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2014 Prairie Island Nuclear Generating Plant Initial License Examination Administered Simulator Scenarios
	ML15126A543
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Site:	Prairie Island
Issue date:	08/22/2014
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Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 1 Op-Test No.: PI-ILT-NRC-14 Examiners: ______________________ Operators: ___________________ ______

Initial Conditions:

-8 Reactor Power at 1 x 10 amps, Boron Concentration at 1369 ppm, RCS temperature at 547°F, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 144 steps, Generator Power at 0 MW.

No equipment is out of service.

Turnover:

Raise reactor power to the point of adding heat.

Event Malf. Event Type* Event No. No. Description R (ATC) 1 RAISE POWER TO THE POAH N (SRO)

I (ATC, SRO) PRZR PRESSURE CHANNEL FAILS LOW 2

TS (SRO) (CONTROLLING CHANNEL)

C (ATC, SRO) 3 22 GPM RCS LEAK INTO CONTAINMENT TS (SRO) 4 M (ALL) SMALL BREAK LOCA 5 C (BOP, SRO) 11 & 12 SI PUMPS FAIL TO AUTO START 6 C (BOP, SRO) 11 & 12 CC PUMPS FAIL TO AUTO START

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 2 Op-Test No.: PI-ILT-NRC-14 Examiners: ______________________ Operators: __________________________

Initial Conditions:

Reactor Power at 100%, Boron Concentration at 1299 ppm, RCS temperature at 560°F, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 218 steps, Generator Power at 581 MW.

12 RHR Pump is out of service. T.S. LCO 3.5.2 Condition A was entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining. D1, 11 TD AFW Pump, 11 RHR Pump, 11 SI Pump, 11 CC Pump, and 12 CLW Pump are PROTECTED. BKR 16-10 is out of service.

Turnover:

nd Place a 2 Letdown Orifice in service in preparation of SP 1047, Control Rod Quarterly Exercise.

Event Malf. Event Type* Event No. No. Description ND 1 N (BOP) PLACE 2 LETDOWN ORIFICE IN SERVICE 2 TS (SRO) CONTAINMENT PRESSURE CHANNEL FAILS HIGH I (ATC, SRO) 3 PRESSURIZER LEVEL FAILS HIGH TS (SRO) 4 C (BOP, SRO) TURBINE MALFUNCTION (10 MW LOAD CYCLING)

R (ATC) 5 RAPID DOWNPOWER (100% TO 95%)

N (SRO) 6 M (ALL) LARGE BREAK LOCA 7 C (BOP, SRO) MAIN TURBINE FAILS TO AUTO TRIP 8 C (ATC, SRO) BOTH SAFEGUARD TRAINS FAIL TO AUTO ACTUATE 9 C (BOP, SRO) 11 & 12 AFW PUMPS FAIL TO AUTO START

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 3 Op-Test No.: PI-ILT-NRC-14 Examiners: ______________________ Operators: __________________________

Initial Conditions:

Reactor Power at 50%, Boron Concentration at 1482 ppm, RCS temperature at 556°F, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 181 steps, Generator Power at 272 MW.

PT-485, Turbine First Stage Pressure, is failed HIGH. Rod Control is in MANUAL. T.S. LCO 3.3.1 Condition A and R entered. P7 was verified to be in required state for existing unit conditions. TRM 3.3.4 Condition A was entered. A Work Request was initiated to repair PT-485. 123 Air Compressor is out of service. 13 Charging Pump Suction Stabilizer PM is complete are ready to be re-started.

Turnover:

Restore RCS Average Coolant Temperature to program temperature.

Swap charging pumps to 11 and 13 running and 12 is secured per 1C12.1.

Event Malf. Event Type* Event No. No. Description R (ATC) 1 RESTORE TAVE TO TREF N (SRO) 2 N (BOP) SWAP CHARGING PUMPS 3 TS (SRO) 11 SI PUMP PLACED IN LOCAL I (BOP, SRO) 4 N43 PR NUCLEAR INSTRUMENT FAILS HIGH TS (SRO) 5 C (ATC, SRO) PRESSURIZER SPRAY VALVE DRIFTS OPEN LOOP A RCS LOSS OF FLOW & REACTOR FAILS TO 6 C (ATC, SRO)

AUTOMATICALLY TRIP 7 M (ALL) FAULT IN 12 SG

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 4 Op-Test No.: PI-ILT-NRC-14 Examiners: ______________________ Operators: __________________________

Initial Conditions:

Reactor Power at 50%, Boron Concentration at 1480 ppm, RCS temperature at 553°F, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 175 steps, Generator Power at 265 MW.

13 Charging Pump is out of service. Two 40 GPM letdown orifices are in service. Pressurizer heaters are on. 11 and 12 Condensate Pumps are running. 11 and 12 Main Feed Pumps are running. 11 MFP recirculation valve is still open. 11 and 12 HDT Pumps are running.

Turnover:

Alternate CFCUs and discharge dampers such that 11 and 13 CFCUs are running in slow to the dome and 12 and 14 CFCUs are running in fast to support/gap.

When directed by the Shift Manager, perform a load increase from 50% to 60%.

Event Malf. Event Type* Event No. No. Description ALTERNATE CONTAINMENT FAN COIL UNITS AND 1 N (BOP)

DISCHARGE DAMPERS I (BOP, SRO) 11 SG PRESS CHANNEL FAILS HIGH 2

TS (SRO) CAUSING 11 SG PORV TO OPEN R (ATC) 3 UNIT 1 LOAD INCREASE FROM 50% TO 60%

N (SRO)

DROPPED ROD (B-8) AND REACTOR FAILS TO 4 C (ATC, SRO)

AUTOMATICALLY TRIP 5 C (BOP, SRO) TURBINE FAILS TO AUTOMATICALLY TRIP 6 M (ALL) LOSS OF ALL AC (OCCURS 10 SECS AFTER TURB TRIP) 7 C (ATC, SRO) 11 TD AFW PUMP FAILS TO AUTO START

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 5a Op-Test No.: PI-ILT-NRC-14 Examiners: ______________________ Operators: __________________________

Initial Conditions:

Reactor Power at 100%, Boron Concentration at 853 ppm, RCS temperature at 560°F, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 218 steps, Generator Power at 581 MW.

11 SI Pump is out of service. T.S. LCO 3.5.2 Condition A was entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining. D2, 12 MD AFW Pump, 12 RHR Pump, 12 SI Pump, 12 CC Pump, and 22 CLW Pump are PROTECTED. PT-485, Turbine First Stage Pressure, is failed LOW. Rod Control is in MANUAL. T.S. LCO 3.3.1 Condition A and R entered. P7 was verified to be in required state for existing unit conditions. TRM 3.3.4 Condition A was entered. A Work Request was initiated to repair PT-485. B/S 1PC-485A is tripped. Bus 15 and 16 are powered from CT11.

A dedicated operator is monitoring phase currents at the G-Panel.

Turnover:

Transfer power on Bus 15 to 1RY after turnover is complete.

Event Malf. Event Type* Event No. No. Description 1 N (BOP) TRANSFER POWER ON BUS 15 FROM CT11 TO 1RY I (ATC, SRO) 2 ROD E-3 POSITION INDICATION FAILS LOW TS (SRO)

I (ATC, SRO) 3 RCS THOT CHANNEL FAILS HIGH TS (SRO) 4 C (BOP, SRO) LOSS OF BUS DUCT COOLING R (ATC) 5 RAPID DOWNPOWER (100% to 50%)

N (SRO) 6 M (ALL) 12 SG TUBE RUPTURE 7 C (BOP, SRO) SI TO CHILLED WATER SIGNAL FAILURE

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 5b Op-Test No.: PI-ILT-NRC-14 Examiners: ______________________ Operators: __________________________

Initial Conditions:

Reactor Power at 100%, Boron Concentration at 853 ppm, RCS temperature at 560°F, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 218 steps, Generator Power at 581 MW.

11 SI Pump is out of service. T.S. LCO 3.5.2 Condition A was entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining. D2, 12 MD AFW Pump, 12 RHR Pump, 12 SI Pump, 12 CC Pump, and 22 CLW Pump are PROTECTED. PT-485, Turbine First Stage Pressure, is failed LOW. Rod Control is in MANUAL. T.S. LCO 3.3.1 Condition A and R entered. P7 was verified to be in required state for existing unit conditions. TRM 3.3.4 Condition A was entered. A Work Request was initiated to repair PT-485. B/S 1PC-485A is tripped. Bus 15 and 16 are powered from CT11.

A dedicated operator is monitoring phase currents at the G-Panel.

Turnover:

Transfer power on Bus 15 to 1RY after turnover is complete.

