ML15126A459

2014 Prairie Island Nuclear Generating Plant Initial License Examination Proposed Simulator Scenarios

ML15126A459
Person / Time
Site:	Prairie Island
Issue date:	05/19/2014
From:	Region 3 Administrator
To:	Northern States Power Co, Xcel Energy
References
Download: ML15126A459 (132)

Text

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) 11 & 12 SI PUMPS FAIL TO AUTO START 6 C (BOP) 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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) MAIN TURBINE FAILS TO AUTO TRIP 8 C (ATC) 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) 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) 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.: 5 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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) SI TO CHILLED WATER SIGNAL FAILURE

• (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 HOUR 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:

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR ALERT.

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

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR o Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Mode 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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 set to current (Target/Demand on-line positions).

___ 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. H 2 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 16 of 22 PI-ILT-NRC-1401S, 2014 ILT NRC SIMULATOR EVALUATION #1, REV. 0

_____ Pink Status Control Tags in place:

___ 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 HOUR 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:

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND verify

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

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND be in Mode

c. 47018-0105, CONTAINMENT HI-HI PRESS 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

CHANNEL ALERT.

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

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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:

5) Exit the manual control screen by pressing the

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

6) The crew can acknowledge the Turbine Control

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

7) Operate the turbine in VPC mode when load

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

8) Operate the turbine in LOAD Mode during load

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

9) If necessary, restore the plant:

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

(a) 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 (b) Bank D Rods at 218 steps. 1C5, CONTROL ROD AND ROD POSITION (cont) (c) 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) Power needs to be reduced to lower the power

• Select the desired control mode (VPC, FSP, or factor so a grid transformer breaker can be re- LOAD).

closed.

• Using the On Line Control screen, select the

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

to 555 MW within the next 10 - 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 RCS 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. H 2 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

_____ 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 23 of 26 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

1. 12 RHR PUMP is OOS for corrective maintenance.

• T.S. 3.5.2 Condition A was entered with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> remaining.

PROTECTED EQUIPMENT D1 DIESEL GENERATOR 11 CC PUMP 11 TDAFWP 12 CLG WATER PUMP 11 RHR PUMP 22 CC PUMP 11 SI PUMP 121 SFP HX RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS

• BKR 16-10 is OOS for corrective maintenance.

• 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.

• Maintain 100% power.

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

• Dilute 10 gallons 1-2 times per shift for temperature control.

NEW PROCEDURES / INSTRUCTIONS 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 24 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, 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 25 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, 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 26 of 26 PI-ILT-NRC-1402S, 2014 ILT NRC SIMULATOR EVALUATION #2, 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 Nic Abney 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 28 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-1403S SEG TITLE: 2014 ILT NRC SIMULATOR EVALUATION #3 REV. # 0 PROGRAM: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 2.0 HOUR Developed by: Shawn Sarrasin 1/18/2014 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:

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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. Restore RCS average coolant temperature to program per Learning C47013-0305.

Objectives: 2. Swap running charging pumps per 1C12.1.

3. Diagnose and perform corrective actions for 11 Safety Injection Pump being placed in local control per C47018-0301.

4. Diagnose and perform corrective actions for N43, Blue Channel Power Range Nuclear Instrument, failing high per 1C51.3.

5. Diagnose and respond to a Pressurizer Spray valve failing 75%

open per C47012-0508.

6. Diagnose and respond to a failure of the Reactor to automatically trip during a RCS Low Flow condition per C47017-0301 and 1E-0.

7. Diagnose and respond to 12 SG faulted into containment per 1E-0 and 1E-2.

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 MSLB (<1%)

Information:

Important Components:

11 SI PUMP Important Operator Actions with Task Number:

Operators fail to isolate AFW to affected SG (0.54%)

CRO 301 003 06 01 000 - Faulted Steam Generator Isolation 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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 11 Safety Injection Pump local-remote switch placed in local.

2. N43, Blue Channel Power Range Nuclear Instrument, fails high.

3. Pressurizer Spray valve opens to the 75% position.

4. Loop A RCS low flow due to Bus 11 lockout.

After EOP Entry:

1. Reactor fails to automatically trip.

Abnormal Events:

1. Nuclear Power Instrument Failure

2. Low Pressurizer Pressure Major Transients:

1. 12 Steam Generator fault inside containment.

Critical Tasks:

1. E A: Manually trip the reactor from the control room before transition out of E-0.

2. E F: Establish and maintain 200 GPM AFW flow to the Steam Generator(s) before transition out of E-0, unless the transition is to FR-H.1, in which case the task must be initiated before RCPs are manually tripped in accordance with step 2 of FR-H.1.

NOTE: E F only applies if BOTH AFW pumps trip on low discharge pressure.

This may occur due to the fault in 12 Steam Generator.

3. E A: Isolate the faulted STEAM GENERATOR before transition out of E-2, unless the transition is to FR-P.1, in which case the task must be completed prior to checking if safety injection should be terminated per step 6 of FR-P.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 4 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS

• Exposure: BOC

• 1PT-485, Turbine First Stage Pressure, is failed high.

• Power: 50%

• 123 Air Compressor

• Boron (CB): 1482 ppm

• Temperature: 556°F

• Pressure: 2235 psig

• Xenon: Equilibrium

• Rods: D @ 181

• Generator: 272 MW SEQUENCE OF EVENTS:

Event 1: Restore RCS Average Coolant Temperature to Program Temperature

• 1PT-485, Turbine First Stage Pressure, failed high prior to shift turnover.

• The previous crew has already responded per 1C5 AOP1, Uncontrolled Rod Motion, and 1C51.2, Instrument Failure Guide.

• RCS Tavg is at 556°F and Program Temperature is 553°F.

• Rods stepped out six steps prior to the previous crew placing Rods in manual.

• The crew will step rods in six steps in increments determined by the RO and SRO.

• Each rod step will change RCS Tavg approximately 0.5°F.

Event 2: Swap Running Charging Pumps

• 11 and 12 Charging Pumps are initially running.

• The crew will swap charging pumps to 11 and 13 running and 12 secured per 1C12.1.

Event 3: 11 Safety Injection Pump Local-Remote Switch placed in LOCAL

• Annunciator 47018-0301, 11 SI PUMP LOCAL CONTROL SI AUTO START BLOCKED, will alarm.

• After being dispatched, an out-plant operator will discover the local-remote switch for 11 SI Pump in local.

• The SS will enter T.S. LCO 3.5.2 Condition A for one train of ECCS inoperable.

• The crew will direct the out-plant operator to place 11 SI Pump in remote.

Event 4: N43, Blue Channel Power Range Instrument, fails HIGH

• Rods will NOT step in because rods are still in manual due to 1st Stage Pressure Instrument failed high.

• The SS will enter T.S. LCO 3.3.1 Conditions A, D, E, Q, and R.

• The crew will remove N43 from service per 1C51.3.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Event 5: Pressurizer Spray Valve Drifts Open

• The RCS Loop A Pressurizer Spray valve slowly opens to the 75% position.

• The crew will place the Pressurizer Spray valve in manual per C47012-0508.

• The Pressurizer Spray valve will close.

Event 6: Loop A RCS Loss of Flow

• Bus 11 locks out.

• Loop A RCS loss of flow occurs due to loss of power to 11 RCP.

• The reactor will fail to automatically trip.

• The crew will manually trip the reactor.

• The crew will enter 1E-0 and then transition to 1ES-0.1, Reactor Trip Recovery.

Event 7: 12 Steam Generator Faults into Containment

• RCS pressure will lower rapidly.

• 12 SG pressure will lower slowly.

• Containment pressure will rise slowly.

• Safety Injection will automatically actuate or be manually actuated by the crew.

• The crew will transition to 1E-0.

• The crew will diagnose a Faulted SG and transition to 1E-2.

• The crew will isolate 12 Steam Generator.

• The crew will transition to 1E-1.

• A red or orange path may occur in the Integrity CSF. If this occurs, the crew will transition to 1FR-P.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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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-263 and place in RUN.

2. If IC-263 is NOT available:

a. Reset to IC-8.

b. Place the simulator in RUN.

c. Place CS-46098, 123 AIR COMPRESSOR, in PULLOUT.

d. Place CS-49011, 122 AIR COMPRESSOR, in PREFERRED.

e. Place CS-49012, 123 AIR COMPRESSOR, in 1st STANDBY.

f. Insert Remote IA101 (CP-40-7) to CLOSED.

g. Insert System Override RX226 to 616 (1st Stage Pressure Fails High).

h. Place CS-46280, ROD BANK SELECTOR, in MANUAL after rods step out 6 steps.

i. Place CS-46338, STEAM DUMP MODE, in STM PRESS.

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 181 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 550 as the new Min EU value for Pen 1U9001A (point 1T0499A).

d. Enter 560 as the new Max EU value for Pen 1U9001A (point 1T0499A).

e. Enter 550 as the new Min EU value for Pen 1U9002A (point 1T0496A).

f. Enter 560 as the new Max EU value for Pen 1U9002A (point 1T0496A).

5. If available, run schedule file PI-ILT-NRC-1403S.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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 activities:

1) Restore Tave to program temperature per C47013-0305:

(a) 1C51.2 actions are complete for the failed instrument with the exception of restoring Tavg to program temperature.

(b) Rods are in MANUAL.

(c) Hand out copy of ERCS trend showing (1) RCS Tavg.

(2) RCS Tref.

(3) Bank D Rod Height.

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

(e) If crew questions why Tavg was not restored prior to performing other actions in 1C51.2, then inform crew that Plant Management used the Operational Decision Making Process and determined to restore Tavg on a latter step.

2) After Tavg is restored to program, the crew will swap charging pumps per Section 5.4.1 of 1C12.1.

(a) 11 and 12 Charging pumps are currently running.

(b) 13 Charging Pump Suction Stabilizer PM is complete and ready for PMT.

(c) 13 Charging Pump desurger has already been checked by the out-plant operator.

(d) The crew will start 13 Charging Pump and secure 12 Charging Pump.

(e) The Lead RO will perform this evolution.

(f) The crew will also brief this evolution prior to entering the simulator.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 restore C47013-0305, AUCTIONEERED TAVG-TREF Tavg to program. DEVIATION RO/SS

• Check Tavg-Tref temperature deviation.

