ML040130673

Initial Submittal of the Scenarios for the Monticello Initial Examination - Sep 2003

ML040130673
Person / Time
Site:	Monticello
Issue date:	09/23/2003
From:	Allex G Nuclear Management Co
To:	NRC/RGN-III
References
50-263/03-301, ES-D-1 50-263/03-301
Download: ML040130673 (138)

Text

2003 MNGP ILO NRC Exam NRC 03-01 Appendix D Scenario Outline Form ES-D-1 Facility: MNGP Scenario No. NRC Op-Test No: 03-01 03-01 Examiners: Operators:

Initial Conditions: A reactor startup is in progress from a refueling outage. The crew will assume the shift with the plant operating at 13% power making preparations for rolling the Main Turbine. Operations Manual C.1, Reactor Startup, has been completed up through step VI.A.18.

Turnover: Withdraw control rods to achieve 1-1/2 Turbine Bypass Valves open in accordance with step C.1 Step VI.B.1 and then roll the Main Turbine per C.1 Step VII.B and continue with plant startup.

Event Malf. Event Event No. No. Type* Description 1 N/A RO (R) Withdraw control rods to establish 1-1/2 Bypass Valves 2 RW01 RO (I) RWM Equipment Failure (Tech Spec Call) 3 N/A BOP (N) Roll the Main Turbine 4 TC05B BOP (C) Pressure Regulator Oscillations, MPR 5 SW01A RO (C) #11 RBCCW Pump Trip 6 IA04 BOP (C) Instrument Air Header Failure 7 CH02 (*) M Failure to Scram (West SDV hydraulic lock)

Note 1 8 RM03K M Rupture of West SDV RM03H RX01 9 S025-01 BOP(C) Failure of A SRV to Open Equipment Out of Service B RWCU Pump APRM Channel #5 Note 1: This event requires 61 malfunctions to be inserted to have 61 control rods associated with the West SDV stuck.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 1 Page 1 of 1 Event

Description:

The crew will assume the shift with the plant operating at 13% power making preparations for rolling the Main Turbine. Operations Manual C.1, Reactor Startup, has been completed up through step VII.A.18. Control Rods need to be pulled to achieve 1 1/2 Turbine Bypass Valves in accordance with step VII.B.1.

Time Position Actions or Behavior SRO Direct withdrawal of control rods to achieve 1 1/2 Main Turbine Bypass Valves open.

RO Withdraws control rods in accordance with Ops Man B.05.05-05.E.1, Control Rod Movement.

Place ROD SELECT POWER switch, 3A-S1, to ON.

Press the appropriate ROD SELECT pushbutton (determined from the roller tape, RWM and control rod sequence package).

NOTE: The control rod will move 1 notch in the indicated direction when the ROD MOVEMENT CONTROL switch is momentarily placed in ROD NOTCH OUT or ROD IN.

Momentarily place ROD MOVEMENT CONTROL switch, 3A-S2, to ROD OUT NOTCH or ROD IN to obtain desired rod movement.

BOP Monitoring plant parameters and may act as Peer Checker.

Notes:

Page 2 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 2 Page 1 of 2 Event

Description:

During control rod withdrawal, the RWM will fail. This will cause control rod withdrawal to stop to investigate the failure. This failure will result in the RWM being bypassed and Tech Specs reviewed.

Time Position Actions or Behavior Simulator TRG #1: When directed by the Chief Examiner insert event trigger #1 to cause the RWM Operator to fail.

SRO Acknowledge report of annunciator 5-A-35, RWM ROD BLOCK.

SRO Notifies the Nuclear Engineer and System Engineer.

Phone When contacted as the Nuclear Engineer, direct the crew to bypass the RWM. (Only Talker provide this direction if asked!)

SRO Refers to Tech Spec 3.3.B.3.b and Form 2169. Reviews Form 2169 and determines that the RWM can be bypassed.

SRO Directs the operator to bypass the RWM.

RO Acknowledges and informs CRS of annunciator 5-A-35, RWM ROD BLOCK.

RO Reviews ARP 5-A-35 and determines alarm is due to an inop RWM.

RO When directed by the SRO, performs procedure B.05.02-05.G.2, RWM BYPASS.

RO Performs procedure 2169, ROD WORTH MINIMIZER BYPASS CHECKLIST.

Lead Note: Provide crew a completed copy of form 2169 after they determine that this Evaluator procedure needs to be performed since some steps cannot be completed in the simulator.

RO Obtains CRS permission and bypasses the RWM by placing the keylock switch to BYPASS.

Page 3 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 2 Page 2 of 2 Event

Description:

During control rod withdrawal, the RWM will fail. This will cause control rod withdrawal to stop to investigate the failure. This failure will result in the RWM being bypassed and Tech Specs reviewed.

Time Position Actions or Behavior RO Withdraws/inserts one group in the rod sequence.

RO Independently verifies the rod pattern.

RO Repeats the previous two steps for each group in the rod sequence.

BOP Monitoring plant parameters and may act as Peer Checker.

Notes:

Page 4 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 3 Page 1 of 2 Event

Description:

After bypassing the RWM, the crew will continue with the startup and begin to roll the Main Turbine.

Time Position Actions or Behavior SRO Direct the BOP operator to roll the turbine in accordance with C.1.VII.B.

RO Monitor plant parameters.

BOP Rolls the Main Turbine in accordance with C.1.VII.B.

BOP Determine initial First Stage Shell Temperature is < 250°F.

BOP Determine Turbine acceleration rate is 60 RPM/min.

BOP NOTE: The acceleration rate may be exceeded momentarily when increasing speed.

Raise the Load Limit setpoint and spin the turbine to approximately 200 rpm.

(LLM CO7)

BOP Adjust the Load Limit to maintain approximately 200 rpm.

BOP Verify the TURB TURNING GEAR amber ENGAGED light is OFF.

BOP STOP the TURB TURNING GEAR drive motor. (CS-42-4216/CS CO7)

BOP Direct that a local inspection of the turbine be conducted and verify the TURBINE TURNING GEAR has disengaged.

Phone When directed as TBO to perform a local inspection of the Main Turbine and verify the Talker turning gear has disengaged reply Local inspection of the Main Turbine is satisfactory, no abnormal noise or vibrations, and the turning gear is disengaged.

BOP Verify condenser vacuum is >25 in. Hg vacuum before turbine speed >400 rpm.

Page 5 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 3 Page 2 of 2 Event

Description:

After bypassing RBM Channel No. 8 the crew will continue with the startup and begin to roll the Main Turbine.

Time Position Actions or Behavior BOP Review turbine roll to rated speed limits. (C.1 page 48 Note #3)

BOP Raise the Load Limit setpoint to accelerate the Turbine at approximately 60 RPM/min.

Notes:

Page 6 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 4 Page 1 of 2 Event

Description:

When turbine speed reaches 500 rpm a failure of the Electrical Pressure Regulator (EPR) will occur resulting in Turbine Bypass Valve oscillations. The crew should recognize cycling of the bypass valves, reactor pressure and Main Steam Pressure Control System. The failure will clear once the crew has taken control with the MPR.

Time Position Actions or Behavior Simulator TRG #2: When directed by the Chief Examiner at 500 rpm main turbine speed insert event Operator trigger #2 to cause a failure of the EPR.

SRO Acknowledge report of computer alarms:

• TRB021 Turb Elec Press Reg Cont Off

• TRB023 Turb Mech Press Reg Cont On SRO Verify Bypass Valve Oscillations are occurring and notices MPR and EPR green and red lights are cycling ON and OFF.

SRO Direct that pressure control be switched to the MPR per B.5.09-05.H.2 BYPASS VALVE OSCILLATIONS.

SRO Direct that the MPR be left in control.

SRO Notify Supt. Electrical and Instrument Engineering.

Phone When contacted as Superintendent of Electrical and Instrument Engineering then Talker acknowledge the report and inform the crew that you will investigate the failure.

RO Monitoring plant parameters.

Acknowledge computer alarms:

BOP TRB021 Turb Elec Press Reg Cont Off TRB023 Turb Mech Press Reg Cont On BOP Notify SRO of computer alarms.

Page 7 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 4 Page 2 of 2 Event

Description:

When turbine speed reaches 500 rpm a failure of the Electrical Pressure Regulator (EPR) will occur resulting in Turbine Bypass Valve oscillations. The crew should recognize cycling of the bypass valves, reactor pressure and Main Steam Pressure Control System. The failure will clear once the crew has taken control with the MPR.

Time Position Actions or Behavior BOP Verify the Bypass Valve oscillation are occurring and notices MPR and EPR green and red lights are cycling ON and OFF.

BOP LOWER the MPR setpoint until the red MPR CONTROLLING YES light is ON.

BOP RAISE the EPR setpoint until the green EPR CONTROLLING NO light is ON.

BOP Determines that oscillations have stopped.

BOP Notify SRO Bypass Valve oscillations have stopped.

BOP Leave MPR in pressure control.

Notes:

Page 8 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 5 Page 1 of 2 Event

Description:

After the bypass valve oscillations have been corrected a trip of the 11 RBCCW Pump will occur with a failure of the standby pump to auto start. The crew will manually start the 12 RBCCW Pump and verify proper system response.

Time Position Actions or Behavior Simulator TRG #3: When directed by the Chief Examiner insert event trigger #3 to cause a trip of the Operator 11 RBCCW Pump with a failure of the 12 RBCCW Pump to auto start.

SRO Acknowledge report of 6-B-32, RBCCW LOW DISCH PRESS.

SRO Acknowledges report of actions taken to start No. 12 RBCCW Pump.

RO Acknowledge annunciator 6-B-32, RBCCW LOW DISCH PRESS.

RO Reports annunciator 6-B-32 to SRO.

RO Refers to ARP 6-B-32, RBCCW LOW DISCH PRESS.

RO Check system pressure.

RO Verifies system pressure is less than 30 psig and enters C.4-B.02.05.A (LOSS OF RBCCW FLOW).

RO Notifies Shift Supervision and System Engineer.

Phone When contacted as System Engineering acknowledge the report and inform the crew that Talker you will investigate the failure.

RO Refers to C.4-B.02.05.A, LOSS OF RBCCW FLOW.

RO Verify a RBCCW pump is running.

Page 9 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 5 Page 2 of 2 Event

Description:

After the bypass valve oscillations have been corrected a trip of the 11 RBCCW Pump will occur with a failure of the standby pump to auto start. The crew will manually start the 12 RBCCW Pump and verify proper system response.

Time Position Actions or Behavior RO Identifies that No. 11 RBCCW Pump has tripped and No. 12 RBCCW Pump has failed to automatically start.

Phone If directed as TBO to investigate the failure, report that the breaker for the No. 11 RBCCW Talker Pump is tripped.

Note: RO may start 12 RBCCW pump without the C.4 procedure in hand as this is an immediate action.

RO Manually starts No. 12 RBCCW Pump.

Phone If directed as RBO to investigate the failure, report that the No. 12 RBCCW Pump is Talker running satisfactorily and that the No. 11 RBCCW Pump is secured; no indication of the trip.

RO Notify Shift Supervision.

BOP Monitoring plant parameters.

Notes:

Page 10 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 6 Page 1 of 6 Event

Description:

At the completion of actions for the trip of the running RBCCW pump a failure of the instrument air header will occur. This event will ultimately result in a manual (or automatic) scram being inserted by the crew. After a scram has been inserted the crew will discover that a hydraulic ATWS has occurred in the West SDV.

Time Position Actions or Behavior Simulator TRG #4: At the completion of actions for trip of the No. 11 RBCCW Pump or when Operator directed by the Chief Examiner, insert event trigger #4 to cause a rupture of the Instrument Air Header.

SRO Acknowledge report of annunciators.

SRO Acknowledge action taken in response to loss of Instrument Air.

SRO Per C.4.K - IMMEDIATE REACTOR SHUTDOWN NOTE: C.4.K actions may not be performed if Instrument Air header pressure decreases too rapidly.

SRO Direct the Reactor Operator to reduce Recirculation flow to minimum.

SRO Direct the Reactor Operator to manually scram the reactor.

SRO Enter: C.5-1100 RPV CONTROL SRO Verify Reactor Scram has been initiated.

SRO Determine all rods ARE NOT in to at least 04.

SRO Determine the reactor WILL NOT stay shutdown under all conditions without boron.

SRO Leave C.5-1100 and Enter C.5-2007 SRO Enter C.5-2007: FAILURE TO SCRAM Page 11 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 6 Page 2 of 6 Event

Description:

At the completion of actions for the trip of the running RBCCW pump a failure of the instrument air header will occur. This event will ultimately result in a manual (or automatic) scram being inserted by the crew. After a scram has been inserted the crew will discover that a hydraulic ATWS has occurred in the West SDV.

Time Position Actions or Behavior SRO *Direct the BOP operator to inhibit ADS

• Critical Step SRO *Direct the BOP operator to prevent Core Spray injection per C.5-3205.

• Critical Step POWER LEG SRO Verify Mode switch in SHUTDOWN.

SRO Directs RO to trip Recirc Pumps.

SRO Direct RO to actuate ATWS.

SRO Directs RO to insert control rods per C.5-3101.

PRESSURE LEG SRO Determine Drywell pressure is < 2 psig.

SRO Determine SRVs are not rapidly cycling.

SRO Determines PRV pressure can be controlled with main turbine bypass valves.

LEVEL LEG SRO Check Detail A for instrument limits.

SRO Determine no instrument limits have been exceeded.

Page 12 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 6 Page 3 of 6 Event

Description:

At the completion of actions for the trip of the running RBCCW pump a failure of the instrument air header will occur. This event will ultimately result in a manual (or automatic) scram being inserted by the crew. After a scram has been inserted the crew will discover that a hydraulic ATWS has occurred in the West SDV.

Time Position Actions or Behavior SRO Directs RO to maintain RPV water level +9 to 48 using condensate and feedwater.

SRO Acknowledges report that all control rods have inserted.

SRO Exits C.5-2007 and re-enters C.5-1100.

RO Determines Main Feedwater Reg Valves have locked up.

RO Reduces Recirc pump speed to minimum.

RO Depress REACTOR SCRAM A and B pushbuttons. (5A-S3A and 5A-S3B)

RO Recognize control rods are NOT inserted to or beyond position 04.

RO Place the reactor mode switch in SHUTDOWN.

RO Notify Shift Supervision.

RO Trips both Recirc Pumps.

RO Refer to procedure B.05.06-05 ATWS SYSTEM MANUAL INITIATION (hard card)

RO SET the arming collars of one pair of the following switches to the armed position and depress the pushbuttons ATWS A MAN and ATWS C MAN (PB S-5A & S-5C) (CO5)

ATWS B MAN and ATWS D MAN (PB S-5B & S-5D) (CO5)

Page 13 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 6 Page 4 of 6 Event

Description:

At the completion of actions for the trip of the running RBCCW pump a failure of the instrument air header will occur. This event will ultimately result in a manual (or automatic) scram being inserted by the crew. After a scram has been inserted the crew will discover that a hydraulic ATWS has occurred in the West SDV.