Event Malf. Event Type* Event No. No. Description 1 N (BOP) TRANSFER POWER ON BUS 15 FROM CT11 TO 1RY 2 TS (SRO) ROD E-3 POSITION INDICATION FAILS LOW I (ATC, SRO) 3 RCS THOT CHANNEL FAILS HIGH TS (SRO) 4 C (BOP, SRO) LOSS OF BUS DUCT COOLING R (ATC) 5 RAPID DOWNPOWER (100% to 50%)

N (SRO) 6 M (ALL) 12 SG TUBE RUPTURE 7 C (BOP, SRO) SI TO CHILLED WATER SIGNAL FAILURE 8 C (ATC, SRO) FAILURE OF THE STEAM DUMP SYSTEM

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 of 22 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-1401S SEG TITLE: 2014 ILT NRC SIMULATOR EVALUATION #1 REV. # 0 PROGRAM: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 2.0 HOURS Developed by: Shawn Sarrasin 2/9/2014 Instructor Date Reviewed by: Fredrick Collins 2/28/2014 Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Shawn Sarrasin 4/21/2014 Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by: Travis Ouret 7/18/2014 Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Guide Requirements

1. During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of the Training: Operations Manuals and Technical Specifications.

2. When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Raise power to the Point of Adding Heat per 1C1.2.

Learning 2. Diagnose and perform corrective actions for a Pressurizer Objectives: Pressure Instrument failing low per 1C51.3.

3. Diagnose and respond to a RCS Leak per 1C4 AOP1.

4. Diagnose and respond to a Small Break LOCA per 1E-0 and 1E-1.

5. Diagnose and respond to a failure of the SI Pumps to automatically start per 1E-0 Attachment L.

6. Diagnose and respond to a failure of the CC Pumps to automatically start per 1E-0 Attachment L.

1. Full Scope Simulator Training 2. NRC Evaluation Team Resources: 3. Booth Operator (Backup Communicator)

4. Primary Communicator Initiating Event with Core Damage Frequency:

Related PRA LOCA (5.1%)

Information:

Important Components:

11 SI PMP 12 SI PMP 11 CC PMP 12 CC PMP Important Operator Actions with Task Number:

NONE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1P-431, Blue Channel Pressurizer Pressure Transmitter, fails low.

2. Unidentified RCS Leak at ~21 gpm.

After EOP Entry:

1. 11 and 12 SI Pumps fail to start automatically.

2. 11 and 12 CC Pumps fail to start automatically.

Abnormal Events:

1. Pressurizer Pressure Instrument Failure.

2. RCS Leak.

Major Transients:

1. Small Break LOCA from the A Loop RTD Bypass Cold Leg Manifold.

Critical Tasks:

1. E H: Manually start at least one Safety Injection pump before transition out of E-0.

2. E K: Manually start at least one CCW pump before transition out of E-0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS

Exposure: MOC

NONE

Power: 1 x 10-8 amps

Boron (CB): 1369 ppm

Temperature: 549°F

Pressure: 2235 psig

Xenon: Equilibrium

Rods: D @ 148

Generator: 0 MW SEQUENCE OF EVENTS:

Event 1: Raise Reactor Power to the Point of Adding Heat

Reactor power is at 1 x 10-8 amps.

Rods will be stepped out to establish a positive startup rate.

Power will rise to between 0.5% and 2%.

Rods will be stepped in to level power out.

Event 2: Blue Channel Pressurizer Pressure Instrument Fails LOW

1P-431 pressure instrument will peg low.

All pressurizer heaters will turn on.

Pressurizer spray valves will close.

Pressurizer pressure will slowly rise.

The crew will take manual control of pressurizer pressure.

Pressurizer pressure will be returned to program.

Pressurizer pressure control will be placed in the 2-1 position.

Pressurizer pressure control will be returned to automatic.

The SS will enter T.S. LCO 3.3.1 Conditions A, E, and K.

The SS will enter T.S. LCO 3.3.2 Conditions A and D.

Event 3: RCS Leak

An unidentified approximate 21 gpm leak will develop on the RCS.

The leak will be un-isolable.

Pressurizer level and pressure will slowly lower.

The crew will enter 1C4 AOP1.

The Letdown and Charging Line will be isolated.

The Regenerative Heat Exchanger will be isolated.

RCP Seal Injection will be isolated and then restored.

The SS will enter T.S. LCO 3.4.14 Condition A.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Events 4, 5, & 6: Small Break Loss of Coolant Accident

RCS pressure will rapidly lower.

Pressurizer level will rapidly lower.

The crew will enter 1E-0.

The crew will manually:

o Trip the reactor and actuate SI.

o Start SI pump(s) and CC pump(s).

The crew will transition to 1E-1.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Setup:

NOTE: The time between simulator reset and placing simulator in RUN should be minimized to reduce the difference between the ERCS time and actual time.

CAUTION: A reactivity and temperature transient will occur if 1HC-484, MAIN STM HDR PRESS (STM DUMP), is NOT set to 72% when the simulator is taken to RUN.

1. If IC-261 is available, then perform the following:

a. Reset to IC-261.

b. Verify 1HC-484, MAIN STM HDR PRESS (STM DUMP), set point is set to 72%.

c. Place the simulator in RUN.

d. Verify RCS Tavg stabilized at 549°F.

2. If IC-261 is NOT available:

a. Reset to IC-18.

b. Verify 1HC-484, MAIN STM HDR PRESS (STM DUMP), set point is set to 72%.

c. Place the simulator in RUN.

d. Verify RCS Tavg stabilized at 549°F.

e. Verify RCP Seal Injection at 8 gpm and charging flow balanced with letdown.

f. Adjust rods as necessary to establish reactor power at 1 x 10-8 amps and stable.

g. Insert Remote SG100 to CW.

h. Take to the following to PULLOUT

i. CS-46362, 4.16KV BUS 11 1M XFMR (BKR 11-4) ii. CS-46363, 4.16KV BUS 12 1M XFMR (BKR 12-4) iii. CS-46364, 4.16KV BUS 13 1M XFMR (BKR 13-9) iv. CS-46365, 4.16KV BUS 14 1M XFMR (BKR 13-9)

3. Verify the ROD DEVIATION alarm is CLEARED as follows:

a. Log into the ERCS terminal with user OVRD and password DUTY (if needed).

b. Go to ERCS Screen RBU (Rod Bank Update).

c. Enter 148 as the new value for point 1U0052A, ROD POS BNK D.

d. Select Apply.

e. Verify Annunciator 47013-0507, COMPUTER ALARM / ROD DEVIATION /

SEQUENCING, has cleared.

4. Verify the Pen Recorder for RCS Tavg and Tref are set correctly as follows:

a. Log into the ERCS terminal with user OVRD and password DUTY (if needed).

b. Go to ERCS Screen PEN_TREND (Pen Trend Configuration).

c. Enter 545 as the new Min EU value for Pen 1U9001A (point 1T0499A).

d. Enter 555 as the new Max EU value for Pen 1U9001A (point 1T0499A).

e. Enter 545 as the new Min EU value for Pen 1U9002A (point 1T0496A).

f. Enter 555 as the new Max EU value for Pen 1U9002A (point 1T0496A).

5. If available, run schedule file PI-ILT-NRC-1401S.sch as follows:

a. Select open file in the Schedule application.

b. Locate schedule file.

c. Open schedule file by double clicking it.

d. Run the schedule file by pressing the Stopped button on the toolbar.

e. Verify the schedule file is running.

6. If schedule file is NOT available, then insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

7. If desired, start Scenario Based Testing Data Collection Program.

8. Complete the "Simulator Setup Checklist.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

1. SIMULATOR PRE-BRIEF:

a. The Simulator Pre-Brief is conducted prior to the crew entering the simulator.

b. Review Unit 1 LPEO / PEO Turnover Log.

c. Perform a pre-job brief for the following activity:

1) Raise power to the Point of Adding Heat per steps 5.10.20 - 5.10.23 of 1C1.2.

(a) Provide Page 71 of 1C1.2 marked up to step 5.10.19.

(b) This activity is to be performed after shift turnover is complete.

(c) Section 5.6 of 1C1.2 is complete.

2. COMPLETE TURNOVER:

a. Crew performs a walk down of the control boards.

b. Review PRA Printout.

c. Crew takes the duty.

EVENT 1 3. After the crew has assumed the duty, they will raise 1C1.2, UNIT 1 STARTUP PROCEDURE power to the Point of Adding Heat.

Raise reactor power to the point of adding heat using RO/SS manual rod control or boron concentration change.

When one or more intermediate range indicates greater than 1 x 10-9 amps, then verify ERCS is in Mode 2, STARTUP.

Maintain reactor power between 0.5 and 2.0%.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 4. After reactor power is stabilized between 0.5 - 2.0%, C47012-0408, PRZR HI/LO PRESS CHANNEL ALERT and/or at the discretion of the lead evaluator, enter:

Check pressurizer pressure high or low.

