JPM RO-A1 — Determine Maximum Reactor Vessel Vent Time Admin | RO/SRO | G2.1.25 (3.9)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 10 minutes

Initial Conditions:
- Unit 2 has experienced a small break LOCA.
- The crew has performed an RCS cooldown and depressurization in EOP-LOCA-2.
- During the depressurization the crew experienced some complications and indications of upper head voiding are now present.
- STA reports a valid CFST YELLOW path exists on Coolant Inventory.
- The TSC recommends initiating EOP-FRCI-3, Response to Void in Reactor Vessel.

Initiating Cue:
- You are the extra NCO.
- The crew has completed actions in EOP-FRCI-3 up to step 17.3 and has directed you to PERFORM Attachment 1 of EOP-FRCI-3 to determine the maximum venting time.
- The following conditions exist in Unit 2 containment:
  - Containment temperature is 140 F
  - Containment hydrogen concentration is 2.3%
  - RCS pressure is 1600 psig
- During your calculations, ONLY perform "rounding" when determining the vent time to the nearest tenths.

Task Standard:
Calculates Maximum Venting Time of 4.5 mins (4.2 - 4.7 mins acceptable band).

JPM RO-A2 — Determine Boration Time for 3 Stuck Rods and Final BAST Level Admin | RO/SRO | G2.1.20 (4.6)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 8 minutes

Initial Conditions:
- Unit 2 experienced an automatic Reactor Trip from an inadvertent Main Turbine Trip.
- SI is not required and the crew is implementing 2-EOP-TRIP-2, Reactor Trip Response.
- Three Control Rods from Control Bank Delta have failed to FULLY insert.
- Current BAST levels:
  - 21 BAST level: 94%
  - 22 BAST level: 76%

Initiating Cue:
- You are the extra NCO.
- The CRS has directed you to determine the amount of time Rapid Boration is required IAW 2-EOP-TRIP-2 Step 4 for the Three Control rods that have failed to insert on Control Bank Delta.
1. How many total minutes of Rapid Boration is required?
2. What will be the final BAST levels?
  - Assume the Rapid Boration flowrate remains at 40 GPM for the entire duration required in question 1, and Both BASTs lower equal amounts.

Task Standard:
1. CALCULATES the total boration time for 3 stuck control rods to be 105 minutes.
2. Calculates total amount of gallons injected to be 4200 gallons and final BAST levels are at 21: 67% +/- 2% and 22: 49% +/- 2%.

JPM RO-A3 — Perform Manual QPTR Calculation Surveillance Admin | RO/SRO | G2.2.12 (3.7)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 20 minutes

Initial Conditions:
- Unit 2 was operating at 100% power when rod 2D4 dropped fully into the core. OHAs E-46, LOWER SECT DEV ABV 50% PWR, and E-38 UPPER SECT DEV ABV 50% PWR, annunciated, cleared and continue to annunciate then clear.
- Operators have not yet started reducing power to 74% to comply with TSAS 3.1.3.1.c.3.d IAW S2.OP-AB.ROD-0002, Dropped Rod.

Initiating Cue:
- The CRS has directed you to perform a Manual QPTR Calculation IAW S2.OP-ST.NIS-0002. Maintain all calculations at three significant digits to the right of the decimal point (Thousandths) unless otherwise directed by procedure.
- All pre-requisites are completed SAT.
- Notify CRS of test results after Step 5.3 is complete and compliance with Technical Specification.
- NI currents are:

	Upper Detectors	Lower Detectors
N41	189	188
N42	206	221
N43	192	193
N44	135	151

Task Standard:
1. Manually calculates the highest QPTR as UNSAT (highest N42T AND N42B) with a value of 1.041 and 1.032 respectively (+/- 0.002).
2. Identifies Maximum Power Tilt exceeds 1.02 and identifies T/S LCO 3.2.4 is NOT met.

JPM RO-A4 — Determine Radiological Dose and Stay Times for Containment Entry Admin | RO/SRO | G2.3.13 (3.4)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 10 minutes

Initial Conditions:
- Salem is in Mode 1 at 100%.
- The 22 CFCU has been declared inoperable.
- Tagging has been completed.