• Recognize Tref is failed high due to instrument failure and use Figure C1-5 to determine program temperature.

• Return Tavg to program using manual rod control.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 4. After the crew has restored Tavg to program 1C12.1, LETDOWN, CHARGING, AND SEAL WATER temperature, they will swap charging pumps so that 11 INJECTION - UNIT 1 and 13 are running.

• Verify 13 Charging Pump discharge desurger is

a. When contacted as the out-plant operator to verify 13 LEAD pressurized.

Charging Pump discharge desurger is pressurized,

• Transfer the speed control for 11 Charging Pump to report the 13 Charging Pump discharge desurger is Manual per C7.

pressurized in accordance with Section 5.13.

• Verify 13 Charging Pump speed controller is at

b. If contacted as the out-plant operator to check 13 minimum.

Charging Pump suction stabilizer, report no issues

• Reduce 11 Charging Pump speed until seal injection noted. flow drops to approximately six gpm.

• Verify charging pump discharge header pressure 1PI-133 is less than 2400 psig.

• Verify 13 Charging Pump control switch green light is LIT and white light is OFF.

• Start 13 Charging Pump.

• Adjust 11 Charging Pump speed to maintain charging pump discharge pressure, 1PI-133 less than 2500 psig and approximately 9.5 gpm seal injection.

• Ensure 12 Charging Pump speed is at minimum and seal injection flow is approximately 9.5 gpm.

• Stop 12 Charging Pump.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 5. When charging pumps have been swapped, and/or at C47018-0301, 11 SI PUMP LOCAL CONTROL SI AUTO the discretion of the lead evaluator, then enter: START BLOCKED Trigger 3, 11 SI PUMP LCL/REM-START/STOP, LEAD

• Dispatch an operator to investigate.

switch to LOCAL.

• Verify CS-46178, 11 SI PUMP, is in desired position,

a. When contacted as the out-plant operator to then return CS-19624, 11 SI PUMP LCL/REM-investigate 11 SI Pump, wait 1 minute and report the START/STOP, selector switch to REMOTE.

11 SI Pump Local-Remote Switch is in the LOCAL SS

• Refer to T.S. 3.5.2. and T.S. 3.5.3.

position and it was inadvertently bumped by NPSAs o Enter T.S LCO 3.5.2 Condition A - Restore cleaning the area. 11 SI Pump to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

b. When contacted as the out-plant operator to place o T.S. LCO 3.5.3 is only applicable in Mode 4 CS-19624 to REMOTE, then wait 1 minute and and Unit 1 is currently in Mode 1.

enter:

Trigger 13, 11 SI PUMP LCL/REM-START/STOP, switch to REMOTE.

6. Plant Response:

a. Annunciator 47018-0301, 11 SI PUMP LOCAL CONTROL SI AUTO START BLOCKED.

b. 11 SI Pump Green indicating light goes OFF.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 7. When 11 SI Pump Remote Control is restored, and/or at C47013-0101, 0102, 0103, 0203, NIS POWER RANGE the discretion of the lead evaluator, then enter: CHANNEL ALERT AND ALARMS Trigger 4, N43 Blue Channel Power Range Nuclear RO

• Determine N43 is the initiating channel by observing Instrument fails HIGH. NIS indications.

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

• Determine a reactor trip is NOT necessary.

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

• Determine there is NO dropped, misaligned, or stuck

b. If contacted as the Operations Management, rod.

acknowledge the report of the failure, and agree to LEAD

• Refer to 1C51, INSTRUMENT FAILURE GUIDE.

make other notifications to the NRC, Duty Station Manager, etc. as asked.

1C51.3, Power Range Nuclear Instrument N High

c. If contacted as the FIN Team Supervisor, inform the RO crew that you will write a work order and assign an

• Determine rod control is already in manual.

I&C Supervisor to investigate. SS

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

8. Plant Response:

• Enter T.S. LCO 3.3.1 Condition D and Condition E -

a. N43 indication will peg high. Place N43 channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in Mode

b. Rods will NOT move because they are already in 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. SR 3.2.4.2 is NOT required since manual. thermal power is less than 85%.

c. The following annunciators will be received:

• Enter T.S. LCO 3.3.1 Condition Q - Verify interlock is

1) 47013-0101, NIS POWER RANGE POS FLUX in required state for existing conditions (P10 Aqua RATE CH ALERT. Light LIT) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

2) 47013-0102, NIS POWER RANGE HI

• Enter T.S. LCO 3.3.1 Condition R - Verify interlock is SETPOINT CH ALERT. in required state for existing conditions (P7, P8, & P9

3) 47013-0103, NIS POWER RANGE Aqua Lights NOT LIT) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 2 in OVERPOWER ROD WITHDRAWAL STOP. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

4) 47013-0203, NIS POWER RANGE CHANNEL LEAD

• Remove N-43 from service as follows:

DEVIATION.

• Place Rod Stop Bypass switch in the N-43 position.

• Place Power Mismatch Bypass switch in the N-43 position.

• Place Upper Section Current Comparator Defeat switch in the N-43 position and verify the Upper Section channel Defeat Light is LIT.

• Place Lower Section Current Comparator Defeat 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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 switch in the N-43 position and verify the Lower (cont) LEAD Section channel Defeat Light is LIT.

• Place Comparator Channel Defeat switch in the N-43 position and verify Comparator Defeat Light is LIT.

• Remove and concurrently verify removal of the N-43 instrument power fuses.

• Remove and concurrently verify removal of the N-43 control power fuses.

• Verify 47013-0101, 0102, 0201, 0202, and 47014-RO 0303 annunciators are received.

• Verify 44178-0306, 0307, and 44205-0304 status lights LIT.

• Determine Tavg is matched to program temperature.

• Determine to NOT place rod control to AUTO due to P-485 Turbine First Stage Pressure instrument failure.

• Call I&C to trip bistables.

• Log Delta I for N41, N42, and N44 at 30 min intervals.

• Verify the NR-45 recorder is selected to an operable channel.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 5 9. When N-43 is removed from service (except for tripping C47012-0508, PRZR HI/LO PRESS bistables) and/or at the discretion of the lead evaluator,

• Determine pressure is low.

enter: RO

• Verify all pressurizer heaters ON.

Trigger 5, Pressurizer Spray Valve PCV-431 drifts to

• Verify PORVs, CV-31231 and CV-31232, are closed.

75% open.

• Verify both spray valves CLOSED.

a. If contacted as the Operations Management,

• Verify CV-31329, AUX PRZR SPRAY, is closed.

acknowledge the report of the failure, and agree to

• Verify pressurizer pressure control in automatic and make other notifications to the NRC, Duty Station functions properly.

Manager, etc. as asked.

• Refer to T.S. 3.4.1 and ensure required DNB

b. If contacted as the FIN Team Supervisor, inform the SS parameters are met.

crew that you will write a work order and assign a

• If Pressurizer pressure drops below 2175 psig, then Maintenance Supervisor to investigate.

enter T.S. LCO 3.4.1 Condition A - Restore RCS DNB parameter(s) to within limit in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (i.e. restore

10. Plant Response:

pressurizer pressure above 2175 psig).

a. Pressurizer pressure lowers slowly.

b. Pressure will reach 1930 psig in approximately two minutes with NO operator action.

c. Pressurizer Heaters turn ON.

CONTIGENCY If the crew trips the reactor due to low pressurizer pressure, then skip Event 6 and proceed to Event 7 after the crew transitions to 1ES-0.1, Reactor Trip Recovery.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 6 11. When the plant is stable, and/or at the discretion of the C47017-0301, ONE LOOP LO FLOW OR RCP BKR lead evaluator, then enter: OPEN REACTOR TRIP Trigger 6, Loss of Loop A RCS flow due to Bus 11 RO

• Perform 1E-0.

Lockout.

a. Upon hearing the announcement of Reactor Trip, or RO/ 1E-0, REACTOR TRIP OR SAFETY INJECTION when called as the Turbine Building Operator to LEAD

• Determine the reactor did NOT automatically trip.

isolate the Unit 1 MSRs per Attachment J, then open and run schedule file E-0_Att-J.sch located in

• Manually trip the reactor.

X:\\Trex_PI\Lightning\Schedule\EOPs. When the

• Verify turbine trip.

isolation is complete, inform the crew the MSRs are

• Verify both safeguards buses are energized.

isolated. SS

• Determine SI is NOT actuated.

• Transition to 1ES-0.1.

12. Plant Response:

a. Annunciators for a Bus 11 Lockout. RO/ 1ES-0.1, REACTOR TRIP RECOVERY

b. 11 RCP NOT running indication. LEAD/

• Announce Unit 1 Reactor Trip.

c. Loop A RCS flow lowers rapidly. SS

• Determine Steam Dump is already in pressure mode.

d. Annunciator C47017-0301 (Reactor Trip First Out) is

• Check RCS temperatures.

received.

• Check Cooling Water Header Pressures greater than

e. The reactor fails to automatically trip.

75 psig.

f. The reactor is capable of a manual trip.

• Notify Turbine Building Operator to Isolate Unit 1 MSRs per ATTACHMENT J.

CRITICAL TASK Manually trip the reactor from the control room before

• Check FW Status.

transition out of E-0.

EMERGENCY PLAN CLASSIFICATION ALERT - SA2.1 due to the reactor failing to automatically trip during the RCS Low Flow condition and the crew successfully manually tripping the reactor.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 13. After the crew has transitioned to 1ES-0.1 and/or at the 1ES-0.1, REACTOR TRIP RECOVERY, INFO PAGE discretion of the lead evaluator, then enter:

• Actuate SI and go to 1E-0 Step 1 if either condition Trigger 7, 12 Steam Generator Fault inside SS listed below occurs:

Containment. o RCS subcooling less than 20°F.

a. If not completed during Event 6, then open and run o PRZR level cannot be maintained >5%.

schedule file E-0_Att-J.sch per step 11 above.

b. Upon hearing the announcement of Safety Injection, 1E-0, REACTOR TRIP OR SAFETY INJECTION or when called as the Turbine Building Operator to RO/

• Verify Reactor Trip.

secure the Turbine Building Roof Exhausters, wait 2 LEAD

• Verify Turbine Trip.

minutes and report the Turbine Building Roof Exhausters are all secured.