LEAD Trigger 2, Pressurizer Pressure Instrument Fails

Restore pressure to normal through use of heaters or LOW. sprays.

a. If contacted as I&C to trip bistables, inform the crew

Refer to 1C51.

two I&C Technicians will be available in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b. If contacted as the Operations Management, 1C51.3, Pressurizer Pressure 1P-431 - Low acknowledge the report of the failure, and agree to

Place Pressurizer Pressure Controller in MANUAL make other notifications to the NRC, Duty Station and stabilize pressure.

Manager, etc. as asked.

Select position 2-1 (WHITE-RED) on channel

c. If contacted as the FIN Team Supervisor, inform the selector switch.

crew that you will write a work order and assign an

When pressure returned to normal with no deviation SS I&C Supervisor to investigate. from setpoint, then return pressure control to

5. Plant Response: automatic.

a. 1P-431 pressure instrument will peg low.

Verify Pressurizer Pressure Recorder not selected to

b. Pressurizer Backup Heaters will turn ON. Blue Channel.

c. Pressurizer Spray Valves will CLOSE.

Enter T.S. LCO 3.3.1 Condition A

d. Pressurizer pressure will slowly rise.

o Reference Table 3.3.1-1 immediately.

e. The following annunciator will come in:

Enter T.S. LCO 3.3.1 Condition E

1) 47012-0108, PRZR LO PRESS SI CHANNEL o Trip 1P-431 bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR ALERT.

o Be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2) 47012-0408, PRZR HI/LO PRESS CHANNEL ALERT.

Enter T.S. LCO 3.3.1 Condition K

3) 47012-0608, PRZR CONTROL HI PRESS OR o Trip 1P-431 bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR BACKUP HTRS ON. o Reduce Thermal Power < P-7 and P-8 (10%).

Enter T.S. LCO 3.3.2 Condition A o Reference Table 3.3.2-1 immediately.

Enter T.S. LCO 3.3.2 Condition D o Trip 1P-431 bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR o Be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Mode 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 6. After Pressurizer Pressure control is back in automatic, 1C4 AOP1, REACTOR COOLANT LEAK or at the discretion of the Lead Evaluator, enter RO

If, at any time, RCS inventory can not be maintained Trigger 3, Reactor Coolant Leak at ~ 21 gpm. by available charging flow, then manually trip the

a. If contacted as the Operations Management, reactor, manually initiate safety injection, and exit this acknowledge the report of the failure, and agree to procedure.

make other notifications to the NRC, Duty Station

Start additional charging pumps as needed to control Manager, etc. as asked. pressurizer level.

b. If contacted as a Maintenance or Engineering or RO

Use ERCS Real-Time RCS Leakage (LEAK 1) display Radiation Protection Department Supervisor, inform and/or Control Board indications to determine the crew that you will coordinate making a approximate leak rate.

containment entry per F2 to locate the leak.

Determine the location of the leak using Figure 1 and associated tables, if necessary.

7. Plant Response:

If unable to identify the source of the leak using tables

a. RCS pressure lowers. 1, 2, 3, or 4, THEN attempt to locate the leak by

b. Pressurizer Level lowers. sequentially isolating service systems from the RCS:

c. Charging pump speed rises. o Remove Letdown from service.

d. R11 and R12 counts rise. o Isolate Charging to the RCS.

e. RCS Leak rate rises. o Close CV-31328, 11 REGEN HX CHG LINE TO

f. Containment humidity rises. RCS.

o Isolate Charging to the RCP Seals.

EMERGENCY PLAN CLASSIFICATION SS

Comply with T.S. 3.4.14. Condition A to reduce UNUSUAL EVENT - SU5.1 due to unidentified RCS leakage to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

leakage greater than 10 gpm.

Notify the Operations Manager and Resident Inspector of entry into this AOP per SWI O-28.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 8. At the discretion of the Lead Evaluator, enter: 1E-0, REACTOR TRIP OR SAFETY INJECTION 4, 5, & 6 Trigger 4, Small Break LOCA.

Verify or manually trip the reactor.

RO/

a. Upon hearing the announcement of Reactor Trip, or

Verify the Main Turbine is tripped.

LEAD when called as the Turbine Building Operator to

Verify both Safeguards buses energized.

isolate the Unit 1 MSRs per Attachment J, then open

Determine SI is required.

and run schedule file E-0_Att-J.sch located in o Either SG pressure < 530 psig.

X:\\Trex_PI\Lightning\Schedule\EOPs. When the o PRZR pressure < 1830 psig.

isolation is complete, inform the crew the MSRs are o Containment pressure > 3.5 psig.

isolated.

Manually actuate SI.

b. Upon hearing the announcement of Safety Injection,

Perform Attachment L (see pages 12 & 13).

or when called as the Turbine Building Operator to

Check AFW Status:

secure the Turbine Building Roof Exhausters, wait 2 o Verify total AFW flow greater than 200 minutes and report the Turbine Building Roof GPM.

Exhausters are all secured. o Verify AFW pumps discharge pressure

c. If Control Room personnel ask if Unit 2 personnel are greater than 1000 psig.

available to perform Attachment L, then inform the o Control feed flow to maintain 11 SG Narrow Control Room that Unit 2 personnel are NOT Range greater than 5% [Wide Range available for performing Attachment L. between 50% and 59%].

d. If contacted as RP or Duty Chemist to sample for

Check RCS Temperatures trending to 547°F.

primary-to-secondary leakage, then wait 2 minutes

Check PRZR PORVs and Spray valves closed.

and report cation column frisks indicate activity is reading background on 11 and 12 SGs.

Determine RCPs should NOT be stopped.

Determine SGs are NOT faulted.

9. Plant Response:

Determine SG Tubes are NOT ruptured.

a. RCS pressure lowers.

Determine RCS is NOT intact due to Containment

b. Pressurizer Level lowers. pressure rising.

c. RCS Leak rate rises. SS

Go to 1E-1.

d. Containment Pressure rises.

e. A RC Bypass Flow lowers.

f. Annunciator C47012-0503, REACTOR COOLANT RTD B-P LOOPS LO FLOW, is received.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1E-1, LOSS OF REACTOR OR SECONDARY 4, 5, & 6 COOLANT (cont) RO/SS EMERGENCY PLAN CLASSIFICATION

Determine RCPs should NOT be stopped.

ALERT - FA1 due to a loss of the RCS Fission Product

Determine SGs are NOT faulted.

Barrier due to RCS leak rate greater than 60 gpm.

Check intact SG levels.

Control feed flow to maintain narrow range level between 5% and 50% [Wide Range 50% and 59%].

Check secondary radiation is normal.

Check power to PRZR PORV block valves available.

Check PRZR PORVs are closed.

Check at least one PRZR PORV block valve is open.

Reset SI and Containment Isolation.

Establish Instrument Air to Containment.

Check power supply to charging pumps are from offsite power.

Check at least one charging pump is running.

Establish charging flow as necessary.

Determine SI flow should NOT be terminated due to subcooling and RCS pressure.

10. If Control Room personnel ask if Unit 2 personnel are

Stop RHR pumps.

available to secure Diesel Generators and/or Safeguards

Check RCS and SG pressures Cooling Water Pumps, then inform the Control Room

Determine Diesel Generators should be stopped.

that Unit 2 personnel WILL secure the Diesel Generators

Determine Safeguards Cooling Water pumps should and/or Safeguards Cooling Water Pumps. be stopped.

Initiate Evaluation of Plant Status.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1E-0 Attachment L: SI Alignment Verification 4, 5, & 6 CRITICAL TASKS

Verify Safeguards Component Alignment:

(cont) LEAD

Manually start at least one Safety Injection pump

Verify both trains of SI actuated:

before transition out of E-0. o Both RHR pumps - RUNNING

Manually start at least one CCW pump before -OR-transition out of E-0. o Both SI pumps - RUNNING o Identify both SI pumps are NOT running and start both SI pumps.

11. If Control Room personnel ask for status of Unit 2 * "SI NOT READY" lights - NOT LIT Cooling Water/Chilled Water lineup, then inform the * "SI ACTIVE" lights - LIT FOR PLANT CONDITIONS Control Room that Unit 2 Cooling Water/Chilled Water

Identify Both CC pumps are NOT running and start valves are in there safeguards positions. both CC pumps.

12. If Control Room personnel ask for status of Battery * "CONTAINMENT ISOLATION" lights - LIT FOR Room Temperatures, then inform the Control Room that PLANT CONDITIONS Battery Room temperatures are less than 84°F.

Check Category 1 Vent Zone Boundary:

13. If Control Room personnel ask for status of Spent Fuel

Close MV-32115, 122 SFP HX INLT HDR MV B Cooling, then inform the Control Room that Spent

Check Cooling Water Header Pressures - BOTH Fueling level and temperature are normal. GREATER THAN 65 PSIG

Verify Plant Announcements Complete:

Check If Main Steamlines Are Isolated:

Determine MSIVs, Bypass Valves, and Containment Instrument Air Valves do NOT need to be closed.