Initiating Cue:
- You have been directed by the WCCS to determine stay times for entering containment to hang additional tags on 22 CFCU.
- Assume the following:
  - Safety has determined the heat stress stay time to be 15 minutes
  - Radiation protection has limited total dose received by individual to 0.002 REM gamma and 0.008 REM Neutron
1. In accordance with the provided survey map perform the following:
  1.1 Calculate the following for the Operator:
    - Gamma dose stay time _____ minutes
    - Neutron dose stay time _____ minutes
  1.2 Determine most limiting allowable time for containment entry team based on ALARA and Heat Stress:
    - Limiting containment entry time _____ minutes

Task Standard:
Determines that based on the dose limits Gamma dose stay time is 24 minutes, Neutron dose stay time is 12 minutes, and heat stress stay time is 15 minutes. Determines that limiting entry time will be based on Neutron dose at 12 minutes.

JPM SRO-A1 — Isolate Non-Essential Chilled Water Loads Admin | SRO | G2.1.7 (4.7)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 15 minutes

Initial Conditions:
- It is July 15th time 1800 and you have just assumed the watch as the Unit 2 CRS. It was turned over that both 21 and 22 Chillers tripped at 1600 and you are currently in T/S 3.7.10 action 'b', entered at 1600.
- To comply with the T/S action, the crew is implementing S2.OP-SO.CH-0001, Chilled Water System Operation, Section 4.6, Isolation of Non-Essential Heat Loads.
- During preparations to align #2 ECAC cooling to Service Water IAW S2.OP-SO.CA-0001, Control Air System Operation, it was reported that the spool pieces required to align to service water cannot be located.
- Unit 2 CREACS has been removed from service IAW step 4.6.2 of S2.OP-SO.CH-0001.
- CW Inlet Water Temperature Readings from SC.OP-DL.ZZ-0008(Q), Circulating / Service Water Log are:
  2TL3756 = 83.4°F
  2TL3757 = 83.6°F

Initiating Cue:
- You are the Unit 2 CRS.
- The Shift Manager directs you to NOT isolate the #2 ECAC and to re-perform the Non-Essential heat load determination IAW Attachment 2.
- DETERMINE the total Non-Essential heat load and SELECT the required components for isolation IAW S2.OP-SO.CH-0001, Chilled Water System Operation, Attachment 2 to comply with Tech Specs.

Task Standard:
1. Determines the Total Heat Load Isolation value required is 902.8 kBTU/HR.
2. Selects the required components on Table B for isolation and ensures that the total value (906.6 kBTU/HR) is greater than 902.8 kBTU/HR.

JPM SRO-A2 — Boration Time for Stuck Rods and BAST Level Evaluation Admin | SRO | G2.1.20 (4.6)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 10 minutes

Initial Conditions:
- Unit 2 experienced an automatic Reactor Trip from an inadvertent Main Turbine Trip.
- 2SJ2 was tagged for emergent repairs prior to the trip.
- SI is not required and the crew is implementing 2-EOP-TRIP-2, Reactor Trip Response.
- Three Control Rods from Control Bank Delta have failed to FULLY insert.
- RWST Concentration is 2350 ppm, and BAST concentration is 6650 ppm.
- Unit 2 remains in Mode 3 throughout the boration.
- Current BAST levels:
  21 BAST level: 70%
  22 BAST level: 70%

Initiating Cue:
- You are the CRS.
- Determine the amount of time Rapid Boration is required IAW 2-EOP-TRIP-2 Step 4 for the Three Control rods that have failed to insert on Control Bank Delta:
  1. How many total minutes of Rapid Boration is required?
  2. What will be the final BAST levels in percent IAW S2.OP-TM.ZZ-0002?
    - Assume the Rapid Boration flowrate remains at 40 GPM for the entire duration required in question 1, and Both BASTs lower equal amounts.
  3. Based on plant conditions after completion of the boration, identify any Tech spec(s) and Tech Spec action statement(s) required related to the boric acid system.

Task Standard:
1. Calculates the total boration time for 3 stuck control rods to be 105 minutes.
2. Determines final BAST tank levels for 21 tank at 43% +/-2% and 22 tank at 43% +/-2%.
3. Determines that TS LCO 3.1.2.6.a.1 is not met and action is required.

