Text

2018 PI Ile Proposed Simulator Scenarios
	ML22179A321
Person / Time
Site:	Prairie Island
Issue date:	08/08/2018
From:	Randy Baker; NRC/RGN-III/DRS/OLB
To:	; Nuclear Management Co
	Baker R
Shared Package
ML17165A322	List: ML22179A316; ML22179A318; ML22179A321; ML22179A323; ML22179A327; ML22179A330; ML22179A331; ML22179A332;
References
	Download: ML22179A321 (122)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 1 Op-Test No.: PI-ILT-NRC-1801 Facility: PRAIRIE ISLAND Examiners:

Operators: Shift Supervisor Lead Reactor Operator Reactor Operator Initial Conditions:

Reactor Power at 1x10-8 amps, Boron Concentration at 1346 ppm, RCS temperature at 549°F, RCS pressure at 2235 psig, Xenon free prior to startup, Bank D rods at 140 steps, Generator Power at 0 MW. Backup pressurizer heaters are ON. Two 40 GPM letdown orifices are in service.

No equipment out of service.

Turnover:

Raise reactor power to the point of adding heat.

Secure 12 MD AFW Pump.

Event No.

Malf.

No.

Event Type*

Event Description 1

R (ATC)

N (SRO)

RAISE POWER TO THE POAH 2

N (BOP)

SECURE 12 MD AUXILIARY FEEDWATER PUMP 3

I (ATC, SRO)

TS (SRO)

PRZR LEVEL WHITE (INTRLK) CHANNEL FAILS HIGH 4

C (BOP, SRO)

TS (SRO)

B PRZR PORV LEAKAGE 5

M (ALL) 12 STEAM GENERATOR TUBE RUPTURE 6

C (BOP) 11 & 12 SAFETY INJECTION PUMPS FAIL TO START AUTOMATICALLY 7

C (BOP)

CTMT ISOLATION RELAY AUTO ACTUATION FAILURE (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 of 29 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-1801S SEG TITLE:

2018 ILT NRC SIMULATOR EVALUATION #1 REV. #

0 PROGRAM:

INITIAL LICENSE OPERATOR TRAINING FL-ILT COURSE:

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

Developed by:

Fredrick Collins 1/7/2018 Instructor Date Reviewed by:

Justin Hasner 6/7/2018 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Justin Hasner 6/7/218 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Shawn Sarrasin Training Supervision Date

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

Guide Requirements Evaluation Objectives:

Evaluate the crews ability to:

1.

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

2.

Secure 12 MDAFW Pump per 1C28.1.

Evaluate the crews ability to diagnose and respond to:

3.

Pressurizer Level Instrument failing high per 1C51.2.

4.

Pressurizer PORV Leakage per C47012.

5.

12 Steam Generator Tube Rupture per 1E-0 & 1E-3.

6.

Failure of SI Pumps to automatically start per 1E-0.

7.

CTMT Isolation relay automatic actuation failure 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 (3.8%)

Important Components:

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

CRO 301 004 06 01 000 - Operator fails to diagnose SGTR and close ruptured SG MSIV and AFW flow from MCR.

CRO 301 004 06 01 000 - Operator fails to C/D and depressurize RCS for a SGTR before SG overfill.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1L-427, White Channel Pressurizer Level Transmitter, fails HIGH.

2. Pressurizer PORV, PCV 431C, Leakage.

After EOP Entry:

1. Train A and B Safety Injection Pumps fail to automatically start.

2. CTMT Isolation Train A relay fails to automatically actuate after SI Signal.

Abnormal Events:

1. Instrument Failure Guide.

2. AOP for RCS leakage.

Major Transients:

1. 12 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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%]

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure: MOC N51 and N52 Displays Power: 1x10-8 amps Boron: (CB): 1346 ppm Temperature: 547°F Pressure: 2235 psig Xenon: Xe Free Rods: D @ 135 Generator: 0 MW SEQUENCE OF EVENTS:

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

Reactor power is at 1 x 10-8 amps.

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

Power will rise to between 0.5% and 2%.

Event 2: Secure 12 MDAFW Pump

The crew will stop 12 MD AFW Pump per 1C28.1 and place in AUTO.

