Entry, Trip and Immediate Actions Flashcards

1
Q

What are the entry criteria for AOP-1, Loss of Load?

A

Symptoms: Pressurizer Level and Pressurizer Pressure rising and….

  • Tave/Tref gross deviation alarm
  • Turbine Control Valve Malfunctions

Less Steam Use = Less Heat Removal from PCS

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2
Q

What is the trip criteria for AOP-1, Loss of Load?

A

Turbine valve control in manual and not controlling

  • Trip reactor if greater than 15% power
  • Trip turbine if less than 15% power
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3
Q

What are the entry criteria for AOP-2, Excessive Load?

A

Symptoms: Pressurizer level and pressure lowering and ….

  • Tave/Tref gross deviation
  • Containment Pressure Off Normal (EK-1162) and steam leak in containment
  • Turbine Governor Valve Malfunction (going open)
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4
Q

What are the trip criteria for AOP-2, Excessive Load?

A
  • 1% change in NI, Delta-T or HB Power Steady with unisolable load
    (approx 9% off turbine pwr = 1% reactor pwr)
  • Condition requiring a power reduction at greater than 30% per hour
  • Steam leak in containment and EK-1162 “Containment Pressure Off-Normal Alarm”
  • Turbine Governor Valve Control in manual and not controlling
    • Reactor trip if greater than 15% power
    • Turbine trip if less than 15% power
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5
Q

What are the entry criteria of AOP-3, Main Feedwater Transients?

A
  • MFP Trip
  • MFP Low Suction Flow or Low Discharge Pressure (2500 gpm/800 psig)
  • Condensate Pump Trip
  • Condensate Pump Low Discharge Pressure (390 psig)
  • Heater Drain Pump Trip
  • Steam Generator High Level (84.7%)
  • Steam Generator Low Level (55%)
  • MFW piping rupture, clean-up mod leak, heater drain pump malfunction
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6
Q

What are the trip criteria of AOP-3, Main Feedwater Transients?

A
  • Steam Generator Level at 30% or less
  • Both Main Feed Pumps not operating
  • High Level Overide Circuit Fault
  • EK-0961/EK-0963 SG High Level Alarm in and level 60% and lowering
  • Reactor Power 80% or higher
    • Trip reactor if either MFP Recirc Valve fails open
    • Trip reactor if either MFP trips
  • Reactor Power Less than 15%
    • Trip turbine if SG Level 90% of High Level Override has not lowered flow
    • Trip turbine if SG Level >95%
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7
Q

What Immediate Actions are contained within the AOPs?

A

AOP-3, Main Feedwater Trainsients

  1. As necessary, take manual control of the following to restore SG levels:
  • A/B Feed Reg Valve Controllers (CV-0701/CV-0703)
  • A/B Feed Reg Bypass Valve Controllers (CV-0735/CV-0734)
  • MFP Speed Controllers (HIC-0525 Combined, 526/529 individual
  1. SG High Level Alarm In and level >90% or <60% - trip reactor

AOP-5. Control Rod Drop

Trip the Reactor if

  • 1 or more control rods drop while critical and less than 15% power
  • 2 or more control rods drop while critical and greater than 15% power
  • More than 1 uncoupled control rod
  • Anomalous or unanticipated reactor behavior

AOP-10, Loss of Bus-1E

  • IF loss of Heater Drain Pump(s) cause the Main Feedwater Pump(s) to trip, THEN TRIP the Reactor.

AOP-18, Loss of Left Train DC Power

  • VERIFY the Reactor tripped, if reset.
  • VERIFY the Turbine tripped.
  • TRIP 25F7 and 25H9, Main Generator Output breakers by connecting a jumper between terminals 1 and 10 on Relay 487U, Diff Relay-Unit Differential

AOP-19, Loss of Right Train DC Power

  • VERIFY the Reactor tripped, if reset.
  • VERIFY the Turbine tripped. If not you must trip by placing HS-0510A, Main Steam from Steam Generator ‘A’ to CLOSE or do it manually at the front standard
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8
Q

What is the entry criteria for AOP-4, Uncontrolled Primary Coolant System Boron Dilution Event?