Time Position Actions or Behavior RO Verify Recirc Pump MG Set generator field breakers have tripped.

(Field breaker indicating lights - CO4)

RO Trip the MG set drive motors.

RO Place HS 2A-S1A to STOP (#11 MG set drive motor breaker)

RO Place HS 2A-S1B to STOP (#12 MG set drive motor breaker)

RO Determine Control Rods DO NOT insert.

RO Inserts control rods per C.5-3101, ALTERNATE ROD INSERTION, Part C.

RO Determines that Parts A through D are not available due to loss of instrument air.

RO Determines that Part E, MANUALLY OPEN SDV VENT AND DRAIN VALVES, should be performed due to the hydraulic lock on the West SDV.

RO Directs the RBO to determine the position of CV-127, OUTLET SCRAM VALVES, for all West SDV HCUs.

Phone When directed as RBO to determine the position of the CV-127 valves associated with the Talker West SDV HCUs, acknowledge the order. No further response is required.

NOTE: The crew will not actually perform all of the steps of C.5-3101, Part E. The next event should begin once the crew has addressed all of the concerns associated with the ATWS.

Page 14 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 6 Page 5 of 6 Event

Description:

At the completion of actions for the trip of the running RBCCW pump a failure of the instrument air header will occur. This event will ultimately result in a manual (or automatic) scram being inserted by the crew. After a scram has been inserted the crew will discover that a hydraulic ATWS has occurred in the West SDV.

Time Position Actions or Behavior AFTER SDV RUPTURE RO Determines that all control rods have inserted.

RO Reports to the CRS of all rods in.

BOP Acknowledge annunciators:

• 6-B-24, INSTRUMENT AIR DRYER BYPASSED.

• 6-B-30, INSTRUMENT AIR PRESSURE LOW.

• 6-B-35, SERVICE AIR HEADER LOW PRESS.

BOP Enters C.4-B.08.04.01.A, LOSS OF INSTRUMENT AIR.

BOP Dispatch an operator to verify proper operation of all available air compressors and an instrument air dryer.

Phone When directed as TBO to investigate the Instrument Air header and air compressors wait 2 Talker minutes and then report, a large rupture exists in the instrument air header and I cant find an isolation.

BOP Notifies Shift Supervision.

BOP Makes plant page announcement to secure use of breathing air.

BOP Closes CV-1474, SERVICE AIR ISOLATION.

Simulator When CV-1474 is manually closed event trigger #7 should automatically activate.

Operator Verify trigger 7 has initiated.

BOP Makes plant page announcement to secure use of air systems.

Page 15 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 6 Page 6 of 6 Event

Description:

At the completion of actions for the trip of the running RBCCW pump a failure of the instrument air header will occur. This event will ultimately result in a manual (or automatic) scram being inserted by the crew. After a scram has been inserted the crew will discover that a hydraulic ATWS has occurred in the West SDV.

Time Position Actions or Behavior BOP *Places ADS INHIBIT switches 2E-S7A & 2E-S7B on CO3 to INHIBIT.

• Critical Step BOP *Prevents Core Spray per C.5-3205, TERMINATE AND PREVENT, Part A.

• Critical Step BOP Places MO-1751 CS INJECTION BYPASS handswitch in BYPASS (14A-S16A).

BOP Closes MO-1751.

BOP Places No. 11 Core Spray Pump in PTL.

BOP Places MO-1752 CS INJECTION BYPASS handswitch in BYPASS (14A-S16B).

BOP Closes MO-1752.

BOP Places No. 12 Core Spray Pump in PTL.

Notes:

Page 16 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 7 Page 1 of 3 Event

Description:

While trying to insert control rods, a rupture of the West SDV will occur. With a loss of instrument air the operators will not be able to reset the scram, which will result in an un-isolable rupture into the reactor building.

This will result in high radiation levels in the West SDV area and Outside RWCU area causing the crew to emergency depressurize.

Time Position Actions or Behavior Prior to initiating this event select (highlight) all 61 stuck control rod malfunctions in the Malfunction block of the Summary Screen.

Simulator Operator TRG #6: When all of the concerns associated with the ATWS have been addressed or as directed by the Chief Examiner, select the Delete button of the Malfunction Block to remove the stuck rod malfunction for all 61 stuck control rods and then insert event trigger

1. 6 to cause a rupture of the West SDV.

SRO Acknowledge report of annunciator 4-A-11, REACTOR BUILDING HI RADIATION.

About 2 minutes after initiation of this event or at the discretion of the Chief Examiner, inform the crew as the RP Tech A rupture of the West SDV has occurred.

Phone OR Talker If the RBO was dispatched to the West HCU area, immediately report as the RBO that a rupture of the West SDV has occurred.

SRO Acknowledges report of alarming ARM.

SRO Enters C.5-1300, SECONDARY CONTAINMENT CONTROL.

SRO Directs the BOP operator to operate all available Reactor Building area coolers.

SRO Determines that a rupture of the West SDV has occurred.

SRO Determines that the leak cannot be isolated due to the loss of Instrument Air.

SRO Acknowledges the report that the West CRD HCU and Outside RWCU room are above max safe radiation.

Page 17 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 7 Page 2 of 3 Event

Description:

While trying to insert control rods, a rupture of the West SDV will occur. With a loss of instrument air the operators will not be able to reset the scram, which will result in an unisolable rupture into the reactor building.

This will result in high radiation levels in the West SDV area and Outside RWCU area causing the crew to emergency depressurize.

Time Position Actions or Behavior SRO Enters C.5-2002, EMERGENCY RPV DEPRESSURIZATION.

SRO Determines Drywell pressure is below 2 psig.

SRO Directs BOP to prevent LPCI injection per C.5-3205.

SRO Determines Torus level is above -5.9 feet.

SRO *Directs RO to open all 3 ADS valves.

• Critical Step RO *Opens all 3 ADS valves.

• Critical Step RO Determines that the A SRV did not open.

RO Opens a third SRV.

RO Reports to the CRS of the failure of the A SRV to open.

RO Performs C.4-A, REACTOR SCRAM, Part A actions.

BOP Acknowledges annunciator 4-A-11, REACTOR BUILDING HI RADIATION.

BOP Checks ARMs on Panel C-11.

BOP Determines that West CRD HCU Area ARM is in alarm.

Page 18 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 7 Page 3 of 3 Event

Description:

While trying to insert control rods, a rupture of the West SDV will occur. With a loss of instrument air the operators will not be able to reset the scram, which will result in an unisolable rupture into the reactor building.

This will result in high radiation levels in the West SDV area and Outside RWCU area causing the crew to emergency depressurize.

Time Position Actions or Behavior BOP Makes plant announcement to evacuate the Reactor Building.

BOP Notifies Radiation Protection to perform surveys and control entry.

BOP Notifies CRS of alarming ARM.

BOP Determines that all available area coolers are operating in the Reactor Building.

BOP Reports that the West CRD HCU and Outside RWCU room are above max safe radiation.

BOP Prevents LPCI Injection per C.5-3205, Part B.

BOP Opens knife switches 10A-S31A and 10A-S31B inside C-03 Panel.

BOP Verifies closed MO-2012 and MO-2013.

BOP Performs C.4-A, REACTOR SCRAM, Part B actions.

Notes:

Page 19 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Termination Point:

• All control rods have been inserted.

• 3 Safety/Relief Valves are open.

• At the discretion of the Chief Examiner.

Classification:

Guideline 28.B (General Emergency) Loss of 2 of 3 Fission Product Barriers with a Potential Loss of the Third Page 20 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Appendix D Scenario Outline Form ES-D-1 Facility: MNGP Scenario No. NRC Op-Test No: 03-01 03-02 Examiners: Operators:

Initial Conditions: Reactor power was reduced to 50% last shift to perform some on-line maintenance on the No. 11 RFP. The maintenance is complete and the RFP is ready to start.

Turnover: Start the No. 11 RFP and return to 100% power.

Event Malf. Event Event No. No. Type* Description 1 N/A BOP (N) Start the No. 11 RFP 2 N/A RO (R) Raise Reactor Power with Recirc 3 RR09A RO (C) A Recirc Speed Control Signal Failure (Tech Spec Call) 4 RC02 BOP (C) RCIC Auto Initiation 5 EG02A BOP (C) No. 11 Stator Cooling Pump Trip with Failure of No. 12 Pump to Auto Start 6 A165-07 RO (I) Failure of RPV Level Control Setpoint 7 ED12 M Loss of Off-Site Power DG02B Failure of No. 12 EDG to Start 8 RR01B M HPCI Steam Line Break on Start (inside drywell)

(simulated via small Recirc line break) 9 RC03 BOP (C) RCIC Turbine Trip Equipment Out of Service B RWCU Pump APRM Channel #5

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 21 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 1 Page 1 of 3 Event

Description:

The crew will take the duty with the plant at 50% reactor power. Power was reduced last shift to perform on-line maintenance on the No. 11 RFP. After taking the duty the crew will start the No. 11 RFP.

Time Position Actions or Behavior SRO Direct the BOP to start the No. 11 RFP per B.06.05-05.D.7, PLACING 11 RFP IN SERVICE FROM WARM-UP.

RO Monitoring plant parameters and may act as Peer Checker.

BOP Directs the TBO to verify normal oil levels exist.

BOP Directs the TBO to verify No. 11 RFP barrel temperature is within 50°F of system operating temperature.

BOP Determines average temp from 13A & B FWHs using computer points CFW560 and CFW561.

Phone When the candidates attempt to verify No. 11 RFP barrel temperature is within 50°F of Talker system operating temperature using computer points CFW560 and CFW561, inform the candidate that step 3 has been completed and that No. 11 RFP barrel temperature is 25°F of system operating temperature.

Verifies the following:

BOP No. 11 RFP Aux Oil Pump is running with control switch in HAND.

Bearing header temp is 110°F.

Bearing header pressure is 8 to 15 psig.

Oil flow through all bearing sight-glasses exists.

Seal water pressure to module > 300 psig.

Service water cooling available for lube oil and motor cooling.

Phone When directed as the TBO to verify the following:

Talker

• No. 11 RFP oil levels are normal.

• No. 11 RFP barrel temperature is within 50°F of system operating temperature (actual is 25°F).

• Bearing header temperature is 100°F.

• Bearing header pressure is 11 psig.

• Oil flow can be seen through all bearing sight-glasses.

• Seal water pressure is 325 psig.

• Service water cooling is available.

Report pre-start checks of the No. 11 RFP are completed satisfactorily.

Page 22 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 1 Page 2 of 3 Event

Description:

The crew will take the duty with the plant at 50% reactor power. Power was reduced last shift to perform on-line maintenance on the No. 11 RFP. After taking the duty the crew will start the No. 11 RFP.

Time Position Actions or Behavior BOP Verifies OPEN FW-61-1.

BOP Places HS-1100, 11 RFP RECIRC VALVE, handswitch in AUTO/START.

BOP Verifies OPEN CV-3489.

BOP Stations an operator at the RFP area, makes a plant announcement and starts the No. 11 RFP.

Phone Talker When directed as TBO to report to the RFP area report that you are standing by in the feed pump area.

BOP Verifies the following:

Balance drum flow is 30 - 115 gpm.

Vibration is less than 2.5 mils on all local vibration monitors.

Axial position is between +35 mils and -35 mils.

Phone When directed to verify the following:

Talker

• Balance drum flow is 30 - 115 gpm.

• Vibration is less than 2.5 mils on all local vibration monitors.

• Axial position is between +35 mils and -35 mils.

Report that post start checks of 12 Reactor Feed Pump are completed satisfactory.

BOP Place HS-1100, 11 RFP RECIRC VALVE, handswitch in AUTO.

BOP Verifies minimum flow of 3300 gpm on local flow controller, FIC-3489.

Phone When requested as TBO to verify minimum flow of 3300 gpm on local flow controller FIC-Talker 3490, report minimum flow of 3300 gpm on FIC-3490.

BOP Verifies the following:

Bearing header oil flow is > 8 gpm.

Bearing header discharge pressure is > 6 psig.

Phone When requested to verify bearing header flow is >8 gpm and bearing header discharge Talker pressure is >6 psig, report bearing header flow and pressure is normal.

Page 23 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 1 Page 3 of 3 Event

Description:

The crew will take the duty with the plant at 50% reactor power. Power was reduced last shift to perform on-line maintenance on the No. 11 RFP. After taking the duty the crew will start the No. 11 RFP.

Time Position Actions or Behavior BOP Places the No. 11 RFP Aux Oil pump handswitch to AUTO, pausing momentarily in OFF to allow logic to reset.

BOP Verifies No. 11 RFP Aux Oil Pump has stopped.

BOP Directs out plant operator to:

Maintain oil temp to bearings at 100 to 120°F.

Ensure seal water drain temperatures are maintained approx. 170°F.

Phone When directed to:

Talker

• Maintain oil temp to bearings at 100 to 120°F

• Ensure seal water drain temperatures are maintained approx. 170°F.

• Close warm-up valves FW-69-2 & FW-70-2.

Wait 2 minutes and then report that the above temperatures are in-spec and warm-up valves are closed.

BOP Closes warm-up valves FW-69-2 & FW-70-2.

BOP Verifies the bias setting of the main FW control valve M/A stations is set to maintain approximately equal flow in each feedwater train.

Note: Bias settings should not require adjustment.

BOP Verifies final FW temperatures within 3.5°F of each other by comparing computer points CFW524 & CFW525.

BOP Report to the SRO that #12 RFP is in service Notes:

Page 24 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 2 Page 1 of 1 Event

Description:

After the No. 11 RFP has been started the crew will begin to return reactor power to 100%.

Time Position Actions or Behavior SRO Review Official 3D Monitor printout and Periodic Log.

SRO Reviews B.06.01-06 Figure 13, Recommended Time To Make Changes From One Steady-State Load To Another Steady-State Load.

SRO Direct RO to raise Reactor power to 60% using recirc flow.

RO Raise Reactor power to 95% per C.2-05, POWER OPERATION.

BOP Monitoring plant parameters and may act as Peer Checker.

Notes:

Page 25 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 3 Page 1 of 2 Event

Description:

When reactor power approaches 60% and while performing adjustments to Recirc pump speed, a failure will occur causing a slow, steady rise in No. 11 Recirc pump speed. The RO should diagnose this failure of speed control and by procedure lock the scoop tube.

Time Position Actions or Behavior Simulator TRG #1: When reactor power has reached 60%, or at the discretion of the Chief Examiner, Operator insert event #1 to cause a speed failure on A Recirc Flow Control.

