley roll up door.
    •  b. All doors around Track Alley (normal use permitted).

    • 3.3 ALIGN Fuel Handling ventilation as follows:
    •  a. ENSURE only one Fuel Handling Area Exhaust Fan, operating.
    •   V-8A
    •   V-8B
    •  b. ENSURE OFF V-7, Fuel Handling Area Supply Fan.
    •  c. PLACE HS-1894 on Panel EC-125 to the REFUEL position.
    •  d. PLACE HS-1893 on Panel EC-125 to EMERGENCY TRIP position.
  126. What do you do if PORVs inadvertently opened and/or failed to properly close when below the actuation setpoint?
    • Close the associated block valve
    • Continuously monitor PZR pressure to ensure LTOP limits are not exceeded
  127. What do you do to PCPs if PZR pressure lowers to <200 psia on PI-0104(narrow range)?
    Trip all PCPs
  128. What do you do to PCPs if PZR pressure lowers to 235 psia on PI-0104(narrow range)?
    If pzr pressure is <235 psia for > 1 minute, trip the PCPs.
  129. AOP-28 "Pressurizer Pressure Control Malfunctions" entry conditions?
    • EK-0753, "PRESSURIZER PRESSURE OFF NORMAL HI-LO" (HI-2110 psia, LO-1975 psia)
    • EK-0754, "PRESSURIZER PRESSURE OFF NORMAL HI-LO" (HI-2110 psia, LO-1975 psia)
    • EK-1373, "SV AND /OR PORV OPEN"
    • Charging or Letdown System malfunctions during solid plant operation
  130. AOP-28 "Pressurizer Pressure Control Malfunctions" auto actions?
    Possible reactor trip
  131. AOP-28 "Pressurizer Pressure Control Malfunctions" Reactor/Equipment trip criteria?
    • Reactor Trip
    •  Either Pressurizer Spray Valve failed open AND Pressurizer pressure not being maintained.

    • Equipment Trip
    •  CV-1057 Pressurizer Spray Valve failed open.
    •  a. Trip P-50A and P-50B, PCPs.
    •  b. Pressurizer pressure not being maintained.
    •      Trip P-50D, PCP.
    •  
    •  CV-1059 Pressurizer Spray Valve failed open.
    •   a. Trip P-50C and P-50D, PCPs.
    •   b. Pressurizer pressure not being maintained.
    •      Trip P-50A, PCP.

    •  Operating PCPs
    •   Pressurizer pressure less than 235 psia for greater than 1 minute, on PI-0104, Narrow Range Pressurizer Pressure Ind.
    •   Pressurizer pressure less than 200 psia on PI-0104, Narrow Range Pressurizer Pressure Ind.
  132. What happens to the ADVs and TBV if the inservice Tave signal (TYT-0100/0200) is failed high and you recieve a turbine trip?
    ADVs and the TBV get a quick open signal.
  133. AOP-27 "Tave/Tref Controller Failure" entry conditions?
    • EK-0967, "LOOP 1-LOOP 2 T AVE DEVIATION" (5°F difference)
    • AND
    • EK-0968, "LOOP 1 T AVE /T REF GROSS DEVIATION" (5°F difference)
    • AND/OR
    • EK-0969, "LOOP 2 T AVE /T REF GROSS DEVIATION" (5°F difference)
  134. AOP-4 "Uncontrolled Primary Coolant System Boron Dilution" auto actions?
    Possible reactor trip
  135. AOP-4 "Uncontrolled Primary Coolant System Boron Dilution" entry conditions?
    • Unexpected rise in power range, wide range and/or source range nuclear instrumentation in conjunction with any of the following:
    •   Unexpected rise of audible count rate
    •   Unexpected VCT level rise
    •   Unexpected lowering of Letdown Temperature as indicated on TIC-0203, Low Pressure Letdown Flow Temp Control
  136. What are the AOP-38 "Acts of Nature" entry conditions?
    Shift Manager Discretion

    Lake level above 585 feet

    • High Wind
    •   Murray and Trettel Notification Form, Winds Category; probability factor of 6 or more for wind gusts over 58 mph
    •   Wind speeds greater than or equal to 40 mph lasting 1 hour or longer, or winds of greater than 58 mph for any duration as measured by the Met Tower (MWS10)
    •   National Weather Service has issued a high wind warning for any of the following areas (forecasted within the next 72 hours):
    •    Van Buren County
    •    Berrien County
    •    Allegan County
    •    Waters of Lake Michigan to the west of the Palisades Nuclear Plant

