Text

Proposed Operating Test - Dynamic Simulator Scenarios
	ML20252A251
Person / Time
Site:	Prairie Island
Issue date:	08/27/2020
From:	; Nuclear Management Co
To:	; NRC/RGN-III/DRS/OLB
	Callaway G
Shared Package
ML19127A304	List: L-PI-20-028, 75 Day Letter; ML20245E566; ML20245E574; ML20245E576; ML20245E579; ML20252A248; ML20252A251; ML20252A254;
References
	Download: ML20252A251 (88)
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Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.:

1 Op-Test No.: PI-ILT-NRC-2001S Examiners:

Gary Calloway Operators: Shift Supervisor (SS)

Joe DeMarshall Balance of Plant (LRO)

Dave Lanyi At the Controls (RO)

Initial Conditions:

Reactor Power:

1x10-8 AMPS Equipment OOS:

NONE Boron Concentration:

1575 PPM RCS temperature:

549°F Other:

B/U PRZR heaters are ON RCS pressure:

2235 PSIG Two 40 GPM orifices are in service Xenon:

Free prior to S/U Rods:

CBD @ 142 STEPS Main Generator:

0 MW Turnover:

Secure the 11 TD AFW Pump Raise reactor power to the point of adding heat (POAH)

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

SECURE 11 TD AUXILIARY FEEDWATER PUMP 2

R (ATC)

N (SRO)

RAISE POWER TO THE POAH 3

C (ATC) 12 CHARGING PUMP TRIP 4

C (BOP)

TS (SRO) 11 TD AFWP ACCUMULATOR LOW AIR PRESSURE 5

TS (SRO) 11 CTMT VACUUM BREAKER FAILS CLOSED 6

M (ALL)

FAULTED 12 SG TO CONTAINMENT 7

C (ATC, SRO) 12 MD AFW PUMP FAILS TO AUTO START 8

C (BOP, SRO)

SI TO FEEDWATER/CONDENSATE RELAY FAILURE (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-2002S Examiners:

Gary Calloway Operators: Shift Supervisor (SS)

Joe DeMarshall Balance of Plant (LRO)

Dave Lanyi At the Controls (RO)

Initial Conditions:

Reactor Power:

100%

Equipment OOS:

11 TD AFW Pump Boron Concentration:

102 PPM RCS temperature:

560°F Other:

RCS pressure:

2235 PSIG Xenon:

Equilibrium Rods:

CBD @ 218 STEPS Main Generator:

582 MW Turnover:

Swap running EH Oil Pumps Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

SWAP RUNNING EH OIL PUMPS 2

I (ATC)

TS (SRO)

CONTROLLING PRZR PRESS CH FAILS LOW 3

TS (SRO)

D1 LOCAL ALARM 4

C (BOP)

TURBINE EH VALVE MALFUNCTION 5

R (ATC)

N (SRO)

RAPID DOWNPOWER TO 50%

6 M (ALL)

LOSS OF ALL AC 7

C (BOP)

TURBINE FAILS TO AUTO TRIP 8

C (BOP, SRO)

D2 FAILS TO AUTO START 9

C (ATC, SRO) 12 MD 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.:

3 Op-Test No.: PI-ILT-NRC-2003S Examiners:

Gary Calloway Operators: Shift Supervisor (SS)

Joe DeMarshall Balance of Plant (LRO)

Dave Lanyi At the Controls (RO)

Initial Conditions:

Reactor Power:

60%

Equipment OOS:

11 SI Pump Boron Concentration:

230 PPM RCS temperature:

554°F Other:

RCS pressure:

2235 PSIG Xenon:

Equilibrium Rods:

CBD @ 178 STEPS Main Generator:

338 MW Turnover:

Swap running RMU pumps Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

SWAP RMU PUMPS 2

I (ATC)

TS (SRO) 1ST STAGE PRESSURE INSTRUMENT FAILS LOW 3

R (ATC)

N (SRO)

RESTORE TAVG TO TREF 4

I (ATC, BOP)

TS (SRO)

PRZR LEVEL INTERLOCK CHANNEL FAILS LOW 5

M (ALL) 11 STEAM GENERATOR TUBE RUPTURE 6

C (BOP, SRO) 11 & 12 RHR PUMPS FAIL TO START AUTOMATICALLY 7

C (BOP, SRO)

SI TO COOLING WATER RELAY SIGNAL FAILURE (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Rev. 0 (12/14/2018) Page 1 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.

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG #

PI-ILT-NRC-2001S SEG TITLE:

2020 ILT NRC SIMULATOR EVALUATION #1 REV. #

0 PROGRAM:

LICENSE REQUALIFICATION TRAINING FL-ILT COURSE:

INITIAL LICENSE OPERATOR TRAINING FL-ILT TOTAL TIME: 1.5 HOURS Developed by:

Fredrick Collins Instructor Date Reviewed by:

Justin Hasner Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Fredrick Collins Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Evaluation Objectives:

Evaluate the crews ability to:

1.

Secure 11 TDAFW Pump IAW 1C28.1.

2.

Raise Reactor Power to the POAH IAW 1C1.2-M2.

Evaluate the crews ability to diagnose and respond to:

3.

12 Charging Pump Trip IAW C47015.

4.

11 TDAFW Pump Accumulator Low Air Pressure IAW C47010.

5.

11 CTMT Vacuum Breaker failing closed IAW C47021.

6.

12 Steam Generator Faulted to Containment IAW 1E-2.

7.

12 MDAFW Pump Fails to Auto Start on SI IAW 1E-0.

8.

SI to Feedwater/Condensate Relay Failure IAW 1E-0 Att. L.

Training Resources:

1.

Full Scope Simulator

2.

Operations Management Representative

3.

Evaluation Team

4.

Booth Operator (Backup Communicator)

5.

Primary Communicator Related PRA Information:

Initiating Event with Core Damage Frequency:

NONE Important Components:

12 MDAFW PMP 11 TDAFW PMP Important Operator Actions with Task Number:

CRO 301 003 06 01 000 - Faulted Steam Generator Isolation

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Secure 11 TDAFW Pump

2. Raise Reactor Power to the POAH

3. 12 Charging Pump Trip

4. 11 TDAFW Pump Accumulator Low Air Pressure

5. 11 CTMT Vacuum Breaker Fails Closed After EOP Entry:

1. SI to Feedwater/Condensate Relay Failure

2. 12 MDAFW Pump Fails to Auto Start Abnormal Events:

1. 12 Charging pump trip

2. 11 TDAFW Pump Accumulator Low Air Pressure

3. CTMT vacuum breaker failure Major Transients:

1. 12 Steam Generator Faulted to Containment Critical Tasks:

PI-CT-10B: Establish feed water flow to the INTACT Steam Generator to prevent the INTACT Steam Generator from reaching DRYOUT conditions.

PI-CT-19: Stop feed flow to the faulted Steam Generator within 45 minutes of this critical tasks plant conditions being met.

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CRITICAL TASK SHEET Number:

PI-CT-10B Critical Task:

Establish feed water flow to the INTACT Steam Generator to prevent the INTACT Steam Generator from reaching DRYOUT conditions.

Safety Significance:

With insufficient feed water flow, the Steam Generators dry out, causing an RCS pressure increase that opens the pressurizer PORVs. The open PORVs create a small break LOCA that challenges the Core Cooling CSF. Failure to maintain an adequate heat sink will result in degradation of the Fuel Clad Barrier and RCS Barrier.

Plant Conditions:

One faulted steam generator.

At least one SG is required for heat sink.

Feed water flow is available but not established from any of the following:

o Auxiliary Feed Water Pumps o

Main Feed Water Pumps o

Condensate Pumps Sufficient time is available to align feed water flow to at least one Steam Generator prior to Wide Range level lowering below 13% [17%].

NO ATWS.

NO Station Blackout.

Initiating Cue:

Less than 200 GPM of feed water flow to the Steam Generators.

Both Steam Generators levels lowering.

RCS pressure is above the pressure of all Steam Generators.

Measurable Performance Standard:

Prior to the need to establish bleed and feed, the crew manipulates controls to establish feed water flow into at least one intact SG with one or more of the following:

o Auxiliary Feed Water Pumps o

Main Feed Water Pumps o

Condensate Pumps NOTES:

The crew establishing RCS bleed and feed instead of using a feed water source would most likely constitute a failure.

Steam Generator dry out indicated by BOTH of the following:

o Wide Range Level <13% [17%] AND o

SG Pressure rapidly lowering or completely depressurized.

Performance Feedback:

Increasing water level in at least one Steam Generator.

Feed water flow into at least one SG.

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CRITICAL TASK SHEET Number:

PI-CT-19 Critical Task:

Stop feed flow to the faulted Steam Generator within 45 minutes of this critical tasks plant conditions being met.

Safety Significance:

Failure to stop feed flow to a Steam Generator that is faulted into Containment and can NOT be isolated will result in a challenge to the Containment Barrier.

Plant Conditions:

One faulted Steam Generator.

The fault is into Containment.

The fault can NOT be isolated.

A Red/Orange Path in Integrity CSF is likely and can NOT be prevented by crew actions.

Initiating Cue:

A single Steam Generator depressurizing in an uncontrolled manner or completely depressurized.

Main feed water or auxiliary feed water continues to be delivered to the faulted SG.

Measurable Performance Standard:

Close/Secure the following valves/pumps aligned to the faulted Steam Generator (as necessary):

o AFW Pump Discharge Valve(s) o AFW Pump(s) o Main and Bypass Feed Water valve(s) o MFW Pump(s)

Performance Feedback:

AFW flow to the faulted Steam Generator is secured.

SG Feed Water Flow to the faulted Steam Generator is secured.

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SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure:

MOC NONE Power:

1x10-8 AMPS Boron: (CB):

1575 PPM TAVG:

549°F Pressure:

2235 PSIG Xenon:

Xe Free Rods:

CBD @ 142 Generator:

0 MW SEQUENCE OF EVENTS:

Event 1: Secure 11 TDAFW Pump The crew will stop 11 TD AFW Pump per 1C28.1 and place in AUTO.

Event 2: 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%.

Event 3: 12 Charging Pump Trip PRZR level will go down.

The crew will respond per C47015-0104, 12 Charging Pump Trip.

The crew will start 13 Charging pump or increase 11 Charging pump speed.

Event 4: 11 TD AFW Pump Accumulator Low Air Pressure Annunciator 47010-0105 will alarm.

The crew will close both steam supply valves to 11 TD AFW pump.

The crew will enter T.S. LCO 3.7.5 Condition B.

Event 5: 11 Containment Vacuum Breaker Fails Closed CV-31621 11 Containment Vacuum Breaker will fail closed 47021-0101 11 CONTAIMNET VACUUM BREAKER CLOSED will alarm.

The crew will respond to the ARP and attempt to open CV-31621.

The SS will enter T.S. LCO 3.6.8 Condition A.

Event 6: 12 Steam Generator Fault to CTMT 12 SG level and pressure will lower, RCS pressure and PRZR level will lower.

SI will auto actuate.

The crew will isolate feedwater to 12 SG IAW 1E-2.

Event 7: 12 MD AFW pump fails to start automatically The crew will manually start 12 MD AFW pump IAW 1E-0.

Event 8: SI to Feedwater/Condensate Relay Fails to Automatically Actuate

SI to Feedwater/Condensate relay fails to actuate on SI actuation.

The crew will manually align feedwater and condensate components IAW Att. L.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SIMULATOR PRE-BRIEF:

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

COMPLETE TURNOVER:

UNIT 1 LPEO / PEO TURNOVER LOG.

Verify crew performs walk down of control boards and reviews turnover checklists.