Verify SI Flow

Verify RHR Flow

Verify Containment Spray is actuated (if necessary).

Check RCP Cooling

Verify Local Actions Complete

Verify Generator Breakers - OPEN

Verify All Heater Drain Pumps - STOPPED

Check Turbine Valves:

o Turbine reheat and intercept valves - CLOSED o Open turbine drain valves Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT

Verify Main Feedwater Alignment:

4, 5, & 6 o Both main feedwater pumps - STOPPED (cont) LEAD o Main and bypass FRVs - CLOSED

Verify All Condensate Pumps - STOPPED:

Place Steam Dump in "STM PRESS" Mode

Verify Unit 1 Cooling Water/Chilled Water Alignment:

o CFCU control switches - "SLOW".

o CFCU dampers - ALIGNED TO DOME o Unit 1 cooling water/chilled water valves closed o Unit 1 CRDM shroud cooling supply and return valves - CLOSED o CFCU cooling water supply and return valves -

OPEN o CFCU chilled water supply and return valves -

CLOSED

Verify 11 Safeguards Screenhouse Ventilation lineup.

Verify Control Room Ventilation Alignment:

o Chillers and fans - RUNNING o Control room chiller suction/discharge tie closed -

STATUS LIGHT LIT

Verify Unit 2 Cooling/Chilled Water Alignment

Verify 21 Safeguards Screenhouse Ventilation lineup.

Verify 11 and 12 Battery Charger Operation is normal.

Verify Battery Room temps less than 84°F.

Check status of Spent Fuel Cooling.

Check Status Of Notifications

Notify SS Of Any Discrepancies.

14. Once the crew has stopped RHR Pumps and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE and inform the crew that training has the duty.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SIMULATOR SETUP CHECKLIST Before Scenario

_____ Simulator Status:

___ 1. "Training Load" ___ 2. Step counters "ON"

___ 3. Alarm sound "ON" ___ 4. Steps 1 - 7 on page 6 complete

___ 5. Speed: REAL ___ 6. IC-261 or IC-18 running

_____ Delete the memory on the Yokogawa Model DX1000 recorders by cycling the Recorder Power OFF pushbutton in the simulator instructors booth.

_____ Verify Schedule File/Summary matches Simulator Input Summary page in the SEG.

_____ Verify that control rod step counters on C panel and ERCS RBU matches the IC conditions.

_____ Boric Acid/RMU integrators set to: BA: 3, RMU: 10, and reset.

_____ MOC I sheet displayed on C panel.

_____ MOC Reactivity Briefing sheet available at Reactor Operator Desk.

_____ Turnover sheet/PRA sheet available.

_____ If it is the first scenario of the day, then perform a shutdown and restart of the floor PCs that are connected to the LAN.

_____ Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID).

_____ Electronic PINGP 577 forms closed on LAN connected PCs.

_____ Board-mounted EAL Tables are cleaned.

_____ EOOS running on PC and updated as follows to reflect equipment OOS:

___ 1. NONE

_____ Update Control Board Placards:

___ 1. NRC Current Authentication Code call date updated to current date.

___ 2. High Flux At Shutdown Alarm Setpoint placards: 5900 cps.

___ 3. Feedwater regulating valve position placard set to current values.

___ 4. Recommended SG Blowdown flow set to current values.

___ 5. RCS boron on the CVCS panel placard: 1369 ppm.

___ 6. Turbine reference/setter values on the CVCS panel are blank.

___ 7. Shift Reactivity Guidance placard: BA: 4.4 gallons, RMU: 67 gallons.

Dilutions @ NONE.

_____ Magnetic placards in place:

___ 1. 11 BA TANK Lined Up For Service

___ 2. 11 BA PUMP Lined Up to 11 BA Tank

___ 3. 12 BA PUMP Lined Up to 11 BA Tank

___ 4. CC to SFP MV-32117 In Service

___ 5. Blowdown 46470 SGB To RIVER

___ 6. HU Flag above 12 RHR HX CC inlet MV-32094 for 1C14 Limitation

___ 7. H2 IN VCT SPACE at VCT

_____ Pink Status Control Tags in place:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0

___ 1. CS-46540, 22 CC WTR PUMP

___ 2. CS-46572, CC TO SFP MV-32117

_____ Yellow Caution Tags in place:

___ 1. CS-46064, CC TO SFP MV-32115, in CLOSED

___ 2. CS-46362, 4.16 KV BUS 11 1M XFMR (BKR 11-4), in PULLOUT

___ 3. CS-46363, 4.16 KV BUS 12 1M XFMR (BKR 12-4), in PULLOUT

___ 4. CS-46364, 4.16 KV BUS 13 1M XFMR (BKR 13-9), in PULLOUT

___ 5. CS-46365, 4.16 KV BUS 14 1M XFMR (BKR 14-9), in PULLOUT

_____ ERCS driven recorders are on-scale (RCS temperature scaled 545º F to 555º F).

_____ ERCS alarm screen operating and alarms reset.

_____ All ERCS terminals operating and set as follows:

CONF VARS R02 Alarm Summary Page CONE1 Group OP31_U1 R03 AFD CONC SAS (XS22) R04 TPM CONG1 Group QP CCDATA R05 QP LOADFOLL ERCS-R01 Group RADMON_U1 R06 Alarm Summary Page

_____ ERCS single point displays: CONB 1T0499A 1U1613A CONE2 1Q0340A 1V4501A

_____ Verify that copy machine and printers are loaded with paper.

_____ Pens/Paper/Markers available on the simulator.

st

_____ Verify 121 IA Compressor is in PREFERRED and 122 IA Compressor is in 1 STANDBY, and nd 123 IA Compressor is in 2 STANDBY.

_____ Verify R11/R12 are lined up correctly (at the R11/R12 local panel):

___ 1. Sample pump is running.

___ 2. Alarms are reset.

___ 3. CS-8006106, Sample Inlet Switch, is selected to CNTMT.

___ 4. CS-8006107, Sample Outlet Switch, is selected to Aux Bldg Stack.

_____ Set Turbine Control HMI Displays as follows:

___ 1. U1 E-H Turb Cont STA 2 (48087) to Control Valve Overview.

___ 2. U1 Turb Aux Cont (48088) to Turb Overview.

___ 3. U1 E-H Turb Cont STA 1 (48086) to Off Line Control.

_____ DEHC alarms cleared.

_____ N51 & N52 Display Sheets for current power are in place as necessary.

_____ Headsets turned on as necessary.

_____ Procedure checklist completed. See following page.

_____ Peer Check performed for simulator setup.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 PROCEDURE CHECKLIST The following procedures will be used during this session. Verify the procedures are free of place keeping marks before starting the session and after the session are complete:

Before After 1C1.2, UNIT 1 STARTUP PROCEDURE 1C12.1, LETDOWN, CHARGING, AND SEAL WATER INJECTION -

UNIT 1 1C4 AOP1, REACTOR COOLANT LEAK 1C51.3, Pressurizer Pressure 1P-431 - Low 1E-0, REACTOR TRIP OR SAFETY INJECTION 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT C47012-0108, PRZR LO PRESS SI CHANNEL ALERT C47012-0408, PRZR HI/LO PRESS CHANNEL ALERT C47012-0608, PRZR CONTROL HI PRESS OR BACKUP HTRS ON C7, REACTOR CONTROL SYSTEM EAL BOARDS EOP INFORMATION BOOK F3-2 EAL STICKER BOOK checked for missing stickers F3-2.1, EMERGENCY ACTION LEVEL TECHNICAL BASES SWI O-28, NOTIFICATION OF OPERATIONS MANAGER & NRC RESIDENT INSPECTOR SWI O-50, REACTIVITY MANAGEMENT T.S. LCO 3.3.1 T.S. LCO 3.3.2 T.S. LCO 3.4.14 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Post-Scenario Checklist

_____ LAN connected computers are cleared of information added during the scenario.

_____ Computer generated PINGP 577 cleared.

_____ Procedure checklist completed. See previous page.

_____ Remove Pink Status Control Tags from the following equipment:

___ 1. NONE

_____ Magnetic placards removed:

___ 1. NONE

_____ Remove Yellow Caution Tags from the following equipment:

___ 1. CS-46362, 4.16 KV BUS 11 1M XFMR (BKR 11-4)

___ 2. CS-46363, 4.16 KV BUS 12 1M XFMR (BKR 12-4)

___ 3. CS-46364, 4.16 KV BUS 13 1M XFMR (BKR 13-9)

___ 4. CS-46365, 4.16 KV BUS 14 1M XFMR (BKR 14-9)

_____ Erase marker on RCS temperature ERCS driven recorder.

_____ Board-mounted EAL Table is cleaned.

_____ All books, note pads, and calculators put away.

End Of Day Checklist

_____ Signs/placards removed and put away unless normal simulator configuration.

_____ Floor PCs logged off if simulator will not be used again that day.

_____ Instructor station returned to normal with all books, paper, and etc. put away.

_____ Headsets turned off and put away if simulator will not be used again that day.

_____ Simulator reset to IC-10 unless another IC will be used for further training.

_____ Simulator placed in DORT if simulator will not be used again that day.

_____ Recorder power "OFF" if simulator will not be used again that day.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 22 RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS NONE PROTECTED EQUIPMENT 22 CC PUMP 121 SFP HX RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Station Air is supplementing Instrument Air per Section 5.1.3 of C34, Station Air System.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT

Xenon is at equilibrium.