JPM SRO-A3 — Review Containment Ventilation Valve Surveillance Admin | SRO | G2.2.12 (4.1)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 15 minutes

Initial Conditions:
- Completed surveillance was given to you at turnover and is in your inbox for review.
- Turnover stated it is just awaiting review and approval.

Initiating Cue:
- You are the Unit 2 CRS.
- Review the completed surveillance for compliance with Acceptance Criteria and document results.

Task Standard:
Upon reviewing the completed surveillance procedure, the SRO identifies that 2VC5 stroke time is in the Required Action Range, declares the 2VC5 Inoperable, and determines TS LCO 3.6.3 is NOT met.

JPM SRO-A4 — Personnel Exposure for Containment Entry at Power Admin | SRO | G2.3.4 (3.7)

Location: Classroom
Time-Critical: No
Alternate Path: No
Estimated Time: 20 minutes

Initial Conditions:
- Salem 2 is at 100% power reducing power at 10% per hour to perform Turbine valve testing.
- The 22 CFCU has been declared inoperable.
- Tagging has been completed.

Initiating Cue:
- You are the WCCS and need to send operators into containment to remove tags to allow work on 22 CFCU disassembly to continue.
- Operator A has 1992 mrem TEDE for the year and Operator B has 1496 mrem TEDE for the year so far.
- Using the provided Radiological Survey Map and procedures, determine the following:
  1. Whose authorization outside of Operations, by position, is needed to enter the containment during the downpower?
  2. In accordance with the provided survey map perform the following:
    2.1. Calculate the dose for each operator (Assume both operators each take 12 minutes in the area to perform their tagging evolution):
      Gamma dose ___ mrem
      Neutron dose ___ mrem
    2.2. Will the operators exceed the Administrative Annual Dose limit? If so, identify which Operator(s)?

Task Standard:
1. Determines the Radiation Protection Supervisor must authorize entry.
2. Determines Gamma dose for each operator is 1 mrem.
3. Determines Neutron dose for each operator is 8 mrem.
4. Determines Operator A total dose is 2001 mrem and Operator B total dose is 1505 mrem. Operator A exceeds administrative dose control limit of 2000 mrem.

JPM SRO-A5 — Classify Event and Determine PARs Admin | SRO | G2.4.41 (4.6)

Location: Classroom
Time-Critical: Yes
Alternate Path: No
Estimated Time: 10 minutes

Initial Conditions:
- Salem Units 1 and 2 are at 100% power.
- 23 Station Power Transformer (SPT) is tagged and is 12 hours into a 24 hour scheduled maintenance window.
- An electrical grid disturbance on the 500 kV lines has caused the Unit 2 Main Generator protection circuit to automatically trip the Unit 2 reactor.
- The crew is transitioning from EOP-TRIP-1 to EOP-TRIP-2.
- Following transition to TRIP-2, 24 SPT de-energizes due to actuation of electrical protection relays.
- The 2A Emergency Diesel Generator (EDG) started then tripped on overspeed and could not be reset; and the 2B 4 KV Vital Bus de-energized following a Bus Differential protection trip.
- Minutes later the Primary Operator reports a loud sound from the EDG rooms and 2C EDG trips.

Initiating Cue:
- Maintenance provides you the following updates:
  - 2A EDG will take 5 hours to repair the bent linkage to the fuel racks.
  - 2B 4 KV Vital Bus has sustained significant damage to the bus bars due to a ground fault.
  - 2C EDG has sustained significant engine damage due to an engine piston failure.
  - 23 SPT needs 8 hours to restore and release tags.
  - 24 SPT sustained an internal fault and will need outside vendor support. Vendor is expected to be on-site in 3.5 hours.
- You are the Emergency Coordinator:
  1. Classify the emergency event, and
  2. Complete the Initial Contact Message Form (ICMF).
- MET computer 33 FT. level wind direction is steady from 90 degrees at 2 mph.
- 2R41D, Plant Vent Radiation monitor is reading normal.
- THIS IS A TIME CRITICAL JPM

Task Standard:
1. Classifies the event as GENERAL EMERGENCY (GE) based on EAL SG1.1 within 15 minutes.
2. Completes Attachment 4 Sections I thru V of the ICMF and selects Default PAR (No RPSA) within 15 minutes from event declaration.