A

Rise in power range, source range,/wide range NI’s that was not expected and is in conjuction with….

  • 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
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9
Q

What are the entry criteria of AOP-5, Control Rod Drop?

A

EK-0948 “Control Rod Drop”

AND

Any Rod Bottom Limit Switch

OR

  • Dropped rod indication on PPC page 410
  • Misaligned Rod by greater than 19 inches
  • Uncouple control rod
  • Reactor Engineering discretion
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10
Q

What are the trip criteria of AOP-5, Control Rod Drop?

A
  • Unanticipated or anomalous reactor behavior
  • More than one uncoupled control rod
  • Reactor Critical and less than 15% power
    • One or more dropped or misaligned Control Rod
  • Reactor Critical and greater than 15% power
    • Two or more dropped or misaligned Control Rods
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11
Q

What are the entry criteria of AOP-6, Loss of Condensor Vacuum?

A

EK-0111 “Vacuum Low” (24 inches Hg)

EK-0110 “Vacuum Pre-Trip” (21.5 inches Hg)

EK-3522 “Clg Wtr Pump P-39A Trip”

EK-3523 “Clg Wtr Pump P-39B Trip”

PT-0763 Turbine Backpress (6 inches Hg)

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12
Q

What are the trip criteria of AOP-6, Loss of Condensor Vacuum?

A
  • Trip Reactor if reactor power >15% and both cooling tower pumps trip or vacuum lowers to 22 inches Hg
  • Trip Turbine if reactor power <15% and both cooling tower pumps trip or vacuum lowers to 22 inches Hg
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13
Q

What are the entry criteria for AOP-7, Rapid Power Reduction?

A

Directed by another AOP

CRS determines that abnormal plant conditions require power reduction at greater than 30% per hour but less than 300% per hour.

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14
Q

What are the trip criteria for AOP-7, Rapid Power Reduction?

A
  • SG Level less than 30% or greater than 95%
  • Pressurizer Level less than 30% or greater than 62.8%
  • Tave less than 525F
  • Rack C, EK-0605, TM/LO Pressure Channel Pre-Trip
  • Rack B, EK-0608, HI Pressurizer Pressure Channel Pre-Trip
  • More than 1 control rod misaligned by >8 inches after adjustment attempted
  • Plant cannot be stabilized followeing termination of power reduction
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15
Q

What are the entry criteria of AOP-8, Loss of C-Bus?

A

Symptoms - loss of left train injection valves/components and ….

  • EK-0515, “2400V 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-0503, “2400V BUS 1C BKR 152-105 TRIP” (if closed)
  • EK-0509, “2400V BUS 1C BKR 152-106 TRIP” (if closed)
  • EK-0532, “BUS 1 C AND/OR 1D OVERCURRENT LOCKOUT”
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16
Q

What are the entry criteria for AOP-9, Loss of D-Bus?

A

Symptoms - loss of right train injection valves/components and ….

  • EK-0515, “2400V 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 1C BKR 152-203 TRIP” (if closed)
  • EK-0532, “BUS 1 C AND/OR 1D OVERCURRENT LOCKOUT”
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17
Q

What are the entry criteria for AOP-10, Loss of Bus 1E?

A

Symptoms - loss of heater drain pumps, P-40B and ….

  • EK-0517, “2400V BUS 1E UNDERVOLTAGE”
  • EK-0522, “BUS FAIL TO TRANSFER”
  • EK-0521, “2400V STANDBY POWER NOT AVAILABLE”
  • EK-0505, “2400V BUS 1E BKR 152-302 TRIP” (if closed)
  • EK-0509, “2400V BUS 1e BKR 152-303 TRIP” (if closed)
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18
Q

What are the trip criteria for AOP-10, Loss of Bus 1E?

A

Loss of Heater Drain Pumps result in Main Feedwater Pump(s) trip

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19
Q

What are the entry criteria for AOP-11, Loss of 480V Buses?