Event 3: 1L-427, White Interlock Channel Pressurizer Level, fails HIGH.

PRZR Level White (Interlock) Channel 1L-427 will fail high.

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 4: PRZR PORV Leakage

PORV PCV-431C will develop seat leakage.

PRZR Relief Line temperatures will rise.

The crew will respond per C47012 & isolate the leak using MV-32195.

The Shift Supervisor will enter TS LCO 3.4.11 Condition A.

Event 5: 12 Steam Generator Tube Rupture

12 SG level will rise, RCS pressure and PRZR level will lower.

Condenser air ejector radiation will alarm before failing off-scale high.

The crew will isolate 12 SG, C/D and depressurize the RCS, and stop both SI pumps.

Event 6: 11 & 12 safety Injection Pumps Fail to Start Automatically

Both SI pumps will fail to start on SI actuation.

The crew will start both SI pumps manually.

Event 7: CTMT Isolation Relay Fails to Automatically Actuate

CTMT Isolation Train A fails to actuate on SI actuation.

The crew will manually actuate CI and/or manually align components.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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 EVENT 1 Booth Operator / Communicator:

1. After the crew has assumed the duty, they will raise power to the Point of Adding Heat per pre-job brief.

Plant Response:

1. IR power will rise.

2. Tavg and PRZR level will rise.

3. PR power will come on scale.

RO/SS 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%.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

SCENARIO TIME-LINE:

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

1. After the crew has raised power to the Point of Adding Heat, they will secure 12 MD AFW Pump per pre-job brief.

2. When directed as an out-plant operator to verify 12 MD AFW Pump has stopped, CV-31154 has closed, and Auxiliary lube oil pump is running, then wait approximately 2 minutes and report 12 MD AFW Pump is stopped, CV-31154 is closed, and Auxiliary lube oil pump is running.

3. When directed as an out-plant operator to stop 12 MD AFW Pump Aux Lube Oil Pump, then wait approximately 3 minutes and report Aux Lube Oil Pump has been stopped.

4. If contacted as the duty chemist, acknowledge 12 MD AFW Pump has been stopped.

LEAD 1C28.1, AUXILIARY FEEDWATER SYSTEM UNIT 1:

CLOSE MV-32381, 12 MD AFWP TO 11 STM GEN, using CS-46316.

CLOSE MV-32382, 12 MD AFWP TO 12 STM GEN, using CS-46317.

Stop 12 MD AFW Pump using CS-46425.

Direct an out-plant operator to verify locally:

o 12 MD AFW Pump has stopped.

o CV-31154, 12 MD AFW PMP RECIRC/L-O CLG CV, has CLOSED.

o Auxiliary lube oil pump is running.

Direct an out-plant operator to locally stop 12 MD AFW Pump Aux Lube Oil Pump when 12 MD AFW Pump stops rotating.

OPEN MV-32381, 12 MD AFWP TO 11 STM GEN, using CS-46316.

OPEN MV-32382, 12 MD AFWP to 12 STM GEN, using CS-46317.

Independently verify MV-32381 and MV-32382 are OPEN.

Verify SI Not Ready panel light 44102-B9, 12 AFW DISCH VLV CLOSED, is NOT LIT, indicating the discharge valves are OPEN.

Place CS-46439, 12 MD AFWP selector switch in AUTO.

Independently verify CS-46439 in AUTO.

Notify the Duty Chemist that 12 MD AFW Pump has been stopped.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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 12 MD AFW pump and/or at the discretion of the Lead Evaluator, enter:

Trigger 1, PRZR Level Intlk (White) Channel fails HIGH.

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 notifications to the NRC, Duty Station Manager, etc.

as asked.

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. 1L-427 will indicate off scale high.

2. The following annunciators will be received:

a.

47012-0307, PRZR HI LVL CHANNEL ALERT

b.

47012-0407, PRZR HI LVL LEAD /

U2 LEAD SS C47012-0307, PRZR HI LVL CHANNEL ALERT:

Check pressurizer level.

Control level in manual.

If channel failed, then refer to 1C51.