CREW Review the following with the off-going operator:

Unit 1 LPEO / PEO Turnover Log Walk-down the control boards and ask questions as appropriate

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 1 Booth Operator / Communicator:

1. After the crew has assumed the duty, they will secure the 11 TD AFWP IAW the pre-job brief.

2. When directed as an out-plant operator to verify 11 TD AFW Pump has stopped, CV-31153 has closed, and Auxiliary lube oil pump is running, then wait approximately 2 minutes and report 11 TD AFW Pump is stopped, CV-31153 is closed, and Auxiliary lube oil pump is running. (1C28.1 steps 6.3.5 A, B, & C)

3. When directed as an out-plant operator to stop 11 TD AFW Pump Aux Lube Oil Pump, then wait approximately 3 minutes and report Aux Lube Oil Pump has been stopped. (1C28.1 step 6.3.6)

4. If contacted as the duty chemist, acknowledge 11 TD AFW Pump has been stopped.

BOP (N) 1C28.1, AUXILIARY FEEDWATER SYSTEM UNIT 1:

CLOSE MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

CLOSE MV-32239, 11 TD AFWP TO 12 STM GEN, using CS-46315.

Stop 11 TD AFW Pump using CS-46424.

Direct an out-plant operator to verify locally:

o 11 TD AFW Pump has stopped.

o CV-31153, 11 TD AFW PMP RECIRC/L-O CLG CV, has CLOSED.

o Auxiliary lube oil pump is running.

Direct an out-plant operator to locally stop 11 TD AFW Pump Aux Lube Oil Pump when 11 TD AFW Pump stops rotating.

OPEN MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

OPEN MV-32239, 11 TD AFWP to 12 STM GEN, using CS-46315.

Independently verify MV-32238 and MV-32239 are OPEN.

Verify SI Not Ready panel light 44102-A9, 11 AFW DISCH VLV CLOSED, is NOT LIT, indicating the discharge valves are OPEN.

Place CS-46438, 11 TD AFWP selector switch in AUTO.

Independently verify CS-46438 in AUTO.

Notify the Duty Chemist that 11 TD AFW Pump has been stopped.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 2 Booth Operator / Communicator:

1.

After the crew has secured the 11 TD AFWP, they raise reactor power to the POAH IAW the pre-job brief.

Plant Response:

1.

Intermediate Range power will rise.

2.

TAVG and PRZR level will rise.

3.

Power Range power will come on scale.

ATC (R)

SS (N) 1C1.2-M2, UNIT 1 STARTUP TO MODE 2:

Raise reactor power to the point of adding heat using 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.

Using ERCS display XS02 and C41, verify the Subcritcality CSF Activation Status is INACTIVE.

Maintain reactor power between 0.5 and 2.0%.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 3 Booth Operator / Communicator:

1. After the crew has stopped the 11 TD AFW Pump, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 3, 12 Charging Pump Trip

2. If contacted as Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

3. If contacted as FIN team to write a CAP and WR acknowledge the request.

4. If contacted as the outplant operator to investigate 12 Charging pump trip, wait 3 minutes and call back and state there are no VFD fault codes and no apparent cause.

5. If contacted as engineering for concurrence for resetting a VFD fault, acknowledge the report and inform them you will investigate it and get back to them.

Plant Response:

1.

12 charging pump trips.

2.

PRZR level lowers.

3.

The following annunciators will alarm:

a.

C47015-0104, 12 CHARGING PUMP TRIP.

ATC (C)

C47015-0104, 12 CHARGING PUMP TRIP:

If necessary, then start another charging pump.

o Crew may start 13 Charging pump or may choose to only increase the speed of 11 charging pump.

Maintain pressurizer level and seal injection flow.

Determine reason for charging pump trip by checking the following:

o Observe and log any VFD fault indicated on 71116, 13 CHG PMP VFD CAB, and CS-7111603, 13 CHG PMP SPEED CONT KEYPAD Reset a VFD Fault by performing the following:

o IF charging pump operation is NOT immediately required, THEN obtain Engineering concurrence prior to resetting VFD fault

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 4 Booth Operator / Communicator:

1. After the crew has started 13 charging pump or increased 11 charging pump speed, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 4, 11 TD AFWP Accumulator Low Air Pressure

2. If contacted as Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

3. If contacted as the FIN Team Supervisor, inform the crew that you will write a CAP, Work Request, and assign an I&C Supervisor to investigate.

4. If contacted as an outplant operator to investigate low air pressure condition, then inform the crew there is no apparent source. Gage 18702 is at 71 PSIG and lowering.

5. If contacted as an outplant operator to locally close CV-31059, then wait 3 minutes and inform the crew that the valve is STUCK and will NOT close.

BOP (C)

SS (TS)

C47010-0105, 11 TD AFWP ACCUMULATOR LO AIR PRESS:

Check for low air pressure on 18702, 11 TD AFW PMP STM BLK VLV AIR ACCUM PI.

If a low air pressure condition exists, then notify the SS that 11 TD AFW pump is inoperable and enter T.S. LCO 3.7.5 Condition B.

If 11 AFW pump is NOT running, then perform one of the following to prevent an undesired start of the pump due to CV-31998 failing OPEN:

o CLOSE both steam supply valves to 11 TDAFW pump: MV-32016 & MV-32017.

OR o

Locally CLOSE CV-31059, 11 TD AFW PMP TRIP THROTTLE CV.

The SS will enter the following TS LCOs:

3.7.5 Condition B:

o Restore AFW train to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND o 10 days from discovery of failure to meet the LCO

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 5 Booth Operator / Communicator:

1. After the crew has closed TD AFWP steam supply valves and addressed tech specs, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 5, 11 Containment Vacuum Breaker Fails Closed

2. If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc.

as asked.

3. If contacted as FIN team to write a CAP and WR acknowledge the request.

Plant Response:

1.

CV-31621 fails closed.

2.

The following annunciator will be received:

a.

47021-0101, CONTAINMENT VACUUM BREAKER CLOSED SS (TS)

C47021-0101 11 CONTAINMENT VACUUM BREAKER CLOSED:

Check CV-31621, 11 CNTMT VSL VAC BKR ISOL CV A, not fully OPEN Reopen valve unless it was closed due to a Containment Isolation signal.

IF no Containment isolation signal, THEN verify CV-31622, 12 CNTMT VSL VAC BKR ISOL CV B, OPEN Refer to T.S. 3.6.8 The SS will enter the following TS LCOs:

3.6.8 Condition A:

o Restore vacuum breaker train to OPERABLE status within 7 days.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 6, 7, & 8 Booth Operator/Communicator:

1. When the crew has addressed tech specs for the CTMT vacuum breaker, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 6: 12 SG Fault to CTMT

2. Upon hearing the announcement of Reactor Trip, or when called as the Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, then open and run schedule file E-0_Att-J.sch located in X:\\\\Trex_PI\\Lightning\\Schedule\\EOPs. Inform the crew when the MSRs are isolated.

3. Upon hearing the announcement of Safety Injection, or when called as the Turbine Building Operator to secure the Turbine Building Roof Exhausters, wait 2 minutes, and report the Turbine Building Roof Exhausters are all secured and NO Aux Building Vent Zones are open.

4. If contacted as an outplant operator to close TD-4-1, then wait 2 minutes and inform the crew that TD-4-1 is closed.

5. If Control Room personnel ask if Unit 2 personnel are available to perform Attachment L, then inform the Control Room that Unit 2 personnel are NOT available for performing Attachment L.

6. If Control Room personnel ask if Unit 2 personnel are available to secure Diesel Generators and/or Safeguards Cooling Water Pumps, then inform the Control Room that Unit 2 personnel WILL secure the Diesel Generators and/or Safeguards Cooling Water Pumps.

7. If Control Room personnel ask for status of Battery Room Temperatures, then inform the Control Room that Battery Room temperatures are 74°F.

ATC (M)

BOP (M)

SS (M)

ATC (C)

SS (C)

CTs 10B

& 19 CT 19 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify the reactor is tripped.

Verify main turbine is tripped.

Verify both Safeguards buses energized.

Determine SI is required and/or actuated.

Perform Attachment L (see SEG pages 14 & 15)

Check AFW Status.

o Manually start 12 MD AFW Pump o Stop feedwater flow to 12 SG Check RCS Temperatures trending to 547°F.

Check PRZR PORVs and Spray valves closed.

If RCS pressure is less than 1600 PSIG, then STOP both RCPs.

Determine 12 SG is faulted & go to 1E-2.

1E-2, FAULTED STEAM GENERATOR ISOLATION:

Close 12 MSIV & verify 12 MSIV B/P is closed.

Identify 12 SG as the faulted generator.

Isolate the following from 12 SG:

o main feedwater o AFW flow o Verify 12 SG PORV is closed.

o Verify 12 SGB isolation valve is closed.

Check CST levels greater than 12,500 gallons.

Check secondary radiation normal.

Go to 1E-1.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 6, 7 & 8 cont.

8. If Control Room personnel ask for status of Spent Fuel Cooling, then inform the Control Room that Spent Fueling level and temperature are normal.

9. If Control Room personnel ask for status of Unit 2 Cooling Water/Chilled Water lineup, then inform Crew Unit 2 Cooling Water/Chilled Water valves are in their Safeguards position.

10. If contacted as Duty Chemist or Duty RP to check status of secondary radiation levels and/or SG activity levels, then inform the control room that both SG cation column frisks are reading background and secondary radiation levels are normal.

11. If contacted as the Duty Chemist to initiate periodic samples of both Unit 1 SGs, then acknowledge the request.

Plant Response:

1. 12 SG pressure lowers rapidly.

2. RCS & PRZR pressure lower.

3. Containment Pressure rises.

CRITICAL TASKS PI-CT-10B: Establish feed water flow to the INTACT Steam Generator to prevent the INTACT Steam Generator from reaching DRYOUT conditions.

PI-CT-19: Stop feed flow to the faulted Steam Generator within 45 minutes of this critical tasks plant conditions being met.

BOP (C)

SS (C) 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT:

If RCS pressure is less than 1600 PSIG, then STOP both RCPs.

Determine 11 SG is NOT faulted.

Check 11 SG level >50% WR.

Check secondary radiation normal.

Verify both PORVs closed, power to both block valves, and one block valve open.

Reset SI.

Reset CI.

Establish IA to CTMT.

Check offsite power available to charging pumps.

Determine SI pumps can or cannot be stopped.

(May transition to 1ES-0.2)

Stop RHR pumps.

1E-0 ATTACHMENT L: SI ALIGNMENT VERIFICATION:

Verify Safeguards Component Alignment o

See table on page 15 Close MV-32115, 122 SFP HX INLT HDR MV B Check Cooling Water Header Pressures Verify plant announcements complete Check If Main Steamlines Are required to be isolated Verify SI & RHR Flow Check RCP Cooling Verify Generator Breakers - OPEN

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 6, 7 & 8 cont.

NOTE The operator will have to perform the following to align Safeguards Components for Safety Injection:

CS #

COMPONENT DESIRED CONDITION (Normally Aligned in Att. L) 46064 MV-32115, 122 SFP HX INLT HDR MV B CLOSED 46018 11 CFCU SLOW 46019 13 CFCU SLOW (Align due to Malfunctions) 46425 12 MD AFW PUMP ON 46410 11 COND PUMP OFF 46418 11 FW PUMP OFF 43062 CV-31127, A FW REG VLV DEMAND:

ZERO 43063 CV-31128, B FW REG VLV DEMAND:

ZERO 1HC480 CV-31369, A BYPASS FW DEMAND:

ZERO 1HC481 CV-31370, B BYPASS FW DEMAND:

ZERO Verify All Heater Drain Pumps - STOPPED Open turbine drain valves Verify Main Feedwater Alignment Verify All Condensate Pumps - STOPPED Place Steam Dump in "STM PRESS" Mode Verify Unit 1 Cooling Water/Chilled Water Alignment Verify 11 Safeguards Screenhouse Ventilation lineup Verify Control Room Ventilation Alignment 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 END Once the crew has isolated 12 SG and completed Att. L, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew training has the duty.