• Verify both Safeguards buses energized.

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

• Determine SI is required or already actuated.

available to perform Attachment L, then inform the o Either SG pressure < 530 psig.

Control Room that Unit 2 personnel are NOT o PRZR pressure < 1830 psig.

available for performing Attachment L. o Containment pressure > 3.5 psig.

• Manually actuate SI if it did not already actuate.

14. Plant Response: LEAD

• Perform Attachment L (see pages 16 & 17).

a. Pressurizer pressure and level rapidly lower.

• Check AFW Status:

RO

b. SI will automatically actuate when Containment o Verify total AFW flow greater than 200 pressure reaches 3.5 psig. GPM.

o Verify AFW pumps discharge pressure CRITICAL TASK greater than 1000 psig.

Establish and maintain 200 GPM AFW flow to the Steam o Stop feed flow to 12 SG.

Generator(s) before transition out of E-0, unless the o Throttle AFW flow to 11 SG to maintain transition is to FR-H.1, in which case the task must be greater than 1000 psig discharge pressure.

initiated before RCPs are manually tripped in o Control feed flow to maintain 11 SG Wide accordance with step 2 of FR-H.1. Range between 50% and 59%.

• Check RCS Temperatures trending to 547°F.

NOTE

• Check PRZR PORVs and Spray valves closed.

This Critical Task only applies if BOTH AFW pumps trip

• Check if RCPs should be stopped.

on low discharge pressure. This may occur due to the o At least one SI pump running and flow fault in 12 Steam Generator. indicated.

o RCS pressure less than 1575 psig.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 o Stop 12 RCP (11 RCP is already secured (cont) from the loss of bus 11).

• Check if SGs are NOT faulted.

• Determine 12 SG pressure is decreasing in an uncontrolled manner.

• Stop feed flow to 12 SG.

SS

• Transition to 1E-2.

1E-2, FAULTED STEAM GENERATOR ISOLATION NOTE RO/

• Check MSIV and Bypass valve on 12 SG are closed.

If a RED or ORANGE path is received on the INTEGRITY LEAD

• Determine 11 SG is NOT faulted.

CRITICAL SAFETY FUNCTION TREE when the crew

• Determine 12 SG is faulted.

transitions to 1E-2, then the crew will transition to 1FR-

• Isolate 12 SG:

P.1 instead.

o Isolate main feedline.

o Isolate AFW flow.

CRITICAL TASK o Close steam supply valve to TD AFW pump Isolate the faulted STEAM GENERATOR before from 12 SG.

transition out of E-2, unless the transition is to FR-P.1, o Verify 12 SG PORV is closed.

in which case the task must be completed prior to o Verify SGB isolation valve closed.

checking if safety injection should be terminated per

• Check Secondary Radiation is normal.

step 6 of FR-P.1. SS

• Transition to 1E-1.

1FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION RO/

• Check RCS pressure greater than 550 psig.

LEAD

• Determine RCS Cold Leg Temperatures lowering.

• Verify SG PORVs & Steam dumps closed.

• Control feed flow to 11 SG.

• Verify MSIV and bypass valves closed.

• Close steam supply from 12 SG to TD AFW Pump.

• Isolate all FW to 12 SG.

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 1E-0 Attachment L: SI Alignment Verification (cont)

• Verify Safeguards Component Alignment:

LEAD

• Verify both trains of SI actuated:

o Both RHR pumps - RUNNING

-OR-o Both SI pumps - RUNNING

• "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:

• MSIVs and bypass valves - CLOSED

• Containment instrument air valves - CLOSED:

• Verify SI Flow:

• Verify RHR Flow

• Verify Containment Spray actuated and verify lineup.

• 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

• Verify All Condensate Pumps - STOPPED:

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 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 15. If Control Room personnel ask for status of Unit 2

• Place Steam Dump In "STM PRESS" Mode (cont) Cooling Water/Chilled Water lineup, then inform the

• Verify Unit 1 Cooling Water/Chilled Water Alignment:

Control Room that Unit 2 Cooling Water/Chilled Water o CFCU control switches - "SLOW".

valves are in there safeguards positions. o CFCU dampers - ALIGNED TO DOME

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

17. If Control Room personnel ask for status of Spent Fuel o CFCU cooling water supply and return valves -

Cooling, then inform the Control Room that Spent OPEN Fueling level and temperature are normal. 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.

18. Once the crew has transitioned to 1E-1, or completed step 6 of 1FR-P.1, 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 19 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 20 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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-263 or IC-8 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. 123 Air Compressor

_____ 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: 1482 ppm.

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

___ 7. Shift Reactivity Guidance placard: BA: 4.8 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. H 2 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 21 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, REV. 0

_____ Pink Status Control Tags in place:

___ 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-46098, 123 Air Compressor, in PULLOUT

_____ ERCS driven recorders are on-scale (RCS temperature scaled 550º F to 560º 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.

_____ Verify 121 IA Compressor is in PREFERRED and 122 IA Compressor is in PREFERRED.

_____ 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 50% power are in place as necessary.

_____ Procedure 1C51 marked up for PT-485 failure.

_____ 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 22 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 1C12.1, LETDOWN, CHARGING, AND SEAL WATER INJECTION -

UNIT 1 1C51.2, First Stage Pressure PT-485 - High 1C51.3, Power Range Nuclear Instrument N High 1E-0, REACTOR TRIP OR SAFETY INJECTION 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT 1E-2, FAULTED STEAM GENERATOR ISOLATION 1ES-0.1, REACTOR TRIP RECOVERY 1FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION C47012-0508, PRZR HI/LO PRESS C47013-0101, NIS POWER RANGE POS FLUX RATE CH ALERT.

C47013-0102, NIS POWER RANGE HI SETPOINT CH ALERT.

C47013-0103, NIS POWER RANGE OVERPOWER ROD WITHDRAWAL STOP.

C47013-0203, NIS POWER RANGE CHANNEL DEVIATION.

C47013-0305, AUCTIONEERED TAVG-TREF DEVIATION C47017-0301, ONE LOOP LO FLOW OR RCP BKR OPEN REACTOR TRIP C47018-0301, 11 SI PUMP LOCAL CONTROL SI AUTO START BLOCKED 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 FIGURE C1-5, PROGRAMMED MODERATOR TEMPERATURE FOR POWER SWING SWI O-28, NOTIFICATION OF OPERATIONS MANAGER & NRC RESIDENT INSPECTOR SWI O-50, REACTIVITY MANAGEMENT T.S. LCO 3.2.1 T.S. LCO 3.3.1 T.S. LCO 3.4.1 T.S. LCO 3.5.2 T.S. LCO 3.5.3 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 23 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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-46098, 123 Air Compressor.

_____ 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 24 of 28 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

1. PT-485, Turbine First Stage Pressure, is failed HIGH.

• T.S. 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 WR was initiated to repair PT-485.

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

• 123 Air Compressor is Out of Service.

• Instrument Air is separated from Station Air due to clam shelling in progress.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE

• Unit 1 was returned on-line two days ago. A 51% hold is in effect due to chemistry.

• 12 Charging Pump Suction Stabilizer PM is complete and ready for PMT. 13 Charging Pump desurger has already been checked by the out-plant operator.

OPERATIONAL PLANS FOR COMING SHIFT

• Maintain Rod Control in Manual and Steam Dump in Steam Pressure Mode.

• 1C51.2 actions are complete for the failed instrument with the exception of restoring Tavg to program temperature. Tref is currently pegged high.

• Restore RCS Average Coolant Temperature to program temperature.

• Swap charging pumps to 11 and 13 are running and 12 secured per per Section 5.4.1 of 1C12.1.

• Xenon is at equilibrium. Maintain 50% - 51% power for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Dilute 10 gallons 1-2 times per shift for temperature control.

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 25 of 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 26 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 27 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 28 of 28 PI-ILT-NRC-1403S, 2014 ILT NRC SIMULATOR EVALUATION #3, 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 Fred Collins Operations Instructor Lead Evaluator Nic Abney Operations Instructor Booth Driver Jeff Human Operations SRO Shift Supervisor Rick Martin Operations RO RO Mark Haren Operations RO LEAD 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 24 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-1404S SEG TITLE: 2014 ILT NRC SIMULATOR EVALUATION #4 REV. # 0 PROGRAM: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 2.0 HOUR Developed by: Shawn Sarrasin 1/25/2014 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:

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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. Alternate Containment Fan Coil Units and discharge dampers Learning per 1C19.2.

Objectives: 2. Diagnose and perform corrective actions for 1PT-468, Red Channel A Steam Generator Steam Pressure, failing high per 1C51.1.

3. Perform a load increase per 1C1.4.

4. Diagnose and respond to a Dropped Rod per 1C5 AOP4.

5. Diagnose and respond to a failure of the Main Turbine to automatically trip per 1E-0.

6. Diagnose and respond to a Station Blackout per 1ECA-0.0.

7. Diagnose and respond to the TD AFW Pump failing to automatically start per 1ECA-0.0.

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 LOOP (1.5%)

Information:

Important Components:

11 TD 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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1PT-468, Red Channel A Steam Generator Pressure Instrument, fails high.

2. Dropped Rod (Control Bank A Group 1 Rod B8).

After EOP Entry:

1. Reactor fails to automatically trip.

2. Main Turbine fails to automatically trip.

3. 11 TD AFW Pump fails to automatically start.

Abnormal Events:

1. SG Pressure Instrument Failure.

2. Dropped RCCA.

Major Transients:

1. Loss of All AC.

Critical Tasks:

1. E A: Manually trip the reactor from the control room before transition out of E-0.

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

3. ECA-0.0 - B: Establish and maintain 200 GPM AFW flow to the Steam Generators prior to Step 3 of ECA-0.0.

4. ECA-0.0 - H: Isolate RCP seal injection before a charging pump is started.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS

• Exposure: BOC

• 13 Charging Pump

• Power: 50%

• Boron (CB): 1480 ppm

• Temperature: 553°F

• Pressure: 2235 psig

• Xenon: Equilibrium

• Rods: D @ 175

• Generator: 265 MW SEQUENCE OF EVENTS:

Event 1: Alternate Containment Fan Coil Units and Discharge Dampers

• 11 and 13 CFCUs are initially in fast speed and aligned to SUP/GAP.