JPM IP-i — Transfer PZR Backup Heater to Emergency Power Supply In-Plant | RO/SRO | 010 A4.03 (3.6/3.4)

Location: In-Plant — 78 ft. and 84 ft. Electrical Penetration / Switchgear Room
Time-Critical: No
Alternate Path: No
Estimated Time: 15 minutes

Initial Conditions:
- A Loss of Offsite Power has occurred on Units 1 and 2.
- The Unit 2 CRS has initiated S2.OP-AB.LOOP-0001, Loss of Offsite Power.

Initiating Cue:
You have been directed to TRANSFER the 22 Backup Group Pressurizer Heaters to the Emergency Power Supply IAW Section 5.3 of S2.OP-SO.PZR-0010, Pressurizer Backup Heaters Power Supply Transfer.

Task Standard:
Transfers the 22 Backup Group Pressurizer heaters to the Emergency Power source by placing 11 of 14 disconnects in OFF, placing the 2EP PZR HTR BUS EMERGENCY FEED DISCONNECT SWITCH in ON, and using the interlock key to unlock breaker 2AX1AX14X.

JPM IP-j — Locally Open Reactor Trip Breakers IAW AB.CR-0001 In-Plant | RO/SRO | 012 A4.06 (4.3/4.3)

Location: In-Plant — Unit 1 RCA, 84 ft. Switchgear Room and 460V Vital Bus Room
Time-Critical: No
Alternate Path: No
Estimated Time: 25 minutes
Unit: Salem Unit 1 ONLY

Initial Conditions:
- The Unit 1 Control Room has been evacuated in accordance with S1.OP-AB.CR-0001, Control Room Evacuation.
- A reactor trip was NOT initiated prior to evacuating the Control Room.

Initiating Cue:
You are directed to perform Unit 1 S1.OP-AB.CR-0001, Control Room Evacuation, Attachment 5.

Task Standard:
1. Locally opens Reactor Trip and Bypass Breakers.
2. Locally opens breakers for 13 Charging Pump and 1CV175 Rapid Borate valve.

JPM IP-k — Perform a Radioactive Liquid Release In-Plant | RO/SRO | 068 A4.03 (3.9/3.8)

Location: In-Plant — 64 ft. Elevation Aux Bldg (RCA), Gas Stripper Feed Pump Room, CVCS MT Room, 104 Panel area
Time-Critical: No
Alternate Path: No
Estimated Time: 25 minutes

Initial Conditions:
- Preparations for a release of 21 CVCS Monitor Tank via Unit 2 SW system to Unit 1 CW system is in progress IAW S2.OP-SO.WL-0001, RELEASE OF RADIOACTIVE LIQUID WASTE FROM 21 CVCS MONITOR TANK.
- Chemistry has granted permission to release 21 CVCS MT at a Maximum Release Rate of 45 gpm due to the high activity (Curie) content of the tank.
- 2R18 Radiation Monitor AND 2FR1064 Flow Recorder are both OPERABLE.
- All Unit 1 CW pumps are in service.

Initiating Cue:
- You are the extra NCO.
- The CRS directs you to release 21 CVCS MT IAW Section 5.5 of S2.OP-SO.WL-0001.
- The Maximum Release Rate and Release Path are recorded on Attachment 2, Section 2.2 of the procedure.

Task Standard:
1. Controls the discharge of 21 CVCS MT to less than the Maximum Release rate of 45 gpm.
2. Notifies control room to close 2WL51 following high alarm on the 2R18 radiation monitor.

JPM Sim-a — Perform Control Rod System Surveillance Sim | RO | 001 A2.11 (4.4/4.7)

Location: Simulator
Time-Critical: No
Alternate Path: Yes
Estimated Time: 10 minutes

Initial Conditions:
- Unit 2 is at 100% power BOL.
- No major equipment is out of service and no Tech Specs are active.
- The rod control system surveillance is in progress. All sections are complete, except for exercising Control Bank D.