Booth Operator:

Collect SBT data per Attachment 1, if necessary.

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SIMULATOR INPUT

SUMMARY

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Simulator Setup:

Beginning of Day:

1st / 2nd

___ / ___ 1. 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.

___ / ___ 2. Log in on floor PCs with user ID & password: <pitrgsim>

___ / ___ 3. Verify on Adobe Acrobat Reader that the Restore Last View Setttings When Reopening Documents box is NOT checked. (Found under EDIT DOCUMENT)

___ / ___ 4. Update or Verify Control Room Placards:

a.

NRC Code Placard:

i.

NRC Current Authentication Code D3RF.

ii.

Todays Date.

b.

High Flux at Shutdown Alarm Setpoint placards: 5200 cps.

c.

Feedwater regulating valve position placard set to current values.

d.

Recommended SG Blowdown flow set to current values.

___ / ___ 5. Verify Current Plant Status Magnetic Placards are in Place:

a.

Blowdown 46470 SGB To RIVER

b.

H2 in VCT Space

c.

11 BA TANK Lined Up For Service

d.

11 BA PUMP Lined Up to 11 BA Tank

e.

12 BA PUMP Lined Up to 11 BA Tank

f.

CC to SFP MV-32115 In Service

g.

CC to SFP MV-32117 In Service

___ / ___ 6. Current Plant Pink Status Control Tags in place:

a.

CS-46540, 22 CC WTR PUMP

b.

CS-46572, 121 SFP HX INLT

___ / ___ 7. Current Plant Yellow Status Control Tags in place:

a.

CS-46063, 11 CC HDR TO WST DISP HX MV-32102

___ / ___ 8. Verify that copy machine and printers are loaded with YELLOW BORDER paper.

___ / ___ 9. Pens/Notepads/Markers available on the simulator.

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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.

1st / 2nd

___ / ___ 1. If this is the first scenario of the day, then perform Beginning of Day checklist on previous page.

___ / ___ 2. If an IC is already created for this scenario, then go to Step 4.

___ / ___ 3. If an IC is NOT created for this scenario, then create as follows:

a. Reset the simulator to IC-18.

b. Verify 1HC-484, MAIN STM HDR PRESS (STM DUMP), set point is set to 71.8% +/- 2%.

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 approx. 1 x 10-8 amps and stable.

g. Insert Remote SG100 to CW.

h. For 11 TD AFW Pump, perform the following:

i. Close MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

ii. Close MV-32239, 11 TD AFWP TO 12 STM GEN, using CS-46315.

iii. Place CS-46438, 11 TD AFWP, to MANUAL.

iv. Start 11 TD AFWP using CS-46424.

v. Throttle MV-32238 and MV-32239 to establish 25 gpm to each SG.

i. Take 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).

j. OPEN SV-33341, AIR EJCTR LOOP SEAL DRN, using CS-46403.

k. Verify TPM is set to NIS.

l. If time permits, run simulator for approximately 30 minutes.

m. Place simulator in FREEZE.

n. If desired, save to available IC.

o. Go to step 4.

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Simulator Setup cont.:

___ / ___ 4. Reset the Simulator to IC-251 and place in RUN.

a. Verify TAVG is stable @ ~549°F. If necessary, adjust Steam Dump SETPOINT DIAL to maintain temperature.

___ / ___ 5. If available, run schedule file PI-ILT-NRC-2001S.sch as follows:

a.

Locate schedule file.

b.

Open schedule file by double clicking it.

c.

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

d.

Verify the schedule file is running.

___ / ___ 6. If schedule file is NOT available, reset Simulator to IC-251 or IC created in step 3, place in RUN, and insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

___ / ___ 7. Mark up 1C1.2-M2, Unit 1 Startup to Mode 2, sections 5.1-5.3. N/A or leave blank any appropriate steps.

___ / ___ 8. If desired, start Scenario Based Testing Data Collection Program per Att 1.

___ / ___ 9. Complete the "Simulator Setup Checklist on next page.

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SIMULATOR SETUP CHECKLIST Pre-Scenario Checklist:

1st / 2nd

_ _/ _

Simulator Status:

___1.

"Training Load"

___2.

Alarm sound: ON

___3.

Speed: REAL

___4.

Step counters: NOT USED

___5.

Simulator running in IC-18 or IC-251.

___6.

Steps 1 - 8 on previous page complete.

_ _/ _

Delete memory on Yokogawa Model DX1000 recorders by cycling Recorder Power.

_ _/ _

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

_ _/ _

Verify that control rod step counters on C panel and ERCS RBU CBD @ 142.

_ _/ _

Boric Acid/RMU integrators set to: BA: 0, RMU: 20, and RESET.

_ _/ _

MOC I sheet displayed on C panel.

_ _/ _

MOC Reactivity Briefing sheet available at Reactor Operator Desk.

_ _/ _

Verify Boric Acid and Reactor Makeup Controllers are set properly:

___ 1.

1HC-110: 34.6%

___ 2.

1HC-111: 44.7%

_ _/ _

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 1575 ppm.

b. RCS H2 - 45 cc/kg.

c. Turbine Reference Value and Mode - matched with DEHC.

___ 2.

Shift Reactivity Guidance placard:

a. BA: 0 gallons

b. RMU: 0 gallons

c. Dilutions @ N/A

___ 3.

EAL Classification Placard CLEANED and placed on side of SS desk.

___ 4.

LCO Timer CLEANED.

_ _/ _

SEG specific Magnetic Placards in place:

_ _/ _

___ 1. NONE

_ _/ _

SEG specific or Protected Equipment Pink Status Control Tags in place:

_ _/ _

___1. NONE

_ _/ _

SEG specific or Out of Service Yellow Caution Tags are in place:

___ 1. NONE

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Pre-Scenario Checklist continued:

1st / 2nd

_ _/ _

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 (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 (NIS - Auto Scaling - Venturi).

_ _/ _

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

___ 4.

DEHC alarms cleared.

_ _/ _

YELLOW turnover sheets 1-9 available.

_ _/ _

All Fire alarms CLEAR.

_ _/ _

Electronic PINGP 577 forms and TABS closed on both LAN connected PCs.

_ _/ _

Board-mounted EAL Tables are cleaned.

_ _/ _

Headsets turned on as necessary.

_ _/ _

Procedure checklist completed. See following page.

_ _/ _

Peer Check performed for simulator setup.

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PROCEDURE CHECKLIST:

Before 1st / 2nd After 1st / 2nd

/

1C1.2-M2, UNIT 1 STARTUP TO MODE 2

/

1C28.1, AUXILIARY FEEDWATER SYSTEM UNIT 1

/

C47010-0105, 11 TD AFWP ACCUMULATOR LO AIR PRESS

/

C47021-0101 11 CONTAINMENT VACUUM BREAKER CLOSED

/

C47015-0104, 12 CHARGING PUMP TRIP

/

1E-0, REACTOR TRIP OR SAFETY INJECTION

/

1E-0, ATT. L, SI ALIGNMENT VERIFICATION

/

1E-1, LOSS OF REACTOR OR SECONDARY COOLANT

/

1E-2, FAULTED STEAM GENERATOR ISOLATION

/

1E-CAS, UNIT 1 CONTINUOUS ACTION & INFO PAGE

SUMMARY

/

EAL BOARD

/

LAMINATE COPY OF 1C5, SECTION 5.5

/

LAMINATE COPY OF 1C12.5, SECTIONS 5.8 & 5.9

/

LAMINATE COPY OF 1C12.5, SECTION 5.10

/

LAMINATE COPY OF 1C1.4 AOP1, RAPID LOAD REDUCTION UNIT 1

/

REACTIVITY BRIEFING SHEET - MOC

/

SWI O-28, NOTIFICATION OF OPS MNGR & NRC RESIDENT INSPECTOR

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S. LCO 3.3.2

/

T.S. LCO BASES 3.3.2

/

NOTE: 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.

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Post-Scenario Checklist 1st / 2nd

_ _/ _

Computer generated PINGP 577 cleared and tab closed.

_ _/ _

Verify no electronic procedures are open on either Sim Floor computer.

_ _/ _

Verify recent history on IE and Adobe are clear for BOTH Sim Floor computers.

_ _/ _

Procedure checklist completed. See previous page.

_ _/ _

Remove Pink Status Control Tags from the following equipment:

___1. NONE

_ _/ _

Remove Magnetic placards from Control Boards:

___ 1. EAL Classification Placard from Control Board.

___ 2. RED/WHITE Critical Parameter Cards

_ _/ _

Remove Yellow Caution Tags from the following equipment:

___ 1. NONE

_ _/ _

Board-mounted EAL Table is cleaned.

_ _/ _

All books, note pads, and calculators put away.

End Of Day Checklist 1st / 2nd

_ _/ _

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

_ _/ _

If desired, floor PCs logged off if simulator will not be used again that day.

_ _/ _

Instructor station returned to normal with all books, paper, and pens, 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.

_ _/ _

Verify the following placards are erased:

CVCS panel Shift Reactivity Guidance LCO Timer NRC Authentication Code

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RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: 8/17/2020 DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS NONE PROTECTED EQUIPMENT SFP COOLING RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure:

MOC Pressure:

2235 PSIG Unit 2 is at 100% power.

Power:

1x10-8 Xenon:

Free Boron (CB): 1575 PPM Rods:

CBD @ 142 TAVG:

549°F Generator: 0 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT Stop 11 TD AFW pump and place in AUTO per 1C28.1, 6.3.

Raise reactor power to the POAH per 1C1.2-M2, 5.4.

NEW PROCEDURES / INSTRUCTIONS 11 TD AFW Pump is running for transition to MFW.

of 9

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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 performance tools.

Yes No X

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No X

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No X

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No X

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. Justification: PRA software not installed on Sim computers.

Yes No X

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No X

7. The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No X

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No X

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No X

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Yes No X

11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No 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.

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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 respect to reactor status, plant configuration, and system operation.

Yes X

No

2. The simulator operated in real time during conduct of validation.

Yes X

No

3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes X

No

4. The simulator permitted use of the reference plants procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes X

No

5. The simulator did not fail to cause or unexpectedly cause any first principle alarm or primary automatic action.

Yes X

No

6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plants expected response.

Yes X

No

7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plants response to the initiating cause.

Yes X

No

8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X

No

9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes X

No

10. Simulator fidelity has been demonstrated to be adequate for this scenario.

Yes X

No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

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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 VELASCO SRO SS HELLAND RO BOP LODERMEIER RO ATC

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ATTACHMENT 1 SBT EXAM DATA COLLECTION BEFORE SCENARIO o START menu o SBT Report o File o OPEN o Select file type.tis (FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT o Select SBT.tis o OPEN or double click o Check TAM log & verify no cycling switches o Run scenario AFTER SCENARIO o FREEZE on Simulator o Click GREEN arrow to generate report o Enter the following:

(NAME is not required)

Test Title (2001S ILT NRC SBT Group x)

Report Name (same as test title) o Click the button to right of Report Name field.

o Select location where file is to be saved (on Locker G3 flash drive) o Enter file name (same as report name) & SAVE o Click GENERATE, verify file location, and close html file o START menu o COMPARE IT o Click + ADD o Select.csv file from previously saved location o OPEN or double click o Click GREEN COMPARE button o Wait for spreadsheet to populate and then save in desired location o Verify all 3 files are saved in proper location o Close spreadsheet, COMPARE IT, and SBT Report

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG #

PI-ILT-NRC-2002S SEG TITLE:

2020 ILT NRC SIMULATOR EVALUATION #2 REV. #

0 PROGRAM:

INITIAL LICENSE OPERATOR TRAINING FL-ILT COURSE:

INITIAL LICENSE OPERATOR TRAINING FL-ILT TOTAL TIME: 2.0 HOURS Additional site-specific signatures may be added as desired.