• 12 and 14 CFCUs are initially in slow speed and aligned to the DOME.

• The crew will perform section 5.6.4.A of 1C19.2.

• 11 and 13 CFCUs will then be in slow speed and aligned to DOME.

• 12 and 14 CFCUs will then be in fast speed and aligned to the SUP/GAP.

Event 2: Red Channel A Steam Generator Pressure Instrument fails HIGH

• FW Control System Trouble alarm will be received.

• 1PT-468, A Steam Generator Pressure, rises until pegged high.

• A Steam Generator PORV will open.

• The crew will place A SG PORV in manual and close it.

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

Event 3: Unit 1 Load Increase from 50% to 60% Power

• The crew briefed the load increase prior to taking the duty.

• Shift Management will direct the crew to raise power to 60% when the 50%

chemistry hold is lifted.

• The crew will increase load per 1C1.4.

Event 4: Control Bank A Group 1 Dropped Rod (B-8)

• Control Bank A Group 1 Rod B-8 will indicate zero steps.

• RCS Tavg will lower.

• NI Power will lower.

• A negative flux rate reactor trip will be received.

• The reactor will fail to automatically trip.

• The crew will diagnose a dropped rod and manually trip the reactor per 1C5 AOP4.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 Event 5: Main Turbine Fails to Automatically Trip

• The crew will enter 1E-0, Reactor Trip or Safety Injection.

• The Main Turbine will fail to automatically trip.

• The Lead will manually trip the turbine from the Control Room.

Events 6 & 7: Loss of All AC

• This event will occur after the Main Turbine is tripped.

• A loss of offsite power occurs.

• A lockout will occur on Bus 15 and Bus 16.

• The crew will transition to 1ECA-0.0, Loss of All Safeguards AC Power.

• 11 TD AFW Pump will have failed to automatically start after the reactor trip.

• The crew will manually start 11 TD AFW Pump from the Control Room.

• Since both safeguards buses are locked out, the crew will go to step 8.

• An out-plant operator will be directed to isolate RCP seals.

• Safeguards loads will be placed in pullout.

• Bus 15 and 16 will remain locked out for the remainder of the scenario.

• The crew will initiate depressurization of both SGs.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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-264 and place in RUN.

2. If IC-264 is NOT available:

a. Reset to IC-8.

b. Place the simulator in RUN.

c. Place ALL pressurizer heaters to ON.

d. Insert remote FW123 to OPEN.

e. Start 12 Condensate Pump using CS-46411.

f. Start 11 FWP using CS-46418.

g. Start 12 HDT Pump per 1C28.4.

h. Raise HDT Pump speed to stabilize HDT level.

i. Wait until heater drains have stabilized.

j. Insert remote MS118 to RESET.

k. Ensure Tavg and Tref are matched.

l. Place CS-46294, 13 CHG PUMP, in PULLOUT.

m. Insert Malfunction VC04C.

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 175 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 550 as the new Min EU value for Pen 1U9001A (point 1T0499A).

d. Enter 560 as the new Max EU value for Pen 1U9001A (point 1T0499A).

e. Enter 550 as the new Min EU value for Pen 1U9002A (point 1T0496A).

f. Enter 560 as the new Max EU value for Pen 1U9002A (point 1T0496A).

5. If available, run schedule file PI-ILT-NRC-1404S.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 available, run event file PI-ILT-NRC-1404S.evt as follows:

a. Select open file in the Event application.

b. Locate event file.

c. Open event file by double clicking it.

8. If event file is NOT available, then enter event codes as specified by the Simulator Event Summary.

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

10. 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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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 activities:

1) Alternate CFCUs and Discharge Dampers per C19.2 section 5.6.4.A.

(a) This is being performed so thermographs can be taken of the 12 and 14 CFCU breakers.

(b) Current CFCU lineup:

(1) 11 and 13 CFCUs are running in FAST to the DOME.

(2) 12 and 14 CFCUs are running in SLOW to the SUP/GAP.

(c) Shift CFCUs such that:

(1) 11 and 13 CFCUs are running in SLOW to the SUP/GAP.

(2) 12 and 14 CFCUs are running in FAST to the DOME.

(d) A copy of C19.2 is provided.

(e) The Lead RO will perform this activity.

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

2) Raise power to 60%.

(a) There is currently a power hold at 51% for chemistry control.

(b) The Duty Chemist is performing samples and will inform the Shift Manager when it is ok to raise power to 60%.

(c) Once power is at 60%, another hold for chemistry will be in effect.

(d) A marked up copy of 1C1.4 Section 5.1 is provided (blank copy of the page for setting up turbine controls).

(e) There are NO fuel conditioning requirements and NO turbine ramp limits.

(f) Raise Reactor Power to 60%:

(1) RATE: 0.5%/minute.

(2) Rods in MANUAL.

(3) Turbine in AUTO in LOAD mode.

(g) A reactivity plan was developed by the off going RO for the power increase from current power to 60%.

(h) Verify the reactivity plan developed by the off going reactor operator.

(i) Nuclear Engineering was NOT available to provide a reactivity prediction.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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 alternate 1C19.2, CONTAINMENT SYS VENTILATION UNIT 1 Containment Fan Coil Units and Discharge Dampers per

• Shift the following fan coil units to SLOW by placing section 5.6.4.A of 1C19.2 so that: LEAD the control switch in OFF for 15 seconds, then

a. 11 and 13 CFCUs are running in SLOW to the placing the control switch in SLOW:

DOME. o CS-46018, 11 CNTMT FAN COIL UNIT

b. 12 and 14 CFCUs are running in FAST to SUP/GAP. o CS-46019, 13 CNTMT FAN COIL UNIT

• Align the fan coil unit discharge dampers as desired:

o CS-46440, 11 FCU DISCH, to DOME.

o CS-46441, 12 FCU DISCH, to SUP.

o CS-46442, 13 FCU DISCH, to DOME.

o CS-46443, 14 FCU DISCH, to GAP.

• Verify the white fan coil unit damper improper lights remain NOT LIT:

o ML-44002-0101, 11 CNTMT FCU DISCH DMPRS IMPROPER o ML-44002-0102, 12 CNTMT FCU DISCH DMPRS IMPROPER o ML-44002-0103, 13 CNTMT FCU DISCH DMPRS IMPROPER o ML-44002-0104, 14 CNTMT FCU DISCH DMPRS IMPROPER

• Shift the following fan coil units to FAST by placing the control switch in OFF for at least one (1) second, then placing the control switch in FAST:

o CS-46020, 12 CNTMT FAN COIL UNIT o CS-46021, 14 CNTMT FAN COIL UNIT.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 4. When CFCUs and Discharge Dampers are alternated, C47011-0405, FW CONTROL SYSTEM TROUBLE and/or at the discretion of the lead evaluator, then enter:

• Verify steam generator level control operating properly Trigger 2, 1PT-468, Red Channel A SG Pressure, fails LEAD in automatic.

HIGH.

• Refer to 1C51, INSTRUMENT FAILURE GUIDE.

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

• Increase monitoring of steam generator level control.

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

• Contact I&C and System Engineer to determine cause

b. If contacted as the Operations Management, of failure.

acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station 1C51.1, 11 Steam Generator Pressure 1P-468 - High Manager, etc. as asked. RO

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

• Take manual control of 11 SG PORV and ensure crew that you will write a work order and assign an valve is CLOSED.

I&C Supervisor to investigate.

• Verify SG level control operating properly in automatic.

SS

• Enter T.S. LCO 3.3.2 Condition A - Reference Table

5. Plant Response: 3.3.2-1 immediately.

a. 1PT-468, A SG Pressure, rises until pegged high.

• Enter T.S. LCO 3.3.2 Condition D - Place 1P-468

b. A SG PORV will automatically open. channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in Mode 3 in 12

c. Annunciator 47011-0405, FW CONTROL SYSTEM hours and Mode 4 in 18 hrs.

TROUBLE, will be received.

• Call I&C to trip bistables.

d. SG level will maintain program level in auto.

• Check if TPM power is affected by the steam pressure channel failure.

• If TPM power is affected, then change TPM Power Source input from Calorimetric to NIS and notify the computer group.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 6. When the plant is stable and/or at the discretion of the 1C1.4, UNIT 1 POWER OPERATION lead evaluator, then:

• Place CS-46280, ROD BANK SELECTOR, in RO/SS

a. As the Shift Manager, inform the Control Room the MANUAL.

Unit 1 50% Power Hold for chemistry is lifted.

• Using the On Line Control screen:

Another Power Hold for chemistry will be in effect o Select LOAD.

when Unit 1 power reaches 60%. o Select 0.5% demand rate.

b. If contacted as the duty chemist, acknowledge Unit 1

• Verify the VPL control is not Red.

power will be raised from 50% to 60%.

• Raise the VPL to 101% using the Valve Limiter pop-up screen.

• Set the Target setting to the desired Load using On Line Control screen Target increase/decrease NOTE controls.

It is NOT intended to wait for the plant to reach 60%

• Initiate an alternate dilution of the RCS per 1C12.5.

power prior to proceeding to the next event. Once the

• When Tave shows an increase, then select the Go Lead Evaluator is satisfied with the reactivity control using the On Line Control screen.

manipulation, proceed to Event 4.

• Adjust the alternate dilution rate or perform alternate dilutions per 1C12.5 to maintain Tave and Tref with the desired +/-1.5°F band.

1C12.5, UNIT 1 BORON CONCENTRATION CONTROL RO/SS

• Verify the RMU integrator is reset.

• Set 1YIC-111, RX MU WTR TO BLENDER BATCH INTEGRATOR, to quantity desired.

• Place CS-46300, MAKE-UP MODE SELECTOR, to ALT DIL.

• Place CS-46454, BA BLENDER TO VCT INLT CV-31201, to CLOSE.

• If desired, then adjust 1HC-111, RX MU WTR TO BLENDER FLOW CONT, set point to desired flow rate or place in MANUAL adjusted for desired flow rate.