    • Extreme Wind
    •    Murray and Trettel Notification Form, Winds Category; probability factor of 6 or more for wind gusts over 70 mph
    •    Sustained (greater than or equal to 15 minutes) wind speed greater than or equal to 70 mph as measured by the Met Tower (MWS10 or MWS60)

    •  Tornado
    •    Tornado sighting in the Owner Controlled Area
    •    National Weather Service Tornado Warning for Van Buren County
    •    National Weather Service Tornado Watch for Van Buren County

    Sustained Heavy Rain Rain in excess of the storm drain capacity causing exterior flooding or creating a high runoff flow that threatens to enter plant structures or equipment (eg, turbine building or screenhouse, fuel oil storage tank) at a rate that could affect the operation of plant equipment

    • Heavy Snowfall or Blizzard Conditions
    •    National Weather Service Notification for Van Buren County - winter storms with sustained or frequent winds of 35 mph or higher with considerable falling and/or blowing snow that frequently reduces visibility to 1/4 of a mile or less. These conditions are expected to prevail for a minimum of 3 hours
    •   Van Buren County Officials - notification that attempts to keep major roadways clear have been suspended

    • Earthquake
    •    Indication of an earthquake felt by people in the Owner Controlled Area

    • Geo-Magnetic Storm Disturbance
    •   Notification by Independent System Operator (ISO), Balancing Authority or Transmission Operator of a predicted Geo-Magnetic Storm Disturbance with a K-index greater than or equal to 7
  137. When does AOP-7 "Rapid power reduction" direct you to adjust your rate of power reduction?
    • IF any of the following are in alarm during
    • the rapid power reduction, THEN ADJUST
    • the rate of power reduction as necessary to
    • correct the condition:
    • -a. EK-0968, “Loop 1 TAVE/TREF Gross
    • Deviation.”
    • -b. EK-0969, “Loop 2 TAVE/TREF Gross
    • Deviation.”
    • -c. EK-0753, “Pressurizer Pressure Off
    • Normal HI-LO.”
    • -d. EK-0761, “Pressurizer Level HI-LO.”
    • -e. EK-0961, “Steam Gen E-50A HI Level.”
    • -f. EK-0962, “Steam Gen E-50A LO
    • Level.”
    • -g. EK-0963, “Steam Gen E-50B HI Level.”
    • -h. EK-0964, “Steam Gen E-50B LO
    • Level.”
  138. AOP-38 "Acts of Nature" Rx trip criteria?
    • Lake water starts to enter the Turbine Building/Screen House
    • Water level at Condensate Pump thrust bearing
    • Water level greater than or equal to 9 inches in the vicinity of electrical buses 1A, 1B, and 1E
  139. AOP-38 "Acts of Nature" equipment trip criteria?
    • Condensate Pump
    •  Water level at Condensate Pump thrust bearing

    • Electrical Buses 1A, 1B, 1E
    •  Water level greater than or equal to 9 inches in the vicinity of electrical buses 1A, 1B, and 1E
  140. What is lost if you lose D-11-1?
    • Generator Breakers won’t open must use jumper to open
    • A MSIV won’t close from the Control Room. Must use B MSIV Control Room Switch.
    • 1-1 EDG won’t start on undervoltage must manually start from Control Room
    • A/C/F Bus won’t fast transfer
    • P-8B, Steam Driven Aux Feed pump, starts and feeds both SG’s Lower Rx power to <98%
    • Letdown becomes isolated, CV-2009, Containment Isolation Valve for letdown, fails close which causes a PCS leak through RV-2006
    • -Close CV-2003/4/5, Letdown Orifice Stop Valves
    • -Control Pressurizer Level
    • -Control Pressurizer Pressure
    • Primary Coolant Pumps Controlled Bleedoff, CV-2083, fails closed must open CV-2191, Primary Coolant Pump Controlled Bleedoff Stop.
  141. What is lost if you lose D-11-2?
    • 1-1 EDG output breaker won’t auto close and Automatic load sequencing will be lost.
    • CV-1212, Service Air Isolation, fails closed so you need to ensure people are not on breathing air.
    • Air Compressors lose standby auto start feature
    • Ability to trip A MFP from the Control Room
    • CCW to SDC heat exchangers fail open so standby starts of CCW pumps may occur.
  142. What is lost if you lose D-11A?
    • 1-1 EDG control power so you can’t start, load, or control the EDG
    • C Bus control Power
    • EC-150, Aux Hot Shutdown panel, loses power
    • P-8A, Aux Feed Water Pump, control power
  143. What do you lose if D-21-1 is lost?
    • Turbine won’t trip, you must trip the turbine locally or close MSIV’s
    • B MSIV won’t close from the Control Room, you must use A MSIV Control Room Switch.
    • B/D/E/G lose fast transfer and breaker control power
    • Letdown becomes isolated because the orifice stop valves fail closed
  144. What do you lose if D-21-2 is lost?
    • You must trip the reactor because you lose Non Critical Service Water
    • B MFP won’t Trip from the Control Room
    • 1-2 EDG output breaker won’t auto close and Automatic load sequencing will be lost
    • Most Control Room Alarm Panels
  145. What do you lose if D-21-A is lost?
    • P-8C, Aux Feed Water Pump, control power
    • 1-2 EDG control power so you can’t start, load, or control the EDG
    • D Bus Control Power
  146. What are the AOP-39 "Internal Plant Flooding" entry criteria?
    • Receipt of any of the following alarms with verification of flooding
    •  EK-28, "(EC-47) FIRE SYSTEM FLOW SCHEME ALARMS"
    •  EK-0171, "CONDENSATE PUMP ROOM FLOODING" (572’ elevation)
    •  EK-1352, "EAST SFGRDS ROOM SUMP HI/PANEL UV" (14.2% on LI-1108)
    •  EK-1353, "WEST SFGRDS ROOM SUMP HI/PANEL UV" (14.2% on LI-1107)
    •  EK-1354, "TURBINE FLR SUMP HI LEVEL" (50" above bottom of sump)