Developed by:

Fredrick Collins Instructor Date Reviewed by:

Justin Hasner Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Justin Hasner Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Evaluation Objectives:

Evaluate the crews ability to:

1.

Swap EH Oil Pumps per 1C23.

Evaluate the crews ability to diagnose and respond to:

2.

Pressurizer Pressure Instrument failing low per 1C51.2.

3.

Emergency Diesel Generator Local Alarm per C47024.

4.

Turbine EH valve malfunction per 1C23 AOP2.

5.

Rapid Load Reduction per 1C1.4 AOP1.

6.

Loss of All Onsite and Offsite Power per 1E-0 and 1ECA-0.0.

7.

Main Turbine fails to automatically trip per 1E-0.

8.

Failure of D2 EDG to automatically start per 1ECA-0.0.

9.

Failure of 12 MD AFW Pump to auto start per 1ECA-0.0.

Training Resources:

1.

Full Scope Simulator

2.

NRC Evaluation Team

3.

Booth Operator (Backup Communicator)

4.

Primary Communicator Related PRA Information:

Initiating Event with Core Damage Frequency:

Loss of Offsite Power (20.3%)

Important Components:

12 MD AFW PMP D2 DSL GEN Important Operator Actions with Task Number:

CRO 000 055 05 01 000 - Loss of Offsite and Onsite Power CRO 062 ATI 00 00 017 - Energize a Dead 4.16KV Bus

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1P-431, PRZR Pressure Blue Channel Fails Low.

2. Turbine EH Valves Fail Closed.

After EOP Entry:

1. Main turbine auto trip failure.

2. D2 Emergency Diesel Generator fails to start automatically.

3. 12 MD AFW pump fails to start.

Abnormal Events:

1. Instrument Failure Guide.

2. Rapid Load Reduction Major Transients:

1. Loss of All Onsite and Offsite AC Power Critical Tasks:

1. PI-CT-6: Energize at least one AC emergency bus when safeguards equipment is required to perform its safety function or prior to ORANGE or RED path on Core Cooling CSF.

2. PI-CT-11: During a Station Blackout, establish Auxiliary Feedwater flow to the Steam generators to prevent both Steam Generators from reaching DRYOUT conditions.

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CRITICAL TASK SHEET Number:

PI-CT-6 Critical Task:

Energize at least one AC emergency bus when safeguards equipment is required to perform its safety function or prior to ORANGE or RED path on Core Cooling CSF.

Safety Significance:

Failure to energize an AC emergency bus when an AC power source is available unnecessarily makes safeguards equipment unavailable when needed.

Plant Conditions:

Loss of Bus 15 AND Bus 16.

At least one source is available to supply power to Bus 15 or Bus 16.

Cues:

Bus 15 and bus 16 is de-energized.

All source breakers to buses 15 and 16 are open or tripped.

Performance Indicator:

Manipulation of controls to establish one safeguards bus powered from an available source.

Feedback:

Bus 15 or 16 is energized.

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CRITICAL TASK SHEET Number:

PI-CT-11 Critical Task:

During a Station Blackout, establish Auxiliary Feed Water flow to the Steam Generators to prevent both Steam Generators from reaching DRYOUT conditions.

Safety Significance:

With insufficient feed water flow, the Steam Generators dry out, causing an RCS pressure increase that opens the pressurizer PORVs. The open PORVs create a small break LOCA that challenges the Core Cooling CSF. Failure to maintain an adequate heat sink will result in degradation of the Fuel Clad Barrier and RCS Barrier.

Plant Conditions:

Loss of Offsite Power.

Loss of Bus 15 AND Bus 16.

11 TD AFW Pump fails to automatically start.

11 TD AFW Pump is capable of being started from the Control Room.

Cues:

11 TD AFW Pump not running.

One or more Steam Generator NR Levels drop below 13%.

Indications of a Station Blackout.

Performance Indicator:

11 TD AFW Pump selector switch placed in MANUAL.

11 TD AFW Pump hand switch momentarily placed in START.

NOTES:

Steam Generator dry out indicated by BOTH of the following:

o Wide Range Level <13% [17%] AND o

SG Pressure rapidly lowering or completely depressurized.

Feedback:

Increasing water level in at least one Steam Generator.

Feed water flow into at least one SG.

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SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure:

EOC 11 TD AFWP Power:

100%

Boron: (CB):

102 PPM TAVG:

560°F Pressure:

2235 PSIG Xenon:

Equilibrium Rods:

CBD @ 218 Generator:

582 MW SEQUENCE OF EVENTS:

Event 1: Swap Running EH Oil Pumps

11 EH Oil pump is running.

The crew will start 12 EH Oil pump and stop 11 EH Oil pump per 1C23.

Event 2: 1P-431, Blue Channel Pressurizer Pressure, fails LOW.

PRZR Level Blue Channel 1P-431 will fail low.

The crew will place PRZR level control in RED-BLUE (1-3).

The Shift Supervisor will enter TS LCO 3.3.1 Conditions A & K.

Event 3: C47024-1203, D1 Local Alarm

The D1 Local Alarm will come in due to low starting air pressure.

The SS will enter TS LCO 3.8.1 Condition B.

Events 4 & 5: Turbine EH Valve Malfunction / Rapid Load Reduction Diagonally opposite turbine control IVs will fail closed.

The crew will determine a rapid load reduction is required per 1C23 AOP2.

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

Event 6: Loss of All AC Power

The reactor will trip upon loss of all AC due to loss of flow.

The crew will enter 1E-0 then transition to 1ECA-0.0.

The crew will have to manually start D2 and place D2 EDG on Bus 16 to restore power to a U1 safeguards bus.

Event 7: Main turbine fails to automatically trip

The crew will manually start D2 per 1ECA-0.0.

Event 8: D2 fails to start automatically

The crew will manually start D2 per 1ECA-0.0.

Event 9: 12 MD AFW pump fails to start automatically

The crew will manually start 11 TD AFW pump per 1ECA-0.0.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SIMULATOR PRE-BRIEF:

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

COMPLETE TURNOVER:

UNIT 1 LPEO / PEO TURNOVER LOG.

Verify crew performs walk down of control boards and the reviews turnover checklists.

CREW Review the following with the off-going operator:

Unit 1 LPEO / PEO Turnover Log Walk-down the control boards and ask questions as appropriate.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 1 Booth Operator / Communicator:

1. After the crew has assumed the duty, they will swap running EH Oil pumps per 1C23 and pre-job brief.

2. If directed as the Outplant Operator to verify proper EH Oil Pump operation, then wait 2 minutes and report back that the pump is operating properly.

BOP (N) 1C23, UNIT 1 TURBINE CONTROL SYSTEM:

Station an operator at the EH Oil Skid.

If swapping from 11 EH Oil pump to 12 EH Oil pump, then perform the following:

o Start 12 EH Oil Pump by placing CS-46385, 12 EH OIL PUMP, to START.

o Locally verify proper pump operation.

Stop 11 EH Oil Pump by placing CS-46384, 11 EH OIL PUMP, in STOP.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 2 Booth Operator / Communicator:

1. After the crew has swapped EH oil pumps, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, PRZR Press Cont. (Blue) Channel fails LOW.

2. If contacted as I&C to trip bistables, inform the crew two I&C Technicians will be available in 45 minutes.

3. If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other SWI O-28 notifications to the NRC, Duty Station Manager, etc.

4. If contacted as the FIN Team Supervisor, inform the crew that you will write a work order and assign an I&C Supervisor to investigate.

Plant Response:

1. PRZR backup heaters energize.

2. The following annunciators will alarm:

a. 47012-0108, PRZR LO PRESS SI CHANNEL ALERT

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

c. 47012-0504, REACTOR COOLANT SYSTEM OVERTEMP T CHANNEL ALERT

d. 47012-0608, PRZR CONTROL HI PRESS OR BACKUP HTRS ON

e. 47013-0205, OTT ROD STOP TURBINE RUNBACK CHANNEL ALERT ATC (I)

C47012-0108, PRZR LO PRESS SI CHANNEL ALERT Check pressurizer pressure.

Verify all heaters ON.

Verify sprays CLOSED.

If necessary, then control pressure in manual.

Refer to 1C51.3.

1C51.3, PRESSURIZER PRESSURE 1P-431 - LOW Place PRZR Pressure controller in MANUAL and STABILIZE pressure.

Select position 2-1 (WHITE-RED) on PRZR Pressure Selector switch.

When pressure is returned to normal with no deviation from setpoint, then return pressure control to auto.

Ensure PRZR Pressure Recorder not selected to Blue channel.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 2 cont.

SS (TS)

The SS will enter the following TS LCOs:

3.3.1 Condition A:

o Enter conditions referenced in Table 3.3.1-1 IMMEDIATELY.

3.3.1 Condition E:

o Place channel in trip in 6 HOURS OR o Be in MODE 3 in 12 HOURS 3.3.1 Condition K:

o Place channel in trip in 6 HOURS.

OR o Reduce thermal power to <P-7 & P-8 in 12 HOURS.

3.3.2 Condition A:

o Enter conditions referenced in Table 3.3.2-1 IMMEDIATELY.

3.3.2 Condition D:

o Place channel in trip in 6 HOURS OR o Be in MODE 3 in 12 HOURS AND o Be in MODE 4 in 18 HOURS

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 3 Booth Operator / Communicator:

1. When the crew has returned pressure control to auto and addressed Tech Specs and/or at the discretion of the Lead Evaluator, then enter:

Trigger 3, D1 Local Alarm.

2. If contacted as an outplant operator to investigate D1 local alarm, wait 2 minutes, then inform the crew that the common line between main and reserve air receiver is sheered, the line is unisolable, that starting air system pressure is at 0 PSIG, and you are responding per C55300-0101.

3. When asked whether the rupture can be isolated, inform the crew the rupture CANNOT be isolated and the air compressor cannot keep up.

4. If contacted as the outplant operator to attempt a crosstie between D1 & D2, wait 2 minutes, then inform the crew that a crosstie valve is stuck in the closed position and crosstie is not available.

5. If asked as a Unit 2 operator to perform SP 1118, then inform the crew Unit 2 will perform SP 1118 for Unit 1.

6. If asked as an outplant operator to determine if D2 has a common cause failure, then wait 2 minutes and inform the crew that D2 starting air system pressure is at 195 PSIG and stable.

7. If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other SWI O-28 notifications to the NRC, Duty Station Manager, etc.

Plant Response:

1. Annunciator 47024-1203 will alarm.

C47024-1203, D1 EMERGENCY GENERATOR LOCAL ALARM:

Dispatch an operator to D1 Diesel Generator Control Room to respond to the alarm per C55300.

Refer to T.S. 3.8.1, as necessary.

C55300-0101, STARTING AIR PRESSURE LOW:

Investigate cause of low air pressure.

Isolate leak or start air compressor.

If unable to restore starting air system pressure, then consider using crosstie.

If at least one air receiver cannot be maintained in-service and at >175 psig, then the diesel generator does not meet its design requirements and operability must be determined. Refer to T.S. 3.8.1.

1C20.7, Precaution 3.17 contains guidance on air receiver pressure (>175 PSIG) and DG operability.

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SCENARIO TIME-LINE:

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

SS (TS)

The SS will enter the following TS LCOs:

3.8.1 Condition B:

o Perform SP 1118 in 1 HOUR AND o Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within 4 HOURS of discovery.