A
  • 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”
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20
Q

What are the entry criteria for AOP-12, Loss of Preferred AC Bus Y-10?

A
  • EK-0543, “PREFERRED AC BUS NUMBER 1 TROUBLE”

AND

  • Channel ‘A’ RPS Trip Ladder Logic Lights Illuminated
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21
Q

What are the trip criteria for AOP-12, Loss of Preferred AC Bus Y-10?

A

If greater than 80% reactor power, trip the reactor as CV-0711, Feed Pump 1A Recirculation Valve fails open.

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22
Q

What are the entry criteria for AOP-13, Loss of Preferred AC Bus Y-20?

A
  • EK-0545, “PREFERRED AC BUS NO 2 TROUBLE”

AND

  • Channel ‘B’ RPS Trip Ladder Logic Lights Illuminated
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23
Q

What are the trip criteria for AOP-13, Loss of Preferred AC Bus Y-20?

A

If greater than 80% power, then trip the reactor as CV-0710, Feed Pump 1B Recirculation Valve fails open.

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24
Q

What are the entry criteria for AOP-14, Loss of Preferred AC Bus Y-30?

A
  • EK-0544, “PREFERRED AC BUS NUMBER 3 TROUBLE”

AND

  • Channel ‘C’ RPS Trip Ladder Logic Lights illuminated
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25
Q

What Automatic Actions are contained within the AOPs?

A

AOP-3, Main Feedwater Transients

  • CV-0608, MS Drain Tank T-5 Level Control ful open on Low Feedwater suction pressure of 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/CV-0703, E-50A/B Feed Regulating Valve, closed by high level override (84.7%).

AOP-4 Uncontrolled PCS Boron Dilution

  • Reactor Trip if TM/LP or High Rate or High SUR exceeded

AOP-5, Control Rod Drop

  • Possible TM/LP or Variable High Power trip

AOP-6, Loss of Condenser Vacuum

  • Turbine Trip at 18-21 inches Hg Main Condensor Vacuum

AOP-8, Loss of C-Bus and AOP-9, Loss of D-Bus

  • 1-1 EDG or 1-2 EDG start

AOP-10, Loss of Bus 1E

  • DEH Controller Power Supply Switches to Battery Backup

AOP-14, Loss of Preferred AC Bus Y-30

  • Reactor Trip if power greater than or equal to 10-4% or less than or equal to 15%

AOP-15, Loss of Preferred AC Bus Y-40

  • Reactor Trip if power greater than or equal to 10-4% or less than or equal to 15%

AOP-16, Loss of Instrument AC Bus Y-01

  • MFP slow to minimum speed
  • Maximum Charging
  • CV-2001, Letdown Stop Valve, closes if HS-2001 in AUTO
  • Charging Pump Suction Shifts to SIRW Tank

AOP-17, Loss of 125 DC Panels

  • Loss of D-10R results in loss of Y-10, the following ocurrs:
  • P-8A/B Aux Feed Pump Controls transfer to Y-30
  • Main Feed control for ‘A’ SG transfers to Y-30
  • P-8B, Steam Driven Aux Feed pump starts.

AOP-18, Loss of Left Train DC Power

  • P-8B, Steam Driven Aux Feed pump starts.

AOP-20 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)
  1. 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)
  1. Pressurizer Low Low Level
  • All Pressurizer heaters trip
  • CV-2003, Letdown Orifice Stop Valve closes

AOP-23, Primary Coolant Leak

  • P-55A Charging Pump speed rises
  • Charging Pumps P-55B and/or P-55C start
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26
Q

What are the entry criteria for AOP-15, Loss of Y-40?

A
  • EK-0546, “PREFERRED AC BUS NUMBER 4 TROUBLE”

AND

  • Channel ‘D’ RPS Trip Ladder Logic Lights illuminated
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27
Q

What is the entry criteria for AOP-18, Loss of Left Train DC Power?