SRO Acknowledges report from RO that speed continues to increase on the A Recirc Pump.

SRO Directs the RO to perform B.01.04-05.H.1, UNSTABLE SPEED CONTROL ON ONE PUMP.

SRO Acknowledge report from RO of annunciator 4-C-5, FLUID DRIVE A SCOOP TUBE LOCK.

SRO Notifies the Nuclear Engineer.

Phone When informed as the Nuclear Engineer of the loss of speed control on the A Recirc Talker Pump, recommend that the crew reduce speed on the A Recirc Pump locally to match B Recirc Pump speed.

SRO Directs the RO to reduce speed locally for the A Recirc Pump, coordinating with licensed RO in-plant, to match B Recirc Pump speed.

SRO Refers to Tech Spec 3/4.6.G.

SRO Notifies the following:

General Superintendent Operations Superintendent Electrical and Instrument Engineering Instrument Engineer Phone Acknowledge report from CRS as the managers stated for the given plant condition.

Talker RO Informs CRS that speed continues to increase on the A Recirc Pump after control switch is released.

Page 26 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 3 Page 2 of 2 Event

Description:

Event

Description:

When reactor power approaches 60% and while performing adjustments to Recirc pump speed, a failure will occur causing a slow, steady rise in No. 11 Recirc pump speed. The RO should diagnose this failure of speed control and by procedure lock the scoop tube.

Time Position Actions or Behavior RO Performs actions from B.01.04-05.H.1, UNSTABLE SPEED CONTROL ON ONE PUMP.

RO Depressed the SCOOP TUBE LOCK pushbutton for the A Recirc Pump.

RO Acknowledges annunciator 4-C-5.

RO Coordinates with in-plant RO to adjust speed of the A Recirc Pump to match speed of the B Recirc Pump.

RO Establishes communications with the RO in-plant.

Phone When directed as in-plant RO, report that communications have been established Talker at the A Recirc MG Set.

RO Directs the in-plant RO to slowly turn the handcrank in the counter-clockwise direction to lower pump speed.

Phone When directed as in-plant RO to slowly reduce A Recirc Pump speed; Talker coordinate with the simulator operator, begin to reduce pump speed from the

& simulator computer, and report to the RO that you are turning the handcrank in Simulator the counter-clockwise direction.

Operator RO Stops the in-plant RO when speeds are matched.

Phone When directed as the in-plant RO to stop reducing pump speed stop, coordinate Talker with the simulator operator to stop reducing pump speed and report to the RO

& that you have stopped turning the handcrank.

Simulator Operator RO Informs CRS that Recirc pump speeds are matched.

BOP Monitoring plant parameters and may act as a peer checker.

Notes:

Page 27 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 4 Page 1 of 2 Event

Description:

After completion of actions for the failure of No. 11 Recirc pump speed control an automatic initiation of the RCIC system will occur. The crew should work together to diagnose this event by watching reactor water level and RCIC controls and indications. The crew should enter the C.4 to secure RCIC and determine Tech Spec and reportability requirements.

Time Position Actions or Behavior Simulator TRG #2: When actions are complete for loss of speed control on A Recirc Pump or when Operator directed by the Chief Examiner, insert event trigger #2 to cause an auto initiation of RCIC.

SRO Recognize RCIC has started.

SRO Review Technical Specification 3.5.A.2 - 14 day LCO SRO Directs System Eng and I&C to investigate.

Phone When contacted as System Engineering or I&C to investigate RCIC initiation acknowledge Talker the request.

SRO May look into Reportability Requirements, this is normally the duty of the Shift Manager.

(Procedure 4 AWI-04.08.02)

RO Recognize RCIC has started.

RO Acknowledge annunciator 5-B-24 REACTOR WATER LEVEL HI/LO (if actuated).

Note: This assumes RCIC injects and RPV high water level results.

RO Verify RPV water level is >-47 inches as indicated on LI-6-94A & B and LI-2-3-85A & B RO Notify Shift Supervision.

Perform applicable C.4-G INADVERTENT ECCS INITIATION Immediate Operator BOP Actions.

BOP Verify RPV water level >-47 inches.

Page 28 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 4 Page 2 of 2 Event

Description:

After completion of actions for the failure of No. 11 Recirc pump speed control an automatic initiation of the RCIC system will occur. The crew should work together to diagnose this event by watching reactor water level and RCIC controls and indications. The crew should enter the C.4 to secure RCIC and determine Tech Spec and reportability requirements.

Time Position Actions or Behavior BOP Verify RPV water level is normal.

BOP Determine manual override is allowed.

BOP Depress the RCIC TURBINE TRIP pushbutton.

BOP Report to SRO actions taken and plant conditions.

Notes:

Page 29 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 5 Page 1 of 2 Event

Description:

After RCIC has been addressed a trip of the running stator cooling pump will occur with a failure of the standby pump to auto start. The BOP operator should manually start the standby pump.

Time Position Actions or Behavior Simulator TRG #3: When actions for RCIC auto initiation are complete or when directed by the Operator Chief Examiner, insert event trigger #3 to cause a trip of the Stator Cooling Pump with a failure of the 12 Stator Cooling Pump to auto start.

SRO Acknowledge report of annunciator 8-A-17, NO. 1 GENERATOR COOLING WTR FAILURE.

SRO Acknowledges failure of 11 Stator Cooling Water Pump and manual start of 12 Stator Cooling Water Pump.

RO Monitoring plant parameters.

BOP Acknowledge annunciator 8-A-17 NO. 1 GENERATOR COOLING WTR FAILURE and reports to SRO.

BOP Determines that 11 Stator Cooling Water pump is not running and 12 Stator Cooling Water Pump has not automatically started.

BOP Manually starts 12 Stator Cooling Water Pump.

BOP Consults ARP 8-A-17 NO. 1 GENERATOR COOLING WTR FAILURE.

BOP Determine trouble from annunciator Panel C-83A.

Phone When requested as TBO to investigate Panel C-83A for cause of generator Talker cooling water failure wait 3 minutes and report Annunciator C-83A-8, Reserve Pump Running, is in alarm.

Page 30 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 5 Page 2 of 2 Event

Description:

After RCIC has been addressed a trip of the running stator cooling pump will occur with a failure of the standby pump to auto start. The BOP operator should manually start the standby pump.

Time Position Actions or Behavior BOP Verify a Stator Cooling Water Pump is running.

Phone If asked as TBO to perform post-start checks of 12 Stator Cooling Water Pump Talker wait 2 minutes and report Post start checks of 12 Stator Cooling Water Pump are completed satisfactorily.

BOP Notify Shift Supervisor and System Engineer.

Phone If asked to investigate the trip of the stator cooling water pump as system engineer Talker acknowledge the request.

BOP Refer to C.4-B.6.2.4.A STATOR COOLING WATER FAILURE for further guidance.

BOP Verify a Stator Cooling Water Pump is running.

BOP Notify Shift Supervision.

BOP Determines that no further action is required per C.4-B.6.2.4.A.

BOP Reports failure of 11 Stator Cooling Water Pump and manual start of 12 Stator Cooling Water Pump to SRO.

Notes:

Page 31 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 6 Page 1 of 1 Event

Description:

At the completion of actions for the trip of the running stator cooling pump a failure of the rector water level setpoint on the digital feedwater control system will occur. This will result in a slowly lowering reactor water level and will require the RO to take manual control of both FWRVs.

Time Position Actions or Behavior Chief NOTE: This event may need to start before completing actions for the loss of No. 11 Examiner Stator Cooling Pump to ensure that the OATC takes the applicable actions.

Simulator TRG #4: When actions for loss of 11 Stator Cooling Pump are completed or when directed Operator by the Chief Examiner, insert event trigger #4 to cause a failure of reactor water level setpoint on the digital feedwater control system.

SRO Acknowledge report of annunciator 5-B-24, REACTOR WATER LEVEL HI/LO.

SRO Acknowledge report of actions taken by RO to control reactor water level.

SRO Notifies I&C and System Engineering to investigate.

Phone When contacted as System Engineering or I&C acknowledge the request; no further Talker response is required.

RO Acknowledge annunciator 5-B-24, REACTOR WATER LEVEL HI/LO.

RO Refers to C.4-B.05.07.A, LOSS OF REACTOR WATER LEVEL CONTROL.

RO Takes manual control of both FW Reg Valves to control reactor water level.

RO Notifies CRS of actions taken.

RO Controls reactor water level between 30 and 40 inches in manual.

RO Notifies System Engineer to investigate the cause and correct if possible.

BOP Monitoring plant parameters and may assume manual control of reactor water level.

Page 32 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 1 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior Simulator TRG #5: When RPV level control is in manual or when directed by the Chief Examiner, Operator insert event trigger #5 to cause a loss of offsite power with a concurrent failure of the No.

12 EDG to start.

SRO Announce now entering Transient Annunciator Response SRO Notify the Transmission System Operator of the LONOP Condition and determine the status of offsite power. (C.4-B.9.02.B)

Phone If notified of the Loss of Offsite Power and questioned about status report that Talker Transmission System Operator acknowledges the loss of off-site power at Monticello, Grid status is normal, and further investigation will be performed.

SRO Enter C.5-1100, RPV CONTROL.

SRO Verify:

• Reactor Scram

• All rods in to at least 04 SRO Check Detail A for instrument limits.

SRO Verify no instrument limits have been exceeded.

SRO Directs RO/BOP to restore and maintain RPV water level +9 to +48 inches using:

• RCIC

• CRD (C.5-3204 - RPV MAKEUP WITH CRD)

• HPCI

• SBLC NOTE: If RCIC is manually started ensure event trigger #7 automatically inserts to cause RCIC overspeed trip.

NOTE: If HPCI is manually started ensure event trigger #6 automatically inserts to cause HPCI steam line break.

Page 33 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 2 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior SRO Ascertain that RPV water level cannot be restored and maintained > +9 inches.

SRO Modify RPV water level band to maintain level >-126 inches.

SRO Direct RO to inject with SBLC per C.5-3203 - USE OF ALTERNATE INJECTION SYSTEMS FOR RPV MAKEUP SRO Ascertain that RPV level cannot be maintained >-126 inches.

SRO Proceed to Step 2 in C.5-1100.

SRO Direct BOP operator to inhibit ADS.

NOTE: ADS may have been inhibited per step 1 if the ADS timer started.

SRO Direct BOP operator to start Div 1 LPCI and Core Spray pumps such that a minimum of two (2) injection subsystems are running.

SRO Verify two or more injection subsystems lined up.

SRO Determine RPV level has dropped to -126 inches.

SRO Verify any injection source lined up with pump running.

SRO Enters C.5-2002 - EMERGENCY RPV DEPRESSURIZATION, before water level drops to -149 inches, while continuing on in 1100 step 5.

SRO C.5-2002 - EMERGENCY RPV DEPRESSURIZATION SRO Verify all rods inserted.

Page 34 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 3 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior SRO Verify drywell pressure >2 psig.

SRO Determine Core Spray and LPCI injection IS required for core cooling and leave pumps running.

SRO Verify Torus level >-5.9 ft.

SRO Direct BOP operator to open 3 ADS valves.

Critical Step SRO Continue C.5-1100 SRO Verify 1 Core Spray and 1 RHR pump available.

SRO Verify injection to the RPV with running injection systems.

SRO When RPV level can be restored and maintained above -126 inches then return to C.5-1100 step 1.

SRO Modify level band to restore and maintain RPV water level +9 to +48 inches.

SRO Direct Core Spray and LPCI injection be prevented, as necessary, to maintain water level per C.5-3205 - TERMINATE AND PREVENT.

RO Carry out actions of C.4.A REACTOR SCRAM RO Determine all control rods are inserted to or beyond position 04.

RO Place the reactor mode switch in SHUTDOWN.

Page 35 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 4 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior RO Notify Shift Supervision.

RO Verify that the Recirc pumps have tripped.

RO Control Reactor water level between +9 and +48.

RO Verify HPCI & RCIC initiate to restore and control Reactor water level. RCIC will need to be started manually.

Simulator NOTE: Verify that RCIC trips on overspeed (Trigger #7) and HPCI steam line rupture Operator occurs (Trigger #6) on start of RCIC and HPCI.

RO Insert SRM and IRM detectors.

RO Verify the Scram Discharge Vent and Drain Valves close.

RO Direct the TBO to verify proper operation of the EDG SW pumps and verify EDG room ventilation is operating properly.

Phone If contacted as TBO to verify proper operation of EDG SW pumps and EDG room Talker ventilation acknowledge direction, no further communication is necessary.

RO Enter C.5-3204 RPV MAKEUP WITH CRD RO Verify 11 pump is available.

RO Verify CRD is not being used to insert control rods.

Page 36 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 5 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior RO Direct the RBO to:

• Verify CLOSED CRD-168.

• Verify OPEN CRD-8.

• Verify OPEN CRD-30.

• Close CRD 7-1.

Phone When directed as RBO to perform the following:

Talker

• Verify CLOSED CRD-168

• Verify OPEN CRD-8

• Verify OPEN CRD-30

• Close CRD 7-1 & CRD 7-2 After approximately 2 minutes report that you have accomplished the above listed items.

RO Locate Part E of procedure C.5-3203 - USE OF ALTERNATE INJECTION SYSTEMS FOR RPV MAKEUP.

RO Verify No. 11 (A) SBLC pump is available.

RO Query the SS as to the desired SBLC suction source: (either is permissible)

• Boron Tank or

• Demin Water RO If directed to use the boron tank suction, perform the following:

RO Verify SBLC in standby readiness.

RO Start 11 or 12 SBLC pump from CO5.

RO Place HS 11A-S1 on CO5 to SYS 1 or SYS 2.

Page 37 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 6 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior RO Direct the RBO to attempt to fill the SBLC tank with any of the following:

• Demin Water

• Condensate Service Water

• Fire System Phone If directed as RBO to attempt to fill the SBLC tank, wait approximately 2 Talker minutes and report that valves have been repositioned.

RO If directed to line up Demin water to the SBLC suction, perform the following:

Phone If directed to line up Demin water to fill the SBLC tank, wait approximately 2 Talker minutes and report that valve XP-1 is closed and valve DM-56 is open.

RO Direct the RBO to CLOSE XP-1.

RO Direct the RBO to OPEN DM-56.

RO Start 11 or 12 SBLC pump from CO5.

RO Place HS 11A-S1 on CO5 to SYS 1 or SYS 2.

BOP Carry out actions of C.4.A REACTOR SCRAM BOP Verify 8N4 and 8N5 are open.

BOP Verify the Turbine is tripped.

BOP Verify the Turbine-Generator field breaker is OPEN.

Page 38 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 7 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior BOP Carry out actions of C.4-B.9.2.B LOSS OF NORMAL OFFSITE POWER BOP Notify Shift Supervision.