    • Flooding observed in any of the following areas:
    •  East Engineered Safeguards Room
    •  West Engineered Safeguards Room
    •  Auxiliary Feedwater Pump Room
    •  Condensate Pump Room
    •  Component Cooling Water Pump Room
    •  Auxiliary Building
    •  Bus 1C Switchgear Room
    •  Bus 1D Switchgear, Electrical Equipment, North Cable Penetration Room
    •  Cable Spreading Room
    •  EDG 1-1 Room
    •  EDG 1-2 Room
    •  Screen House
    •  Turbine Building
  147. What are the AOP-39 "Internal Plant Flooding" reactor and equipment trip criteria?
    • Reactor Trip
    •  Water depth approaches either operating Condensate Pump thrust bearings (height of security switch on AFW Pump Rm door)
    •  Water depth exceeds 5 inches in Bus 1C area
    •  Erratic equipment operation during Bus 1C area flooding
    •  Water depth exceeds 5 inches in Bus 1D area
    •  Erratic equipment operation during Bus 1D area flooding
    •  Erratic equipment operation during Cable Spreading area flooding
    •  Water depth greater than or equal to 9 inches in area of Buses 1A, 1B, 1E

    Equipment Trip

    • Condensate Pump
    •  Water level at Condensate Pump thrust bearing (height of security switch on AFW Pump Rm door)

    • Electrical Buses 1A, 1B, 1E
    •  Water depth greater than or equal to 9 inches in area of Buses 1A, 1B, 1E
  148. What automatic actions are associated with AOP-39 "Internal Plant Flooding"?
    • P-72A, P-72B, East ESG Room Sump Pumps start (first pump starts at 14.2 %, second pump starts at 15%, pump auto start blocked if CHR present)
    • P-73A, P-73B, West ESG Room Sump Pumps start (first pump starts at 14.2 %, second pump starts at 15%, pump auto start blocked if CHR present)
    • P-45A, P-45B, Turbine Building Sump Pumps start (first pump starts at 32", second pump starts at 44")
  149. What are the entry conditions of AOP-22 "Pressurizer Level Control Malfunctions"?
    • EK-0735, "CHARGING LO FLOW"
    • EK-0761, "PRESSURIZER LEVEL HI-LO"
    • EK-0763, "PRESSURIZER LEVEL CH "A" LO-LO"
    • EK-0764, "PRESSURIZER LEVEL CH "B" LO-LO"
    • EK-0769, "PRESSURIZER HIGH LEVEL"
    • Loss of level control program output signal causing a deviation from the calculated level control setpoint
  150. What are the automatic actions of AOP-22 "Pressurizer Level Control Malfunctions"?
    • 1. Pressurizer High Level
    •  CV-2004 and CV-2005, Letdown Orifice Stop Valves, open
    •  P-55B and P-55C, Charging Pumps, stop
    •  P-55A, Charging Pump, operates at minimum speed (33 gpm)
    •  Pressurizer Backup Heaters energize (in Auto position only)

    • 2. Pressurizer Low Level
    •  CV-2004 and CV-2005, Orifice Stop Valves, close
    •  P-55B and P-55C, Charging Pumps, start
    •  P-55A, Charging Pump operates at maximum speed (53 gpm)