A
  • 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”
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28
Q

What are the entry criteria of AOP-19, Loss of Right Train DC Power?

A
  • 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
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29
Q

What is the entry criteria for AOP-22, Pressurizer Level Control Malfunctions?

A
  • 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
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30
Q

What is the trip criteria for AOP-22, Pressurizer Level Control Malfunctions?

A

Pressurizer level less than 30%, then trip the reactor.

31
Q

What is the entry criteria for AOP-23, Primary Coolant Leak?

A
  • 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” (200F)
  • EK-0731, “QUENCH TANK HI TEMP” (150F)
  • 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” (180F)
  • EK-0744, “PRESSURIZER SAFETY VALVE RV-1039 DISCH HI TEMP” (180F)
  • EK-0745, “PRESSURIZER SAFETY VALVE RV-1040 DISCH HI TEMP” (180F)
  • EK-0746, “PRESSURIZER SAFETY VALVE RV-1041 DISCH HI TEMP” (180F)
  • 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 bottom)
  • EK-1351, “CONTAINMENT SUMP HI LEVEL” (5” from 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)
32
Q

What is the trip criteria for AOP-23, Primary Coolant Leak?

A
  • Unidentified PCS leak rate greater than 10 gpm
  • Non-isolable intersystem leak identified
33
Q

What are the entry criteria of AOP-24, Steam Generator Tube Rupture?

A

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”

OR

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
34
Q

What are the trip criteria of AOP-24, SGTR?

A
  • 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
35
Q

What are the entry criteria of AOP-25, Loss of Refueling Water Accident?

A
  • Visual observation of loss of Refueling Cavity water
  • Steam Generator Dam Monitoring Panel Alarm AND visual observation of loss of Refueling Cavity water
  • Door-950, SFP South Tilt Pit Gate, removed with transfer tube open AND any of the following:
    • EK-1309, “SPENT FUEL POOL HI/LO LEVEL” (LO-Elevation 646’)
    • Visual observation of loss of Spent Fuel Pool water
    • Spent Fuel Pool Level lowering as indicated on: LI-2141, Channel A, SFP Level OR LI-2142, Channel B, SFP Level
36
Q

What are the trip criteria of AOP-25, Loss of Refueling Water Accident?

A

Equipment Trip

  • P-51A/B Spent Fuel Pool Cooling Pumps
    • EK-1308, “FUEL POOL CLG PUMPS DISCH LO PRESS” in alarm
    • Spent Fuel Pool Level Lowering

P-67A/B, LPSI Pumps

  • Shutdown Cooling Flow less than 170 gpm
  • Severe cavitation not corrected by throttling flow
37
Q

What are the Immediate Actions of AOP-25, Loss of Refueling Water Accident?

A
  1. 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
  1. LOWER SFP Elevator to Lower Limit.
  2. MOVE irradiated fuel bundles in Ultrasonic Test Rig or Ultrasonic Fuel Cleaning Rig to their fuel storage rack location.
38
Q

What are the entry criteria for AOP-26, Loss of Spent Fuel Pool Cooling?

A
  1. 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
  2. EK1309, “SPENT FUEL POOL HI/LO LEVEL” (LO-Elevation 646’)
  3. Spent Fuel Pool Level lowering as indicated on: LI-2141, Channel A, SFP Level OR LI-2142, Channel B, SFP Level
  4. TIA_0925_D, “PPC Urgent Alarm, SFP HIGH TEMPERATURE” (140F)
  5. TIA_0926_D, “PPC Urgent Alarm, SFP NORTH TILT PIT HIGH TEMPERATURE” (140F)
39
Q

What are the trip criteria of AOP-26, Loss of Spent Fuel Pool Cooling?

A

None, tripping of pumps on low level is an operator action.

40
Q

What are the Immediate Actions of AOP-26, Loss of Spent Fuel Pool Cooling?