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

Select position 1-3 (RED-BLUE) on PRZR Level Control switch, CS-46291.

Ensure pressurizer level recorder not selected to white channel.

The SS will evaluate but not enter the following TS LCOs due to inapplicability in MODE 2:

3.3.1 Condition A:

o Enter conditions referenced in Table 3.3.1-1 IMMEDIATELY.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

SCENARIO TIME-LINE:

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

1.

After the crew has placed PRZR level control in R-B and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, PRZR PORV B, PCV-431C, Leakage.

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 the FIN Team Supervisor or RCS Engineer, inform the crew that you will write a work order and investigate.

Plant Response:

1.

Temperature rises on PRZR Safeties.

2.

PRZR PORV outlet temperature rises.

3.

The following annunciators will be received:

a.

47012-0109,

b.

47012-0506, PRZR POWER RELIEF LINE HI TEMP

c.

47012-0509,

d.

47012-0606, PRZR SAFETY VALVE LINE A OR B HI TEMP RO /

LEAD /

SS SS C47012-0506, PRZR POWER RELIEF LINE HI TEMP:

Check PRZR relief line temperature.

Check PRZR pressure.

Isolate CV-31231 by CLOSING MV-32195, PRZR RELIEF ISOL, using CS-46263.

Determine CV-31231 is the leaking PORV and leave MV-32195 closed.

Refer to 1C4 AOP1.

Refer to Tech Spec LCO 3.4.11.

1C4 AOP1, REACTOR COOLANT LEAK:

Determine the reactor does NOT need to be tripped.

Use ERCS LEAK-1 to determine leak rate.

Determine leak location and isolate.

The SS will enter the following TS LCO:

3.4.11 Condition A:

o Close and maintain power to associated block valve in 1 HOUR.

The SS will evaluate the following LCO but should not enter based on IDENTIFIED RCS leakage <10 gallons.

3.4.14 Condition A:

o Reduce leakage to within limits in 4 HOURS.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

EVENTS 5, 6, & 7 Booth Operator / Communicator:

1. When the crew has isolated the leaking PORV and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 3, 12 SG 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 12 SG and reading background on 11 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. If Control Room personnel ask for status of Unit 2 Cooling Water/Chilled Water lineup, then inform the Control Room that Unit 2 Cooling Water/Chilled Water valves are in their safeguards positions.

CRITICAL TASKS Establish at least 250 psid between the ruptured SG and intact SG prior to depressurizing the RCS.

RO /

LEAD /

SS 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify reactor is tripped.

Verify both Safeguards buses energized.

Verify SI actuated due to inability to maintain pressurizer level above 5%.

Perform Attachment L (see SEG page 15).

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 based on increasing SG level with no AFW flow.

Go to 1E-3.

1E-3, STEAM GENERATOR TUBE RUPTURE:

Determine RCPs should NOT be stopped.

Identify 12 SG as the ruptured SG.

Isolate flow from ruptured SG:

12 SG PORV in AUTO at 75%.

12 SG PORV closed.

Close 12 SG steam supply to 11 TD AFWP.

Verify 12 SG Blowdown valves closed.

Close 12 MSIV and bypass valve.

Determine 12 SG narrow range level is >7%.

Stop feed flow to 12 SG.

Reset SI.

Determine 12 SG pressure >290 psig.

Initiate RCS Cooldown:

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Stop the RCS cooldown before an ORANGE or RED path in Integrity CSF occurs.

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

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%.

Plant Response:

1. Reactor and turbine trip.

2. 12 SG level rises rapidly.

3. High condenser air ejector radiation.

4. RCS & PRZR pressure lower.

NOTE The operator will have to perform the following to align safeguards components for SI:

Determine required CETC temperature.

Check steam dump to condenser available.

Start one condensate pump.

Establish steam dump to condenser.

Dump steam to the condenser from intact SG at the maximum rate. When RCS temperature is

<540°F, place SD transfer switches to BYPASS INTERLOCK.

Stop cooldown when CETCs less than required temperature.

Maintain CETCs less than required temperature.

Check 11 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 12 SG pressure stable or increasing.

Determine RCS subcooling greater than 40°F.