Initiating Cue:
- You are the Reactor Operator.
- The CRS directs you to complete the rod control system surveillance IAW S2.OP-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.
- A Maintenance Technician is stationed at the Rod Control Power Cabinets (Relay Room).
- CRS directs that 15 steps of rod insertion will be performed to ensure each rod moves at least 10 steps.
- Notify the CRS when the testing is complete.
- Your evaluator will take care of all alarms not related to your task.

Task Standard:
Exercises Control Bank D at least 10 steps and upon completion of the test recognizes unexpected continuous rod movement requiring a manual reactor trip.

JPM Sim-b — Perform Manual Makeup to VCT Sim | RO/SRO | 004 A4.04 (3.2/3.6)

Location: Simulator
Time-Critical: No
Alternate Path: No
Estimated Time: 15 minutes

Initial Conditions:
- 100% power, MOL. RCS boron concentration is 900 ppm.
- The crew has entered S2.OP-AB.CVC-0001, Loss of Charging, due to VCT level channel 2LT112 failing high.

Initiating Cue:
- You are the Reactor Operator.
- The CRS has directed you to PERFORM a manual makeup of the VCT to RESTORE VCT level to 53% IAW S2.OP-SO.CVC-0006, Boron Concentration Control, Section 5.2, Manual Makeup Mode.
- All prerequisites are complete.
- Boric Acid Storage Tank boron concentration is 6700 ppm.

Task Standard:
Initiates manual makeup to VCT and stops the makeup when informed that VCT level is at 53%.

JPM Sim-c — Isolate ECCS Accumulators in EOP-LOCA-1 Sim | RO/SRO | 006 A3.10 (4.0/3.9)

Location: Simulator
Time-Critical: No
Alternate Path: Yes
Estimated Time: 8 minutes

Initial Conditions:
- The reactor was tripped when a RCS leak occurred.
- The operating crew has progressed through the EOPs and is now in 2-EOP-LOCA-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Initiating Cue:
- You are the Reactor Operator.
- The CRS directs you to isolate the SI Accumulators IAW Step 14 of 2-EOP-LOCA-1, LOSS OF REACTOR OR SECONDARY COOLANT.
- Notify the CRS when Step 14 is completed.
- Your evaluator will take care of all alarms not related to your task.

Task Standard:
1. Closes 21, 22, and 23 SJ54s. 2. Vents 24 SI Accumulator to atmospheric pressure.

JPM Sim-d — Respond to RCP Standpipe Low Level Alarm Sim | RO/SRO | 003 A1.10 (2.5/2.7)

Location: Simulator
Time-Critical: No
Alternate Path: No
Estimated Time: 6 minutes

Initial Conditions:
- Unit 2 is at 100% power.
- No major equipment is out of service and no Tech Specs are active.

Initiating Cue:
- You are the Reactor Operator.
- Respond to all alarms and indications.
- Your evaluator will respond to all alarms not related to your task.

Task Standard:
Upon receipt of a RCP standpipe low level alarm, the operator aligns valves to fill the standpipe with primary water, and terminates the fill when the high level alarm is received.

JPM Sim-e — Loss of SGFP Immediate Actions Sim | RO/SRO | 059 A4.14 (3.1/3.3)

Location: Simulator
Time-Critical: No
Alternate Path: Yes
Estimated Time: 5 minutes

Initial Conditions:
- Unit 2 power ascension is in progress to 90% at 10% per hour.
- S2.OP-SO.TRB-0001 Attachment 5 is in progress up to step 4.

Initiating Cue:
- You are the Reactor Operator. Respond to all indications and alarms.

Task Standard:
Initiates a manual Main Turbine load reduction at 15%/min to 66% and inserts control rods in MANUAL due to failure of the rods to insert in AUTO.

JPM Sim-f — Manually Actuate Containment Spray Sim | RO/SRO | 026 A2.03 (4.4/4.4)

Location: Simulator
Time-Critical: No
Alternate Path: Yes
Estimated Time: 8 minutes

Initial Conditions:
- A Large Break LOCA has occurred.
- The Reactor Automatically Tripped and SI was actuated.
- The crew has completed Steps 1 through 8 of 2-EOP-TRIP-1, Rx Trip or Safety Injection.

Initiating Cue:
- You are the Reactor Operator.
- The CRS directs you to continue on with EOP-TRIP-1 starting at STEP 9.
- Your evaluator will respond to any alarms not associated with your task.