Raise Reactor Power from 1 x 10-8 amps to the POAH.

Stabilize power between 0.5 - 2%.

Section 5.6 of 1C1.2 is complete.

NEW PROCEDURES / INSTRUCTIONS Review altered scale on Tavg ERCS Recorder.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human Yes No performance tools. X

2. The scenario identifies key parameter response, expected alarms, and Yes No automatic actions associated with the induced perturbations. X

3. The scenario content adequately addresses the desired tasks, through Yes No simulator performance, instructor-led training freezes, or both. X

4. Plant PRA initiating events, important equipment, and important tasks are Yes No identified. X

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Yes No Assessment. X

6. The scenario contains procedurally driven success paths. Procedural Yes No discrepancies are identified and corrected before training is given. X

7. The scenario guide includes responses for all anticipated communications to Yes No simulated personnel outside the Control Room, based on procedural guidance X and standard operating practices. Include estimated completion times and/or notes for use of time compression.

8. The scenario includes related industry experience. SOER, SER and similar Yes No OE recommendations are clearly identified and fully addressed.* X

9. The scenario guide incorporates verification of Operator Fundamental Yes No application.* X

10. Training elements and specific human performance elements are addressed Yes No in the scenario critique guide to be used by the critique facilitator. The critique X guide includes standards for expected performance.*

11. For evaluations, it has been verified that without operator action the critical Yes No tasks will be failed. X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial conditions agreed with the reference plant with Yes No respect to reactor status, plant configuration, and system operation. X

2. The simulator operated in real time during conduct of validation. Yes No X

3. The simulator demonstrated expected plant response to operator input Yes No and to normal, transient, and accident conditions. X

4. The simulator permitted use of the reference plants procedures. The Yes No scenario was completed without procedural exceptions, simulator X performance exceptions, or deviation from the scenario sequence.

5. The simulator did not fail to cause or unexpectedly cause any first Yes No principle alarm or primary automatic action. X

6. Observable changes in parameters relevant to the scenario Yes No corresponded in trend and direction to reference plants expected X response.

7. All malfunctions and other instructor interface items were functional and Yes No demonstrated the expected reference plants response to the initiating X cause.

8. All malfunctions and other instructor interface items were initiated in the Yes No same sequence described within the simulator scenario. X

9. The scenario satisfies the learning or examination objectives without Yes No any significant simulator performance issues, or deviations from the X approved scenario sequence.

10. Simulator fidelity has been demonstrated to be adequate for this Yes No scenario. X Discrepancies noted (Check none or list items found) None SMAR = Simulator Action Request SMAR: SMAR: SMAR: SMAR:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 22 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Validation Personnel Name Job Title / Qualification Validation Position Shawn Sarrasin Operations Instructor Lead Evaluator Fred Collins Operations Instructor Booth Driver Jeff Human Operations SRO Shift Supervisor Mark Haren Operations RO LEAD Rick Martin Operations RO RO Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 of 26 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-1402S SEG TITLE: 2014 ILT NRC SIMULATOR EVALUATION #2 REV. # 0 PROGRAM: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 2.0 HOURS Developed by: Shawn Sarrasin 2/2/2014 Instructor Date Reviewed by: Fredrick Collins 2/26/2014 Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Shawn Sarrasin 4/22/2014 Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by: Travis Ouret 7/18/2014 Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Guide Requirements

1. During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of the Training: Operations Manuals and Technical Specifications.

2. When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Place a second letdown orifice in service per 1C12.1.

Learning 2. Diagnose and perform corrective actions for a Containment Objectives: Pressure Instrument failing high per C47018-0105.

3. Diagnose and perform corrective actions for a Pressurizer Level Instrument failing high per 1C51.3.

4. Diagnose and respond to a Turbine Malfunction per 1C23 AOP2.

5. Perform a rapid power reduction per 1C1.4 AOP1.

6. Diagnose and respond to a Large Break LOCA per 1E-0 and 1E-1.

7. Diagnose and respond to a failure of the Main Turbine to Automatically Trip.

8. Diagnose and respond to a failure of the Safeguards System to automatically actuate per 1E-0.

9. Diagnose and respond to a failure of the AFW Pumps to automatically start per 1E-0 Attachment L.

1. Full Scope Simulator Training 2. NRC Evaluation Team Resources: 3. Booth Operator (Backup Communicator)

4. Primary Communicator Initiating Event with Core Damage Frequency:

Related PRA LOCA (5.1%)

Information:

Important Components:

11 TD AFW PMP 12 MD AFW PMP Important Operator Actions with Task Number:

NONE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1P-950, Yellow Channel Containment Pressure Instrument, fails high.

2. 1LT-428, Blue Channel Pressurizer Level Transmitter, fails high.

3. Turbine Control System cycling output (10 MW Swing).

After EOP Entry:

1. Main Turbine fails to automatically trip.

2. Failure of safeguards automatic actuation.

3. 11 and 12 AFW Pumps fail to start automatically.

Abnormal Events:

1. Pressurizer Level Instrument Failure.

2. Turbine Malfunction.

3. Rapid Power Reduction.

Major Transients:

1. Large Break LOCA from the B Loop Hot Leg.

Critical Tasks:

1. E D: Manually actuate at least one train of SI-actuated safeguards equipment before transition out of E-0.

2. E Q: Manually trip the main turbine before transition out of E-0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS

Exposure: BOC

12 RHR Pump

Power: 100%

BKR 16-10

Boron (CB): 1299 ppm

Temperature: 560°F

Pressure: 2235 psig

Xenon: Equilibrium

Rods: D @ 218

Generator: 581 MW SEQUENCE OF EVENTS:

Event 1: Place 2nd Letdown Orifice in Service

Initially, there is only one 40 gpm letdown orifice in service.

There are already two charging pumps running.

The crew will place a second 40 gpm letdown orifice in service per 1C12.1.

Event 2: Yellow Channel Containment Pressure WR Instrument Fails HIGH

1P-950 pressure instrument will peg high.

Containment High Pressure alarm will come in.

The SS will enter T.S. LCO 3.3.2 Condition A, E, and D.

Event 3: Blue Channel Pressurizer Level Instrument Fails HIGH

Charging pump speed will lower.

1L-428 level instrument will peg high

Actual pressurizer level will lower.

Charging pump speed control will be placed in manual.

Pressurizer heaters will be controlled in manual.

Pressurizer level control will be placed in the 2-1 position.

Pressurizer level control will be returned to automatic.

Pressurizer heater control will be returned to automatic.

The SS will enter T.S. LCO 3.3.1 Conditions A and K.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Event 4: Turbine Malfunction

A Turbine Control Trouble Alarm will be received.

An approximately 10 MW load cycle will occur.

RCS Tavg will rise and lower as turbine loading changes.

Rods will step in and out as necessary to maintain RCS Tavg.

First Stage Pressure indication on the Turbine Control System will oscillate.

The crew will place Turbine Control in manual per 1C23 AOP2.

Event 5: Rapid Power Reduction

The TSO will call the Control Room requesting Unit 1 power be reduced 5% over the next 10 minutes due to impending loss of transmission capacity.

The crew will perform a Rapid Power Reduction to 95% per 1C1.4 AOP1.

Events 6, 7, 8, & 9: Large Break Loss of Coolant Accident

RCS pressure will rapidly lower.

Pressurizer level will rapidly lower.

A reactor trip will automatically actuate.

The main turbine will fail to automatically trip.

The crew will manually trip the main turbine.

Both trains of ECCS will fail to automatically actuate.

The crew will manually actuate ECCS.

11 and 12 AFW pumps will fail to automatically start.

The crew will manually start AFW pump(s).

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Simulator Setup:

NOTE: The time between simulator reset and placing simulator in RUN should be minimized to reduce the difference between the ERCS time and actual time.

1. If available, reset the simulator to IC-262 and place in RUN.

2. If IC-262 is NOT available:

a. Reset to IC-9.

b. Place the simulator in RUN.

c. Place CS-46185, 12 RHR PUMP, in PULLOUT.

d. Place CS-46914, BUSTIE BUS 16 / BUS 26 BKR 16-10, in PULL TO LOCK.