• Momentarily place CS-46457, BORIC ACID MAKE-UP CONTROL, to START, to initiate dilution.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3

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

• If additional alternate dilution is desired, then return to step 2.

• Verify CS-46454, BA BLENDER TO VCT INLT CV-31201, is selected to AUTO.

• Verify 1HC-111, RX MU WTR TO BLENDER FLOW CONT, is in AUTO set to 45%.

• Place CS-46300, MAKE-UP MODE SELECTOR, to AUTO.

• Momentarily place CS-46457, BORIC ACID MAKE-UP CONTROL, to START.

• Reset the RMU integrator.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 7. When the lead evaluator is satisfied with the reactivity 1C5 AOP4, DROPPED RCCA

& manipulation, enter:

• Confirm Rod Drop using diverse indications:

EVENT 5 Trigger 4, Dropped Rod B CBA GR1. RO

• Rod Position Indication and RCS Tavg Changes

a. Verify: OR AUTO Trigger 5, Auto Turbine Trip Failure, is

• Rod Position Indication and NIS Changes.

entered when the reactor is manually tripped.

• Manually trip the reactor.

b. Upon hearing the announcement of Reactor Trip, or

• Perform 1E-0.

when called as the Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, then open C47017-0404, FLUX RATE REACTOR TRIP and run schedule file E-0_Att-J.sch located in

• Perform 1E-0.

X:\\Trex_PI\Lightning\Schedule\EOPs. When the isolation is complete, inform the crew the MSRs are isolated. 1E-0, REACTOR TRIP OR SAFETY INJECTION

• Determine the reactor did NOT automatically trip.

RO/

8. Plant Response:

• Manually trip the reactor.

LEAD

a. CB-A Group1 Rod B-8 rod bottom indication.

• Manually trip the main turbine.

b. NIS power and RCS Tavg lowering.

• Verify both safeguards buses are energized.

c. Flux Rate Reactor Trip and Rod at Bottom Alarms.

• Determine SI is NOT actuated.

d. The reactor fails to automatically trip.

e. The reactor is capable of a manual trip.

CRITICAL TASKS

• Manually trip the reactor from the control room before transition out of E-0.

• Manually trip the main turbine before transition out of E-0.

EMERGENCY PLAN CLASSIFICATION ALERT - SA2.1 due to the reactor failing to automatically trip during the high flux rate condition and the crew successfully manually tripping the reactor.

However, this classification may NOT be used due to a higher classification being met in the next event.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTs 9. Ten (10) seconds after the Main Turbine is manually SS 1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER 6&7 tripped, verify:

• Check PRZR PORVs closed.

RO AUTO Trigger 6, LOSS OF ALL AC, is entered.

• Check Letdown isolation valves closed.

a. Approximately 15 seconds after the Loss of All AC, o CV-31255 announce the following: o CV-31226

1) Attention all plant personnel, Unit 2 Reactor Trip. o CV-31330 Attention all plant personnel, Unit 2 Reactor Trip.

• Recognize AFW flow is below 200 GPM.

b. If contacted as an out-plant operator to establish

• Manually start 11 TD AFW Pump.

communications with the CR to throttle AFW flow,

• Announce Unit 1 Reactor Trip then wait 2 minutes and report you are in the AFW

• Notify Shift Manager and SEC.

Pump room standing by to throttle AFW flow.

• Check cooling water header pressures are both Throttle AFW flow as necessary using the following greater than 25 PSIG.

remotes: LEAD

• Determine neither safeguards bus is available for

1) FW134 - 11 AFW Pump to 11 SG (MV-32238) sequencer loading due to both being LOCKED OUT.

2) FW135 - 11 AFW Pump to 12 SG (MV-32239)

• Proceed to step 8.

c. If directed to investigate Bus 15 and 16, after 2 minutes, report Bus 15 and Bus 16 have 50G current

• Dispatch personnel to locally close valves to isolate relays showing. As an Electrical Maintenance RCP seals.

Supervisor, report it will take at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to get

• Place the following equipment switches in PULLOUT.

one safeguards bus restored. o MD AFW Pump.

d. If contacted as an out-plant operator to isolate RCP o Groups A & B PRZR heaters (Off position).

seals, then enter: o RHR pumps.

Trigger 16, Isolate RCP Seals. o SI pumps.

1) When Trigger 16 is complete, report to the CR o CS pumps.

that Step 8 of 1ECA-0.0 is complete. o CFCUs (Off position).

e. If contacted as an out-plant operator to perform o CC pumps.

Attachment H, then acknowledge order. o CR Chillers and Fans.

f. When the crew reaches step 18 of 1ECA-0.0, inform o 121 and 122 Air Compressors.

the crew that Unit 2 operators will perform the

• Place safeguards bus voltage restoration switches to following: MANUAL:

1) Initiate monitoring of DC supply using ERCS o Bus 15

2) Dispatch personnel to open Foxboro instrument o Bus 16 rack doors

• Verify Bus 15 and Bus 16 source breakers are open.

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTs 3) Transfer MCC and Buses to Unit 2 LEAD

• Determine both Safeguards buses are LOCKED OUT.

6&7 4) Establish Battery Room Cooling.

• Proceed to step 13.

(cont)

• Close Condenser makeup isolation valve CV-31121.

10. Plant Response:

• Check condenser makeup flow is zero.

a. Loss of lighting in the Control Room.

• Manually close MSIVs.

b. Bus 15 and 16 voltages read zero.

• Check MS Bypasses, MFW, MFW bypasses, and SGB

c. Bus 15 and 16 Lockout Annunciators. valves are closed.

d. 11 TD AFW Pump fails to auto start. RO/

• Check if SGs are NOT faulted.

LEAD

• Check if SGs are NOT ruptured.

CRITICAL TASKS

• Check SG Narrow Range levels greater than 5%.

• Establish and maintain 200 GPM AFW flow to the

• Control AFW flow to maintain narrow range level Steam Generators prior to Step 3 of ECA-0.0.

between 5% and 50%.

• Isolate RCP seal injection before a charging pump is

• Dispatch operator to perform Attachment H, DC Bus started.

Load Shed.

EMERGENCY PLAN CLASSIFICATION

• Initiate monitoring of DC supply using ERCS.

GENERAL EMERGENCY -

• Dispatch personnel to open Foxboro instrument rack SG1.1 due to loss of offsite power to both safeguards doors.

buses 15 and 16;

• Power transferrable MCCs and buses from Unit 2.

AND SS

• Contact security to provide access control and block Failure of both Diesel Generators D1 and D2 to supply open all Battery Room doors, including fire doors power to safeguards buses 15 and 16; between Battery Rooms.

AND

• Arrange for fire watches at the Battery Rooms.

Restoration of Safeguards Bus 15 or 16 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is

• Check CST level is greater than 10,000 Gallons.

not likely.

• Depressurize Intact SGs to 300 PSIG.

• Check SG Narrow Range level greater than 5%.

• Manually dump steam using SG PORVs to maintain cooldown rate in RCS cold legs - LESS THAN 100°F.

11. Once the crew has initiated a SG depressurization to 300 psig 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 15 of 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SIMULATOR INPUT

SUMMARY

SIMULATOR EVENT

SUMMARY

Event ID Code Description 5 ZRPG439(1)==1 REACTOR TRIP 6 HWZTCT6427(1)==1 TURBINE TRIP 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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 SIMULATOR SETUP CHECKLIST Before Scenario

_____ Simulator Status:

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

___ 3. Alarm sound "ON" ___ 4. Steps 1 - 9 on page 6 complete

___ 5. Speed: REAL ___ 6. IC-264 or IC-8 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 Event File has been entered per Simulator Event 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. 13 Charging Pump

_____ 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: 1465 ppm.

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

___ 7. Shift Reactivity Guidance placard: BA: 4.8 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. H 2 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 17 of 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0

_____ Pink Status Control Tags in place:

___ 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-46294, 13 CHG PUMP, in PULLOUT

_____ ERCS driven recorders are on-scale (RCS temperature scaled 550º F to 560º 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 50% 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 18 of 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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, UNIT 1 POWER OPERATION 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL 1C19.2, CONTAINMENT SYSTEM VENTILATION UNIT 1 1C28.1 AOP3, AUXILIARY FEEDWATER SYSTEM OPERATION WHEN AC POWER IS LOST 1C5 AOP4, DROPPED RCCA 1C51.1, 11 Steam Generator Pressure 1P-468 - High 1E-0, REACTOR TRIP OR SAFETY INJECTION 1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER C47011-0405, FW CONTROL SYSTEM TROUBLE C47013-0407, ROD AT BOTTOM C47013-0507, COMPUTER ALARM ROD DEVIATION/SEQUENCING C47017-0404, FLUX RATE REACTOR TRIP C47019-0301, 11 CONTAINMENT SPRAY PUMP LOCAL CONTROL AUTO START BLOCKED 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 3.3.2 T.S. LCO 3.6.5 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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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-46293, 12 CHG PUMP

_____ 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 20 of 24 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

• 12 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 recirc valve is still open; waiting until 70 percent to close per step 5.5.12 and 5.5.13 of 1C28.2.

• Station Air is supplementing Instrument Air per Section 5.1.3 of C34, Station Air System.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE

• Unit 1 was returned on-line two days ago.

• A 51% hold is in effect due to chemistry.

OPERATIONAL PLANS FOR COMING SHIFT

• Xenon is at equilibrium.

• Per section 5.6.4.A of 1C19.2, alternate CFCUs and discharge dampers to the following in preparation of thermography on 12 and 14 CFCU breakers:

o 11 and 13 CFCUs running in SLOW to the DOME.

o 12 and 14 CFCUs running in FAST to SUP/GAP.

• Perform a load increase from 50% to 60% when Chemistry releases the hold.

• Dilute 10 gallons 1-2 times per shift for temperature control.

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 21 of 24 Reactivity Plan Load increase from 50% to 60%.

Prior to entering the simulator:

• Verify the reactivity plan completed by the off going reactor operator.

• Complete a Pre-Job Brief of 1C1.4 Section 5.1.

Current conditions are:

• 11 and 12 MFPs are running.