AND o Determine OPERABLE DG is not inoperable due to a common cause failure in 24 HOURS.

AND o Restore DG to OPERABLE status in 14 DAYS.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 4 & 5 Booth Operator / Communicator:

1.

After the crew has addressed tech specs and/or at the discretion of the Lead Evaluator enter:

Trigger 4, Turbine Control IV Malfunction

2.

If contacted as the out-plant operator to investigate, wait 2 minutes and report there are no indication of an EH Oil System problem.

3.

If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

4.

If contacted as the FIN Team Supervisor or Turbine Engineer, inform the crew that you will write a work order and investigate.

Plant Response:

1. Turbine control IVs CV-31167 & 31173 fail closed.

2. TAVG will rise.

3. Turbine load will lower.

4. The following annunciators will be received:

a. 47008-0409, TURB CONTROL SYSTEM TROUBLE BOP (C)

ATC (R)

SS (N) 1C23 AOP2, MALFUNCTION OF TURBINE EH CONTROL SYSTEM:

Determine that 2 IVs from diagonally opposite MSRs have CLOSED.

Reduce turbine load to 50% per 1C1.4 AOP1.

1C1.4 AOP1, RAPID POWER REDUCTION - UNIT 1:

Determine predicted boron addition and final control rod position from contingency reactivity plan for the target power level.

Borate RCS to maintain control rods above insertion limit and control delta I within limits.

Place PRZR heaters to ON.

Reduce turbine load to desired value.

NOTE:

It is not necessary to complete the full down power prior to moving on to the next event.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 6, 7, & 8 Booth Operator / Communicator:

1. When the crew has initiated a rapid load reduction, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 6, Loss of All AC.

2. Wait 1 minute & announce over PA, Attention all plant personnel, Unit 2 Reactor Trip. Unit 2 Reactor Trip.

3. If contacted as an out-plant operator to report seal injection flow, then wait 3 minutes and report to the control room seal injection flow as indicated on THUNDERVIEW-SIMVC02.

4. If contacted as an out-plant operator to investigate and/or Acknowledge the D2 Local Alarm, then report that it is due to C55800-0105, Stand-By Lube Oil System Trouble alarm and enter REMOTE: DG107 to SILENCE.

5. When the crew places synchroscope in D2, verify AUTO Trigger 16 is entered.

6. If crew asks if a Unit 2 operator is available to work on restoring Bus 15, then inform the crew that Unit 2 WILL work on restoring Bus 15.

7. If contacted as an out-plant operator to establish communications with the CR to throttle AFW flow, then wait 2 minutes and report via handheld radio that you are in the AFW Pump room standing by to throttle AFW flow.

CRITICAL TASKS PI-CT-6: Energize at least one AC emergency bus when safeguards equipment is required to perform its safety function or prior to ORANGE or RED path on Core Cooling CSF.

PI-CT-11: During a Station Blackout, establish Auxiliary Feedwater flow to the Steam generators to prevent both Steam Generators from reaching DRYOUT conditions.

ATC (M)

BOP (C & M)

SS (M)

BOP (C)

SS (C)

CT 6 1E-0, REACTOR TRIP OR SAFETY INJECTION Verify reactor is tripped.

Manually trip the main turbine.

Determine both Safeguards buses NOT energized.

Transition to 1ECA-0.0.

1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER Check PRZR PORVs CLOSED.

Check Letdown isolation valves CV-31255 & CV-31226 CLOSED.

Check Excess Letdown isolation valve CV-31330 CLOSED.

Determine AFW flow is NOT greater than 200 gpm.

Announce Unit 1 reactor trip.

Determine CL header pressure greater than 25 PSIG.

Determine Bus 16 is available.

Start D2 diesel generator.

Place BKR 16-9 MAN/AUTO switch to MANUAL Place synchroscope select switch to D2 Close BKR 16-9.

Verify Bus 16 energized.

Start one charging pump.

Return to 1E-0, step 3.

1E-0, REACTOR TRIP OR SAFETY INJECTION Determine Bus 16 energized.

Determine SI is NOT actuated nor required.

Transition to 1ES-0.1.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 6, 7, & 8 cont.

8. Throttle AFW flow as necessary using the following remotes:

a.

FW136 - 12 AFW Pump to 11 SG (MV-32381)

b.

FW137 - 12 AFW Pump to 12 SG (MV-32382)

Plant Response:

1. Reactor trip.

2. Bus 15 locks out and Bus 16 de-energizes.

3. D1 locks out & D2 fails to start.

4. Multiple annunciators associated with loss of power.

ATC (C)

SS (C)

CT 11 1ES-0.1, REACTOR TRIP RECOVERY Transfer steam dump to STM PRESS mode.

Check RCS cold leg temps at 547°F.

Check CL header pressure greater than 75 psig.

Notify TBO to perform Att. J.

Determine AFW flow to SGs less than 200 gpm.

o Start 12 MD AFW pump.

Determine all control rods NOT fully inserted.

1FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK:

Determine secondary heat sink is required.

Determine bleed & feed is NOT required.

Restore AFW to at least one SG.

o Start 12 MD AFW pump.

END Once the crew has restored power to Bus 16 and started 12 MD AFW pump, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew that training has the duty.

Booth Operator:

Collect SBT data per Attachment 1.

NOTE:

It takes approximately 3 minutes for AFW MVs to fully close after the remote has been entered.

Ensure MV shows closed on Thunderview prior to telling crew the valve is closed.

NOTE: Depending on crew timing, a RED PATH in Heat Sink CSF may come in due to turbine auto trip failure.

This is NOT a failure. The crew will then restore AFW in 1FR-H.1 and return to procedure and step in effect.

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SIMULATOR INPUT

SUMMARY

SIMULATOR EVENT

SUMMARY

Event ID Description Code 16 RESTORE BKR 16-9 HWZDGD6906(2)==1

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Simulator Setup:

Beginning of Day:

___ 1.

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.

___ 2.

Log in on floor PCs with user ID & password: <pitrgsim>

___ 3.

Update or Verify Control Room Placards:

a. NRC Code Placard:

i. NRC Current Authentication Code D3RF.

ii. Todays Date.

b. High Flux at Shutdown Alarm Setpoint placards: 5000 cps.

c. Feedwater regulating valve position placard set to current values.

d. Recommended SG Blowdown flow set to current values.

___ 4.

Verify Current Plant Status Magnetic Placards are in Place:

a. Blowdown 46470 SGB to CDSR

b. H2 in VCT Space

c. 11 BA TANK Lined Up for Service

d. 11 BA PUMP Lined Up to 11 BA Tank

e. 12 BA PUMP Lined Up to 11 BA Tank

f. CC to SFP MV-32115 In Service

g. CC to SFP MV-32117 In Service

___ 5.

Current Plant Pink Status Control Tags in place:

a. CS-46540, 22 CC WTR PUMP

b. CS-46572, 121 SFP HX INLT

___ 6.

Current Plant Yellow Caution Tags in place:

a. NONE

___ 7.

Verify that copy machine and printers are loaded with YELLOW BORDER paper.

___ 8.

Pens/Notepads/Markers available on the simulator.

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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 this is the first scenario of the day, then perform Beginning of Day checklist on previous page.

___ 2.

Reset the Simulator to IC-252 and go to step 4.

___ 3.

If IC-252 is not available, then perform the following:

a. Reset the Simulator to IC-11 and place in RUN.

b. Place CS-46424, 11 TD AFW Pump in PULLOUT.

c. Place CS-46438, 11 TD AFWP in MANUAL.

d. Close 11 MAIN STM TO 11 TD AFWP MV-32016 using CS-46127.

e. Close 12 MAIN STM TO 11 TD AFWP MV-32017 using CS-46128.

f. Close MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

g. Close MV-32239, 11 TD AFWP TO 12 STM GEN, using CS-46315.

___ 4.

Place the simulator in RUN.

___ 5.

If available, run schedule file PI-ILT-NRC-2002S.sch as follows:

a. Locate schedule file.

b. Open schedule file by double clicking it.

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

d. 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-2002S.evt as follows:

a. Locate event file.

b. Open event file by double clicking file.

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

___ 9.

If desired, start Scenario Based Testing Data Collection Program per Attachment 1.

___ 10. Complete the "Simulator Setup Checklist on next page

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SIMULATOR SETUP CHECKLIST Pre-Scenario Checklist:

Simulator Status:

___1.

"Training Load"

___2.

Alarm sound ON

___3.

Speed: REAL

___4.

Step counters: NOT USED

___5.

Simulator running in IC-252 or IC-11.

___6.

Steps 1 - 9 on previous page complete.

Delete memory on Yokogawa Model DX1000 recorders by cycling Recorder Power.

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

Verify that control rod step counters on C panel and ERCS RBU CBD @ 218.

Boric Acid/RMU integrators set to: BA: 0, RMU: 20, and reset.

EOC I sheet displayed on C panel.

EOC Reactivity Briefing sheet available at Reactor Operator Desk.

Verify Boric Acid and Reactor Makeup Controllers are set properly:

___ 1.

1HC-110: 2.1%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a.

RCS boron - 102 ppm.

b.

RCS H2 - 45 cc/kg.

c.

Turbine Reference Value and Mode - matched with DEHC.

___ 2.

Shift Reactivity Guidance placard:

a.

BA: 0.3 gallons

b.

RMU: 67 gallons

c.

Dilutions: 20 gal RMU, 1-2 times per shift

___ 3.

EAL Classification Placard CLEANED and placed on side of SS desk.

___ 4.

LCO Timer CLEANED.

SEG specific Magnetic Placards in place:

___1.

NONE SEG specific or Protected Equipment Pink Status Control Tags in place:

___1. CS-46425, 12 MD AFWP SEG specific or Out of Service Yellow Caution Tags are in place:

___ 1. CS-46424, 11 TD AFWP

___ 2. CS-46127, 11 MAIN STM TO 11 TD AFWP MV-32016

___ 3. CS-46128, 12 MAIN STM TO 11 TD AFWP MV-32017

___ 4. CS-46314, 11 TD AFWP TO 11 STM GEN MV-32238

___ 5. CS-46315, 11 TD AFWP TO 12 STM GEN MV-32239

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Pre-Scenario Checklist continued:

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 - VENT).

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

___ 4.

DEHC alarms cleared.

Verify DEHC VPL set ~0.1 to 0.3 above current valve position (not on limiter).

YELLOW turnover sheets 1-9 available.

Electronic PINGP 577 forms and TABS closed on both LAN connected PCs.

Board-mounted EAL Tables are cleaned.

Headsets turned on as necessary.

Perform one of the following:

Clear web browser history and recent procedures in pdf.

Complete post-scenario checklist.

Procedure checklist completed. See following page.

Peer Check performed for simulator setup.

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PROCEDURE CHECKLIST:

Before 1st / 2nd After 1st / 2nd

/

1C1.4 AOP1, RAPID POWER REDUCTION - UNIT 1

/

1C23, UNIT 1 TURBINE CONTROL SYSTEM

/

1C23 AOP 2, MALFUNCTION OF TURBINE EH CONTROL SYSTEM

/

1C51.3, 1P-431 PRESSURIZER PRESSURE - LOW

/

C47012-0108, PRZR LO PRESS SI CHANNEL ALERT

/

C47024-1203, D1 EMERGENCY GENERATOR LOCAL ALARM

/

1E-0, REACTOR TRIP OR SAFETY INJECTION

/

1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER

/

1ES-0.1, REACTOR TRIP RECOVERY

/

1E-CAS, UNIT 1 CONTINUOUS ACTION & INFO PAGE

SUMMARY

/

EAL Board

/

1FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK

/

LAMINATE COPY OF 1C5, SECTION 5.5

/

LAMINATE COPY OF 1C12.5, SECTIONS 5.8, 5.9, & 5.10

/

REACTIVITY BRIEFING SHEET - MOC

/

SWI O-28, NOTIFICATION OF OPS MNGR & NRC RESIDENT INSPECTOR

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S. LCO 3.3.2

/

T.S. LCO BASES 3.3.2

/

T.S. LCO 3.8.1

/

T.S. LCO 3.8.1 NOTE: 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.