BOP Place the following C-O8 switches in the position noted.

Control Switch Breaker Position 152-301/CS 2R XFMR SEC TO 13 BUS NORMAL AFTER TRIP 152-101/CS 2R XFMR SEC TO 11 BUS NORMAL ATER TRIP 152-201/CS 2R XFMR SEC TO 12 BUS NORMAL AFTER TRIP 152-401/CS 2R XFMR SEC TO 14 BUS NORMAL AFTER TRIP 52-209/CS 101/102 LC TIE ACB 52-908 PULL-TO-LOCK 52-908/CS 109/102 LC TIE ACB 52-908 PULL-TO-LOCK BOP Verify 1AR Voltmeter indicates zero volts.

BOP Place the following C-08 switches in the position noted.

Control Switch Breaker Position 152-511/CS 1AR TRANS TO 15 BUS PULL-TO-LOCK 152-610/CS 1AR TRANS TO 16 BUS PULL-TO-LOCK BOP If Bus 16 is de-energized perform the following:

BOP Place the following control switches on C-03 in the position noted.

Control Switch Breaker Position 152-604/CS 12 RHR PUMP (10A-S2B) PULL-TO-LOCK 152-603/CS 12 RHR PUMP (10A-S2B) PULL-TO-LOCK 152-605/CS 12 CS PUMP (14A-S5B) PULL-TO-LOCK Page 39 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 8 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior BOP Place the following control switches on C-08 in the position noted.

Control Switch Breaker Position 152-610/CS 1AR TRANS TO 16 BUS PULL-TO-LOCK 152-602/CS 12 STDBY DG TO BUS 16 PULL-TO-LOCK BOP Initiate an investigation to determine the status of the No. 12 EDG.

Phone Talker If contacted as System Engineer to investigate the cause of the failure of No. 12 EDG to start, report that you will investigate the problem.

BOP Place DG2/CS, 12 EDG CS, in PTL.

BOP Place 152-602/CS in PTL.

BOP Press both local ENGINE STOP pushbuttons on C-94 simultaneously.

BOP Verify a Service Water Pump is running.

NOTE: No. 11 Service Water Pump breaker remains closed therefore

1. 11 Service Water Pump will automatically restart when power is restored to #15 4160 Bus.

BOP Start an RBCCW Pump.

NOTE: RBCCW will trip and must be restarted after power is restored via the EDGs.

BOP CRD Pumps will trip and must be restarted after power is restored via the EDGs.

NOTE: CRD Pumps will trip and must be restarted after power is restored via the EDGs.

Page 40 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 9 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior BOP Place the following switches on C-06 in the position noted.

Control Switch Position 11 REACTOR FEED PUMP P-2A STOP 12 REACTOR FEED PUMP P-2B STOP 11 CONDENSATE PUMP P-1A STOP 12 CONDENSATE PUMP P-1B STOP 11 CIRC WATER PUMP P-100A TRIP S/D 12 CIRC WATER PUMP P-100B TRIP S/D BOP Restore Drywell Cooling as conditions allow.

BOP Drywell Cooling fans will trip on the ECCS load shed.

NOTE: Drywell Cooling fans will restart but the fan dampers must be opened.

BOP Verify the Emergency Diesel Generators meet the following load limitations during the performance of procedure.

2500 KW 2750 KW 3050 KW Continuous 2000 hrs 30 min BOP Verify start of the Emergency Seal Oil Pump.

BOP Start the Turning Gear Oil Pump.

BOP Direct the TBO to verify proper operation of #13 Diesel Generator.

Phone When directed as the TBO to verify proper operation of the No. 13 EDG Talker wait 4 minutes and reply, The No. 13 EDG is operating properly.

Page 41 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 10 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior BOP C.4-H, Part C, Step 6, Div. I ECCS Load Shed bypass.

NOTE: When high drywell pressure (+2 psig) is reached an ECCS load shed will occur which trips operating Service Water, RBCCW, CRD pumps and Drywell Cooling fans. Part C, step 6, of C.4-H RESTORATION OF PLANT LOADS must be performed to restore Div. I loads. Personnel availability may preclude entering C.4-H until EOP Containment Control (1200 series) actions are complete.

BOP Place 11 Instrument and Service Air Compressor to OFF.

BOP Place 11 Service Water Pump handswitch 52-305/CS in STOP.

BOP Place 11 RBCCW Pump P-6A handswitch 42-3318/CS in STOP.

BOP Verify A CGCS Containment isolation switches CS-1A &

CS-2A are in close. (Panel C-291A)

BOP Place Drywell Fan control switches 42-3312/CS (V-RF-1) and 42-3313/CS (V-RF-3) in OFF.

BOP Boot contacts 7-8 on Relay 14A-K1A. (Div. I Bypass)

BOP Start loads as necessary (see attached procedures).

BOP 11 Service Water Pump per steps 1 - 10 of B.08.01.01-05.D.1 BOP 11 RBCCW Pump per steps 1 - 14 of B.02.05-05.D.1 BOP 11 Instrument & Service Air Compressors per steps 1 - 16 of B.08.04.01-05.D.1 Page 42 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 2 Event No. 7 Page 11 of 11 Event

Description:

After the crew has manual control of both FWRVs, or if the reactor scrams, then a loss of off-site power with a failure of the No. 12 EDG to start will occur. The crew will need to take level control actions through the use of HPCI, RCIC, CRD and SBLC.

Time Position Actions or Behavior BOP 11 and 13 Drywell Fans per steps 1 - 10 of B.08.16-05.D.1 BOP 11CRD Pump per steps 1 - 15 of B.01.03-05.D.1 BOP Place switches 2E-S7A & 2E-S7B on CO3 to INHIBIT.

BOP Place hand switches on CO3 for RHR and Core Spray pumps to START as directed.

_____ 11 RHR PUMP (HS 10A-S2A)

_____ 13 RHR PUMP (HS 10A-S3A)

_____ 11 CORE SPRAY (HS 14A-S5A)

BOP Verify the Emergency Diesel Generators meet the following load limitations during the performance of procedure C.4-B.9.02.B).

2500 KW 2750 KW 3050 KW Continuous 2000 hrs 30 min BOP Place hand switches for A, C & D SRVs to OPEN.

BOP Critical Verify 3 SRVs are open.

Step Notes:

Page 43 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 1 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control.

Time Position Actions or Behavior SRO Acknowledge Annunciator 5-B-28 DRYWELL HI PRESS SCRAM TRIP SRO Confirm Drywell high pressure as indicated on PR-2994 (CO4) and SPDS SRO Enter C.5-1200 PRIMARY CONTAINMENT CONTROL.

SRO Determine Drywell pressure >2 psig SRO Go to step 17 SRO Verify Torus level <14.1 ft and Torus pressure >2 psig.

SRO Direct BOP operator to start Torus spray per C.5-3502 - CONTAINMENT Critical SPRAY.

Step NOTE: If it is determined that RHR pumps are needed for core cooling, Torus spray will not be initiated until RPV level is restored.

SRO Determine Drywell pressure >12 psig.

SRO Verify within Fig. N, DW SPRAY LIMIT (SPDS 79)

SRO Verify Torus level below 4.3 ft.

SRO Verify Recirc Pumps have tripped Page 44 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 2 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control.

Time Position Actions or Behavior SRO Direct BOP operator to place DW COOLING FAN CONTROL SWITCHES in OFF.

SRO Direct BOP operator to start Drywell spray per C.5-3502.

Critical Step NOTE: Drywell spray will not be initiated until RPV level is restored.

SRO Direct BOP operator to stop Torus spray if Torus pressure drops below 2 psig.

SRO Direct BOP operator to start all available DW cooling per C.5-3503 - DEFEAT DRYWELL COOLER TRIPS SRO Maintain Torus level -4.0 to +3.0 inches SRO Determine that Torus level can be maintained <+4.3 ft and >-3.3 ft. (steps 15 &

19)

SRO Determine that Torus temperature cannot be maintained <90 deg F.

SRO Direct BOP operator to place Torus cooling in service.

NOTE: If it is determined that RHR pumps are needed for core cooling, Torus Cooling will not be initiated until RPV water level is restored.

SRO Direct BOP operator to perform procedure C.5-3501 - H2/O2 ANALYZER OPERATION, as time permits.

BOP Start Div 1 Torus Spray per C.5-3502 - CONTAINMENT SPRAY, Part A.

Critical Step Page 45 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 3 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control.

Time Position Actions or Behavior BOP Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch to MANAUL OVERRIDE.

BOP Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch to BYPASS.

BOP Open MO-2006.

BOP Open MO-2010.

BOP Throttle open MO-2008.

BOP Verify closed, if necessary:

• MO-2012

• MO-2013 Verify CV-1728 controller set at 20%.

BOP BOP Close MO-2002.

BOP Place 11 and 13 RHRSW PUMPS LPCI AND ECCS LOAD SHED MANUAL OVERRIDE switch to MANUAL OVERRIDE.

BOP Place 11 or 13 RHRSW Pump in PTL.

BOP Start 11 or 13 RHRSW Pump.

BOP Adjust RHRSW flow using CV-1728.

Page 46 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 4 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control..

Time Position Actions or Behavior BOP Verify MO-2002 closed.

BOP Place DW COOLING FAN CONTROL SWITCHES in OFF.

BOP Start Div 1 Drywell Spray per C.5-3502 - CONTAINMENT SPRAY, Part C.

Critical Step BOP Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch to MANAUL OVERRIDE.

BOP Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch to BYPASS.

BOP Open MO-2020.

BOP Open MO-2022.

BOP Verify closed MO-2008.

BOP Verify closed, if necessary:

• MO-2012

• MO-2013 BOP Verify CV-1728 controller set at 20%.

BOP Close MO-2002.

BOP Place 11 and 13 RHRSW PUMPS LPCI AND ECCS LOAD SHED MANUAL OVERRIDE switch to MANUAL OVERRIDE.

Page 47 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 5 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control.

Time Position Actions or Behavior BOP Place 11 or 13 RHRSW Pump in PTL.

BOP Start 11 or 13 RHRSW Pump.

BOP Adjust RHRSW flow using CV-1728.

BOP Verify MO-2002 closed.

BOP Stops Torus spray if Torus pressure drops below 2 psig.

BOP Close MO-2010.

BOP Stops Drywell spray if Drywell pressure drops below 2 psig.

BOP Close MO-2020.

BOP Close MO-2022.

BOP Perform procedure C.5-3503 - DEFEAT DRYWELL COOLER TRIPS BOP Place all DW cooling fan control switches to OFF.

BOP OPEN knife switch KS3100 (behind panel C25).

BOP Verify FAN INLET DAMPER control switches in AUTO (C25).

BOP Place DW cooling fan control switch in ON.

Page 48 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 6 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control.

Time Position Actions or Behavior BOP OPEN associated discharge dampers for started fans.

BOP Perform procedure B.03.04-05.H.3 - TRANSFERRING A RHR FROM LPCI TO TORUS COOLING UNDER LOSS OF NORMAL OFF-SITE POWER CONDITIONS DURING ABNORMAL AND EMERGENCY CONDITIONS.

BOP Verify CV-1728 controller is set at 20%.

BOP Verify 11 and 13 RHRSW PUMPS LPCI AND ECCS LOAD SHED MANUAL OVERRIDE switch is in MANUAL OVERRIDE.

BOP Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch to MANAUL OVERRIDE.

BOP Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch to BYPASS.

BOP Verify closed MO-2002.

BOP Verify 11 or 13 RHR Pump in PTL.

BOP Verify 11 or 13 RHRSW Pump is running.

BOP Adjust RHRSW flow to approximately 3500 gpm using CV-1728.

BOP Partially open MO-2008 by holding handswitch to OPEN for 8 seconds.

Page 49 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 1 Event No. 8 Page 7 of 7 Event

Description:

When HPCI starts a steam line rupture from the HPCI system will occur. This will prevent HPCI from injecting into the reactor. If RCIC is manually started it will trip on overspeed. This will result in reactor water level continuing to lower until a blowdown is required. In addition to the HPCI steam line break, a small Recirc line break will occur simultaneously to help cause drywell pressure and temperature to rise. The crew will need to prioritize the needs of the low pressure systems for core cooling and containment control.

Time Position Actions or Behavior BOP Open MO-2006.

BOP Close MO-2012 or MO-2013 while throttling open MO-2008 to maintain approximately 4000 gpm total flow.

BOP Verify MO-2002 closed.

BOP Verify V-AC-5 in operation.

Phone If directed as RBO to verify V-AC-5 is in operation then wait 2 minutes and Talker report, V-AC-5 is operating normally.

BOP Perform C.5-3501 - H2/O2 ANALYZER OPERATION.

Notes:

Page 50 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Termination Point:

• Low pressure systems are injecting into the RPV.

• RPV level is above the top of active fuel.

• At the discretion of the Lead Evaluator.

Classification:

Classification: Guideline 4 (Reactor Coolant Leak); Site Area Emergency Page 51 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Appendix D Scenario Outline Form ES-D-1 Facility: MNGP Scenario No. NRC Op-Test No: 03-01 03-03 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 14% power. The Main Turbine has been placed on-line and the next step is to place the Main Turbine Generator in service. Ops Man C.1 is complete through step VII.C.4.

Turnover: Place the Main Turbine Generator in service and continue power increase.

Event Malf. Event Event No. No. Type* Description 1 N/A BOP (N) Synchronize the Main Generator to the Grid 2 N/A RO (R) Increase Power by Pulling Control Rods 3 SW03A BOP (C) No. 11 Service Water Pump Trip B22 4 FW22 RO (C) Hotwell Low Level 5 A28 BOP (C) Steam Packing Exhauster High Temperature 6 NI13D RO (I) APRM Channel No. 4 Fails Upscale 7 C08 M Design Basis Earthquake C13 C18 8 ED05C BOP (C) Loss of No. 13 Bus 9 RR04A M Nuclear Boiler Reference Line Break (results in loss of all RR24 level indication)

RR04B Equipment Out of Service B RWCU Pump APRM Channel #5

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 52 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 1 Page 1 of 5 Event

Description:

The Main Turbine has been placed in service by the previous shift. The crew will take the shift and then place the Main Generator in service.

Time Position Actions or Behavior SRO Direct the BOP Operator to synchronize the Main Generator to the grid.

SRO Acknowledge that Main Generator has been synchronized to the grid.

RO Monitoring plant parameters and may act as Peer Checker BOP Place the synchronizing switch for 8N4 or 8N5 in ON and verify the following:

(8N4SS or 8N5SS) (PROCEDURE C.1, STEP VI.C.5)

BOP Synchronizer pointer is moving. (Synchronizing meter CO8)

BOP Synchronizing Voltmeters and sensing lights are activated.