A
  1. 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
  1. LOWER SFP Elevator to Lower Limit.
  2. MOVE irradiated fuel bundles in Ultrasonic Test Rig or Ultrasonic Fuel Cleaning Rig to their fuel storage rack location.
41
Q

What are the entry criteria for AOP-27, T-Ave/T-Ref Controller Failure?

A
  • EK-0967, “LOOP 1-LOOP 2 TAVE DEVIATION” (5F difference)

AND

  • EK-0968, “LOOP 1 TAVE/TREF GROSS DEVIATION” (5F difference)

AND/OR

  • EK-0969, “LOOP 2 TAVE/TREF GROSS DEVIATION” (5F difference)
42
Q

What are the AOP-27, T-Ave/T-Ref Controller Failure trip criteria and immediate actions?

A

None

43
Q

What are the entry criteria of AOP-28, Pressurizer Pressure Control Malfunctions?

A
  1. EK-0753, “PRESSURIZER PRESSURE OFF NORMAL HI-LO” (HI-2110 psia, LO-1975 psia)
  2. EK-0754, “PRESSURIZER PRESSURE OFF NORMAL HI-LO” (HI-2110 psia, LO-1975 psia)
  3. EK-1373, “SV AND /OR PORV OPEN”
  4. Charging or Letdown System malfunctions during solid plant operation
44
Q

What are the Reactor and Equipment Trip Criteria of AOP-28, Pressurizer Pressure Control Malfunctions?

A

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.

  • Trip 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.

45
Q

What are the entry criteria of AOP-29, Primary Coolant Pump Abnormal Conditions?

A
  • EK-0913, “PRI COOLANT PUMP VIB ALERT/MON TROUBLE”
  • EK-0914, “PRI COOLANT PUMP VIBRATION DANGER”
  • EK-0959, “PRI COOLANT PUMPS CONT BLEEDOFF HDR HI PRESS”
  • EK-0960, “PRI COOLANT PUMPS CONT BLEEDOFF HDR HI-HI PRESS”

Any of the alarms associated with the 4 PCPs for:

  • HI TEMP OVERLOAD
  • OIL LEVEL HI LO
  • CLG WTR LO FLOW
  • SEAL LEAKAGE FLOW LOW
  • SEAL PRESSURE OFF NORMAL
  • SEAL HEAT EX HI TEMP LEAKAGE HI

Any of the alarms associated with A, B & C pumps for:

  • Backstop Oil Flow Low
46
Q

What are some indications of imminent PCP failure per AOP-29, Primary Coolant Pump Abnormal Conditions?

A

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

47
Q

What are the Reactor Trip Criteria of AOP-29, Primary Coolant Pump Abnormal Conditions?

A

Reactor Trip:

Loss of CCW AND:

  • Any PCP bearing temperature exceeds setpoint
      • Upper Guide 175F
      • Lower Guide 175F
      • Upper Thrust 185F
      • Down Thrust 175F
  •  Any PCP Lower Seal temperature exceeds 185F
  •  Any PCP Vapor Seal temperature exceeds 185F

Any PCP vibration is greater than 29 mils

Imminent PCP failure corroborated by other indications

TRIP THE AFFECTED PCP ON VERIFICATION OF REACTIVITY POST REACTOR TRIP

48
Q

What are the entry criteria for AOP-30, Loss of Shutdown Cooling?

A

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
49
Q

What are the equipment trip criteria of AOP-30, Loss of Shutdown Cooling?

A

EDG Mechanical Overspeed Trip/Reset

  • Jacket water temp greater than or equal to 195F
  • Lube oil temp greater than or equal to 200F

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
50
Q

What are the entry criteria for AOP-31, Spurious Containment Isolation?

A

EK-1126, “CIS INITIATED” with Containment pressure and radiation levels normal.

51
Q

What are the automatic actions of AOP-31, Spurious Containment Isolation?

A
  1. Containment Isolation Valves close
  2. Safety Injection initiated (CHP only)
  3. Containment Spray initiated (CHP only)
  4. Reactor trip (CHP only)
52
Q

What are the trip criteria of AOP-31, Spurious Containment Isolation?