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Post-Scenario Checklist Clear web browser history and recent procedures in pdf.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___ 1.

CS-46425, 12 MD AFWP Magnetic placards removed:

___ 1.

NONE Remove Yellow Caution Tags from the following equipment:

___ 1. CS-46424, 11 TD AFWP

___ 2. CS-46127, 11 MAIN STM TO 11 TD AFWP MV-32016

___ 3. CS-46128, 12 MAIN STM TO 11 TD AFWP MV-32017

___ 4.

CS-46314, 11 TD AFWP TO 11 STM GEN MV-32238

___ 5. CS-46315, 11 TD AFWP TO 12 STM GEN MV-32239 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.

If desired, 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.

Verify the following placards are erased:

CVCS panel Shift Reactivity Guidance LCO Timer NRC Authentication Code

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RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: 8/18/2020 DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

1. 11 TD AFW PUMP is Out of Service for corrective maintenance.

T.S. LCO 3.7.5 Condition B has been entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining.

11 TD AFW Pump is expected to be returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

PROTECTED EQUIPMENT 12 MD AFW PUMP SFP COOLING RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure:

EOC Pressure:

2235 PSIG Unit 2 is at 100% power.

Power:

100%

Xenon:

Equilibrium Boron (CB): 102 PPM Rods:

CBD @ 218 TAVG:

560°F Generator:

582 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT Prior to entering the simulator, perform a Pre-Job Brief for the following:

o Swap EH oil pumps per 1C23.

After taking the duty, swap running EH oil pumps per 1C23 and pre-job brief.

NEW PROCEDURES / INSTRUCTIONS of 9

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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 performance tools.

Yes No X

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No X

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No X

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No X

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. Justification: PRA software not installed on Sim computers.

Yes No X

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No X

7. The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No X

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No X

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No X

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Yes No X

11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No 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.

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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 respect to reactor status, plant configuration, and system operation.

Yes X

No

2. The simulator operated in real time during conduct of validation.

Yes X

No

3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes X

No

4. The simulator permitted use of the reference plants procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes X

No

5. The simulator did not fail to cause or unexpectedly cause any first principle alarm or primary automatic action.

Yes X

No

6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plants expected response.

Yes X

No

7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plants response to the initiating cause.

Yes X

No

8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X

No

9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes X

No

10. Simulator fidelity has been demonstrated to be adequate for this scenario.

Yes X

No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

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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 VELASCO SRO SS HELLAND RO BOP LODERMEIER RO ATC

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ATTACHMENT 1 SBT EXAM DATA COLLECTION BEFORE SCENARIO o START menu o SBT Report o File o OPEN o Select file type.tis (FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT o Select SBT.tis o OPEN or double click o Check TAM log & verify no cycling switches o Run scenario AFTER SCENARIO o FREEZE on Simulator o Click GREEN arrow to generate report o Enter the following:

(NAME is not required)

Test Title (2002S ILT NRC SBT Group x)

Report Name (same as test title) o Click the button to right of Report Name field.

o Select location where file is to be saved (on Locker G3 flash drive) o Enter file name (same as report name) & SAVE o Click GENERATE, verify file location, and close html file o START menu o COMPARE IT o Click + ADD o Select.csv file from previously saved location o OPEN or double click o Click GREEN COMPARE button o Wait for spreadsheet to populate and then save in desired location o Close spreadsheet, COMPARE IT, and SBT Report o Verify all 3 files are saved in proper location

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG #

PI-ILT-NRC-2003S SEG TITLE:

2020 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 HOURS Additional site-specific signatures may be added as desired.

Developed by:

Fredrick Collins Instructor Date Reviewed by:

Justin Hasner Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Justin Hasner Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Evaluation Objectives:

Evaluate the crews ability to:

1.

Swap running RMU pumps per C13.1.

Evaluate the crews ability to diagnose and respond to:

2.

1st Stage Pressure Instrument fails low per 1C51.3.

3.

Restore TAVG to TREF per 1C51.3 and.

4.

PRZR Level White Channel fails LOW per 1C51.2 & 1C12.1.

5.

Steam Generator Tube Rupture per 1E-3.

6.

RHR pumps fail to start on SI per 1E-0.

7.

SI to Cooling Water Relay fails to actuate per 1E-0.

Training Resources:

1.

Full Scope Simulator

2.

NRC Evaluation Team

3.

Booth Operator (Backup Communicator)

4.

Primary Communicator Related PRA Information:

Initiating Event with Core Damage Frequency:

SGTR - 7.6%

Important Components:

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

CRO 301 004 06 01 000 - SGTR

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. First Stage Pressure 1PT-485 Fails Low

2. 1L-427, PRZR Level White Channel Fails Low After EOP Entry:

1. 11 & 12 RHR Pumps Fail to Auto start on SI

2. SI to Cooling Water Relay Fails to Actuate Abnormal Events:

1. Instrument Failure Guide

2. Uncontrolled Rod Motion

3. Letdown Restoration Major Transients:

1. Steam Generator Tube Rupture Critical Tasks:

1. PI-CT-20: Establish at least 250 PSID between the ruptured SG and intact SG prior to depressurizing the RCS.

2. PI-CT-21: Stop the RCS cooldown before an ORANGE or RED path in Integrity CSF occurs.

3. PI-CT-22: Depressurize the RCS to meet SI termination criteria before overfilling the ruptured Steam Generator.

4. PI-CT-23: Secure feed flow to the ruptured Steam Generator and terminate Safety Injection before overfilling the ruptured Steam Generator.

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CRITICAL TASK SHEET Number:

PI-CT-20 Critical Task:

Establish at least 250 PSID between the ruptured SG and intact SG prior to depressurizing the RCS.

Safety Significance:

Securing steam flow from the ruptured Steam Generator and cooling down the RCS with the intact Steam Generator establishes a pressure differential between the ruptured and non-ruptured Steam Generators. This allows RCS depressurization to minimize primary-to-secondary leakage.

Plant Conditions:

Reactor tripped.

Safety Injection actuated.

SGTR from only one Steam Generator.

Non-ruptured Steam Generator remains intact.

LOCA to containment not occurring.

Steam flow from ruptured Steam Generator is capable of being secured.

Cues:

Secondary radiation levels are NOT normal.

Steam Generator NR level increasing in an uncontrolled manner.

Performance Indicator:

Performing the following as necessary to establish at least a 250 PSID between ruptured SG and intact SG:

o Securing and/or reducing steam loads from the ruptured SG.

o If necessary, cooling down the RCS by:

Dumping steam to the condenser from the intact SG ONLY.

Manually opening the intact SG PORV ONLY.

NOTE:

If Attachment B is used to secure steam flow from the Steam Generator instead of closing the MSIV and Bypass, then RCS cooldown using steam dumps would most likely constitute a failure.

Feedback:

Stable or increasing pressure in the ruptured SG.

Ruptured Steam Generator pressure is at least 250 PSIG above intact Steam Generator pressure.

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CRITICAL TASK SHEET Number:

PI-CT-21 Critical Task:

Stop the RCS cooldown before an ORANGE or RED path in Integrity CSF occurs.

Safety Significance:

Excessive rate of RCS cooldown creates large thermal stresses on the reactor vessel. Large thermal stresses on the vessel lead to initiation and growth of a small flaw into a larger crack.

Growth or extension of such a flaw leads to a loss of vessel integrity.

Plant Conditions:

LOCA to containment not occurring.

SGTR in progress.

An operator initiated RCS cooldown in progress.

Cues:

RCS cooldown in progress from one of the following:

o Steam Dump to condenser.

o SG PORV RCS temperature lowering.

Performance Indicator:

Securing the cool down by manipulating one of the following:

Steam Dump controller.

SG PORV controller.

Feedback:

RCS temperature stops lowering.

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CRITICAL TASK SHEET Number:

PI-CT-22 Critical Task:

Depressurize the RCS to meet SI termination criteria before overfilling the ruptured Steam Generator.

Safety Significance:

A SGTR allows radioactive RCS inventory to leak into the SG. As a result, the SG inventory, radioactivity, and pressure increase. If the primary-to-secondary leakage is not stopped, the SG will overfill causing water release through the SG PORV or SG Safety. This can cause an un-isolable fault from the ruptured SG and significantly increase the radioactive release to the public.

Plant Conditions:

SGTR from only one Steam Generator.

Ruptured Steam Generator pressure is at least 250 PSIG above intact Steam Generator pressure.

Cues:

Stable or increasing pressure in the ruptured SG.

Ruptured Steam Generator pressure is at least 250 PSIG above intact Steam Generator pressure.

Performance Indicator:

Pressurizer Spray valve(s) or Pressurizer PORV(s) opened and closed as necessary to establish SI termination criteria prior to overfilling the Steam Generator.

The Steam Generator is considered overfilled if BOTH conditions below exist:

o 30 minutes has elapsed since indications of a SGTR were available.

o Ruptured SG Narrow Range Level has reached 100%.

Feedback:

RCS depressurization is stopped when one of the following is met:

RCS sub-cooling is greater than 21°F [40°F].

Secondary Heat Sink available:

o Total feed flow to intact SG greater than 200 GPM.

-OR-o Intact SG NR level greater than 7% [WR 50%].

RCS pressure stable or increasing.

Pressurizer level greater than 8% [27%]

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CRITICAL TASK SHEET Number:

PI-CT-23 Critical Task:

Secure feed flow to the ruptured Steam Generator and terminate Safety Injection before overfilling the ruptured Steam Generator.

Safety Significance:

A SGTR allows radioactive RCS inventory to leak into the SG. As a result, the SG inventory, radioactivity, and pressure increase. If the primary-to-secondary leakage is not stopped, the SG will overfill causing water release through the SG PORV or SG Safety. This can cause an un-isolable fault from the ruptured SG and significantly increase the radioactive release to the public.

Plant Conditions:

SGTR from only one Steam Generator.

Cues:

Feed flow is established to the ruptured Steam Generator.

SI termination criteria are met.

Performance Indicator:

Close/Secure the following valves/pumps aligned to the ruptured Steam Generator (as necessary):

o AFW Pump Discharge Valve(s) o AFW Pump(s) o Main and Bypass Feed Water valve(s) o MFW Pump(s)

Stopping all running SI Pumps The Steam Generator is considered overfilled if BOTH conditions below exist:

30 minutes has elapsed since indications of a SGTR were available.

Ruptured SG Narrow Range Level has reached 100%.

Feedback:

Feed flow to the ruptured Steam Generator is secured.

Safety Injection flow is secured.

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SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure:

EOC 11 SI PUMP Power:

60%

Boron: (CB):

230 PPM TAVG:

554°F Pressure:

2235 PSIG Xenon:

Equilibrium Rods:

CBD @ 178 Generator:

338 MW SEQUENCE OF EVENTS:

Event 1: Swap Running RMU Pumps 11 RMU pump is running.

The crew will start 12 RMU pump and stop 11 RMU pump per C13.1.

Event 2: 1PT-485 1st Stage Pressure Fails Low Rods will automatically step in.

The crew will place rod control in manual per 1C5 AOP1.

The crew will place steam dump in steam pressure mode per 1C51.2 Instrument failure guide.

The crew will enter T.S. LCO 3.3.1 Conditions A & R and TRM 3.3.4 Condition A.

Event 3: Restore TAVG to TREF The crew will withdraw Control Bank D rods to restore TAVE to TREF per 1C51.1.