(Running and Incoming voltage meters CO8)

(White sensing lights below synchronizing meter CO8)

BOP Using the Speed Load Changer control switch, ADJUST generator speed until synchronous pointer rotation of one revolution in 30 - 120 seconds is achieved.

BOP Verify Generator Voltage is between 20.9 KV and 23.1 KV.

(Main Generator voltage meter CO8)

BOP Using the Manual Voltage Adjust control switch, ADJUST incoming voltage to match running voltage. (Running and Incoming voltage meters CO8)

BOP Verify the synchroscope makes at least two complete revolutions.

BOP Load the Main Generator by performing the following:

BOP Verify the synchrocope pointer is in the GREEN band.

Page 53 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 1 Page 2 of 5 Event

Description:

The Main Turbine has been placed in service by the previous shift. The crew will take the shift and then place the Main Generator in service.

Time Position Actions or Behavior BOP Place either 8N4 or 8N5 control switch to close for approx. 1 sec.

(Closed indication for the output breaker is indicated by RED lamp indication above the breaker and generator load present)

BOP If the selected output breaker does not close place the breaker control switch to TRIP and return to step 1 above. (step 5 in C.1)

BOP If the selected output breaker does not close on the second attempt, DO NOT reset the breaker and notify System Engineer.

Phone If contacted as System Engineering because the output breaker will not close direct that Talker several more attempts may be made because of the close tolerances for breaker closure.

Chief NOTE: If the breaker does not close the second time allow several more attempts.

Examiner BOP Place the SPEED LOAD CHANGER to RAISE and increase load to approximately 30 Mwe. (HS SLCM CO8)

BOP Verify phase-to-phase voltages are approx. equal. (HS VS1 CO8)

(Main Generator voltage meter CO8)

BOP Verify phase-to-phase currents are approx. equal.

(3 Generator Amperage meters CO8)

BOP Place synchroscope to OFF and remove handle from switch.

BOP LOG in the Control Room log.

BOP Direct TBO to locally inspect the No. 1 Generator Transformer area and 345KV disconnects.

If directed as the TBO to inspect the No. 1 Generator Transformer area and 345KV disconnects wait 2 minutes and report back that everything appears normal.

Page 54 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 1 Page 3 of 5 Event

Description:

The Main Turbine has been placed in service by the previous shift. The crew will take the shift and then place the Main Generator in service.

Time Position Actions or Behavior BOP Place the other output breaker synchronizing switch to ON and verify.

BOP Incoming and Running voltmeters are matched.

BOP Synchroscope indicated frequency is matched.

BOP CLOSE the selected output breaker. (8N4/CS or 8N5/CS)

BOP Verify phase-to-phase voltages are approx. equal. (HS VS1 CO8)

(Main Generator voltage meter CO8)

BOP Verify phase-to-phase currents are approx. equal.

(3 Generator Amperage meters CO8)

BOP Place synchroscope to OFF and remove handle from switch.

BOP LOG in the Control Room log.

BOP Notify the Transmission System Operator.

Phone If notified as Transmission System Operator of Generator synchronization, acknowledge Talker report.

BOP CLOSE the following valves:

• MO-1197 (HS 1197 CO7)

• MO-1184 (HS 1184 CO7)

• MO-1185 (HS 1185 CO7)

• MO-1186 (HS 1186 CO7)

• MO-1187 (HS 1187 CO7)

• MO-1180 (HS-1180 CO7)

• MO-1181 (HS-1181 CO7)

• MO-1182 (HS-1182 CO7)

• MO-1183 (HS-1183 CO7)

Page 55 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 1 Page 4 of 5 Event

Description:

The Main Turbine has been placed in service by the previous shift. The crew will take the shift and then place the Main Generator in service.

Time Position Actions or Behavior BOP ZERO the No. 1 MAIN GENERATOR AMPLIDYNE VOLTAGE using the REGULATOR VOLTAGE ADJUST. (CS-70 CO8)

BOP Place the REGULATOR TRANSFER switch to AUTO. (243/CS CO8)

BOP Verify the white and red lights above the switch are ON.

BOP ADJUST MVAR loading per system dispatch. (CS-90 CO8) (MVAR digital display)

Phone When contacted as System Dispatch to determine what MVAR loading should be Talker maintained at, direct to maintain MVAR loading between +10 and +20 MVAR.

BOP ZERO the No. 1 MAIN GENERATOR AMPLIDYNE VOLTAGE using the MANUAL VOLTAGE ADJUST. (CS-70 CO8)

NOTE: The following steps place the Power System Stabilizer in service. These steps will not be completed.

BOP Verify the Automatic Voltage Regulator is in service.

(white and red lights above the switch are ON)

Verify the No. 1 MAIN GENERATOR AMPLIDYNE VOLTAGE meter is at ZERO.

PRESS the Power System Stabilizer START button on CO8.

Verify the RED light below the button is ON.

BOP Verify Exhaust Hood Temperature is < 125 deg F.

(SPDS 654, Pt. TRB138 or TR-1717 Pts. 16 & 17)

BOP RAISE (slowly) the SPEED/LOAD CHANGER to increase generator load.

BOP Verify the SPEED/LOAD CHANGER is no longer controlling.

Page 56 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 1 Page 5 of 5 Event

Description:

The Main Turbine has been placed in service by the previous shift. The crew will take the shift and then place the Main Generator in service.

Time Position Actions or Behavior BOP RAISE the SPEED/LOAD CHANGER setpoint to the high speed stop (107%).

BOP SELECT SPDS Format 701 and monitor Generator Gross Rate of Change.

BOP Report to the SRO that the Main Generator has been synchronized to the grid.

Notes:

Page 57 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 2 Page 1 of 1 Event

Description:

The crew will increase Reactor power using control rods in accordance with the roller tape starting at Step 30 rod 14-39.

Time Position Actions or Behavior SRO C.1.VII - Power Ascension Verify outside air temperature is > 32 deg.

Verify Isophase Bus Blower in service.

Phone If directed to verify that Isophase Bus Blower is in service report that the Isophase Bus Talker Blower is in service.

SRO Direct RBO to reduce RWCU flow to 140 GPM.

Phone When directed to reduce RWCU flow to 140 gpm wait 2 minutes, verify that the Simulator Talker Operator has reduced flow to 140 gpm, and then report that RWCU flow has been reduce to 140 gpm.

SRO Increase reactor power per C.2-05 Power Operation - System Operation.

• Direct the RO to commence Control Rod Withdrawal continuing at step 30, Control Rod 14-39.

RO Withdraws control rods in accordance with Ops Man B.05.05-05.E.1, Control Rod Movement.

Place ROD SELECT POWER switch, 3A-S1, to ON.

Press the appropriate ROD SELECT pushbutton (control rod 14-39, step 30).

NOTE: The control rod will move 1 notch in the indicated direction when the ROD MOVEMENT CONTROL switch is momentarily placed in ROD NOTCH OUT or ROD IN.

Momentarily place ROD MOVEMENT CONTROL switch, 3A-S2, to ROD OUT NOTCH or ROD IN to obtain desired rod movement.

BOP Monitor Plant Parameters Notes:

Page 58 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 3 Page 1 of 2 Event

Description:

No. 11 Service Water Pump will trip and No. 12 Service Water Pump will not automatically start.

Operators will need to manually start No. 12 Service Water Pump.

Time Position Actions or Behavior Simulator TRG #1: When directed by the Chief Examiner insert event trigger #1 to cause the 11 Operator Service Water Pump to trip.

SRO Acknowledge report of 6-B-22, SERVICE WATER HDR LOW PRESSURE.

SRO Acknowledge report of action taken for trip of No. 11 Service Water Pump.

RO Monitor plant parameters.

BOP Acknowledge annunciator 6-B-22, SERVICE WATER HDR LOW PRESSURE.

BOP Report 6-B-22 to SRO BOP Monitor Service Water System pressure. (PI-1535 CO6)

BOP Determine Service Water System pressure is low, #11 Service Water Pump has tripped and 12 Service Water Pump did not automatically start.

(Indicating lights above HS 52-305CS & HS 52-405CS)

BOP Start #12 Service Water Pump. (HS 52-405CS to START)

BOP Verify #12 Service Water Pump starts and system pressure is restored.

(Indicating lights above HS 52-405CS) (PI-1535 CO6)

BOP Verify actions per C.4-B.8.1.1.A, LOSS OF SERVICE WATER.

BOP Notify Shift Supervision.

Page 59 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 3 Page 2 of 2 Event

Description:

No. 11 Service Water Pump will trip and No. 12 Service Water Pump will not automatically start.

Operators will need to manually start No. 12 Service Water Pump.

Time Position Actions or Behavior BOP Direct TBO to:

• Verify proper operation and alignment of Service Water Pumps.

• Verify integrity of the Service Water System.

• Verify proper operation of the Service Water Auto Strainer.

When directed to:

Phone

• verify proper operation and alignment of Service Water Pumps.

Talker

• verify integrity of the Service Water System.

• verify proper operation of the Service Water Auto Strainer.

Wait 2 minutes and then report that system integrity is intact and operation appears normal.

Notes:

Page 60 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 4 Page 1 of 2 Event

Description:

A Hotwell Low Level will be received due to the reject valve controller (CV-1093A & B) calling for 100% open. The controller will need to be placed in manual and the reject valve closed.

Time Position Actions or Behavior Simulator TRG #2: When actions for trip of No. 11 Service Water pump are complete or when Operator directed by the Chief Examiner, insert event trigger #2 to cause the hotwell reject level control valve to fail open.

NOTE: This event takes approx. 10 minutes from actuation to the Hotwell Low Level Alarm occurring.

Chief NOTE: Annunciators 6-A-24, COND BYPASS VALVE OPEN POSITION and Examiner 6-A-35, COND DMIN SYSTEM TROUBLE, will alarm prior to 6-A-31, COND E-1B HOTWELL HIGH/LOW LEVEL, alarming. These alarms indicate that plant conditions have changed but do not specifically identify the condensate reject valve throttled open. Candidates may ascertain the problem prior to 6-A-31 alarming.

SRO Acknowledge report of the following annunciators:

• 6-A-24, COND BYPASS VALVE OPEN POSITION

• 6-A-35, COND DMIN SYSTEM TROUBLE

• 6-A-31, COND E-1B HOTWELL HIGH/LOW LEVEL SRO Acknowledge report of action taken on Hotwell Low Level.

RO Acknowledge annunciator 6-A-35, COND DMIN SYSTEM TROUBLE.

RO Consult ARP 6-A-35 RO Contact TBO to ascertain which alarm on C-80 is actuated.

Phone When contacted as TBO to determine which alarm on C-80 is actuated wait 2 minutes then Talker report, Alarm 80-A-21, POWDEX SYSTEM HIGH D/P, is in alarm and system dP is 60 psid.

RO Acknowledge annunciator 6-A-24, COND BYPASS VALVE OPEN POSITION.

RO Consult ARP 6-A-24 RO Acknowledge annunciator 6-A-31, COND E-1B HOTWELL HIGH & LOW LEVEL Page 61 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 4 Page 2 of 2 Event

Description:

A Hotwell Low Level will be received due to the reject valve controller (CV-1093A & B) calling for 100% open. The controller will need to be placed in manual and the reject valve closed.

Time Position Actions or Behavior RO Consult ARP 6-A-31.

RO Verify Hotwell low level exists. (LR-1278 CO6)

Phone If directed as TBO to reset the Flow Balance Override (FBO) per B.06.06-05.G.4 then wait Talker 3 minutes and report, I have performed steps 1 thru 3 for resetting the FBO and it would not reset.

RO Determine LC-1093, Hotwell Reject Level Controller, is calling for 100% open.

RO Place LC-1093 in MANUAL.

RO Close LC-1093.

RO Monitor Reactor Feed Pump suction pressure. (PI-1120 & PI-1121 CO6)

RO Notify Shift Supervision.

RO Contact I&C to correct controller problem.

Phone If contacted as I&C about controller CV-1093A & B failure acknowledge report, and state Talker that it will be looked at very soon.

BOP Monitor plant parameters and assist in following up on annunciators.

Notes:

Page 62 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 5 Page 1 of 1 Event

Description:

A high temperature will be experienced on Steam Packing Exhauster K-3A. This will require the operator to start Steam Packing Exhauster K-3B and establish vacuum and then shutdown Steam packing Exhauster K-3A.

Time Position Actions or Behavior Simulator TRG #3: When actions for hotwell low level are complete or when directed by the Chief Operator Examiner, insert event trigger #3 to cause high motor temperatures on steam packing exhauster K-3A.

SRO Acknowledge report of 7-A-28, STM PKG EXH K3A & K3B BLWR MTR HI TEMP.

SRO Acknowledge report of action taken for Steam Packing Exhauster trouble.

RO Monitor plant parameters.

BOP Acknowledge annunciator 7-A-28 STM PKG EXH K3A & K3B BLWR MTR HI TEMP.

BOP Consult ARP 7-A-28 BOP Determine Steam Packing Exhauster K-3A is in service.

BOP START Steam Packing Exhauster K-3B. (HS 42-2122/CS to RUN CO7)

BOP ADJUST K-3B outlet valve MO-1049 to establish 10 H20 as indicated on PI-1220, STEAM PACKING EXH VAC. (HS-1049 CO7)

BOP STOP Steam Packing Exhauster K-3A. (HS 3122/CS to OFF CO7)

BOP CLOSE K-3A outlet valve MO-1048. (HS-1048 to CLOSE CO7)

BOP Notify Shift Supervision and Plant Electrician.

Phone If called as Plant Electrician to look at Steam Packing Exhauster K-3A aknowledge report Talker and state that you will have somebody look at it as soon as possible.

Notes:

Page 63 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 6 Page 1 of 2 Event

Description:

Channel 4 APRM will fail high causing a 1/2 trip of Channel B RPS scram logic. The OATC will need to insert a full B 1/2 scram. An evaluation will need to be done to ensure Tech Specs is being complied with.

Channel 4 APRM will then be bypassed and Channel B RPS scram logic will be reset.

Time Position Actions or Behavior Simulator TRG #4: When actions for steam packing exhauster high temperature are complete or Operator when directed by the Chief Examiner, insert event trigger #4 to cause APRM channel 4 to fail full scale.

SRO Acknowledge report of annunciators SRO Acknowledge failure of full RPS Bus B 1/2 scram to occur.

SRO Acknowledge action taken in response to APRM failure.

SRO Determine APRM has failed due to equipment failure.

SRO Determines minimum number of APRM channels is not satisfied per Technical Specification, Section 3.2 - Table 3.2.3.

SRO Direct RO to insert a full RPS B 1/2 scram.

SRO Notify System Engineer and I&C.

Phone If called as System Engineer about APRM Channel 4 failing high acknowledge report and Talker state that you will begin an investigation of the problem.