Depressurize RCS to minimize break flow & refill PRZR:

Determine normal PRZR spray available.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

SCENARIO TIME-LINE:

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

COMPONENT DESIRED CONDITION (Normally Aligned in Att. L) 46064 MV-32115, 122 SFP HX INLT HDR MV B CLOSED DEHC 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) 46235 RCDT GAS ANALY HDR ISOL CLOSED 46339 A SG BD ISOL, MV-32044 CLOSED 46968 B SG BD ISOL, MV-32043 CLOSED 46054 1 CTMT VACUUM TRN A CV-31621 CLOSED Spray PRZR with maximum spray until PRZR level greater than 75%.

Close spray valves.

Determine SI pumps can be stopped.

Stop 11 & 12 SI 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 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 Verify Main Feedwater Alignment Verify All Condensate Pumps - STOPPED 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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EMERGENCY PLAN CLASSIFICATION ALERT - FA1 due to SGTR which results in an ECCS actuation.

Check Status of Notifications Notify SS Of Any Discrepancies END Once the crew has stopped SI pumps, 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 INPUT

SUMMARY

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 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 RYLC.

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 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

___ 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 Setup:

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

CAUTION: A reactivity and temperature transient will occur if 1HC-484, MAIN STM HDR PRESS (STM DUMP), is NOT set to ~71.8% when the simulator is taken to RUN. 1HC-484 has an error of +/- of ~2%. Validation data and conversations with Sim Engineer suggests dial should be closer to 70% to avoid transiet.

___ 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 1 x 10-8 amps and stable.

g. Insert Remote SG100 to CW.

h. For 12 MD AFW Pump, perform the following:

i. Close MV-32381, 12 MD AFWP TO 11 STM GEN, using CS-46316.

ii. Close MV-32382, 12 MD AFWP TO 12 STM GEN, using CS-46317.

iii. Place CS-46439, 12 MD AFWP, to MANUAL.

iv. Start 12 MD AFWP using CS-46425.

v. Throttle MV-32381 and MV-32382 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 IC-241 or to another available IC.

o. Go to step 4.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 Setup cont.:

___ 4.

Reset the Simulator to IC-241 or other IC created from Step 3.

___ 5.

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

___ 6.

Place the simulator in RUN.

___ 7.

If available, run schedule file PI-ILT-NRC-1801S.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.

___ 8. If schedule file is NOT available, then insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

___ 9.

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

___ 10.

Markup sections 5.1 - 5.6.9 of 1C1.2 - BOP as complete.

___ 11.

Markup sections 5.1 - 5.4.1 of 1C1.2 - M2 as complete

___ 12.

Complete the "Simulator Setup Checklist on next page.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 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-241.

___6.

Steps 1 - 11 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 @ 135.

Boric Acid/RMU integrators set to: BA: 0, RMU: 10, 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: 29.8%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 1346 ppm.

b. RCS H2 - 25 cc/kg.

c. Turbine Reference Value and Mode - 0.

___ 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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 22 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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 - LEFM).

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 0.2 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.

Procedure checklist completed. See following page.

Peer Check performed for simulator setup.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 23 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

PROCEDURE CHECKLIST:

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

/

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

/

1C4 AOP1, REACTOR COOLANT LEAK

/

1C28.1, AUXILIARY FEEDWATER SYSTEM UNIT 1

/

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

/

C47012-0109,

/

C47012-0307, PRZR HI LVL CHANNEL ALERT

/

C47012-0407, PRZR HI LVL

/

C47012-0506, PRZR POWER RELIEF LINE HI TEMP

/

C47012-0509,

/

C47012-0606, PRZR SAFETY VALVE LINE A OR B HI TEMP

/

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

/

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

/

REACTIVITY BRIEFING SHEET - MOC

/

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

/

SWI O-50, REACTIVITY MANAGEMENT

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S. LCO 3.4.11

/

T.S. LCO BASES 3.4.11

/

T.S. LCO 3.4.14

/

T.S. LCO BASES 3.4.14 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 24 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

Post-Scenario Checklist EOOS computer is cleared of information added during the scenario.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___ 1.