Event 4: 1L-427, PRZR Level White Channel Fails Low PRZR Level White (Interlock) Channel 1L-427 will fail low.

Letdown will isolate.

The crew will place PRZR level control in RED-BLUE (1-3).

The crew will restore letdown per 1C12.1.

The crew will enter TS LCO 3.3.1 Conditions A & K.

Event 5: 11 Steam Generator Tube Rupture Pressurizer level and RCS pressure will lower rapidly.

11 SG level will rise.

The crew will trip the reactor and actuate safety injection per 1E-0.

The crew will isolate 11 SG, cooldown & depressurize the RCS, and stop 12 SI pump per 1E-3.

Event 6: 11 and 12 RHR Pumps Fail to Start Automatically The crew will manually start both RHR pumps per 1E-0 Att. L.

Event 7: SI to Cooling Water Relay Failure The crew will manually align CLG WTR components per 1E-0 Att. L.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SIMULATOR PRE-BRIEF:

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

COMPLETE TURNOVER:

UNIT 1 LPEO / PEO TURNOVER LOG.

Verify crew performs walk down of control boards and the reviews turnover checklists.

CREW Review the following with the off-going operator:

Unit 1 LPEO / PEO Turnover Log Walk-down the control boards and ask questions as appropriate.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 1 Booth Operator / Communicator:

1. After the crew has assumed the duty, they will swap running RMU pumps per C13.1 and pre-job brief.

2. If directed as the Outplant Operator to verify 12 RMU tank is not aligned for degasification, then wait 2 minutes and report back that 22 RMU tank is currently aligned for degas.

BOP (N)

C13.1, REACTOR MAKEUP SYSTEM:

Verify the standby reactor makeup tank is NOT aligned for degasification.

Start the oncoming (12) RMU pump using CS-46117, 12 RX M-U PMP START/STOP CS.

Stop the off-going (11) RMU pump using CS-46116, 11 RX M-U PMP START/STOP CS.

Check 47022-0601, UNIT1 REACTOR MAKEUP LO PRESS, is NOT LIT.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 2 & 3

1.

After the crew has swapped RMU pumps, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, 1st Stage Pressure Fails Low

2.

If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

3.

If contacted as FIN team to write a CAP and WR acknowledge the request.

Plant Response:

1. Control Rods automatically step IN.

2. TAVG will lower due to rod movement.

3. The following annunciators will alarm:

a.

C47011-0405, FW CONTROL SYSTEM TROUBLE.

b.

C47013-0305, AUCTIONEERED TAVG-TREF DEVIATION ATC (I)

ATC (R)

SS (N) 1C5 AOP1, UNCONTROLLED ROD MOTION:

Check turbine generator electrical load STABLE.

Place rods in MANUAL.

Check rod motion STOPPED.

Check for failed instruments.

Go to 1C51.

1C51.2, TURBINE 1ST STAGE PRESSURE 1P-485 -

LOW:

Place rod control in manual.

Control TAVG at value appropriate for power level.

(Must use Fig. C1-5 to determine TAVG and TREF)

Place one steam dump interlock bypass to OFF.

Place steam dump in pressure mode.

Verify steam dump valves are CLOSED.

Verify zero output on steam dump controller.

Return steam dump interlock bypass to ON.

Verify SG level control operating properly in AUTO.

Refer to TS LCO 3.3.1 Condition A and Table 3.3.1-1 Function 16.b.2.

Refer to TRM TLCO 3.3.4 Condition A and Table 3.3.4-1 Function 3.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 2 & 3 cont.

SS (TS)

The SS will enter the following TS LCOs:

3.3.1 Condition A o Enter Condition referenced in Table 3.3.1-1 for the channel(s) or train(s) IMMEDIATELY.

3.3.1 Condition R o Verify P-7 is in required state in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

OR o Be in MODE 2 in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

TRM 3.3.4 Condition A o Initiate actions to restore to OPERABLE immediately.

TRM 3.3.4 Table 3.3.4-1 Function 3 o Perform channel check every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 4 Booth Operator / Communicator:

1.

After the crew has addressed tech specs and restored TAVG to TREF, and/or at the discretion of the Lead Evaluator, enter:

Trigger 4, PRZR Level White Channel Fails Low

2.

If contacted as I&C to trip bistables, inform the crew two I&C Technicians will be available in 45 minutes.

3.

If contacted as FIN team to write a CAP and WR acknowledge the request.

4.

If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

5.

If contacted as Duty RP, then acknowledge report of letdown being secured.

6.

If contacted as Duty RP, then acknowledge report of letdown being restored.

Plant Response:

1. Letdown automatically secures.

2. PRZR heaters de-energize.

3. PRZR level rises.

4. Annunciator 47012-0607, PRZR LO-LO LVL HEATERS OFF AND LETDOWN SECURED will alarm.

ATC (I)

BOP (I)

C47012-0607, PRZR LO-LO LVL HEATERS OFF AND LETDOWN SECURED:

Determine PRZR level is slowly rising.

Verify all PRZR heaters are off.

Verify Letdown is isolated.

Place charging pump speed control in manual and control pressurizer level.

Refer to 1C51.2.

1C51.2, PRESSURIZER LEVEL 1L-427 - LOW:

Place PRZR heaters in off.

Select position 1-3 (RED-BLUE) on PRZR Level Control Selector switch.

Restore pressurizer heaters.

Restore Letdown per 1C12.1.

Ensure PRZR Level Recorder not selected to White channel.

1C12.1, LETDOWN, CHARGING, AND SEAL WATER INJECTION - UNIT1:

Notify Duty RP tech normal LD is being returned to service.

Place 1HC-130, LTDN TEMP CONT, in MANUAL and OPEN to 50%.

Place 1HC-135A, LTDN PRESS CONT, in MANUAL and OPEN to about 50%.

Position CV-31204, LTDN DIVERT TO PURIF, to the DIVERT position, using CS-46167.

Establish charging to the regen HX as follows:

o Adjust 1HC-142, CHG LINE FLOW CONT, AND the inservice charging pump speed.

o Verify sufficient charging to prevent flashing of LD.

Note: The crew may leave PRZR level control in manual until level has returned to the normal band.

It is not necessary to wait before moving on to the next event.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 4 cont.

SS (TS)

OPEN CV-31339, LTDN LINE CNTMT ISOL, using CS-46166.

OPEN the loop B LD isolation valves:

o CV-31226, LETDOWN LINE ISOL, CS-46165 o CV-31255, LETDOWN LINE ISOL, CS-46133 OPEN the desired LD orifice isolation valve while adjusting1HC-135A so the 600 psig LD relief doesnt lift and the desired flow rate is obtained.

o CV-31325, LETDOWN ORIFICE ISOL 40 GPM, CS-46170 o CV-31326, LETDOWN ORIFICE ISOL 40 GPM, CS-46171 Return 1HC-135A and 1HC-130 to AUTO per C7.

The SS will enter the following TS LCOs:

3.3.1 Condition A o Enter Condition referenced in Table 3.3.1-1 for the channel(s) or train(s) IMMEDIATELY.

3.3.1 Condition K o Place channel in trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

OR o Reduce THERMAL POWER to <P-7/P-8 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 5, 6, & 7 Booth Operator/Communicator:

1. When the crew has restored normal letdown and addressed tech specs, and/or at the discretion of the Lead Evaluator then enter:

Trigger 5: 11 Steam Generator Tube Rupture

2. Upon hearing the announcement of Reactor Trip, or when called as the Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, then open and run schedule file E-0_Att-J.sch located in X:\\\\Trex_PI\\Lightning\\Schedule\\EOPs. When the isolation is complete, inform the crew the MSRs are isolated.

3. Upon hearing the announcement of Safety Injection, or when called as the Turbine Building Operator to secure the Turbine Building Roof Exhausters, wait 2 minutes and report the Turbine Building Roof Exhausters are all secured.

4. If contacted as RP or Duty Chemist to sample for primary-to-secondary leakage, then wait 2 minutes and report cation column frisks indicate high activity on 11 SG and reading background on 12 SG.

5. If Control Room personnel ask if Unit 2 personnel are available to perform Attachment L, then inform the Control Room that Unit 2 personnel are NOT available for performing Attachment L.

6. Control Room personnel ask if Unit 2 personnel are available to secure Diesel Generators and/or Safeguards Cooling Water Pumps, then inform the Control Room that Unit 2 personnel WILL secure the Diesel Generators and/or Safeguards Cooling Water Pumps.

7. If CR personnel ask for status of Battery Room Temperatures, then report Battery Room temps are 74°F.

ATC (M)

BOP (M)

SS(M)

CT-23 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify reactor is tripped.

Verify main turbine tripped.

Verify both Safeguards buses energized.

Manually actuate SI due to inability to maintain pressurizer level above 5%.

Perform Attachment L (see SEG page 17).

Check AFW Status.

Check RCS TAVG trending to 547°F.

Check PRZR PORVs and Spray valves closed.

Determine RCP trip criteria are NOT met.

Determine SGs are NOT faulted.

Determine SG Tubes are ruptured.

Transfer to 1E-3.

1E-3, STEAM GENERATOR TUBE RUPTURE Determine RCPs should NOT be stopped.

Identify 11 SG as the ruptured SG.

Isolate flow from ruptured SG:

o 11 SG PORV in AUTO at 75%.

o 11 SG PORV closed.

o Close 11 SG steam supply to 11 TD AFWP.

o Verify 11 SG Blowdown valves closed.

o Close 11 MSIV and bypass valve.

Determine 11 SG narrow range level is >7%.

Stop feed flow to 11 SG.

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SCENARIO TIME-LINE:

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

8. If Control Room personnel ask for status of Spent Fuel Cooling, then inform the Control Room that Spent Fueling level and temperature are normal.

9. If Control Room personnel ask for status of Unit 2 Cooling Water/Chilled Water lineup, then inform Crew Unit 2 Cooling Water/Chilled Water valves are in their Safeguards position.

10. If contacted as the aux building operator to open 11/13 CFCU orifice bypass valves, then acknowledge the order, wait 2 minutes, and enter TRIGGER 15. Call the control room and report 11/12/13/14 Orifice bypass valves are open.

Plant Response:

1. Reactor and turbine trip.

2. 11 SG level rises rapidly.

3. RCS & PRZR pressure lower CRITICAL TASKS PI-CT-20: Establish at least 250 PSID between the ruptured SG and intact SG prior to depressurizing the RCS.

PI-CT-21: Stop the RCS cooldown before an ORANGE or RED path in Integrity CSF occurs.

PI-CT-22: Depressurize the RCS to meet SI termination criteria before overfilling the ruptured Steam Generator.

PI-CT-23: Secure feed flow to the ruptured Steam Generator and terminate Safety Injection before overfilling the ruptured Steam Generator.

NOTE:

The Steam Generator is considered overfilled if BOTH conditions below exist:

30 minutes has elapsed since indications of a SGTR were available.

Ruptured SG Narrow Range Level has reached 100%.

CT-20 CT-21 CT-22 CT-23 Reset SI.

Determine 11 SG pressure >290 PSIG.

Initiate RCS Cooldown:

o Determine required CETC temperature.

o Check one running condensate pump.

o Establish steam dump to condenser.

o Stop cooldown when CETCs less than required temperature.

o Maintain CETCs less than required temperature.

Check 12 SG NR level greater than 7%.

Control feed flow to maintain between 18% and 50%.

Check power available to PRZR block valves and at least one open.

Verify PRZR PORVs closed.

Reset SI.

Reset CI.

Establish Instrument Air to CTMT.

Stop RHR pumps.

Establish charging flow.

Check 11 SG pressure stable or increasing.

Determine RCS subcooling greater than 41°F.