RO Acknowledge annunciators:

• 5-A-3, ROD WITHDRAW BLOCK

• 5-A-14, APRM HIGH

• 5-A-30, APRM HI HI INOP CH 4, 5, 6

• 5-B-3, REACTOR NEUTRON MONITOR SCRAM TRIP

• 5-B-5, REACTOR AUTO SCRAM CHANNEL B RO Report annunciators to SRO RO Determines that only RPS Bus B Scram Lights 1 & 4 have de-energized and that the full 1/2 scram has not occurred.

Page 64 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 6 Page 2 of 2 Event

Description:

Channel 4 APRM will fail high causing a 1/2 trip of Channel B RPS scram logic. The OATC will need to insert a full B 1/2 scram. An evaluation will need to be done to ensure Tech Specs is being complied with.

Channel 4 APRM will then be bypassed and Channel B RPS scram logic will be reset.

Time Position Actions or Behavior RO Consult ARPs RO Determine APRM #4 is indicating UPSCALE. (NR-7-46B CO5)

RO Determine Rod Block is actuated. (Annunciator 5-A-3 is in alarm)

RO Determine HI-HI indicating lamp for APRM 4 on panel C37 is ON.

RO Determine remaining APRM channels are within expected range. (NR-7-46A -D CO5)

RO Notify Shift Supervision and I&C.

Phone If called as I&C about APRM Channel 4 failing high and failure of a complete RPS Bus Talker B 1/2 scram, acknowledge report and state that somebody will begin to check it out as soon as possible.

RO Inserts a full 1/2 scram on RPS Bus B by depressing the B Scram Pushbutton.

BOP Monitors plant parameters and may act as a peer checker.

Notes:

Page 65 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 7&8 Page 1 of 6 Event

Description:

A Design Basis Earthquake will be felt which will cause a lockout of Bus 13. The Reactor will be manually scrammed and mitigative actions will be taken for the scram and the Bus 13 lockout.

Time Position Actions or Behavior TRG #5: When actions for failure of APRM No. 4 are complete or when directed by the Simulator Chief Examiner, insert event trigger #5 to initiate the following:

Operator

• Earthquake

• Operational Basis Earthquake

• Design Basis Earthquake after a 45 second time delay

• Lockout of 4160 VAC Bus 13 NOTE: When trigger #5 is inserted shake the procedure/form file cabinet for 5 seconds. When the Design Basis Earthquake alarms, 45 seconds after initiation of the event, shake the file cabinet again for 5 seconds.

SRO Acknowledge report of annunciators.

SRO May announce now entering Transient Annunciator Response.

SRO Determine a Design Basis Earthquake has occurred. (Prairie Island could be called if further clarification is desired).

Phone If called as Prairie Island to confirm the earthquake reply an earthquake has been Talker confirmed.

Chief NOTE: C.4.K Immediate Reactor Shutdown may be entered but is not required.

Examiner SRO Direct the RO to manually scram the reactor.

SRO Per C.4-B.09.06.B LOSS OF BUS 13 OR BUS 14:

• Monitor and control Reactor water level between +30 and +40 inches.

RO Depress REACTOR SCRAM A and B pushbuttons. (5A-S3A and 5A-S3B)

Page 66 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 7&8 Page 2 of 6 Event

Description:

At the completion of Event No. 6 or at the direction of the Chief Examiner, a Design Basis Earthquake will be felt which will cause a lockout of Bus 13. The Reactor will be manually scrammed and mitigative actions will be taken for the scram and the Bus 13 lockout.

Time Position Actions or Behavior RO Carry out actions of C.4.A REACTOR SCRAM RO Determine all control rods are inserted to or beyond position 04.

RO Place the reactor mode switch in SHUTDOWN.

RO Notify Shift Supervision.

RO Verify that the Recirc pumps are at minimum speed.

RO Control Reactor water level between +9 and +48 with Cond & Feed.

RO Place CV-6-13 (low flow valve) in AUTO.

RO Place CV-6-13 controller setpoint to 15 to 20 inches.

RO Verify CV-6-13 is closed when RPV level reaches 15 to 20 inches.

RO Insert SRM and IRM detectors.

RO Switch APRM/IRM recorders to IRM.

RO Monitor power by ranging down the IRMs to maintain indication on scale.

RO Verify the Scram Discharge Vent and Drain Valves close.

Page 67 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 7&8 Page 3 of 6 Event

Description:

At the completion of Event No. 6 or at the direction of the Chief Examiner, a Design Basis Earthquake will be felt which will cause a lockout of Bus 13. The Reactor will be manually scrammed and mitigative actions will be taken for the scram and the Bus 13 lockout.

Time Position Actions or Behavior RO Performs actions of C.4-B.01.03.A, LOSS OF CRD PUMP FLOW.

RO Start #12 CRDH Pump.

RO Verify CRD flow is available.

(PI-3-302 Charging Water Header Pressure - CO5)

(FI-3-306 Cooling Water Header Flow - CO5)

BOP Acknowledge annunciators:

• 6-C-8, EARTHQUAKE

• 6-C-13, OPERATIONAL BASIS EARTHQUAKE BOP Consult ARPs 6-C-8 & 6-C-13.

BOP Verify actuation of the Accelerograph Recording System. (Contacting system engineering is an option)

BOP Enter C.4-B.5.14A, EARTHQUAKE NOTE: Annunciator 6-C-18 will occur 45 seconds after initial earthquake annunciators (6-C-8 & 6-C-13).

BOP Acknowledge annunciator 6-C-18, DESIGN BASIS EARTHQUAKE.

BOP Announce over the paging system that a Reactor scram has occurred. (C.4.A)

BOP Carry out actions of C.4.A, REACTOR SCRAM BOP When Generator power is 0 Mwe OPEN 8N4 and 8N5. (CO8)

Page 68 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 7&8 Page 4 of 6 Event

Description:

At the completion of Event No. 6 or at the direction of the Chief Examiner, a Design Basis Earthquake will be felt which will cause a lockout of Bus 13. The Reactor will be manually scrammed and mitigative actions will be taken for the scram and the Bus 13 lockout.

Time Position Actions or Behavior BOP TRIP the Turbine (Turbine emergency trip switch - CO7)

BOP Verify that Turbine-Generator field breaker is OPEN. (CO8)

BOP STOP the amplidyne. (Regulator Transfer Switch to OFF - CO8)

BOP START the Turbine Auxiliary Oil Pump. (CO7)

NOTE: Turbine Aux Oil Pump electrical reset is required for start. (C.4.H)

BOP Enter the following procedure:

• C.4-B.09.06.B, LOSS OF BUS 13 OR BUS 14

• C.4-B.01.03.A, LOSS OF CRD PUMP FLOW

• C.4-B.06.04.A, DECREASED CIRCULATING WATER FLOW

• C.4-B.06.03.A, DECREASING CONDENSER VACUUM

• C.4-B.09.06.C, LOSS OF BUS 15 OR BUS 16

• C.4-B.09.07.A, LOSS OF POWER TO LC-101 OR ITS MCCS

• C.4-B.09.07.C, LOSS OF POWER TO LC-103 OR ITS MCCS

• C.4-B.09.07.E, LOSS OF POWER TO LC-107 OR MCC-114

• C.4-B.09.07.G, LOSS OF POWER TO LC-109 OR ITS MCCS BOP Per ARP 8-B-11 NO 13 4160V BUS LOCKOUT BOP Verify #15 4160V bus has transferred to 1AR.

(152-511 breaker indication - Red OFF, Green ON - CO8)

(#15 bus voltage indication - CO8)

BOP Verify #11 & #12 Emergency Diesel Generators have started.

(#11 & #12 EDG voltage indication - CO8)

BOP Verify LC-107 transfer to LC-108.

Page 69 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 7&8 Page 5 of 6 Event

Description:

At the completion of Event No. 6 or at the direction of the Chief Examiner, a Design Basis Earthquake will be felt which will cause a lockout of Bus 13. The Reactor will be manually scrammed and mitigative actions will be taken for the scram and the Bus 13 lockout.

Time Position Actions or Behavior BOP Per C.4-B.09.06.B, LOSS OF BUS 13 OR BUS 14:

BOP OPEN ACB 52-901 (52-901/CS - CO8)

BOP Place 52-908/SS SYNC 109 CTR SEC ACB to ON - CO8 BOP CLOSE ACB 52-908 109/102 LOAD CTR TIE ACB (52-908/CS - CO8)

BOP Verify MO-1850 11 Cir Wtr Pump P-100 Discharge Valve has closed. (Bkr indicating lamps - CO6)

NOTE: MO-1850 will begin to automatically close when power is restored to LC-109.

BOP C.4-B.06.04.A, DECREASED CIRCULATING WATER FLOW BOP Place #11 Circulating Water Pump control switch to SHUTDOWN.

(152-305/CS - CO6)

BOP C.4-B.06.03.A, DECREASING CONDENSER VACUUM BOP Monitor LP Turbine exhaust pressures per SPDS 656.

BOP C.4-B.09.06.C, LOSS OF BUS 15 OR BUS 16 BOP Determine that Bus 15 is being powered by 1AR.

(152-511 breaker indication - Red OFF, Green ON - CO8)

(#15 bus voltage indication - CO8)

Page 70 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 7&8 Page 6 of 6 Event

Description:

At the completion of Event No. 6 or at the direction of the Chief Examiner, a Design Basis Earthquake will be felt which will cause a lockout of Bus 13. The Reactor will be manually scrammed and mitigative actions will be taken for the scram and the Bus 13 lockout.

Time Position Actions or Behavior BOP Consider shutdown of #11 & #12 Emergency Diesel Generators.

BOP C.4-B.09.07.A, LOSS OF POWER TO LC-101 OR ITS MCCS BOP No action required - LC-101 re-powered automatically.

BOP C.4-B.09.07.C, LOSS OF POWER TO LC-103 OR ITS MCCS BOP Monitor system operation for RBCCW, Stator Cooling, Drywell Ventilation, Service Water and Hydrogen Seal Oil.

BOP C.4-B.09.07.E, LOSS OF POWER TO LC-107 OR MCC-114 BOP Determine crosstie between LC-107 and LC-108 is closed.

(Indicated by control room lighting restored)

BOP C.4-B.09.07.G, LOSS OF POWER TO LC-109 OR ITS MCCS BOP No action required - LC-109 re-powered when breaker 52-908 was closed.

Notes:

Page 71 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 9 Page 1 of 6 Event

Description:

A reference line break will occur on the A side followed by a break in the B side after approximately 4 minutes. This will cause a loss of all level indication, which will drive the crew into C.5-2006, RPV FLOODING. Emergency Depressurization will be accomplished and then water injected to flood the vessel.

Time Position Actions or Behavior Simulator TRG #6: When directed by the Chief Examiner, insert event trigger #6 to cause the Operator following to occur:

• Rupture of RPV Instrumentation Line A immediately.

• Failure of the Wide Range Level Transmitter after 1 minute.

• Rupture of RPV Instrumentation Line B after 5 minutes.

NOTE: B side level instruments will fail 4 minutes after the A side. B side Chief instruments will fail as drywell pressure approaches +2 psig requiring entry Examiner into C.5-1100.

SRO Acknowledge report of annunciators.

SRO Verify RPV water level is known per:

• SPDS (Display 051)

• LI-6-52B and LI-2-3-85A.

SRO Enter C.5-1100, RPV CONTROL (Entry condition +2 psig drywell pressure)

SRO Verify:

• Reactor scram

• All rods in to at least 04 SRO Verify RPV water level instrument limits have not been exceeded.

SRO Determine RPV water level is unknown Critical Step SRO Leave C.5-1100 - RPV CONTROL SRO Enter C.5-2006 - RPV FLOODING at step 24 SRO Determine Torus level is above -5.9 ft.

Page 72 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 9 Page 2 of 6 Event

Description:

At the completion of Event No. 7&8 or at the direction of the Chief Examiner, A reference line break will occur on the A side followed by a break in the B side after approximately 4 minutes. This will cause a loss of all level indication which will drive the crew into C.5-2006, RPV FLOODING.

Time Position Actions or Behavior SRO Direct BOP operator to open 3 ADS valves.

Critical Step SRO Verify 3 ADS valves are open.

SRO Direct BOP operator to close the:

• MSIVs

• Main Steam Line Drains

• RCIC steam isolation valves SRO Direct BOP and RO to inject to the RPV using:

Critical

• Condensate Step

• LPCI

• Core Spray

• CRD SRO Inject until 3 SRVs are verified OPEN and RPV pressure at least 50 psi above DW pressure, but low as possible.

SRO Confirm Drywell high pressure as indicated on PR-2994 (CO4) and SPDS SRO Enter C.5-1200 PRIMARY CONTAINMENT CONTROL (Entry Condition +2 psig Drywell pressure).

SRO Determine Drywell pressure >2 psig SRO Go to step 17 SRO Verify Torus level <14.1 ft and Torus pressure >2 psig.

Page 73 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 9 Page 3 of 6 Event

Description:

At the completion of Event No. 7&8 or at the direction of the Chief Examiner, A reference line break will occur on the A side followed by a break in the B side after approximately 4 minutes. This will cause a loss of all level indication which will drive the crew into C.5-2006, RPV FLOODING.

Time Position Actions or Behavior SRO Direct BOP operator to start Torus spray per C.5-3502.

NOTE: If it is determined that RHR pumps are needed for core cooling, Torus spray will not be initiated until RPV level is restored.

SRO Direct BOP operator to stop Torus spray if Torus pressure drops below 2 psig.

SRO Direct BOP operator to start all available DW cooling per C.5-3503 SRO Maintain Torus level -4.0 to +3.0 inches SRO Determine that Torus level can be maintained <+4.3 ft and >-3.3 ft.

(steps 15 & 19)

SRO Direct BOP operator to perform procedure C.5-3501 as time permits.

RO Acknowledge annunciator 5-B-24 REACTOR WATER LEVEL HI/LO.

RO Consult ARP 5-B-24 REACTOR WATER LEVEL HI/LO.

RO Report annunciator 5-B-24 to SRO RO Determine LI-6-52A and LI-2-3-85B have failed upscale. (CO5)

RO Verify LI-6-52B and LI-2-3-85A indicates correctly. (CO5)

RO Determine Reactor Feed Pump trip has occurred on high RPV level and cannot be re-started.

Page 74 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 9 Page 4 of 6 Event

Description:

At the completion of Event No. 7&8 or at the direction of the Chief Examiner, A reference line break will occur on the A side followed by a break in the B side after approximately 4 minutes. This will cause a loss of all level indication which will drive the crew into C.5-2006, RPV FLOODING.

Time Position Actions or Behavior BOP Place hand switches for A, C & D SRVs to OPEN.