3. If available, run schedule file PI-ILT-NRC-1402S.sch as follows:

a. Select open file in the Schedule application.

b. Locate schedule file.

c. Open schedule file by double clicking it.

d. Run the schedule file by pressing the Stopped button on the toolbar.

e. Verify the schedule file is running.

4. If schedule file is NOT available, then insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

5. If desired, start Scenario Based Testing Data Collection Program.

6. Complete the "Simulator Setup Checklist.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

1. SIMULATOR PRE-BRIEF:

a. The Simulator Pre-Brief is conducted prior to the crew entering the simulator.

b. Review Unit 1 LPEO / PEO Turnover Log.

c. Perform a pre-job brief for the following activity:

1) Place a second 40 GPM Letdown Orifice in service per Section 5.9 of 1C12.1.

(a) A second letdown orifice is being placed in service in preparation of SP 1047, Control Rod Quarterly Exercise.

(b) SP 1047 is scheduled for the next day.

(c) The Lead RO will conduct this activity.

(d) This activity is to be performed after shift turnover is complete.

2. COMPLETE TURNOVER:

a. Crew performs a walk down of the control boards.

b. Review PRA Printout.

c. Crew takes the duty.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1 3. After the crew has assumed the duty, they will place a 1C12.1, LETDOWN, CHARGING, AND SEAL WATER second 40 gpm letdown orifice in service per Section 5.9 INJECTION - UNIT 1 of 1C12.1. LEAD

Notify RP Tech that an additional letdown orifice is

a. If contacted as the RP Tech or Duty Chemist, being placed into service.

acknowledge a second 40 gpm letdown orifice is

Determine steps 5.9.2 through 5.9.8 are not applicable being placed in service. due to two charging pumps already running.

b. If contacted as the Duty Chemist, acknowledge

Place 11 Charging Pump in manual speed control.

purification flow has been raised.

Establish approximately 70 gpm charging flow to the Regen HX by:

o Increasing charging pump speed.

o Maintain 8 gpm seal injection to each RCP.

Place 1HC-135A, LTDN PRESS CONT, in MANUAL.

Using 1HC-135A, lower letdown heat exchanger outlet pressure to approximately 200 psig.

Open CV-31325, LETDOWN ORIFICE 40 GPM, using CS-46170.

Return 1HC-135A, LTDN PRESS CONT, to AUTO.

Transfer one (1) of the inservice charging pumps from MANUAL to AUTOMATIC speed control per C7.

Notify the Duty Chemist that purification flow has been raised.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 4. After the crew has placed a second letdown orifice in C47018-0105, CONTAINMENT HI-HI PRESS CHANNEL service, and/or at the discretion of the lead evaluator, ALERT LEAD enter:

Check containment pressure channels.

Trigger 2, Containment Pressure WR Instrument

Determine steam line isolation is NOT required.

Fails HIGH.

Determine containment spray actuation is NOT

a. If contacted as I&C to trip bistables, inform the crew required.

two I&C Technicians will be available in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Check safeguards bistable status lights on Panel

b. If contacted as the Operations Management, 44179, Columns 13, 14, and 15.

acknowledge the report of the failure, and agree to

Refer to 1C51.

make other notifications to the NRC, Duty Station Manager, etc. as asked. 1C51.4, Containment Pressure 1P-950 - High

c. If contacted as the FIN Team Supervisor, inform the

Enter T.S. LCO 3.3.2 Condition A SS crew that you will write a work order and assign an o Reference Table 3.3.2-1 immediately.

I&C Supervisor to investigate.

Enter T.S. LCO 3.3.2 Condition E o Trip 1P-950 bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND verify

5. Plant Response: one channel per pair operable in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

a. 1P-950, will peg high. OR

b. The following annunciator will come in: o Be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND be in Mode

1) 47018-0105, CONTAINMENT HI-HI PRESS 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

CHANNEL ALERT.

Enter T.S. LCO 3.3.2 Condition D o Trip 1P-950 bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in Mode 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 6. After the crew has responded to the Containment C47012-0307, PRZR HI LVL CHANNEL ALERT Pressure Instrument failing high, and/or at the discretion RO

Check pressurizer level.

of the lead evaluator, then enter:

Control level in manual Trigger 3, 1LT-428, Blue Channel Pressurizer Level,

Reduce level to program level.

fails HIGH.

Maintain pressurizer pressure

a. If contacted as I&C to trip bistables, inform the crew

Refer to 1C51.

two I&C Technicians will be available in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b. If contacted as the Operations Management, C47012-0507, PZR LVL DEVIATION acknowledge the report of the failure, and agree to

Verify charging pump in automatic and charging flow make other notifications to the NRC, Duty Station RO proper for the level.

Manager, etc. as asked.

Place charging pump speed control in MANUAL.

c. If contacted as the FIN Team Supervisor, inform the

Control charging pump speed as necessary to restore crew that you will write a work order and assign an pressurizer level to program level.

I&C Supervisor to investigate.

Refer to 1C51.

d. If contacted as an out-plant operator, acknowledge the order to check Pressurizer Heater Backup Heater Breakers (closing springs charged). 1C51.3, Pressurizer Level 1L-428 - High RO

Control pressurizer heaters manually.

7. Plant Response:

Place charging pump speed control in Manual and

a. Blue Channel Pressurizer Level pegs high. adjust pressurizer level to setpoint.

b. 11 Charging Pump speed will lower.

Select position 2-1 (WHITE-RED) on PRZR Level

c. Pressurizer level will slowly lower. Control Selector switch.

d. The following annunciators will come in:

Return pressurizer heaters to AUTO.

1) 47012-0307, PZR HI LVL CHANNEL ALERT.

Return one charging pump speed control to AUTO.

2) 47012-0507, PZR LVL DEVIATION.

Ensure pressurizer level recorder not selected to blue channel.

SS

Enter T.S. LCO 3.3.1 Condition A o Reference Table 3.3.1-1 immediately.

Enter T.S. LCO 3.3.1 Condition K o Trip bistable for 1L-428 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or reduce thermal power to less than P-7 and P-8 (10%).

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 8. When the plant is stable and/or at the discretion of the 1C23 AOP2, MALFUNCTION OF TURBINE EH lead evaluator, then enter: CONTROL SYSTEM LEAD Trigger 4, Turbine Malfunction (Cycling Output).

Place the turbine control system in Manual by

a. If contacted as the out-plant operator to investigate, selecting Manual control using the On Line Control wait 2 minutes and report there are no indication of screen AND attempt to control load using the CV an EH Oil System problem. decrease control.

b. If contacted as the Operations Management,

Notify System Engineer.

acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station 1C1.4, UNIT 1 POWER OPERATION Manager, etc. as asked.

Notify the Duty Chemist of the load change.

c. If contacted as the FIN Team Supervisor or Turbine

If desired, then place CS-46280, ROD BANK Engineer, inform the crew that you will write a work SELECTOR, in MANUAL.

order and investigate.

Using the On Line Control screen, select the desired

d. After the plant is stable, enter the Control Room as Control Mode (VPC, FSP, or LOAD).

the Turbine Engineer and communicate the following

Using the On Line Control screen, select the desired to the crew: demand rate.

1) A 1 HR TIME COMPRESSION is being used.

Verify the VPL control is not Red.

2) Both First Stage Pressure inputs to Turbine

Raise the VPL as necessary using the Valve Control are faulted.

Limiter pop-up screen.

3) Turbine Control will operate correctly in VPC or

Set the Target setting to the desired load by using Load Mode.

the On Line Control screen Target

4) Plant Management has performed an ODMI and increase/decrease controls.

has decided the following:

(a) Exit the manual control screen by pressing

Select the Go control using the On Line Control the exit button. screen.

(b) The crew can acknowledge the Turbine

To suspend the load change, select turbine control Control alarm, but do NOT reset it. Hold on the On Line Control screen.

(c) Operate the turbine in VPC mode when load

Verify the load change stops when desired load is changes are NOT in progress. obtained.

(d) Operate the turbine in LOAD Mode during

Lower the VPL until the Valve Position Limit signal load changes. is at or close to the Current Valve Demand signal.

(e) If necessary, restore the plant:

Verify CS-46280, ROD BANK SELECTOR, in AUTO.

(1) 100% power.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 (2) Bank D Rods at 218 steps. 1C5, CONTROL ROD AND ROD POSITION (cont) (3) Tavg at 560°F. INDICATION SYSTEMS

Verify automatic control rod withdrawal or insertion is

9. Plant Response: NOT required.

a. Annunciator 47008-0409, TURBINE CONTROL

Transfer CS-46280, ROD BANK SELECTOR, to SYSTEM TROUBLE MAN.

b. SCADA Yellow High Priority Alarm for 1st Stage

Adjust Control Rod Bank to desired position, using Pressure Fault. CS-46281, DIGITAL ROD CONTROL.

c. Unexpected load changes.