A

Containment Isolation caused by Containment High Pressure signal (CHP)

53
Q

What are the entry criteria of AOP-32, Loss of Containment Integrity?

A
  1. Obvious breach in Containment
  2. Inoperable Containment Isolation valve(s)
  3. Failed interlock mechanism on a Containment Air Lock
  4. Inoperable Containment Air Lock door(s)
54
Q

What are the trip criteria of AOP-32, Loss of Containment Integrity?

A

There are no trip criteria, no immediate actions and no automatic actions.

However, Step 1 of Operator Actions has you verify the loss of containment integrity is NOT due to an act of nature, aviation accident or sabotage. RNO is to

  • Emergency Borate as needed
  • Trip the Reactor
55
Q

What are the entry criteria for AOP-34, Fuel Handling Accident?

A
  1. Instance of a dropped or unintentionally tipped irradiated fuel element
  2. Heavy object dropped into the pool or core, including the Reactor Vessel Head dropped during transport
  3. High radiation alarms during fuel handling operations from area monitors or CAM units
  4. Malfunction of fuel handling machinery interlocks allowing impact of irradiated fuel with fixed objects
  5. Loaded fuel shipping or storage cask dropped inside the Auxiliary Building
56
Q

What are the automatic actions of AOP-34, Fuel Handling Accident?

A

Auxiliary Building ventilation system(s) trip due to local rad alarms

Containment Isolation Valves close if CHR received

57
Q

What are the immediate actions of AOP-34, Fuel Handling Accident?

A
  1. STOP fuel handling operations.
  2. EVACUATE unnecessary personnel from affected area(s) (for example, Containment Building/Fuel Handling Area).
58
Q

What are the entry criteria of AOP-35, Loss of Service Water?

A
  1. EK-1124, “TRAVELING SCREEN HI DP” (9”H2O)
  2. EK-1129, “SERVICE WATER PUMP BAY LO LEVEL” (Elevation 574’3”)
  3. EK-1163, “CRITICAL SERV WATER HEADER “B” LO PRESSURE” (45 psig)
  4. EK-1164, “CRITICAL SERV WATER HEADER “A” LO PRESSURE” (45 psig)
  5. EK-1165, “NON-CRITICAL SERV WATER LO PRESS” (45 psig)
59
Q

What are the automatic actions of AOP-35, Loss of Service Water?

A
  1. Standby Service Water Pump starts at 40 psig discharge pressure on an operating Service Water Pump.
  2. Screen Wash Pump P-4 starts at 6” H2O Δ Level across the Traveling Screens.
60
Q

What are the Reactor Trip criteria of AOP-35, Loss of Service Water?

A
  1. Service Water Bay level lowers to 572’
  2. Operator actions are not maintaining either Critical Service Water Header Pressure greater than or equal to 42 psig
  3. 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)
61
Q

What are the Immediate Actions of AOP-35, Loss of Service Water?

A
  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” (50C)

RNO

  • Trip the Reactor
  • 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 80C or rising

THEN:

PERFORM Attachment 1, “Break Condenser Vacuum,” to slow generator rotor speed.

62
Q

What are the entry criteria of AOP-36, Loss of CCW?

A
  1. T-3, CCW Surge Tank level lowering and not being recovered
  2. CCW cooled components indicate degraded cooling
  3. EK-1169, “COMPONENT CLG PUMP DISCHARGE LO PRESS” (80 psig)
63
Q

What are the automatic actions of AOP-36, Loss of CCW?

A

Standby pump starts at 80 psig on header.

64
Q

What are the Reactor Trip Criteria of AOP-36, Loss of CCW?

A
  1. CCW flow to Containment lost for greater than 10 minutes
  2. Failure to restore a Component Cooling Water Pump to service
65
Q

What are the entry criteria for AOP-37, Loss of Instrument Air?