Critical Step BOP Determine ADS valves opened. (amber lamps on CO3 for A, C & D SRVs illuminated)

BOP Place MSIV handswitches to CLOSE. (C-03)

(HS 16A-S1A - 16A-S1D) (HS 16A-S2A - 16A-S2D)

BOP CLOSE MO-2373. (C-03) (Main Steam Line Drain) (HS 16A-S5)

BOP CLOSE MO-2374. (C03) (Main Steam Line Drain) (HS 16A-S6)

BOP CLOSE MO-2075. (C-04) (RCIC Isolation) (HS 13A-S1)

BOP CLOSE MO-2076. (C-04) (RCIC Isolation) (HS 13A-S3)

BOP Verify injection from Core Spray A & B and LPCI.

Critical Step BOP Verify 3 SRVs are OPEN after floodup is complete by SRV open AMBER lamps ON and RPV pressure increasing as indicated by Recirculation Pump Seal pressure.

BOP Remove Core Spray & LPCI injection as directed.

Notes:

Page 75 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 9 Page 5 of 6 Event

Description:

At the completion of Event No. 7&8 or at the direction of the Chief Examiner, A reference line break will occur on the A side followed by a break in the B side after approximately 4 minutes. This will cause a loss of all level indication which will drive the crew into C.5-2006, RPV FLOODING.

Time Position Actions or Behavior BOP Perform C.5-3502 Part A (B) for placing Torus Spray in service.

BOP Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch to MANAUL OVERRIDE.

BOP Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch to BYPASS.

BOP Open MO-2006 (MO-2007).

BOP Open MO-2010 (MO-2011).

BOP Throttle open MO-2008 (MO-2009).

BOP Verify closed, if necessary:

• MO-2012

• MO-2013 BOP Verify CV-1728 controller set at 20%.

BOP Close MO-2002 (MO-2003).

BOP Place 11 and 13 RHRSW PUMPS LPCI AND ECCS LOAD SHED MANUAL OVERRIDE switch to MANUAL OVERRIDE.

BOP Start 11 and/or 13 RHRSW Pump.

BOP Adjust RHRSW flow using CV-1728.

BOP Verify MO-2002 (MO-2003) closed.

Page 76 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 3 Event No. 9 Page 6 of 6 Event

Description:

At the completion of Event No. 7&8 or at the direction of the Chief Examiner, A reference line break will occur on the A side followed by a break in the B side after approximately 4 minutes. This will cause a loss of all level indication which will drive the crew into C.5-2006, RPV FLOODING.

Time Position Actions or Behavior BOP Locate procedure C.5-3503, Defeat Drywell Cooler Trips.

BOP Place all DW cooling switches to OFF (42-3312/CS, 42-4312/CS, 42-3313/CS, 42-4313/CS on C25 BOP OPEN knife switch KS3100 (behind panel C25)

BOP Verify FAN INLET DAMPER control switches in AUTO (C25)

BOP Place DW cooling fan control switch in ON. (42-3312/CS, 42-4312/CS, 42-3313/CS, 42-4313/CS on C25)

BOP OPEN associated discharge dampers for started fans.

BOP Locate C.5-3501 - H2/O2 ANALYZER OPERATION

• Perform as time allows.

Notes:

Page 77 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Termination Point:

• 3 SRVs open

• RPV pressure >50 psig above Drywell pressure

• Upon approval of Chief Examiner Classification:

Site Area Emergency - Guideline 22 (Earthquake)

Page 78 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Appendix D Scenario Outline Form ES-D-1 Facility: MNGP Scenario No. NRC Op-Test No: 03-01 03-04 Examiners: Operators:

Initial Conditions: The crew will take the duty with the plant at 100% reactor power. HPCI has been inoperable for the past 5 days for repairs. The off-going crew is in the progress of performing procedure 0255-06-IA-1 to complete the PMT requirements to restore HPCI to operable status. The next step in the procedure is to secure Torus cooling. The off-going crew has secured A RHR from Torus Cooling.

Turnover: Secure B RHR from the Torus Cooling Mode per step 81 of 0255-06-IA-1.

Event Malf. Event Event No. No. Type* Description 1 N/A BOP (N) Secure B RHR from Torus Cooling 2 CH08A RO (C) Trip of No. 11 CRD Pump Breaker 3 NI16B RO (I) RBM Channel No. 8 Failure Upscale (Tech Spec) 4 CW02B BOP (C) Trip of No. 12 Circ Water Pump 5 N/A RO (R) Rapid Power Reduction 6 TU05 BOP (C) Loss of Turbine Bearing Oil Header Pressure 7 CH16 M Failure to Scram CH19 Multiple Stuck Control Rods 8 SL01A RO (C) Failure of SBLC System 1(2)

(SL01B)

Equipment Out of Service B RWCU Pump APRM Channel #5 HPCI is inop for performance of 0255-06-IA-1.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 79 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 1 Page 1 of 2 Event

Description:

The crew will take the duty with the plant at 100% reactor power. HPCI has been inoperable for the past 5 days for repairs. The off-going crew is in the progress of performing procedure 0255-06-IA-1 to complete the PMT requirements to restore HPCI to operable status. The next step in the procedure is to secure Torus cooling. The off-going crew has secured A RHR from Torus Cooling. The crew should secure the B loop of Torus Cooling.

Time Position Actions or Behavior SRO Directs the BOP operator to secure B RHR from Torus Cooling per B.03.04-05.F.2, TORUS COOLING MODE-SHUTDOWN.

SRO Exits LCO 3.5.A and declares both LPCI injection paths operable.

SRO Directs BOP operator to complete procedure 0255-06-IA-1.

RO Monitors plant parameters.

BOP Secures Torus Cooling on B RHR per B.03.04-05.F.2.

BOP Slowly closes MO-2009 and holds control switch in close for 5 seconds after valve indicates closed.

BOP Closes MO-2007.

BOP Makes a plant announcement for securing 12 RHR Pump and to stand clear of the breaker in the upper 4kv room.

BOP Stops 12 RHR Pump and verifies min flow valves are closed.

BOP Verifies MO-2003 is open.

BOP Informs CRS that LCO 3.5.A can be exited.

BOP Makes a plant announcement for securing 12 RHRSW Pump and to stand clear of the breaker in the upper 4kv room.

Page 80 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 1 Page 2 of 2 Event

Description:

The crew will take the duty with the plant at 100% reactor power. HPCI has been inoperable for the past 5 days for repairs. The off-going crew is in the progress of performing procedure 0255-06-IA-1 to complete the PMT requirements to restore HPCI to operable status. The next step in the procedure is to secure Torus cooling. The off-going crew has secured A RHR from Torus Cooling. The crew should secure the B loop of Torus Cooling.

Time Position Actions or Behavior BOP Stops 12 RHRSW Pump per B.08.01.03-05.F.1 (SHUTDOWN OF RHRSW LOOP).

BOP Verifies closed RHRSW-32.

Phone When directed as the TBO to verify RHRSW-32 is closed wait 2 minutes Talker and reply, RHRSW-32 is closed.

BOP Contacts Chemistry to inject Biocide if required.

Phone When contacted as Chemistry to determine if Biocide injection is Talker required reply, Biocide injection is not required.

BOP Adjusts DPIC-10-130A to 0 to close CV-1728.

BOP Stops the 12 RHRSW Pump.

BOP Directs TBO to verify no motor cooling water flow into floor drain.

Phone When directed as TBO to perform step 7 and verify no motor cooling Talker water flow into floor drain wait 2 minutes and reply, B.08.01.03-05.F.1 Step 7 has been completed.

BOP Notifies Shift Chemist to valve out B RHR conductivity cell.

Phone When directed as Shift Chemist to valve out B RHR conductivity cell, Talker acknowledge the order, wait 3 minutes and then reply, The B RHR conductivity cell is valved-out .

BOP Vents high points and depressurizes per procedure 2145, RHR SYSTEM DISCHARGE VENTING.

Notes:

Page 81 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 2 Page 1 of 2 Event

Description:

When Torus cooling has been secured a trip of the running CRD pump breaker will occur. The OATC should immediately start the standby CRD pump and investigate the cause of the running pump trip. The in-plant operator should find the breaker in the trip free position. System engineering will need to investigate to determine the cause of the breaker trip.

Time Position Actions or Behavior Simulator TRG #1: When Torus Cooling has been secured or as directed by the Chief Examiner, Operator insert event trigger #1 to cause a trip of the No. 11 CRD Pump breaker.

SRO Directs OATC to perform actions of C.4-B.01.03.A, LOSS OF CRD PUMP FLOW.

SRO Notify Shift Supervision and System Engineer.

Phone If directed as system engineering to investigate the cause of the trip, acknowledge the Talker request; no further communication is necessary.

SRO Dispatch TBO to ACB-152-506 to investigate cause of the trip.

Phone If dispatched as TBO to ACB-152-506 to investigate cause of #11 CRD Pump trip, wait Talker approximately 2 minutes and report, The breaker overcurrent flag is dropped for the No.

11 CRD Pump.

SRO Acknowledge report of actions taken by RO.

RO Acknowledge annunciators:

• 5-B CHARGING WATER LOW PRESSURE

• 5-B CRD PUMP 3-16A BREAKER TRIPPED

• 5-B CRD PUMP 3-16A OL RO Verify #11 CRD Pump has tripped.

• #11 CRD Pump Breaker indication on CO5. (Green lamp ON, Red lamp OFF)

• CRDH system flow and pump discharge pressure has decreased to 0 as indicated on:

• PI-3-302 Charging Water Header Pressure. (CO5)

• FI-3-306 Cooling Water Header Flow (CO5)

If dispatched as RBO to investigate cause of No. 11 CRD Pump trip report, The No. 11 Phone CRD Pump motor seems to be hot.

Talker Page 82 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 2 Page 2 of 2 Event

Description:

When Torus cooling has been secured a trip of the running CRD pump breaker will occur. The OATC should immediately start the standby CRD pump and investigate the cause of the running pump trip. The in-plant operator should find the breaker in the trip free position. System engineering will need to investigate to determine the cause of the breaker trip.

Time Position Actions or Behavior RO Start #12 CRD Pump. (HS-3B-S4B to START)

RO Verify #12 CRD Pump Starts

• (#12 CRD Pump breaker indication - Green lamp OFF, Red lamp ON)

• (PI-3-302 Charging Water Header Pressure - CO5)

• (FI-3-306 Cooling Water Header Flow - CO5)

Phone If dispatched as RBO to check the No. 12 CRD Pump for proper operation wait 2 minutes Talker and report, The No. 12 CRD Pump is operating properly.

RO Monitor and Control system pressures and flows.

RO Verify required action per C.4-B.01.03.A, LOSS OF CRD PUMP FLOW, are complete.

RO Report actions taken for trip of CRD Pump to SRO.

BOP Monitoring plant parameters and may act as Peer Checker.

Notes:

Page 83 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 3 Page 1 of 1 Event

Description:

After completion of actions for the CRD pump trip, RBM Channel No. 8 will fail upscale. This failure will result in that RBM channel being bypassed and Tech Specs reviewed.

Time Position Actions or Behavior Simulator TRG #2: After completion of actions for trip of No. 11 CRD Pump or when directed by Operator the Chief Examiner, insert event trigger #2 to cause RBM Channel No. 8 to fail upscale.

SRO Acknowledge report of annunciator 5-A-51, RBM HI/INOP and 5-A-3, ROD WITHDRAWAL BLOCK.

SRO Notifies the Nuclear Engineer and System Engineer.

Phone When contacted as the Nuclear Engineer, direct the crew to de-select and then re-select the Talker control rod that was being withdrawn. (Only provide this direction if asked!)

SRO Refers to Tech Spec 3.2.C.2 and determines that RBM Channel No. 8 can be bypassed.

Phone If asked as RBM System Engineer, recommend that the crew bypass RBM Channel No. 8 to Talker allow for troubleshooting.

SRO Directs the operator to bypass RBM Channel No. 8.

RO Acknowledge annunciators 5-A-51, RBM HI/INOP and 5-A-3, ROD WITHDRAWAL BLOCK.

RO Reports 5-A-51 and 5-A-3 to SRO.

RO Check control rod withdrawal sequence.

RO Determines annunciator is due to RBM Channel No. 8 HI upscale.

RO Places the RBM BYPASS switch to position 8.

BOP Monitoring plant parameters and may act as Peer Checker.

Notes:

Page 84 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 4 Page 1 of 2 Event

Description:

At the completion of actions for the failure of RBM Channel No. 8, a trip of the No. 12 Circ Water pump will occur. This will cause condenser vacuum to start decreasing. The crew should enter the abnormal procedures for reduced circ water flow and lowering condenser vacuum. The CRS should direct the OATC to perform a rapid power reduction to aid in holding condenser vacuum. With Recirc reduced to minimum condenser vacuum will start to recover and power reduction can stop.

Time Position Actions or Behavior Simulator TRG #3: When the actions for RBM Channel 8 upscale are complete or when directed by Operator the Chief Examiner, insert event trigger #3 to cause a trip of the No. 12 Circ Water Pump.

SRO Acknowledges report of annunciators 6-C-10, CIRC WTR PP P-100B TRIP, 6-C-15, CIRC WTR PP P-100B OVERLOAD, and 5-B-46, CONDENSER LOW VACUUM.

SRO Directs BOP to perform C.4-B.06.04.A, DECREASED CIRCILATING WATER FLOW, and C.4-B.06.03.A, DECREASING CONDENSER VACUUM.

SRO Directs OATC to reduce Reactor Recirc flow per C.4-F, RAPID POWER REDUCTION.

SRO Notifies Shift Supervision.

SRO Notifies the System Engineer.

Phone When contacted as the System Engineer to investigate the trip of the No. 12 Circ Water Talker Pump acknowledge the order.

SRO Directs the TBO to investigate the cause of the pump trip.

Phone If contacted as TBO to investigate the cause of No. 12 Circ Water Pump trip wait 5 minutes Talker and report, I am unable to determine the cause of the No. 12 Circ Water Pump trip.

RO Acknowledges annunciator 5-B-46, CONDENSER LOW VACUUM.

RO Reduces Recirc flow per C.4-F, RAPID POWER REDUCTION, as necessary, to control condenser vacuum.

RO If core flow is < 26 Mlbm/hr then performs C.4-B.05.01.02.A, CONTROL OF NEUTRON FLUX OSCILLATIONS, concurrently.

Page 85 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 4 Page 2 of 2 Event

Description:

At the completion of actions for the failure of RBM Channel No. 8, a trip of the No. 12 Circ Water pump will occur. This will cause condenser vacuum to start decreasing. The crew should enter the abnormal procedures for reduced circ water flow and lowering condenser vacuum. The CRS should direct the OATC to perform a rapid power reduction to aid in holding condenser vacuum. With Recirc reduced to minimum condenser vacuum will start to recover and power reduction can stop.