    • 3. Pressurizer Low Low Level
    •  All Pressurizer heaters trip
    •  CV-2003, Letdown Orifice Stop Valve closes
  151. What percent EESG/WESG sump level is floor level?
    27.5%
  152. How many gallons per percent sump level in EESG/WESG?
    19 gallons/% less than 27.5%
  153. AOP-22 "Pressurizer Level Control Malfunctions" Reactor trip criteria?
    Pressurizer level less than 30%
  154. What is the mitigating strategy of AOP-22 "Pressurizer Level Control Malfunctions"?
    • 1. Respond to Pressurizer level control not operating correctly.
    • 2. Secure Charging flow due to gas binding and perform necessary repairs.
    • 3 Operate Charging and Letdown as needed to maintain/restore Pressurizer level.
  155. AOP-29 "Primary Coolant Pump Abnormal Conditions" entry criteria?
    • Any of the following alarms received during steady state conditions with associated PCP operating:
    •  EK-0907, "PRI COOLANT PUMP P-50A HI TEMP OVERLOAD"
    •  EK-0908, "PRI COOLANT PUMP P-50B HI TEMP OVERLOAD"
    •  EK-0909, "PRI COOLANT PUMP P-50C HI TEMP OVERLOAD"
    •  EK-0910, "PRI COOLANT PUMP P-50D HI TEMP OVERLOAD"
    •  EK-0913, "PRI COOLANT PUMP VIB ALERT/MON TROUBLE"
    •  EK-0914, "PRI COOLANT PUMP VIBRATION DANGER"
    •  EK-0925, "PRI COOLANT PUMP P-50A OIL LEVEL HI-LO"
    •  EK-0926, "PRI COOLANT PUMP P-50B OIL LEVEL HI-LO"
    •  EK-0927, "PRI COOLANT PUMP P-50C OIL LEVEL HI-LO"
    •  EK-0928, "PRI COOLANT PUMP P-50D OIL LEVEL HI-LO"
    •  EK-0931, "PRI COOLANT PUMP P-50A, CLG WTR LO FLOW"
    •  EK-0932, "PRI COOLANT PUMP P-50B, CLG WTR LO FLOW"
    •  EK-0933, "PRI COOLANT PUMP P-50C, CLG WTR LO FLOW"
    •  EK-0934, "PRI COOLANT PUMP P-50D, CLG WTR LO FLOW"
    •  EK-0937, "PRI COOLANT PUMP P-50A BACKSTOP OIL LOW FLOW"
    •  EK-0938, "PRI COOLANT PUMP P-50B BACKSTOP OIL LOW FLOW"
    •  EK-0939, "PRI COOLANT PUMP P-50C BACKSTOP OIL LOW FLOW"
    •  EK-0943, "PRI COOLANT PUMP P-50A, SEAL LEAKAGE FLOW LOW"
    •  EK-0944, "PRI COOLANT PUMP P-50B, SEAL LEAKAGE FLOW LOW"
    •  EK-0945, "PRI COOLANT PUMP P-50C, SEAL LEAKAGE FLOW LOW"
    •  EK-0946, "PRI COOLANT PUMP P-50D, SEAL LEAKAGE FLOW LOW"
    •  EK-0949, "PRI COOLANT PUMP P-50A SEAL PRESS OFF NORMAL"
    •  EK-0950, "PRI COOLANT PUMP P-50B SEAL PRESS OFF NORMAL"
    •  EK-0951, "PRI COOLANT PUMP P-50C SEAL PRESS OFF NORMAL"
    •  EK-0952, "PRI COOLANT PUMP P-50D SEAL PRESS OFF NORMAL"
    •  EK-0955, "PRI COOLANT PUMP P-50A SEAL HEAT EX HI TEMP LEAKAGE HI FLOW"
    •  EK-0956, "PRI COOLANT PUMP P-50B SEAL HEAT EX HI TEMP LEAKAGE HI FLOW"
    •  EK-0957, "PRI COOLANT PUMP P-50C SEAL HEAT EX HI TEMP LEAKAGE HI FLOW"
    •  EK-0958, "PRI COOLANT PUMP P-50D SEAL HEAT EX HI TEMP LEAKAGE HI FLOW"
    •  EK-0959, "PRI COOLANT PUMPS CONT BLEEDOFF HDR HI PRESS"
    •  EK-0960, "PRI COOLANT PUMPS CONT BLEEDOFF HDR HI-HI PRESS"