Verify NO rod control demand signals present.

d. VPL limit red light cycling.

Return CS-46280, ROD BANK SELECTOR, to

e. Rods stepping in and then out. AUTO.

f. RCS Tavg temperature rising and lowering.

EVENT 5 OPTIONAL EVENT 1C1.4 AOP1, RAPID POWER REDUCTION UNIT 1 Event 5 can be skipped if the Lead Evaluator determines

Determine the predicted Boron addition and final RO / SS a sufficient reactivity manipulation was performed Control Rod Position by obtaining values from the during Event 4. appropriate contingency reactivity plan.

Borate the RCS as necessary to maintain control rods

10. When the plant is stable and/or at the discretion of the above the insertion limit and control delta I within lead evaluator, then: limits.

a. As the TSO, call the Control Room and communicate

Place pressurizer heaters to ON.

the following:

Using the On Line Control screen, select the Control

1) The King Plant has tripped offline. Mode pop-up screen.

2) Generator output needs to be reduced to lower

Select the desired control mode (VPC, FSP, or the power factor so a grid transformer breaker LOAD).

can be re-closed.

Using the On Line Control screen, select the

3) Prairie Island Unit 1 generator output needs to be Demand Rate pop-up screen.

lowered to 555 MW within the next 15 minutes.

Select the desired rate of load change.

4) This is urgent and needs to be done as soon as

Set the desired Target setting using the On Line possible.

Control screen.

Using the On Line Control screen, select the Go NOTE control to initiate load reduction.

Once the Lead Evaluator is satisfied with the reactivity manipulation, proceed to Event 6.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 5 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL (cont)

Verify the Boric Acid integrator is reset.

RO / SS

Set 1YIC-110, BA TO BLENDER BATCH INTEGRATOR, to quantity desired.

Place CS-46300, MAKE-UP MODE SELECTOR, to BORATE.

If desired, then adjust 1HC-110, BA TO BLENDER FLOW CONT, to MANUAL and adjust output for desired flow rate.

Momentarily place CS-46457, BORIC ACID MAKE-UP CONTROL, to START, to initiate the boration.

When the desired quantity of boric acid has been added, then verify automatic makeup stopped as indicated by CS-46457, BORIC ACID MAKE-UP CONTROL, green light LIT.

If additional boration is desired, then return to step 2.

When the boration is complete, then verify 1HC-110, BA TO BLENDER FLOW CONT, is in AUTO.

Reset the Boric Acid integrator.

Perform a 10 gallon flush.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTs 11. When the lead evaluator is satisfied with the reactivity 1E-0, REACTOR TRIP OR SAFETY INJECTION 6, 7, 8, & manipulation, enter:

Verify Reactor Trip.

9 RO/

Trigger 6, Large Break LOCA from Loop B Hot Leg.

Manually trip the Main Turbine.

LEAD

a. Upon hearing the announcement of Reactor Trip, or

Verify both Safeguards buses energized.

when called as the Turbine Building Operator to

Determine SI is required.

isolate the Unit 1 MSRs per Attachment J, then open o Either SG pressure < 530 psig.

and run schedule file E-0_Att-J.sch located in o PRZR pressure < 1830 psig.

X:\\Trex_PI\Lightning\Schedule\EOPs. When the o Containment pressure > 3.5 psig.

isolation is complete, inform the crew the MSRs are

Manually actuate SI.

isolated.

Perform Attachment L (see pages 16 & 17).

b. Upon hearing the announcement of Safety Injection,

Check AFW Status:

or when called as the Turbine Building Operator to o Verify total AFW flow greater than 200 secure the Turbine Building Roof Exhausters, wait 2 GPM.

minutes and report the Turbine Building Roof o Manually start AFW pump(s).

Exhausters are all secured. o Verify AFW pumps discharge pressure

c. If Control Room personnel ask if Unit 2 personnel are greater than 1000 psig.

available to perform Attachment L, then inform the o Control feed flow to maintain 11 SG Wide Control Room that Unit 2 personnel are NOT Range between 50% and 59%.

available for performing Attachment L.

Check RCS Temperatures trending to 547°F.

d. If Control Room personnel ask if Unit 2 personnel are

Check PRZR PORVs and Spray valves closed.

available to secure Diesel Generators and/or Safeguards Cooling Water Pumps, then inform the

Stop RCPs due to RCS pressure below 1250 psig and Control Room that Unit 2 personnel WILL secure the SI flow.

Diesel Generators and/or Safeguards Cooling Water

Determine SGs are NOT faulted.

Pumps.

Determine SG Tubes are NOT ruptured.

Determine RCS is NOT intact due to Containment CRITICAL TASKS SS pressure rising.

Manually trip the main turbine before transition out

Go to 1E-1.

of E-0.

Manually actuate at least one train of SI-actuated safeguards equipment before transition out of E-0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTs 12. Plant Response: 1FR-P.1, RESPONSE TO IMMINENT PRESSURIZED 6, 7, 8, & a. RCS and PRZR pressure lowers rapidly. THERMAL SHOCK CONDITION 9 RO/SS

b. The reactor automatically trips on low pressurizer

Determine RCS pressure is less than 550 psig and (cont) pressure. RHR pump flow is greater than 950 gpm.

Return to procedure and step in effect.

EMERGENCY PLAN CLASSIFICATION ALERT - FA1 due to a loss of the RCS Fission Product 1E-1, LOSS OF REACTOR OR SECONDARY Barrier due to RCS leak rate greater than 60 gpm or a COOLANT red path in Integrity.

Stop RCPs if not already done in 1E-0.

RO/SS

Determine SGs are NOT faulted and SG levels intact.

SITE AREA EMERGENCY - FS1 due to a loss of the RCS

Control feed flow to maintain narrow range level Fission Product Barrier and potential loss of the Fuel between 5% and 50% [Wide Range 50% and 59%].

Cladding Fission product barrier. This classification will

Check secondary radiation is normal.

only be applicable if an orange path in Core Cooling

Check power to PRZR PORV block valves available.

occurs.

Check PRZR PORVs are closed.

Check at least one PRZR PORV block valve is open.

13. If Control Room personnel ask if Unit 2 personnel are

Reset SI and Containment Isolation.

available to secure Diesel Generators and/or Safeguards

Establish Instrument Air to Containment.

Cooling Water Pumps, then inform the Control Room

Check power supply to charging pumps are from that Unit 2 personnel WILL secure the Diesel Generators offsite power.

and/or Safeguards Cooling Water Pumps.

Check at least one charging pump is running.

Establish charging flow as necessary.

Determine SI flow should NOT be terminated due to subcooling and RCS pressure.

Determine RHR pumps should NOT be stopped due to RCS pressure being too low.

Check RCS and SG pressures

Determine Diesel Generators should be stopped.

Determine Safeguards Cooling Water pumps should be stopped.

Initiate Evaluation of Plant Status.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTs 1E-0 Attachment L: SI Alignment Verification 6, 7, 8, & NOTE

Verify Safeguards Component Alignment:

9 LEAD There should be NO discrepancies with Attachment L,

Verify both trains of SI actuated:

(cont) except for 12 RHR pump being OOS. o Both RHR pumps - RUNNING

-OR-o Both SI pumps - RUNNING o 12 RHR Pump is OOS and should NOT be started.

"SI NOT READY" lights - NOT LIT

"SI ACTIVE" lights - LIT FOR PLANT CONDITIONS

"CONTAINMENT ISOLATION" lights - LIT FOR PLANT CONDITIONS

Check Category 1 Vent Zone Boundary:

Close MV-32115, 122 SFP HX INLT HDR MV B

Check Cooling Water Header Pressures - BOTH GREATER THAN 65 PSIG

Verify Plant Announcements Complete:

Check If Main Steamlines Are Isolated:

Determine MSIVs, Bypass Valves, and Containment Instrument Air Valves do NOT need to be closed.

Verify SI Flow

Verify RHR Flow

Verify Containment Spray is actuated (if necessary).

Check RCP Cooling

Verify Local Actions Complete

Verify Generator Breakers - OPEN

Verify All Heater Drain Pumps - STOPPED

Check Turbine Valves:

o Turbine reheat and intercept valves - CLOSED o Open turbine drain valves

Verify Main Feedwater Alignment:

o Both main feedwater pumps - STOPPED o Main and bypass FRVs - CLOSED Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTs 14. If Control Room personnel ask for status of Unit 2

Verify All Condensate Pumps - STOPPED:

6, 7, 8, & Cooling Water/Chilled Water lineup, then inform the

Place Steam Dump in "STM PRESS" Mode 9 LEAD Control Room that Unit 2 Cooling Water/Chilled Water

Verify Unit 1 Cooling Water/Chilled Water Alignment:

(cont) valves are in there safeguards positions. o CFCU control switches - "SLOW".