Time Position Actions or Behavior RO Determines core flow is > 26 Mlbm/hr.

RO Notifies CRS of actions taken.

BOP Acknowledges annunciators 6-C-10, CIRC WTR PP P-100B TRIP, and 6-C-15, CIRC WTR PP P-100B OVERLOAD.

BOP Enters C.4-B.06.04.A, DECREASED CIRCILATING WATER FLOW.

BOP Places the control switch for the No. 12 Circ Water Pump in SHUTDOWN and verifies system valves automatically reposition.

BOP Monitors condenser d/p and circulating water condenser outlet temperature for air binding.

BOP Verifies that one cooling tower pump is shutdown and that cooling towers are aligned for one pump operation.

BOP Enters C.4-B.06.03.A, DECREASING CONDENSER VACUUM.

BOP Monitors LP turbine exhaust pressure on SPDS screen 656.

BOP Determines that neither LP turbine is in the ALERT region of Figure 1, TURBINE EXHAUST PRESSURE LIMITS. (after Recirc flow is reduced)

Notes:

Page 86 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 5 Page 1 of 2 Event

Description:

After the crew has performed the rapid power reduction and addressed the loss of the circ water pump, then a loss of turbine bearing oil header pressure will occur. Header pressure will slowly begin to lower and eventually cause a low pressure to alarm. The BOP operator will respond to the annunciator procedure and start the AOP and TGOP. This will cause header pressure to begin to rise but should only reach approximately 22-25 psig. The annunciator procedure will direct them to take the main turbine off line if pressure cannot be restored to above 30 psig.

In-plant operators will report that there is a large lube oil rupture in the turbine building.

Time Position Actions or Behavior Simulator TRG #4: When the actions for trip of the No. 12 Circ Water Pump are completed or when Operator directed by the Chief Examiner, insert event trigger #4 to cause a rupture of the turbine bearing oil header.

Phone Two minutes after inserting event trigger #4, call the Control Room as the TBO and report Talker that there is a large oil rupture near the Main Turbine.

SRO Acknowledges report of annunciator 7-A-33, TURB BRG OIL LOW PRESSURE.

SRO Acknowledges report from BOP operator for the need to remove the Turbine Generator from service.

SRO May direct the OATC to scram the reactor per C.4-K, IMMEDIATE REACTOR SHUTDOWN.

SRO May enter C.3, SHUTDOWN PROCEDURE, and commence a normal shutdown.

SRO Notifies Shift Supervision and System Engineer.

Phone When contacted as System Engineer about turbine bearing oil header rupture, Talker acknowledge the report. No further action is necessary.

RO Monitors plant parameters.

RO May manually scram the reactor based on plant conditions or as directed by CRS.

NOTE: If the crew does not manually scram the reactor and decides to shutdown the Turbine Generator per C.3, SHUTDOWN PROCEDURE, then the reactor will automatically scram due a loss of oil pressure to the TCVs and TSVs.

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2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 5 Page 2 of 2 Event

Description:

After the crew has performed the rapid power reduction and addressed the loss of the circ water pump, then a loss of turbine bearing oil header pressure will occur. Header pressure will slowly begin to lower and eventually cause a low pressure to alarm. The BOP operator will respond to the annunciator procedure and start the AOP and TGOP. This will cause header pressure to begin to rise but should only reach approximately 22-25 psig. The annunciator procedure will direct them to take the main turbine off line if pressure cannot be restored to above 30 psig.

In-plant operators will report that there is a large lube oil rupture in the turbine building.

Time Position Actions or Behavior RO Reports reactor scram and all control rods not inserted to the CRS.

BOP Acknowledges annunciator 7-A-33, TURB BRG OIL LOW PRESSURE.

BOP Monitors turbine bearing oil header pressure on C-07 Panel.

BOP Determines that header pressure continues to lower and starts the following pumps:

• Auxiliary Oil Pump

• Turning Gear Oil Pump BOP Determines that turbine bearing oil header pressure cannot be maintained above 30 psig.

BOP Notifies CRS of requirement to remove the Turbine Generator from service per C.3, SHUTDOWN PROCEDURE.

Notes:

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2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 1 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior SRO Acknowledges report of Reactor Scram and ATWS.

SRO Enter C.5-1100 RPV CONTROL (Entry Condition - Reactor power above 3% when scram required.

SRO Verify Reactor Scram has been initiated.

SRO Determine all rods ARE NOT in to at least 04.

SRO Determine the reactor WILL NOT stay shutdown under all conditions without boron.

SRO Leave C.5-1100 and Enter C.5-2007 SRO Enter C.5-2007 FAILURE TO SCRAM SRO Direct the BOP operator to inhibit ADS Critical Step SRO Direct the BOP operator to prevent Core Spray injection per C.5-3205, Critical TERMINATE AND PREVENT.

Step SRO Directs BOP operator to defeat RPV low water level MSIV isolation per C.5-3301.

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2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 2 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior POWER LEG SRO Verify Mode switch in SHUTDOWN.

SRO Directs RO to run back Recirc to minimum.

SRO Directs RO to trip Recirc Pumps.

SRO Direct RO to actuate ATWS.

SRO Directs RO to insert control rods per C.5-3101.

SRO Direct RO to inject SBLC.

Critical Step SRO Acknowledge report that SBLC System No. 1 failed and that SBLC System No. 2 is injecting.

PRESSURE LEG SRO Determine Drywell pressure is < 2 psig.

SRO Determine SRVs are not rapidly cycling.

SRO Consider LO-LO SET can stabilize RPV pressure.

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2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 3 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior LEVEL LEG SRO Check Detail A for instrument limits.

SRO Determine no instrument limits have been exceeded.

SRO Determine:

• Reactor power above 3%

• RPV water level >-33 inches SRO Direct BOP operator to Terminate and Prevent HPCI, LPCI and Condensate and Feed per C.5-3205.

SRO Determine Reactor power is < 3%.

SRO Record final RPV level on line 3.

SRO Direct that RPV level be maintained between -149 inches and value recorded on line 3 with Condensate and Feedwater and RCIC.

SRO Enter C.5-1200 PRIMARY CONTAINMENT CONROL TORUS TEMPERATURE STEP SRO Determine Torus temperature cannot be maintained < 90 deg f.

SRO Direct BOP operator to start all available torus cooling.

Page 91 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 4 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior SRO Verify Reactor scram has occurred.

SRO Determine Torus temperature can be maintained below fig M, HEAT CAPACITY LIMIT. (SPDS 78)

SRO Direct BOP operator to perform procedure C.5-3501 as time permits.

RO Carry out actions of C.4.A REACTOR SCRAM.

RO Determine if all control rods are inserted to or beyond position 04.

RO Place the reactor mode switch in SHUTDOWN.

RO Notify Shift Supervision.

RO Verify that the Recirc pumps have tripped.

RO Control Reactor water level between +9 and +48.

RO Verify Condensate and Feedwater and RCIC are used to restore and control Reactor water level.

RO Insert SRM and IRM detectors.

RO Verify the Scram Discharge Vent and Drain Valves close.

Page 92 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 5 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior RO Direct the TBO to verify proper operation of the EDG SW pumps and verify EDG room ventilation is operating properly.

Phone When directed as TBO to verify proper operation of the EDG SW pumps and Talker verify EDG room ventilation is operating properly wait 4 minutes and reply EDG SW Pumps and EDG Room Ventilation is operating properly.

RO Refer to procedure B.05.06-05 ATWS SYSTEM MANUAL INITIATION (hard card)

B MAN and ATWS D MAN (PB S-5B & S-5D) (CO5)

RO SET the arming collars of one pair of the following switches to the armed position and depress the pushbuttons:

ATWS A MAN and ATWS C MAN (PB S-5A & S-5C) (CO5)

OR ATWS B MAN and ATWS D MAN (PB S-5B & S-5D) (CO5)

RO Verify Recirc Pump MG Set generator field breakers have tripped.

(Field breaker indicating lights - CO4)

RO Trip the MG set drive motors.

RO Place HS 2A-S1A to STOP (#11 MG set drive motor breaker)

RO Place HS 2A-S1B to STOP (#12 MG set drive motor breaker)

RO Determine Control Rods DO NOT insert.

Page 93 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 6 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior RO Injects SBLC per the hard card.

RO Place SLC system selector switch to SYS 1.

RO Determines SBLC SYS 1 did not actuate (green OFF pump light lit).

NOTE: The simulator is setup such that the first SBLC Pump started will fail requiring the standby SBLC pump to start.

RO Places SLC system selector switch to SYS 2.

Critical Step RO Determines that SBLC SYS 2 did actuate.

RO System 2 SBLC Pump breaker indication - (Green- OFF, Red-ON CO5).

RO SBLC DISCHARGE PRESSURE reads slightly higher than reactor vessel pressure. (PI-11-65 CO5)

RO SBLC tank level decreasing. (LI-11-66)

RO Review procedure B.03.05-05 MANUAL INITIATION as time permits.

RO Inserts control rods per C.5-3101, ALTERNATE ROD INSERTION, Part C.

RO Determine Part C is appropriate.

Page 94 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 7 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior RO Determine prerequisites are met:

• CRD pump available (Breaker indication CO5)

• Instrument air available (PI-1476 - CO6 or PR-1176 - CO7)

• Reactor Building accessible.

RO Places RWM Owner Display Keylock Switch is in BYPASS.

RO Place FC-301 - CRD FLOW CONTROL STATION in MANUAL.

RO ADJUST FC-301 to 100%.

RO OPEN MO-3-20, DRIVE PRESSURE TO CRD.

RO CLOSE the following valves:

• CRD-79-1, RV-7364A INLET (behind CRDH instrument rack)

• CRD-79-2, RV-7364B INLET (behind CRDH instrument rack)

• CRD-168, CRD PUMP BYPASS ISOL Phone When directed as RBO to close CRD-79-1, CRD-79-2, and CRD-168, then wait 3 minutes Talker and reply, CRD 79-1, CRD 79-2, and CRD-168 are closed.

RO Establishes 400 psid drive pressure by throttling closed on MO-3-20.

RO Inserts control rods using RMCS.

RO Reports to the CRS of all rods in.

Page 95 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 8 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior BOP Places ADS INHIBIT switches 2E-S7A & 2E-S7B on CO3 to INHIBIT.

Critical Step BOP Prevents Core Spray per C.5-3205, TERMINATE AND PREVENT, Part A.

Critical Step BOP Places MO-1751 CS INJECTION BYPASS handswitch in BYPASS (14A-S16A).

BOP Closes MO-1751.

BOP Places No. 11 Core Spray Pump in PTL.

BOP Places MO-1752 CS INJECTION BYPASS handswitch in BYPASS (14A-S16B).

BOP Closes MO-1752.

BOP Places No. 12 Core Spray Pump in PTL.

BOP Defeat RPV low-low level isolation for MSIV closure per C.5-3301.

BOP Determines prerequisites are met.

• Main condenser available

• No fuel element failure

• No steam line break Page 96 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 9 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior BOP Places the following switches in BYPASS (Panels C-15 and C-17):

• 16A-S62A

• 16A-S62C

• 16A-S62B

• 16A-S62D BOP Maintain Reactor water level within band given by CRS using Condensate and Feed or RCIC.

BOP Terminate and Prevent Condensate and Feed, HPCI & LPCI per C.5-3205 TERMINATE AND PREVENT parts E, B & C.

Part E BOP Verify CLOSED CV-6-12A, A MAIN FW REG VALVE.

BOP Verify CLOSED CV-6-12B, B MAIN FW REG VALVE.

BOP Verify CLOSED CV-6-13, FW LOW FLOW REG VALVE.

Part C BOP Determine HPCI is operating.

BOP Depress and hold the TURBINE TRIP pushbutton.

BOP Verify HPCI has stopped.

Page 97 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 10 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus.

Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power.

When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior BOP Place AUX OIL PUMP in PULL-TO-LOCK.

BOP Wait 5 seconds after AUX OIL PUMP in placed PULL-TO-LOCK then release the HPCI TURBINE TRIP pushbutton.

BOP Verify HO-7 CLOSED.

Part B BOP OPEN knife switch 10A-S31A.

BOP OPEN knife switch 10A-S31B.

BOP CLOSE MO-2012.

BOP CLOSE MO-2013.

BOP Perform procedure B.03.04-05.H.1(2) - TRANSFERRING A (B) RHR FROM LPCI TO TORUS COOLING WITH NORMAL OFF-SITE POWER AVAILABLE DURING ABNORMAL AND EMERGENCY CONDITIONS.

BOP Verify CV-1728 (CV-1729) controller is set at 20%.

BOP Place MO-2002 (MO-2003) bypass keylock switch in CLOSE.

BOP Place 11 and 13 (12 and 14) RHRSW PUMPS LPCI AND ECCS LOAD SHED MANUAL OVERRIDE switch in MANUAL OVERRIDE.

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2003 MNGP ILO NRC Exam NRC 03-01 Op-Test No. Scenario No. 4 Event No. 6 Page 11 of 11 Event

Description:

Because of the loss of turbine bearing oil header pressure a scram will occur. The crew will identify that all control rods have not inserted and will enter failure to scram procedure. Without any oil pressure the bypass valves will not open to relieve reactor pressure and with the turbine tripped all of the steam will dump into the Torus. Torus temperature will eventually rise above 110°F forcing the crew to terminate and prevent to control reactor power. When directed to inject SBLC the first system selected by the OATC will not work (the pump will trip). However, the second SBLC system will work. The success path for the crew will be to inject SBLC and insert control rods both manually and via additional scram attempts.

Time Position Actions or Behavior BOP Start No. 11 and/or No. 13 (No. 12 and/or No. 14) RHRSW Pump.

BOP Adjust RHRSW flow to approximately 3500 gpm using CV-1728 (CV-1729).

BOP Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch to MANAUL OVERRIDE.

Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch BOP to BYPASS.

BOP Partially open MO-2008 (MO-2009) by holding handswitch to OPEN for 8 seconds.

BOP Open MO-2006 (MO-2007).

BOP Close MO-2012 or MO-2013 while throttling open MO-2008 (MO-2009) to maintain approximately 4000 gpm total flow per pump.

BOP Verify MO-2002 (MO-2003) closed.

BOP Verify V-AC-5 (V-AC-4) in operation.

BOP Perform C.5-3501 - H2/O2 ANALYZER OPERATION, as time permits.

Notes:

Page 99 of 100

2003 MNGP ILO NRC Exam NRC 03-01 Termination Point:

• All control rods have been inserted.

• RPV level has been restored to the normal band.

• Primary containment parameters are being addressed.

• At the discretion of the Chief Examiner.

Classification:

Guideline 12 (Alert) RPS Failure Page 100 of 100