• 11 and 12 Condensate Pumps are running.

• Power level: 50% (263 MW)

• Xenon: Equilibrium

• Control Rod Position: Bank D @ 175 steps

• Boron Concentration: 1465 ppm

• Core Exposure: 1000 MWD/MTU Target: Turbine Load: 311 MW (60%)

Rate: 0.50% /minute Control Mode: LOAD control with Rod Control in Manual Boration/Dilution: 267 gallon dilution (batch)

Final Control Rod Position: Bank D @ 178 steps Reactivity Prediction:

Change in Power Defect: -100 pcm (Figure C1-7A)

Differential Boron Worth: -6.2 pcm/ppm (Figure C1-11A)

Differential Rod Worth: 3.8 pcm/step (Figure C1-4A)

Calculated RCS PPM change: -13 ppm (80 pcm ÷ -6.2 pcm/ppm)

Calculated Rod Step change: 5 steps (20 pcm ÷ 3.8 pcm/step)

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 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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 23 of 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, 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 SWO = Simulator Work Order SWO: B4D-040 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 24 of 24 PI-ILT-NRC-1404S, 2014 ILT NRC SIMULATOR EVALUATION #4, REV. 0 Comments: The simulator is modeled to turn on the Low Press annunciator if the AFWP Aux Lube Oil Pump loses power. However, per B28B for both AFW Pumps, A shaft-driven lube oil pump provides lubrication for the bearings during AFW pump operation. A motor-driven auxiliary oil pump is used to ensure a sufficient oil film for AFW pump starting is maintained during idle periods. The simulator modeling should be revised to have sufficient oil pressure, regardless of the power availability to the Aux LO Pump (i.e., have no alarm). Annunciators 47010-0505 and 47010-0507 were overridden to OFF for this scenario as a compensatory action until the simulator model is updated.

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 Nic Abney Operations Instructor Booth Driver Jeff Human Operations SRO Shift Supervisor Rick Martin Operations RO RO Mark Haren Operations RO LEAD 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 27 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-1405S SEG TITLE: 2014 ILT NRC SIMULATOR EVALUATION #5 REV. # 0 PROGRAM: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 2.0 HOUR Developed by: Shawn Sarrasin 1/26/2014 Instructor Date Reviewed by: Fredrick Collins 2/27/2014 Instructor Date (Simulator Scenario Development Checklist.)

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

Approved by:

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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. Transfer power on Bus 15 from 1RY to CT11 per 1C19.2.

Learning 2. Diagnose and perform corrective actions for an Individual Rod Objectives: Position Indicator failing low per 1C5 AOP4 and 1C5 AOP5.

3. Diagnose and perform corrective actions for a Red Channel RCS Thot Instrument failing high per 1C51.1.

4. Respond to a Loss of Bus Duct Cooling per 1C22.5 AOP1 and perform a rapid power reduction per 1C1.4 AOP1.

5. Diagnose and respond to a 12 Steam Generator Tube Rupture per 1E-0 and 1E-3.

6. Diagnose and respond to a failure of the SI to Chilled Water signal to actuate 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 SGTR (1.8%)

Information:

Important Components:

NONE Important Operator Actions with Task Number:

Operator fails to cooldown and depress RCS for SGTR before SG overfill (1.46%)

CRO 301 004 06 01 000 - Steam Generator Tube Rupture 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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Rod E-3 (SBA GR1) Position Indicator fails low.

2. 1TE-401, Red Channel RCS Thot Transmitter, fails high.

3. 11 and 12 Generator Bus Duct Cooler Blowers fail.

After EOP Entry:

1. Failure of SI to Chilled Water Signal to Actuate.

2. Both pressurizer spray valves fail CLOSED.

Abnormal Events:

1. RPI Failure.

2. RCS Thot Instrument Failure.

3. Loss of Bus Duct Cooling.

4. Rapid Power Reduction.

Major Transients:

1. 12 Steam Generator Tube Rupture.

Critical Tasks:

1. E A: Isolate feedwater flow into and steam flow from the ruptured Steam Generator before a transition to ECA-3.1 occurs.

2. E B: Establish/maintain an RCS temperature so that transition from E-3 does not occur because of the inability to maintain required subcooling or such that an extreme or severe challenge to the Subcriticality and/or the Integrity CSF occurs.

3. E C: Depressurize RCS to meet SI termination criteria prior to overfilling the ruptured Steam Generator.

4. E D: Terminate SI prior to overfilling the ruptured Steam Generator.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS

• Exposure: MOC

• 1PT-485, Turbine First Stage Pressure, is failed low.

• Power: 100%

• 11 Safety Injection Pump

• Boron (CB): 853 ppm

• Temperature: 560°F

• Pressure: 2235 psig

• Xenon: Equilibrium

• Rods: D @ 218

• Generator: 581 MW SEQUENCE OF EVENTS:

Event 1: Transfer Power on Bus 15 from CT11 to 1RY

• Bus 15 is initially receiving power from CT11.

• A designated operator is stationed to monitor Bus Phase Currents.

• The crew will transfer Bus 15 to 1RY transformer per 1C20.5.

Event 2: Shutdown Bank Group 1 Rod E-3 Position Indication fails LOW

• Rod E-3 rod bottom light will turn on.

• Rod E-3 position indication will indicate 0.

• RCS Tavg and NI Power will remain stable.

• The crew will enter 1C5 AOP4 and 1C5 AOP5.

• The SS will enter T.S. LCO 3.1.7 Condition A.

Event 3: Red Channel RCS Thot Instrument Fails HIGH

• Rods will NOT step in because rods are still in manual due to 1st Stage Pressure Instrument failed low.

• Pressurizer level control will be controlled manually.

• Red Channel Tavg will be defeated.

• The crew will restore pressurizer level control to automatic.

• The SS will enter T.S LCO 3.3.1 Conditions A and E and T.S. LCO 3.3.2 Conditions A and D.

Events 4 & 5: Loss of Bus Duct Cooling and Rapid Power Reduction

• 11 Bus Duct Cooler Blower will trip offline.

• 12 Bus Duct Cooler Blower will fail to start.

• Bus Duct temperature will rise above 92°C.

• The crew will respond per 1C22.5 AOP1.

• The crew will perform a Rapid Power Reduction per 1C1.4 AOP1.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 Events 6 & 7: 12 Steam Generator Tube Rupture

• RCS pressure will slowly lower.

• Pressurizer level will slowly lower.

• The crew will:

o Trip the reactor and initiate Safety Injection per 1E-0.

o Isolate 12 Steam Generator per 1E-3.

o Manually align Safeguards Chilled Water components per 1E-0, Attachment L.

o Cooldown the RCS per 1E-3.

o Depressurize the RCS to meet SI termination per 1E-3.

o Terminate SI.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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-265 and place in RUN.

2. If IC-265 is NOT available:

a. Reset to IC-10.

b. Place the simulator in RUN.

c. Place CS-46178, 11 SI PUMP, in PULLOUT.

d. Place CS-46280, ROD BANK SELECTOR, in MANUAL.

e. Place CS-46338, STEAM DUMP MODE, in STM PRESS.

f. Insert System Override RX226 to 0 (1st Stage Pressure Fails Low).

g. Insert Remote RP181 (B/S PC-485A) to TRIP.

h. Transfer Bus 15 power to CT11 as follows:

i. Place CS-46909, BKR 15-7 MAN/AUTO, to MANUAL.

ii. Place CS-46951, BKR 15-3 MAN/AUTO, to MANUAL.

iii. Place CS-46906, BUS 15 SYNCH SEL SW, to CT11.

iv. Close BKR 15-7 using CS-46955.

v. Trip BKR 15-3 using CS-46953.

vi. Place CS-46909, BKR 15-7 MAN/AUTO, to AUTO.

vii. Place CS-46951, BKR 15-3 MAN/AUTO, to AUTO.

viii. Place CS-46906, BUS 15 SYNCH SEL SW, to OFF.

3. If available, run schedule file PI-ILT-NRC-1405S.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.

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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) Transfer power on Bus 15 from CT11 to 1RY per section 5.16 of 1C20.5.

(a) Maintenance on Bus 15 1RY Source Breaker is complete and has been returned to service.

(b) A designated operator is stationed at the G-Panel to monitor Bus Phase Currents and perform actions of Bus 15 Sequencer Channel Alert and Bus 16 Sequencer Channel Alert Alarm Response Procedures.

(c) The designated operator is NOT one of the examinees.

(d) The Lead RO will conduct the activity to transfer power on Bus 15 from CT11 to 1RY.

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

(f) After Bus 15 is transferred to 1RY, then secure the designated operator at the G-Panel.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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 transfer 1C20.5, UNIT 1 - 4.16KV SYSTEM power on Bus 15 from 1RY to CT11 per section 5.16 of LEAD

• Place CS-46951, BKR 15-3 MAN/AUTO CLOSURE 1C20.5. SEL SW, in MANUAL.

a. If contacted as the out-plant operator to check Bus

• Place CS-46906, BUS 15 SYNCHROSCOPE SEL 15 Room clear, then wait two minutes and report SW, in 1RY.

back that Bus 15 Room is clear of personnel.

• Check 115 - 130 volts on Bus Incoming volt meter.

b. If contacted as the out-plant operator to check

• Check 115 - 130 volts on Bus Running volt meter.

closing springs on BKR 15-3, then wait two minutes

• Check the difference between incoming and running is and report back the closing springs are charged on less than 8 volts.

BKR 15-3.

• Check Synchroscope is less than or approximately 20° from the twelve oclock position.

• Check the two white synchronizing lights are NOT LIT.

• Place CS-46953, BKR 15-3 BUS 15 SOURCE FROM 1RY XFMR, in CLOSE.

• Place CS46955, BKR 15-7 BUS 15 SOURCE FROM BUS CT11, in TRIP.

• Check Bus 15 voltage is approximately 4.16kv.

• Check 44021 Bus 15 light LIT.

• Place CS-46906, BUS 15 SYNCHROSCOPE SEL SW, in OFF.

• Place CS-46951, BKR 15-3 MAN/AUTO CLOSURE SEL SW, in AUTO.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 4. At the discretion of the lead evaluator, enter: 1C5 AOP4, DROPPED RCCA Trigger 2, Rod E3 IRPI Failure.