Depressurize RCS:

o Determine normal PRZR spray available.

o Spray PRZR with maximum spray.

o Close spray valves when step 18 criteria met.

o Stop 12 SI pump.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES NOTE The operator will have to perform the following to align Safeguards Components for Safety Injection:

CS #

COMPONENT DESIRED CONDITION (Normally Aligned in Att. L) 46064 MV-32115, 122 SFP HX INLT HDR MV B CLOSED CV-31079 thru CV-31082 (TURBINE DRAIN VALVES)

OPEN 46338 STEAM DUMP MODE STM PRESS 46018 11 CFCU SLOW 46019 13 CFCU SLOW (Align due to Malfunctions) 46184 11 RHR PUMP ON 46185 12 RHR PUMP ON 46039 LOOP A/B CLG WTR HDR XOVR VLV A MV-32144 CLOSE 46144 LOOP A/B CLG WTR HDR XOVR VLV B MV-32159 CLOSE 46519 121 CLG WTR HDR VLV C MV-32036 CLOSE 46509 121 CLG WTR HDR VLV D MV-32037 CLOSE 46336 12 DDCLWP MAN/AUTO MANUAL 46053 12 DDCLWP START 46537 22 DDCLWP MAN/AUTO MANUAL 46523 22 DDCLWP START BOP (C)

SS (C) 1E-0 Attachment L: SI Alignment Verification:

Verify Safeguards Component Alignment o

See table on page 17 Close MV-32115, 122 SFP HX INLT HDR MV B Check Cooling Water Header Pressures Verify plant announcements complete Check If Main Steamlines Are required to be isolated Verify SI & RHR Flow Check RCP Cooling Verify Generator Breakers - OPEN Verify All Heater Drain Pumps - STOPPED Open turbine drain valves Verify Main Feedwater Alignment Verify All Condensate Pumps - STOPPED Place Steam Dump in "STM PRESS" Mode Verify Unit 1 Cooling Water/Chilled Water Alignment Verify 11 Safeguards Screenhouse Ventilation lineup Verify Control Room Ventilation Alignment 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

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES END Once the crew has cooled down & depressurized 11 SG and stopped the 12 SI pump, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew that training has the duty.

Booth Operator:

Collect SBT data per Attachment 1.

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SIMULATOR INPUT

SUMMARY

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Simulator Setup:

Beginning of Day:

___ 1.

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.

___ 2.

Log in on floor PCs with user ID & password: <pitrgsim>

___ 3.

Update or Verify Control Room Placards:

a. NRC Code Placard:

i. NRC Current Authentication Code D3RF.

ii. Todays Date.

b. High Flux at Shutdown Alarm Setpoint placards: 5000 cps.

c. Feedwater regulating valve position placard set to current values.

d. Recommended SG Blowdown flow set to current values.

___ 4.

Verify Current Plant Status Magnetic Placards are in Place:

a. Blowdown 46470 SGB to CDSR

b. H2 in VCT Space

c. 11 BA TANK Lined Up for Service

d. 11 BA PUMP Lined Up to 11 BA Tank

e. 12 BA PUMP Lined Up to 11 BA Tank

f. CC to SFP MV-32115 In Service

g. CC to SFP MV-32117 In Service

___ 5.

Current Plant Pink Status Control Tags in place:

a. CS-46540, 22 CC WTR PUMP

b. CS-46572, 121 SFP HX INLT

___ 6.

Current Plant Yellow Caution Tags in place:

a. NONE

___ 7.

Verify that copy machine and printers are loaded with YELLOW BORDER paper.

___ 8.

Pens/Notepads/Markers available on the simulator.

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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 this is the first scenario of the day, then perform Beginning of Day checklist on previous page.

___ 2.

Reset the Simulator to IC-253 and go to step 4.

___ 3.

If IC-253 is not available, then perform the following:

a. Reset the Simulator to IC-12 and place in RUN.

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

c. Verify RMU DEGAS sign is on 22 RMU Pump.

___ 4.

Place the simulator in RUN.

___ 5.

If available, run schedule file PI-ILT-NRC-2003S.sch as follows:

a. Locate schedule file.

b. Open schedule file by double clicking it.

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

d. 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 per Attachment 1.

___ 8.

Complete the "Simulator Setup Checklist on next page

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SIMULATOR SETUP CHECKLIST Pre-Scenario Checklist:

Simulator Status:

___1.

"Training Load"

___2.

Alarm sound ON

___3.

Speed: REAL

___4.

Step counters: NOT USED

___5.

Simulator running in IC-253 or IC-12.

___6.

Steps 1 - 7 on previous page complete.

Delete memory on Yokogawa Model DX1000 recorders by cycling Recorder Power.

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

Verify that control rod step counters on C panel and ERCS RBU CBD @ 178.

Boric Acid/RMU integrators set to: BA: 0, RMU: 20, and reset.

EOC I sheet displayed on C panel.

EOC Reactivity Briefing sheet available at Reactor Operator Desk.

Verify Boric Acid and Reactor Makeup Controllers are set properly:

___ 1.

1HC-110: 2.1%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a.

RCS boron - 230 ppm.

b.

RCS H2 - 45 cc/kg.

c.

Turbine Reference Value and Mode - matched with DEHC.

___ 2.

Shift Reactivity Guidance placard:

a.

BA: 0.3 gallons

b.

RMU: 67 gallons

c.

Dilutions: 20 gal RMU, 1-2 times per shift

___ 3.

EAL Classification Placard CLEANED and placed on side of SS desk.

___ 4.

LCO Timer CLEANED.

SEG specific Magnetic Placards in place:

___1.

NONE SEG specific or Protected Equipment Pink Status Control Tags in place:

___1.

CS-46425, 12 MD AFWP

___2.

CS-46185, 12 RHR PUMP

___3.

CS-46179, 12 SI PUMP

___4.

CS-46037, 12 CC WTR PUMP

___5.

CS-46523, 22 CLG WTR PUMP (DIESEL)

___6.

CS-46930, D2 DIESEL GENERATOR SEG specific or Out of Service Yellow Caution Tags are in place:

___ 1. CS-46178, 11 SI PUMP

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Pre-Scenario Checklist continued:

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 (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 - VENT).

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

___ 4.

DEHC alarms cleared.

Verify DEHC VPL set ~0.1 to 0.3 above current valve position (not on limiter).

YELLOW turnover sheets 1-9 available.

Electronic PINGP 577 forms and TABS closed on both LAN connected PCs.

Board-mounted EAL Tables are cleaned.

Headsets turned on as necessary.

Perform one of the following:

Clear web browser history and recent procedures in pdf.

Complete post-scenario checklist.

Procedure checklist completed. See following page.

Peer Check performed for simulator setup.

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PROCEDURE CHECKLIST:

Before 1st / 2nd After 1st / 2nd

/

1C5 AOP1, UNCONTROLLED ROD MOTION

/

1C5 AOP1 CRITICAL PARMETER CARD

/

1C12.1, LETDOWN, CHARGING, AND SEAL WATER INJECTION - UNIT 1

/

1C51.2, TURBINE 1ST STAGE PRESSURE1P-485 - LOW

/

1C51.2, PRESSURIZER LEVEL 1L-427 - LOW

/

C13.1, REACTOR MAKEUP SYSTEM

/

C47012-0104, REACTOR COOLANT SYSTEM HI TAVG

/

C47012-0304, REACTOR COOLANT SYSTEM TAVG DEVIATION

/

C47012-0604, REACTOR COOLANT SYSTEM T DEVIATION

/

C47013-0305, AUCTIONEERED TAVG-TREF DEVIATION

/

1E-0, REACTOR TRIP OR SAFETY INJECTION

/

1E-0 ATT. L, SI ALIGNMENT VERIFICATION

/

1E-3, STEAM GENERATOR TUBE RUPTURE

/

1E-CAS, UNIT 1 CONTINUOUS ACTION & INFO PAGE

SUMMARY

/

LAMINATE COPY OF 1C5, SECTION 5.5

/

LAMINATE COPY OF 1C12.5, SECTIONS 5.8, 5.9, & 5.10

/

REACTIVITY BRIEFING SHEET - EOC

/

SWI O-28, NOTIFICATION OF OPS MNGR & NRC RESIDENT INSPECTOR

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S TRM 3.3.4

/

NOTE: 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.

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Post-Scenario Checklist Clear web browser history and recent procedures in pdf.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___1.

CS-46425, 12 MD AFWP

___2.

CS-46185, 12 RHR PUMP

___3.

CS-46179, 12 SI PUMP

___4.

CS-46037, 12 CC WTR PUMP

___5.

CS-46523, 22 CLG WTR PUMP (DIESEL)

___6.

CS-46930, D2 DIESEL GENERATOR 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.

If desired, 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.

Verify the following placards are erased:

CVCS panel Shift Reactivity Guidance LCO Timer NRC Authentication Code

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 26 of 30 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: 8/18/2020 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 Out of Service for corrective maintenance.

T.S. LCO 3.5.2 Condition A has been entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining.

11 SI Pump is expected to be returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

PROTECTED EQUIPMENT SFP COOLING 12 MD AFW PUMP 12 RHR PUMP 12 SI PUMP 12 CC PUMP 22 CL WTR PUMP D2 DIESEL GENERATOR RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure:

EOC Pressure:

2235 PSIG Unit 2 is at 100% power.

Power:

60%

Xenon:

Equilibrium Unit 1 power was reduced from 100% to 60% 7 days ago for plant maintenance.

Boron (CB):

230 PPM Rods:

CBD @ 178 TAVG:

554°F Generator: 338 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT Prior to entering the Simulator, perform a Pre-Job Brief for the following:

o Swap running RMU pumps per C13.1.

After taking the duty, swap running RMU pumps per C13.1 and PJB.

NEW PROCEDURES / INSTRUCTIONS

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 27 of 30 PI-ILT-NRC-2003S, 2020 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

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 performance tools.

Yes No X

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No X

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No X

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No X

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. Justification: PRA software not installed on Sim computers.

Yes No X

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No X

7. The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No X

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No X

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No X

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Yes No X

11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 28 of 30 PI-ILT-NRC-2003S, 2020 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

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 respect to reactor status, plant configuration, and system operation.

Yes X

No

2. The simulator operated in real time during conduct of validation.

Yes X

No

3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes X

No

4. The simulator permitted use of the reference plants procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes X

No

5. The simulator did not fail to cause or unexpectedly cause any first principle alarm or primary automatic action.

Yes X

No

6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plants expected response.

Yes X

No

7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plants response to the initiating cause.

Yes X

No

8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X

No

9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes X

No

10. Simulator fidelity has been demonstrated to be adequate for this scenario.

Yes X

No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 29 of 30 PI-ILT-NRC-2003S, 2020 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

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 SNYDER SRO SS STRAIN RO BOP PARADA SRO ATC

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ATTACHMENT 1 SBT EXAM DATA COLLECTION BEFORE SCENARIO o START menu o SBT Report o File o OPEN o Select file type.tis (FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT o Select SBT.tis o OPEN or double click o Check TAM log & verify no cycling switches o Run scenario AFTER SCENARIO o FREEZE on Simulator o Click GREEN arrow to generate report o Enter the following:

(NAME is not required)

Test Title (2003S ILT NRC SBT Group x)

Report Name (same as test title) o Click the button to right of Report Name field.

o Select location where file is to be saved (on Locker G3 flash drive) o Enter file name (same as report name) & SAVE o Click GENERATE, verify file location, and close html file o START menu o COMPARE IT o Click + ADD o Select.csv file from previously saved location o OPEN or double click o Click GREEN COMPARE button o Wait for spreadsheet to populate and then save in desired location o Close spreadsheet, COMPARE IT, and SBT Report o Verify all 3 files are saved in proper location

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