NONE Magnetic placards removed:

___ 1.

NONE Remove Yellow Caution Tags from the following equipment:

___ 1.

NONE 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 25 of 29 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:

DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

1. N51 and N52 displays are OOS.

TS LCO 3.3.3 Condition A was entered with 23 days remaining.

TS LCO 3.3.3 Condition D was entered with 5 days remaining.

N51 and N52 counts can be viewed in ERCS.

PROTECTED EQUIPMENT RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure: MOC Power: 1x10-8 amps (MODE 2)

Boron: (CB): 1346 ppm Temperature: 547°F Pressure: 2235 psig Xenon: Xe Free prior to startup Rods: D @ 135 Generator: 0 MW Two 40 GPM Letdown Orifices are in service.

Backup Pressurizer Heaters are ON.

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 Raising reactor power to the POAH per section 5.4 of 1C1.2 - M2.

o Securing 12 MDAFW Pump per step 5.6.10.A of 1C1.2-BOP and section 5.4 of 1C28.1.

Out-plant operator is already briefed on evolution.

After turnover, raise Reactor Power to the POAH.

After Reactor Power is at the POAH, secure 12 MDAFW Pump and place in AUTO.

Sections 5.1 - 5.6.9 of 1C1.2 - BOP, UNIT 1 BALANCE OF PLANT SYSTEMS STARTUP, are complete.

Sections 5.1 - 5.4.1 of 1C1.2 - M2, UNIT 1 STARTUP TO MODE 2, are complete.

NEW PROCEDURES / INSTRUCTIONS Once reactor power is at POAH, maintain reactor power between 0.5% and 2.0% (MODE 2).

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 26 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 27 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 28 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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 Jeff Human SM / SRO SS Jason Snyder SS / SRO LEAD Mike Helland RO / RO RO Fredrick Collins NRC Exam Developer Floor Instructor Justin Hasner Senior Ops Instructor Booth Driver

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 29 of 29 PI-ILT-NRC-1801S, 2018 ILT NRC SIMULATOR EVALUATION #1, 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.

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 (1801 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

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 Op-Test No.: PI-ILT-NRC-1802 Facility: PRAIRIE ISLAND Examiners:

Operators: Shift Supervisor Lead Reactor Operator Reactor Operator Initial Conditions:

Reactor Power at 60%, Boron Concentration 217 ppm, RCS temperature 554°, RCS pressure 2235 psig, Xenon at equilibrium, Bank D rods at 178 steps, Generator power at 336 Mw.

11 TD AFW Pump is out of service. T.S. LCO 3.7.5 Condition B entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining. 12 MD AFW Pump is protected.

Turnover:

Place a 2nd 40 gpm Letdown orifice in service in preparation for reactor up power.

Raise reactor power to 60%.

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

PLACE 2nd LETDOWN ORIFICE IN SERVICE 2

R (ATC)

N (SRO)

RAISE RX POWER FROM 50% TO 60%

3 I (ATC, SRO)

TS (SRO)

CONTROLLING PRZR PRESS CH FAILS LOW 4

C (BOP, SRO)

TS (SRO)

SI ACCUMULATOR LEAKAGE 5

M (ALL)

LBLOCA, w/ TRANSFER to RECIRCULATION 6

C (BOP)

SAFETY INJECTION PUMPS FAIL TO AUTO START 7

C (BOP)

SI TO CC RELAY ACTUATION FAILURE 8

C (ATC) 12 MDAFWP AUTO START FAILURE (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 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.

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG #

PI-ILT-NRC-1802S SEG TITLE:

2018 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 1/28/2018 Instructor Date Reviewed by:

Justin Hasner 6/7/2018 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Justin Hasner 6/7/218 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Shawn Sarrasin Training Supervision Date

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

Guide Requirements Evaluation Objectives:

Evaluate the crews ability to:

1.

Place a Second Letdown Orifice in Service per 1C12.1.

2.

Raise Reactor Power from 60% to 70% per 1C1.4.

Evaluate the crews ability to diagnose and respond to:

3.

Pressurizer Pressure Instrument failing Low per 1C51.3.

4.

SI Accumulator Leakage per 1C18.

5.