• Confirm rod drop using diverse indications:

RO

a. If contacted as the Operations Management, o Rod Position Indication and RCS Tavg changes acknowledge the report of the failure, and agree to OR make other notifications to the NRC, Duty Station o Rod Position Indication and NIS Changes Manager, etc. as asked.

• Determine a Rod Drop did NOT occur.

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

• Go to 1C5 AOP5.

crew that you will write a work order and assign an I&C Supervisor to investigate.

1C5 AOP5, MISALIGNED ROD, STUCK ROD, AND/OR

c. If contacted as Nuclear Engineer, acknowledge order RPI FAILURE OR DRIFT to perform applicable steps of SP 1319.

SS

• Determine symptoms are indicative of a failed RPI.

5. Plant Response:

• Declare rod D4 inoperable.

a. Rod E3 rod bottom light

• Initiate a work order.

b. Rod E3 rod position at 0 steps

• Enter T.S. LCO 3.1.7 Condition A.

c. NO change in NIS. o Verify position of rod once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

d. NO change in RCS Tavg.

e. The following annunciators will come in:

1) 47013-0407, ROD AT BOTTOM.

2) 47013-0507, COMPUTER ALARM ROD DEVIATION/SEQUENCING.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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 IRPI failure, and/or C47012-0104, 0304, 0404, 0504, 0507, & 0604, at the discretion of the lead evaluator, then enter: PANEL C ALARM RESPONSE PROCEDURES Trigger 3, 1T-401, Red Channel RCS Thot, fails HIGH. RO

• Check RCS Tavg and deviations.

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

• Check RCS T and deviations.

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

• Verify Rod Control is in MANUAL.

b. If contacted as the Operations Management,

• Check all pressurizer level channels.

acknowledge the report of the failure, and agree to

• Shift charging pump control to MANUAL and adjust make other notifications to the NRC, Duty Station speed as necessary.

Manager, etc. as asked.

• Verify steam dumps are NOT open.

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

• Refer to 1C51, INSTRUMENT FAILURE GUIDE.

crew that you will write a work order and assign an

• Verify steam flow/feed flow balance.

I&C Supervisor to investigate.

7. Plant Response: 1C51.1, Tavg Loop 1B 1T-401 - High

a. Red Channel RCS Tavg pegs high. RO

• Determine Rod Control is already in manual.

b. Red Channel T pegs high.

• Place charging pump speed control in MANUAL AND

c. 11 Charging Pump speed will rise. maintain pressurizer level.

d. Pressurizer level will slowly rise.

• Select Red channel on the Tavg defeat switch and pull

e. The following annunciators will come in: out.

1) 47012-0104, RCS HI TAVG.

• Return charging pump speed control to AUTO.

2) 47012-0304, RCS TAVG DEVIATION.

• Rod Control and Steam Dump Control should NOT be

3) 47012-0404, OVERPOWER T CH ALERT. placed in AUTO due to the 1st Stage Pressure

4) 47012-0504, OVERTEMP T CH ALERT. Instrument failure.

5) 47012-0507, PRZR LVL DEVIATION. SS

• Enter T.S. LCO 3.3.1 Condition A - Ref Table 3.3.1-1.

6) 47012-0604, RCS DT DEVIATION.

• Enter T.S. LCO 3.3.1 Condition E - Place 1T-401

7) 47013-0105, OPT ROD STOP TURBINE channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in Mode 3 in 12 hr.

RUNBACK CHANNEL ALERT.

• Enter T.S. LCO 3.3.2 Condition A - Ref Table 3.3.2-1.

8) 47013-0205, OTT ROD STOP TURBINE

• Enter T.S. LCO 3.3.2 Condition D - Place 1T-401 RUNBACK CHANNEL ALERT. channel in trip within 6 hrs or be in Mode 3 in 12 hrs AND in Mode 5 in 18 hrs.

• Enter TLCO 3.3.3 Condition A - Place channel in trip.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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 C47007-0301 & 0302, BUS DUCT COOLING SYSTEM HI lead evaluator, then enter: TEMP AND BLOWERS NOT RUNNING LEAD Trigger 4, Loss of Bus Duct Cooling.

• Dispatch an operator to the bus duct coolers to

a. If contacted as the out-plant operator to investigate, provide an assessment of the problem.

wait 2 minutes and report the following:

• Monitor 1T2118A, 11/12 GEN BUS DUCT

b. Both Bus Duct Cooler Blowers are NOT running. CONDUCTOR TEMP, on ERCS.

c. The following alarms are in locally:

• Refer to C22.5 AOP1.

1) Bus Duct Air Hi Temp.

2) Bus Duct Conductor Hi Temp. C22.5 AOP1, LOSS OF GENERATOR BUS DUCT

d. If contacted as the out-plant operator to perform COOLING actions of C22.5 AOP1, then report the following as

• Dispatch an operator to the bus duct coolers to LEAD applicable: provide an assessment of the problem.

1) Cooling water flow to both Bus Duct Coolers are

• Direct out-plant operator to perform the following:

normal and cooling water valve lineups are o Note any alarms on the Bus Duct Cooler proper. Blower Control Panel.

2) Both Bus Duct Cooler Blowers are NOT running o Verify cooling water flow.

and attempts to start either blower are NOT o Attempt to start standby blower.

successful. o Verify discharge dampers for the inservice

3) The power supply breakers to both Bus Duct blower are OPEN.

Cooler Blowers are CLOSED. o Verify power supply breakers to the Bus Duct Cooler Blowers are CLOSED.

9. Plant Response: o Inspect dampers.

a. Bus Duct temperatures will rise.

• When 1T2118A exceeds 92°C, then reduce power per

b. The following annunciators will come in: 1C1.4 AOP1 to reduce generator output to less than

1) 47007-0301, BUS DUCT COOLING SYSTEM HI 9,000 amps.

TEMP.

• During load reduction, reduce generator excitation

2) 47007-0302, BUS DUCT COOLING BLOWERS using CS-46377, GEN VOLT REG ADJ.

NOT RUNNING.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 5 10. Rapid Load Reduction: 1C1.4 AOP1, RAPID POWER REDUCTION UNIT 1

a. If contacted as the TSO, acknowledge that Unit1 is

• Determine the predicted Boron addition and final RO/SS reducing power due to loss of bus duct cooling. Control Rod Position by obtaining values from the

b. If contacted as Unit 2 Control Room Operators to appropriate contingency reactivity plan.

monitor Unit 1 Heater Drain Tank alarms (Panel F),

• Borate the RCS as necessary to maintain control rods then acknowledge request and inform Unit 1 above the insertion limit and control delta I within Operators that an extra operator will monitor Panel F. limits.

• Control Rods in manual during the load reduction.

• Place pressurizer heaters to ON.

• Using the On Line Control screen, select the Control NOTE Mode pop-up screen.

It is NOT intended to wait for the plant to reach 55%

• Select the desired control mode (VPC, FSP, or power prior to proceeding to the next event. Once the LOAD).

Lead Evaluator is satisfied with the reactivity

• Using the On Line Control screen, select the manipulation, proceed to Event 6. Demand Rate pop-up screen.

• Select the desired rate of load change.

• Set the desired Target setting using the On Line Control screen.

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

1C12.5, UNIT 1 BORON CONCENTRATION CONTROL RO/SS

• Verify the Boric Acid integrator is reset.

• 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.

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

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SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 5

• When the desired quantity of boric acid has been (cont) 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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

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

• Manually trip the reactor or verify Reactor Trip.

RO/

Trigger 6, 12 Steam Generator Tube Rupture.

• Verify Turbine Trip.

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 or already actuated.

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 if it did not already actuate.

isolated.

• Perform Attachment L (see pages 17 & 18).

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 Verify AFW pumps discharge pressure Exhausters are all secured. greater than 1000 psig.

c. If Control Room personnel ask if Unit 2 personnel are o Control feed flow to maintain 11 SG Narrow available to perform Attachment L, then inform the Range between 5% and 50%.

Control Room that Unit 2 personnel are NOT

• Check RCS Temperatures trending to 547°F.

available for performing Attachment L.

• Check PRZR PORVs and Spray valves closed.

d. If contacted as RP or Duty Chemist to sample for primary-to-secondary leakage, then wait 2 minutes

• Determine RCPs should NOT be stopped due to RCS and report cation column frisks indicate activity is pressure greater than 1250 psig.

high on 12 SG and reading background on 11 SG.

• Determine SGs are NOT faulted.

SS

• Determine a SG Tube is ruptured.

12. Plant Response:

• Go to 1E-3.

a. RCS pressure lowers.

b. 11 SG level rises.

c. Secondary radiation rises.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1E-3, STEAM GENERATOR TUBE RUPTURE 6&7

• Determine RCPs should NOT be stopped due to RCS (cont) RO/SS EMERGENCY PLAN CLASSIFICATION pressure greater than 1250 psig.

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

• Identify 12 Steam Generator as ruptured.

Barrier due to the 12 Steam Generator Tube Rupture.

• Isolate flow from 12 SG:

o Verify 12 SG PORV at 75%.

o Check 12 SG PORV closed.

o Close steam supply valve from 12 SG to TD AFWP.

o Verify blowdown isolation valves closed on 12 CRITICAL TASKS SG.

1. Isolate feedwater flow into and steam flow from the o Close 12 SG MSIV.

ruptured Steam Generator before a transition to

• Stop feed flow to 12 SG after narrow range level is ECA-3.1 occurs. greater than 5%.

2. Establish/maintain an RCS temperature so that

• Reset SI transition from E-3 does not occur because of the

• Check 12 SG pressure greater than 210 psig.

inability to maintain required subcooling or such

• Initiate RCS Cooldown:

that an extreme or severe challenge to the o Determine required core exit temperature.

Subcriticality and/or the Integrity CSF occurs. o Check one condensate pump running.

o Establish steam dump to condenser o Stop RCS cooldown.

o Maintain CETC less than required temperature.

• Control feed flow to 11 SG to maintain narrow range level between 5% and 50%.

• Check PRZR PORV Block valves open.