    • NOTE: Rising activity, level, temperatures, or flow on the following may be indications of an intersystem leak from the Primary Coolant System into the Component Cooling Water System.
    •  RIA-0915, CCW Radiation Monitor for rise in activity
    •  LIA-0917, CCW Surge Tank T-3 Level
    •  LIA-0920, CCW Surge Tank T-3 Level
    •  LTVR-0901 CH 10 (TIA-0960A), P-50A Cooling Water Out Temp
    •  LTVR-0901 CH 20 (TIA-0960B), P-50B Cooling Water Out Temp
    •  LTVR-0901 CH 30 (TIA-0970A), P-50C Cooling Water Out Temp
    •  LTVR-0901 CH 40 (TIA-0970B), P-50D Cooling Water Out Temp
    •  REC-C11-02 (FRA-0133), P-50A/B Controlled Bleedoff Flow
    •  REC-C-11-03 (FRA-0143), P-50C/D Controlled Bleedoff Flow
    •  LTVR-0901 CH 03 (TIA-0131A), P-50A Lower Seal Temp
    •  LTVR-0901 CH 13 (TIA-0131B), P-50B Lower Seal Temp
    •  LTVR-0901 CH 23 (TIA-0131C), P-50C Lower Seal Temp
    •  LTVR-0901 CH 33 (TIA-0131D), P-50D Lower Seal Temp
    •  LTVR-0901 CH 4 (TIA-0133A), P-50A Vapor Seal Temp
    •  LTVR-0901 CH 14 (TIA-0133B), P-50B Vapor Seal Temp
    •  LTVR-0901 CH 24 (TIA-0143A), P-50C Vapor Seal Temp
    •  LTVR-0901 CH 34 (TIA-0143B), P-50D Vapor Seal Temp
    •  PR-0130A, P-50A Seal Pressure
    •  PR-0130B, P-50B Seal Pressure
    •  PR-0140A, P-50C Seal Pressure
    •  PR-0140B, P-50D Seal Pressure 

    NOTE: Other indications of imminent PCP failure can include:

    • Erratic or sudden change in motor current reading unless attributed to:
    •   Electric bus supply swap between Startup and Station Power
    •    Motor current lowers as PCS temperature rises
    •    Starting or stopping another PCP, particularly in the same loop
    •  
    • Rapid or unexplained rise in motor bearing temperature unless attributed to:
    •    Upthrust temperature rising when rising PCS pressure lifts the impeller (downthrust temperature will lower simultaneously). This thrust shift will occur at approximately 1000 psia.
    •    Bearing temperature rise from at rest values to normal operating ranges

     A sudden drop in PCS flow, unless attributable to stopping another PCP

    •  Continuing rise in indicated vibration, unless attributable to:
    •    Normal indicator fluctuation (trend the mean readings, not the peaks)
    •    Starting or stopping of other PCPs
    •  
    • One vibration monitor axis failing high and the other axis failing low

    Abnormal noises or tangible vibration changes reported by personnel near the pump
  156. AOP-29 "Primary Coolant Pump Abnormal Conditions" Reactor and equipment trip criteria?
    • Reactor Trip
    •  Loss of CCW AND:
    •    Any PCP bearing temperature exceeds setpoint
    •    - Upper Guide 175°F
    •    - Lower Guide 175°F
    •    - Upper Thrust 185°F
    •    - Down Thrust 175°F
    •    Any PCP Lower Seal temperature exceeds 185°F
    •    Any PCP Vapor Seal temperature exceeds 185°F

     Any PCP vibration is greater than 29 mils 

     Imminent PCP failure corroborated by other indications

    • Equipment Trip
    •   Affected Operating Primary Coolant Pump(s)
    •   Any Reactor Trip criteria met
  157. What is the AOP-29 "Primary Coolant Pump Abnormal Conditions" mitigating strategy?
    • 1. Determine failed component and/or support system.
    • 2. Restore CCW as needed to maintain cooling per AOP-36, "Loss of Component Cooling."
    • 3. Mitigate Intersystem LOCA using AOP-23, "Primary Coolant Leak," and AOP-29, "Primary Coolant Pump Abnormal Conditions."
    • 4. Determine if PCP operating parameters place the PCP at risk.
    • 5. Remove the PCP from service if needed for equipment protection.
  158. At what PCP vibration value does AOP-29 "Primary Coolant Pump Abnormal Conditions" require tripping the Reactor?
    29 mils
  159. At what PCP vibration value does AOP-29 "Primary Coolant Pump Abnormal Conditions" require performing a GOP-8 plant shutdown?
    25 mils or Channel A and B vibration have risen 2 mils in any 24 hour period.

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