Large Break LOCA & Transfer to Recirc per 1E-1 & 1ES-1.2.

6.

Failure of SI Pumps to automatically start per 1E-0.

7.

SI to CC relay automatic actuation failure per 1E-0.

8.

12 MDAFW Pump automatic start failure 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:

LOCA (14.3%)

Important Components:

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

CRO 008 ATI 00 00 007 - Operator fails to perform initial actions of C14 AOP1 upon Loss of CC.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1PT-431, Blue Channel Pressurizer Pressure Transmitter, fails LOW.

2. 11 Safety Injection Accumulator Relief Valve Leakage.

After EOP Entry:

1. Train A and B Safety Injection Pumps fail to automatically start.

2. SI to Component Cooling relay signal fails to automatically actuate.

Abnormal Events:

1. Instrument Failure Guide.

2. ARP/C Procedure for SI Accumulator leakage.

Major Transients:

1. LBLOCA w/ Transfer to Recirc Critical Tasks:

1. PI-CT-13: Manually start at least one CC Pump before the end of the scenario.

2. PI-CT-24: Transfer to cold leg recirculation and establish ECCS recirculation flow before an ORANGE or RED path in Core Cooling CSF occurs.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

CRITICAL TASK SHEET Number:

PI-CT-13 Critical Task:

Manually start at least one CC Pump before the end of the scenario.

Safety Significance:

Operation of the ECCS injection pumps without Component Cooling Water could lead to pump failure or damage. This would result in a degraded emergency core cooling system (ECCS) capacity.

Plant Conditions:

Safety Injection.

Both Component Cooling Water Pumps are NOT running.

At least one Component Cooling Water Pump can be started from the Control Room.

Cues:

Indication that Safety Injection actuated.

SI ACTIVE lights are NOT lit for both CC Pumps.

Component Cooling Water Discharge pressure reads zero.

Component Cooling Water Low Flow alarms to ECCS Pumps.

Performance Indicator:

Starting one or both CC Pumps by operating the following switches:

o CS-46036, 11 CC WTR PUMP.

o CS-46037, 12 CC WTR PUMP.

Feedback:

SI ACTIVE lights are LIT for at least one CC Pump.

Component Cooling Water Low Flow alarm clears for at least one train of Safeguards components.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

CRITICAL TASK SHEET Number:

PI-CT-24 Critical Task:

Transfer to cold leg recirculation and establish ECCS recirculation flow before an ORANGE or RED path in Core Cooling CSF occurs.

Safety Significance:

If the ECCS system is not transferred to recirculation mode, a loss of the ECCS pumps will occur when RWST level is lost. Subsequently, if recirculation is not established, a loss of water inventory in the core will occur and fuel temperatures will rise. This will result in damage to the fuel cladding barrier.

Plant Conditions:

Large Break LOCA inside Containment.

RWST level is less than 33%.

Containment level greater than 2.25 feet OR Sump B level greater than 82%.

At least one train of ECCS recirculation equipment is available and can be operated from the Control Room.

Cues:

SI Actuation.

RWST level less than 33%.

Containment Level greater than 2.25 feet.

Sump B level greater than 82%.

Performance Indicator:

Manipulation of the following controls, as required, to align at least one train of ECCS to cold leg recirculation:

o Close RWST to RHR Isolation Valve.

o Close at least one SI Test Line to RWST Valve.

o Open CC to RHR HX.

o Open Sump B to RHR Isolation Valve.

o Restart RHR Pump.

Feedback:

RHR flow for the train aligned for recirculation.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure: EOC N51 and N52 Displays Power: 60%

11 TDAFW Pump Boron: (CB): 217 ppm Temperature: 554°F Pressure: 2235 psig Xenon: Xe Free Rods: D @ 178 Generator: 336 MW SEQUENCE OF EVENTS:

Event 1: Place 2nd Letdown Orifice in Service

Initially, there is only 1 40 gpm letdown orifice & 2 charging pumps in service.

There are already two charging pumps running.

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

Event 2: Unit 1 Load Increase from 60% to 70% Power

The crew will stop 12 MD AFW Pump per 1C28.1 and place in AUTO.