• Check PRZR PORVs closed.

• Reset SI and Containment Isolation.

• Verify IA to Containment is established.

• Stop RHR pumps because RCS pressure is greater than 250 psig.

• Align charging pump suction to RWST.

• Establish maximum charging flow.

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

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

• Verify CETC less than required temperature.

6&7

• Check 12 SG pressure is stable or increasing.

(cont) RO/SS CRITICAL TASKS

• Check RCS subcooling greater than 40°F.

3. Depressurize RCS to meet SI termination criteria

• Depressurize RCS to minimize Break Flow and Refill prior to overfilling the ruptured Steam Generator. PRZR.

4. Terminate SI prior to overfilling the ruptured Steam

• Use one pressurizer spray to depressurize RCS until Generator. ANY of the following conditions satisfied:

o Both of the following:

RCS pressure less than 12 SG pressure.

PRZR level greater than 7%.

o PRZR level greater than 75%.

o RCS subcooling less than 20°F.

• Check RCS pressure increasing.

• Check if SI flow should be terminated.

• Stop 12 SI pump (11 SI pump is OOS).

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 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1E-0 Attachment L: SI Alignment Verification 6&7 13. If contacted as the out-plant operator to locally close

• Verify Safeguards Component Alignment:

(cont) LEAD Safeguards Chilled Water Cross Tie, acknowledge order

• Verify both trains of SI actuated:

to close the valve. Wait 2 minutes, enter: o Both RHR pumps - RUNNING Trigger 7 to CLOSE the CW Cross Tie Valves. -OR-

a. Report completion to the Control Room. o Both SI pumps - RUNNING o 11 SI Pump is OOS and should NOT be started.

14. 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 * "CONTAINMENT ISOLATION" lights - LIT FOR valves are in there: PLANT CONDITIONS

a. Non safeguards position if the crew has NOT

• Check Category 1 Vent Zone Boundary:

re-aligned the cooling water/chilled water lineup on

• Close MV-32115, 122 SFP HX INLT HDR MV B Unit 2.

• Check Cooling Water Header Pressures - BOTH

b. Safeguards position if the crew has re-aligned the GREATER THAN 65 PSIG cooling water/chilled water lineup on Unit 2.

• Verify Plant Announcements Complete:

15. If Control Room personnel ask for status of Battery Room Temperatures, then inform the Control Room that

• Check If Main Steamlines Are Isolated:

Battery Room temperatures are less than 84°F.

• Determine MSIVs, Bypass Valves, and Containment

16. If Control Room personnel ask for status of Spent Fuel Instrument Air Valves do NOT need to be closed.

Cooling, then inform the Control Room that Spent

• Verify SI Flow:

Fueling level and temperature are normal.

• Verify RHR Flow

• Determine Containment Spray is NOT required.

• 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 18 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 SCENARIO TIME-LINE:

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

• Verify All Condensate Pumps - STOPPED:

6&7

• Determine Steam Dump already in "STM PRESS" (cont) LEAD Mode

• Verify Unit 1 Cooling Water/Chilled Water Alignment:

NOTE o CFCU control switches - "SLOW".

The operator will have to perform the following to align o CFCU dampers - ALIGNED TO DOME safeguards chilled water for SI Alignment: o Unit 1 cooling water/chilled water valves closed o Unit 1 CRDM shroud cooling supply and return

• Place CS-46018, 11 CFCU, to SLOW. valves - CLOSED

• Place CS-46019, 13 CFCU, to SLOW. o CFCU cooling water supply and return valves -

• Place CS-46080, Train A Unit 1 CLG WTR/CHILLED OPEN WATER ISOL VALVES, in ISOLATE. o CFCU chilled water supply and return valves -

• Place CS-46081, Train B Unit 1 CLG WTR/CHILLED CLOSED WATER ISOL VALVES, in ISOLATE.

• Verify 11 Safeguards Screenhouse Ventilation lineup.

• Place CS-46772, Train A Unit 2 CLG WTR/CHILLED

• Verify Control Room Ventilation Alignment:

WATER ISOL VALVES, in ISOLATE. o Chillers and fans - RUNNING

• Place CS-46773, Train B Unit 2 CLG WTR/CHILLED o Control room chiller suction/discharge tie closed -

WATER ISOL VALVES, in ISOLATE. STATUS LIGHT LIT

• Place CS-46068, 121 CONT RM CHILLER & PUMP, in

• Verify Unit 2 Cooling/Chilled Water Alignment START.

• Verify 21 Safeguards Screenhouse Ventilation lineup.

• Place CS-46076, 122 CONT RM CHILLER & PUMP, in

• Verify 11 and 12 Battery Charger Operation is normal.

START.

• Verify Battery Room temps less than 84°F.

• Determine 44071-0101, CR CHILLER XTIE LIGHT, is

• Check status of Spent Fuel Cooling.

NOT LIT; therefore valve is open.

• Check Status Of Notifications

• Notify SS Of Any Discrepancies.

17. Once the crew has stopped 12 SI Pump 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 19 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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 20 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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-265 or IC-10 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. 11 Safety Injection Pump

_____ 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: 853 ppm.

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

___ 7. Shift Reactivity Guidance placard: BA: 2.7 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. H 2 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 21 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0

___ 1. CS-46540, 22 CC WTR PUMP ___ 5. CS-46185, 12 RHR PUMP

___ 2. CS-46572, CC TO SFP MV-32117 ___ 6. CS-46179, 12 SI PUMP

___ 3. CS-46930, D2 DIESEL GENERATOR ___ 7. CS-46037, 12 CC WTR PUMP

___ 4. CS-46425, 12 MDAFWP ___ 8. CS-46523, 22 CLG WTR PUMP

_____ Yellow Caution Tags in place:

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

___ 2. CS-46178, 11 SI PUMP, in PULLOUT

_____ 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.

_____ Procedure 1C51 marked up for PT-485 failure.

_____ 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 22 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL 1C20.5, UNIT 1 - 4.16KV SYSTEM 1C51.1, Tavg Loop 1B 1T-401 - High st 1C51.2, Turbine 1 Stage Pressure 1P-485 - Low 1C5 AOP4, DROPPED RCCA 1C5 AOP5, MISALIGNED ROD, STUCK ROD, AND/OR RPI FAILURE OR DRIFT 1E-0, REACTOR TRIP OR SAFETY INJECTION 1E-3, STEAM GENERATOR TUBE RUPTURE C22.5 AOP1, LOSS OF GENERATOR BUS DUCT COOLING C47003-0503, 11 HEATER DRAIN TANK HI LVL C47007-0301, BUS DUCT COOLING SYSTEM HI TEMP C47007-0302, BUS DUCT COOLING BLOWERS NOT RUNNING C47012-0104, RCS HI TAVG C47012-0304, RCS TAVG DEVIATION C47012-0404, OVERPOWER T CH ALERT C47012-0504, OVERTEMP T CH ALERT C47012-0507, PRZR LVL DEVIATION C47012-0604, RCS DT DEVIATION C47013-0105, OPT ROD STOP TURBINE RUNBACK CH ALERT C47013-0205, OTT ROD STOP TURBINE RUNBACK CH ALERT C47013-0407, ROD AT BOTTOM C47013-0507, COMPUTER ALARM ROD DEVIATION/SEQUENCING 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 - MOC SWI O-28, NOTIFICATION OF OPERATIONS MANAGER & NRC RESIDENT INSPECTOR SWI O-50, REACTIVITY MANAGEMENT T.S. LCO 3.1.7 T.S. LCO 3.3.1 T.S. LCO 3.3.2 TLCO 3.3.3 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 23 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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-46930, D2 DIESEL GENERATOR

___ 2. CS-46425, 12 MDAFWP

___ 3. CS-46185, 12 RHR PUMP

___ 4. CS-46179, 12 SI PUMP

___ 5. CS-46037, 12 CC WTR PUMP

___ 6. CS-46523, 22 CLG WTR PUMP

_____ Magnetic placards removed:

___ 1. NONE

_____ Remove Yellow Caution Tags from the following equipment:

___ 1. CS-46178, 11 SI PUMP

_____ 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 24 of 27 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

1. 11 SI PUMP is OOS for corrective maintenance.

• T.S. 3.5.2 Condition A was entered with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> remaining.

2. PT-485, Turbine First Stage Pressure, is failed LOW.

• T.S. 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 WR was initiated to repair PT-485.

• B/S 1PC-485A is tripped.

PROTECTED EQUIPMENT D2 DIESEL GENERATOR 12 CC PUMP 12 MDAFWP 22 CLG WATER PUMP 12 RHR PUMP 22 CC PUMP 12 SI 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.

• Bus 15 and 16 are powered from CT11. A designated operator is stationed at the G-Panel to monitor Bus Phase Currents and perform actions of Bus 15 Sequencer Channel Alert and Bus 16 Sequencer Channel Alert Alarm Response Procedures.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE BKR 15-3, BUS 15 1RY SOURCE BREAKER, RTS OPERATIONAL PLANS FOR COMING SHIFT

• Maintain Rod Control in Manual and Steam Dump in Steam Pressure Mode.

• Xenon is at equilibrium. Maintain 100% power.

• Transfer power on Bus 15 to 1RY per Step 5.11 of 1C20.5.

• Dilute 10 gallons 1-2 times per shift for temperature control.

NEW PROCEDURES / INSTRUCTIONS 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 25 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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 26 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, 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: 01422319 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 27 of 27 PI-ILT-NRC-1405S, 2014 ILT NRC SIMULATOR EVALUATION #5, REV. 0 Comments: CS-46955, BKR 15-7, indication is erratic. In the simulator, BKR 15-7 is normally open. When CS-46955 is taken to close, BKR 15-7 closes, the red lamp illuminates, and the green lamp extinguishes. All as expected. When CS-46955 is taken to TRIP, the red light should extinguish, and the green light should light, indicating BKR 15-7 is open (tripped). The red lamp does extinguish as expected; but the green light sometimes either fails to light or it flickers on and off. If the switch is wiggled slightly, the green light usually lights, but not always.

This improper indication shows up in the TAM log, indicating a possible problem with the switch. SMAR-01422319 was initiated to investigate and repair/replace the control switch.

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.