Task Standard:
1. Manually initiates Containment Spray and Phase B isolation. 2. Closes 2CC131 OR 2CC190 Phase B valves. 3. Opens 2CS16 OR 2CS17 NaOH Discharge Valves.

JPM Sim-g — Respond to Loss of 2A 4KV Vital Bus Sim | RO | 062 A2.04 (3.1/3.4)

Location: Simulator
Time-Critical: No
Alternate Path: Yes
Estimated Time: 10 minutes

Initial Conditions:
- 100% power, BOL.

Initiating Cue:
- You are the Reactor Operator. Respond to all indications and alarms.

Task Standard:
Operator closes the 2CV55 and starts 21 Charging Pump. Upon receiving indications that 21 Charging Pump trips; starts 22 Charging Pump.

JPM Sim-h — Respond to Fire Alarm Sim | RO/SRO | 086 A4.02 (3.5/3.5)

Location: Simulator
Time-Critical: No
Alternate Path: No
Estimated Time: 10 minutes

Initial Conditions:
- 100% power.
- All systems are in Automatic and normal alignment.

Initiating Cue:
- You are the Reactor Operator.
- Respond to all alarms and indications.

Task Standard:
Upon fire alarm in control room, the operator makes page announcement for fire location, places Control Room Ventilation in FIRE INSIDE MODE, places the 2PR1 and 2PR2 in Manual and Closed, Closes 2PR6 and 2PR7, and dispatches operator to place the PZR PORV valves in EMERG CLOSE.

Scenario 1 — Load Reduction / LBLOCA Simulator | 8 Events | 3 Critical Tasks

Initial Conditions: IC-240: Unit 2 is at 100% power, EOL; 21 Charging Pump I/S. The following equipment is out of service: 23 Charging Pump and 21 RHR Pump are C/T for maintenance.

Turnover: The crew is directed to reduce power to 89% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using boration, control rods and turbine load control in preparation for Main Turbine Valve testing.

Major Events:

1. Planned Load Reduction to 89% at 10%/hour
2. 24 Vacuum Pump trips
3. RC Loop 24 Cold Leg RTD Fails High (TS)
4. RCS Leak — 20 gpm (TS)
5. LBLOCA (leak worsens to 350 gpm)
6. Auto SI fails to actuate
7. 22 RHR Pump Fails to Start on SEC Signal
8. Loss of Emergency Recirculation capability (22 RHR Pump Trips)

Scenario 3 — Power Ascension / Loss of Heat Sink Simulator | 8 Events | 2 Critical Tasks

Initial Conditions: IC-242: Unit 2 is at 93% power, MOL; 2A EDG is running unloaded for maintenance run. The following equipment is out of service: 21 AFW Pump C/T for oil bubbler replacement and 21 Containment Spray pump for lube.

Turnover: The crew is directed to continue power ascension to 98% power at 10% per hour IAW S2.OP-IO.ZZ-0004 by use of dilution, control rods and turbine load control.

Major Events:

1. Power ascension to 100% at 10%/hour
2. 21 CRDM Vent Fan damper fails closed
3. PZR Level controlling channel fails high (TS)
4. 21CN22 FWH Inlet valve fails closed
5. 2A EDG emergency trip (TS)
6. 23 RCP motor oil level low
7. Main turbine fails to trip by all means in the control room
8. Loss of all AFW flow and recovery by initiating Condensate flow using MS10

Scenario 4 — Startup / SGTR Simulator | 7 Events | 2 Critical Tasks

Initial Conditions: IC-243: Unit 2 is at 2% power, BOL; 21 SGFP in service.

Turnover: The crew is directed to continue power ascension to 10% reactor power IAW S2.OP-IO.ZZ-0003 using control rods, steam dumps, and turbine load control.

Major Events:

1. Power Ascension
2. 2PR2 PZR PORV leakage
3. High DP across 23A CW Traveling Screen
4. 23 SG Tube Leak (35 gpm)
5. 23 SG Tube Rupture (650 gpm)
6. 21 CFCU fails to start in LOW speed
7. PZR Spray Valve 2PS3 fails to close during RCS depressurization