15. If Control Room personnel ask for status of Battery o CFCU dampers - ALIGNED TO DOME Room Temperatures, then inform the Control Room that o Unit 1 cooling water/chilled water valves closed Battery Room temperatures are less than 84°F. o Unit 1 CRDM shroud cooling supply and return

16. If Control Room personnel ask for status of Spent Fuel valves - CLOSED Cooling, then inform the Control Room that Spent o CFCU cooling water supply and return valves -

Fueling level and temperature are normal. OPEN o CFCU chilled water supply and return valves -

CLOSED

Verify 11 Safeguards Screenhouse Ventilation lineup.

Verify Control Room Ventilation Alignment:

o Chillers and fans - RUNNING o Control room chiller suction/discharge tie closed -

STATUS LIGHT LIT

Verify Unit 2 Cooling/Chilled Water Alignment

Verify 21 Safeguards Screenhouse Ventilation lineup.

Verify 11 and 12 Battery Charger Operation is normal.

Verify Battery Room temps less than 84°F.

Check status of Spent Fuel Cooling.

Check Status Of Notifications

Notify SS Of Any Discrepancies.

17. Once the crew has determined SI Pumps and RHR Pumps should NOT be stopped and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE and inform the crew that training has the duty.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SIMULATOR SETUP CHECKLIST Before Scenario

_____ Simulator Status:

___ 1. "Training Load" ___ 2. Step counters "ON"

___ 3. Alarm sound "ON" ___ 4. Steps 1 - 5 on page 6 complete

___ 5. Speed: REAL ___ 6. IC-262 or IC-9 running

_____ Delete the memory on the Yokogawa Model DX1000 recorders by cycling the Recorder Power OFF pushbutton in the simulator instructors booth.

_____ Verify Schedule File/Summary matches Simulator Input Summary page in the SEG.

_____ Verify that control rod step counters on C panel and ERCS RBU matches the IC conditions.

_____ Boric Acid/RMU integrators set to: BA: 3, RMU: 10, and reset.

_____ BOC I sheet displayed on C panel.

_____ BOC Reactivity Briefing sheet available at Reactor Operator Desk.

_____ Turnover sheet/PRA sheet available.

_____ If it is the first scenario of the day, then perform a shutdown and restart of the floor PCs that are connected to the LAN.

_____ Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID).

_____ Electronic PINGP 577 forms closed on LAN connected PCs.

_____ Board-mounted EAL Tables are cleaned.

_____ EOOS running on PC and updated as follows to reflect equipment OOS:

___ 1. 12 RHR Pump

___ 2. BKR 16-10 (CLOSE)

_____ Update Control Board Placards:

___ 1. NRC Current Authentication Code call date updated to current date.

___ 2. High Flux At Shutdown Alarm Setpoint placards: 5900 cps.

___ 3. Feedwater regulating valve position placard set to current values.

___ 4. Recommended SG Blowdown flow set to current values.

___ 5. RCS boron on the CVCS panel placard: 1299 ppm.

___ 6. Turbine reference/setter values on the CVCS panel set to current (Target/Demand on-line positions).

___ 7. Shift Reactivity Guidance placard: BA: 4.2 gallons, RMU: 67 gallons.

Dilutions @ 10 gal RMU, 1-2 times per shift.

_____ Magnetic placards in place:

___ 1. 11 BA TANK Lined Up For Service

___ 2. 11 BA PUMP Lined Up to 11 BA Tank

___ 3. 12 BA PUMP Lined Up to 11 BA Tank

___ 4. CC to SFP MV-32117 In Service

___ 5. Blowdown 46470 SGB To CDSR

___ 6. HU Flag above 12 RHR HX CC inlet MV-32094 for 1C14 Limitation

___ 7. H2 IN VCT SPACE at VCT Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0

_____ Pink Status Control Tags in place:

___ 1. CS-46540, 22 CC WTR PUMP ___ 5. CS-46184, 11 RHR PUMP

___ 2. CS-46572, CC TO SFP MV-32117 ___ 6. CS-46178, 11 SI PUMP

___ 3. CS-46935, D1 DIESEL GENERATOR ___ 7. CS-46036, 11 CC WTR PUMP

___ 4. CS-46424, 11 TDAFWP ___ 8. CS-46053, 12 CLG WTR PUMP

_____ Yellow Caution Tags in place:

___ 1. CS-46064, CC TO SFP MV-32115, in CLOSED

___ 2. CS-46185, 12 RHR PUMP, in PULLOUT

___ 3. CS-46914, BUSTIE BUS 16 / BUS 26 BKR 16-10, in PULL TO LOCK

_____ ERCS driven recorders are on-scale (RCS temperature scaled 555º F to 565º F).

_____ ERCS alarm screen operating and alarms reset.

_____ All ERCS terminals operating and set as follows:

CONF VARS R02 Alarm Summary Page CONE1 Group OP31_U1 R03 AFD CONC SAS (XS11) R04 TPM CONG1 Group QP CCDATA R05 QP LOADFOLL ERCS-R01 Group RADMON_U1 R06 Alarm Summary Page

_____ ERCS single point displays: CONB 1T0499A 1U1613A CONE2 1Q0340A 1V4501A

_____ ERCS TPM set (Calorimetric - Auto Scaling - LEFM).

_____ Verify that copy machine and printers are loaded with paper.

_____ Pens/Paper/Markers available on the simulator.

st

_____ Verify 121 IA Compressor is in PREFERRED and 122 IA Compressor is in 1 STANDBY, and nd 123 IA Compressor is in 2 STANDBY.

_____ Verify R11/R12 are lined up correctly (at the R11/R12 local panel):

___ 1. Sample pump is running.

___ 2. Alarms are reset.

___ 3. CS-8006106, Sample Inlet Switch, is selected to CNTMT.

___ 4. CS-8006107, Sample Outlet Switch, is selected to Aux Bldg Stack.

_____ Set Turbine Control HMI Displays as follows:

___ 1. U1 E-H Turb Cont STA 2 (48087) to Control Valve Overview.

___ 2. U1 Turb Aux Cont (48088) to Turb Overview.

___ 3. U1 E-H Turb Cont STA 1 (48086) to On Line Control.

_____ DEHC VPL set ~ 0.1 to 0.2 above current valve position (not on limiter).

_____ DEHC alarms cleared.

_____ N51 & N52 Display Sheets for 100% power are in place as necessary.

_____ Headsets turned on as necessary.

_____ Procedure checklist completed. See following page.

_____ Peer Check performed for simulator setup.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 PROCEDURE CHECKLIST The following procedures will be used during this session. Verify the procedures are free of place keeping marks before starting the session and after the session are complete:

Before After 1C1.4 AOP1, RAPID POWER REDUCTION UNIT 1 1C12.1, LETDOWN, CHARGING, AND SEAL WATER INJECTION -

UNIT 1 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL 1C23 AOP2, MALFUNCTION OF TURBINE EH CONTROL SYSTEM 1C5 AOP1, UNCONTROLLED ROD MOTION 1C51.3, Pressurizer Level 1L-428 - High 1C51.4, Containment Pressure 1P-950 - High 1E-0, REACTOR TRIP OR SAFETY INJECTION 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT 1FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION C47008-0409, TURBINE CONTROL SYSTEM TROUBLE C47012-0307, PRZR HI LVL CHANNEL ALERT C47012-0407, PRZR HI LVL C47012-0507, PZR LVL DEVIATION C47018-0105, CONTAINMENT HI-HI PRESS CHANNEL ALERT C7, REACTOR CONTROL SYSTEM EAL BOARDS EOP INFORMATION BOOK F3-2 EAL STICKER BOOK checked for missing stickers F3-2.1, EMERGENCY ACTION LEVEL TECHNICAL BASES REACTIVITY BRIEFING BINDER - BOC SWI O-28, NOTIFICATION OF OPERATIONS MANAGER & NRC RESIDENT INSPECTOR SWI O-50, REACTIVITY MANAGEMENT T.S. LCO 3.3.1 T.S. LCO 3.3.2 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 22 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Post-Scenario Checklist

_____ LAN connected computers are cleared of information added during the scenario.

_____ Computer generated PINGP 577 cleared.

_____ Procedure checklist completed. See previous page.

_____ Remove Pink Status Control Tags from the following equipment:

___ 1. CS-46935, D1 DIESEL GENERATOR

___ 2. CS-46424, 11 TDAFWP

___ 3. CS-46184, 11 RHR PUMP

___ 4. CS-46178, 11 SI PUMP

___ 5. CS-46036, 11 CC WTR PUMP

___ 6. CS-46053, 12 CLG WTR PUMP

_____ Magnetic placards removed:

___ 1. NONE

_____ Remove Yellow Caution Tags from the following equipment:

___ 1. CS-46185, 12 RHR PUMP

___ 2. CS-46914, BUSTIE BUS 16 / BUS 26 BKR 16-10