A
  1. EK-1101, “CONTAINMENT INSTR AIR LO PRESS” (85 psig)
  2. EK-1102, “INSTRUMENT AIR LO PRESS” (85 psig)
  3. EK-1103, “SERVICE AIR LO PRESS” (80 psig)
66
Q

What are the automatic actions of AOP-37, Loss of Instrument Air?

A
  • Standby Instrument Air Compressor(s) starts at 92 psig
  • CV-1212, Service Air Header Isol closes at 85 psig in the Instrument Air Header
67
Q

What are the reactor trip criteria of AOP-37, Loss of Instrument Air?

A

Erratic equipment behavior observed on equipment required for safe plant operation

68
Q

What are the entry criteria of AOP-38, Acts of Nature?

A
  1. Shift Manager Discretion
  2. Lake level above 585 feet
  3. 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
  • National Weather Service has issued a high wind warning for any of the following areas (forecasted within the next 72 hours):
    • Van Buren, Berrien or Allegan County
    • Waters of Lake Michigan to the west of the Palisades Nuclear Plant
  1. 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)
  2. 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
  1.  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
  2.  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
  1. Earthquake
    * Indication of an earthquake felt by people in the Owner Controlled Area
  2. Geo-Magnetic Storm Disturbance
    * Notification by Independent System Operator (ISO), Balancing Authority orTransmission Operator of a predicted Geo-Magnetic Storm Disturbance with a K-index greater than or equal to 7
69
Q

What are the Reactor and Equipment Trip criteria of AOP-38, Acts of Nature?

A

Reactor Trip

  1. Lake water starts to enter the Turbine Building/Screen House
  2. Water level at Condensate Pump thrust bearing
  3. Water level greater than or equal to 9 inches in the vicinity of electrical buses 1A, 1B, and 1E

Equipment Trip

  1. Condensate Pump

Water level at Condensate Pump thrust bearing

  1. Electrical Buses 1A, 1B, 1E

Water level greater than or equal to 9 inches in the vicinity of electrical buses 1A, 1B, and 1E

70
Q

What are the entry criteria of AOP-39, Internal Plant Flooding?

A

Receipt of any of the following alarms with verification of flooding

  1. EK-28, “(EC-47) FIRE SYSTEM FLOW SCHEME ALARMS”
  2. EK-0171, “CONDENSATE PUMP ROOM FLOODING” (572’ elevation)
  3. K-1352, “EAST SFGRDS ROOM SUMP HI/PANEL UV” (14.2% on LI-1108)
  4. EK-1353, “WEST SFGRDS ROOM SUMP HI/PANEL UV” (14.2% on LI-1107)
  5. 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
71
Q

What are the automatic actions of AOP-39, Internal Plant Flooding?

A
  1. 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)
  2. 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)
  3. P-45A, P-45B, Turbine Building Sump Pumps start (first pump starts at 32”, second pump starts at 44”)
72
Q

What are the Reactor and Equipment Trip criteria of AOP-39, Internal Plant Flooding?

A

Reactor Trip

  1. Water depth approaches either operating Condensate Pump thrust bearings (height of security switch on AFW Pump Rm door)
  2. Water depth exceeds 5 inches in Bus 1C area
  3. Erratic equipment operation during Bus 1C area flooding
  4. Water depth exceeds 5 inches in Bus 1D area
  5. Erratic equipment operation during Bus 1D area flooding
  6. Erratic equipment operation during Cable Spreading area flooding
  7. 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
73
Q

What are the entry criteria for AOP-40, Fire Which Threatens Safety Related Equipment?

A

Fire or explosion in any of the following Power Block Fire Areas:

Auxiliary Building

  • 1, 2, 3, 4, 5, 6, 7, 8, 10, 11,
  • 12, 13, 15, 16, 17, 18, 19,
  • 21, 26, 27, 28, 29, 30, 31,
  • 32, 33, 34, 35, and 36.

Feedwater Purity Building 39

Reactor Containment Building 14

Switchyard 40

Turbine Building 9, 22, 23, 24, 25, and 56

Outside Area within the Protected Area and

Transformer Area 41

74
Q
A