Event 3: Controlling Pressurizer Pressure Channel fails LOW

1PT-431 fails low.

Both spray valves close and PRZR heaters energize.

The crew will take manual control of PRZR pressure and select WHITE/RED on selector switch.

The Shift Supervisor will address TS LCO 3.3.1 and TS LCO 3.3.2.

Event 4: SI Accumulator Relief Valve Leakage

11 SI Accumulator pressure will lower and low pressure annunciator will be received.

The crew will raise pressure in 11 SI Accumulator per 1C18.

The Shift Supervisor will address TS LCO 3.5.1 and TS LCO 3.6.3.

Event 5: Large Break Loss of Coolant Accident

A large break LOCA occurs on the B Hot Leg. The reactor will trip and the crew will enter 1E-0.

Containment Pressure rises, RCS pressure and Pressurizer level rapidly lowers.

The crew will transition into and out of 1FR-P.1 when a red path in integrity CSF occurs.

The crew will diagnose a Loss of Coolant Accident, trip RCPs, and transition to 1E-1.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

Event 5: Transfer to Cold Leg Recirculation:

RWST level will lower due to RHR, Charging, and CS flow.

The crew will transfer one train of RHR to low head recirc per 1ES-1.2.

Event 6: 11 & 12 Safety Injection Pumps Fail to Start Automatically

Both SI pumps will fail to start on SI actuation.

The crew will start both SI pumps manually.

Event 7: Loss of Component Cooling

After the Safety Injection, both Component Cooling Water Pumps will fail to automatically start.

The crew will manually start Component Cooling Water Pumps per Attachment L of 1E-0.

Event 8: 12 MDAFW Pump Automatic start Failure

The 12 MDAFW pump will fail to automatically start after SI is actuated.

The crew will manually start the 12 MDAFW pump per 1E-0.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

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 place a second 40 gpm letdown orifice in service per section 6.10 of 1C12.1.

2. If contacted as the RP Tech or Duty Chemist, acknowledge a 2nd letdown orifice is being placed in service and implement radiation surveys per PINGP 1841.

3. If contacted as the Duty Chemist, acknowledge purification flow has been raised.

RO /

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

Notify RP Tech that an additional letdown orifice is being placed into service.

Determine steps 6.10.2 through 6.10.8 are not applicable due to two charging pumps already running.

Place 11 Charging Pump in manual speed control.

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

o Increasing charging pump speed.

o Maintain 8 gpm seal injection to each RCP.

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

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

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

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

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

Notify the Duty Chemist that purification flow has been raised

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

EVENT 2 Booth Operator / Communicator:

1. After the crew has placed a 2nd 40 gpm letdown orifice in service, they will raise reactor power to 70% per 1C1.4.

2. If contacted as the duty chemist, acknowledge Unit 1 power will be raised from 60% to 70%.

NOTE It is NOT intended to wait for the plant to reach 70%

power prior to proceeding to the next event. Once the Lead Evaluator is satisfied with the reactivity manipulation, proceed to Event 3.

RO /

LEAD /

SS 1C1.4, UNIT 1 POWER OPERATION:

Notify Duty Chemist of the load increase.

Verify ERCS TPM Power Source is NIS power.

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

Using the On Line Control screen:

o Select LOAD.

o Select 0.5% demand rate.

Verify the VPL control is not Red.

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

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

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

When Tave shows an increase, then select the Go control using the On Line Control screen.

Adjust the alternate dilution rate or perform alternate dilutions per 1C12.5 to maintain Tave and Tref with the desired +/-1.5°F band 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL Verify 1YIC-111, RX MU WTR TO BLENDER BATCH INTEGRATOR, is reset.

Set 1YIC-111, RX MU WTR TO BLENDER BATCH INTEGRATOR, to quantity desired. ________ gal Place CS-46300, MAKE-UP MODE SELECTOR, to ALT DIL.

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

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

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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES When the desired quantity of makeup has been added, then verify automatic makeup stopped as indicated by CS-46457, BORIC ACID MAKE-UP CONTROL, green light LIT.

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

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

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

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

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

Reset the RMU integrator

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

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 load increase at 70%

and/or at the discretion of the Lead Evaluator, enter:

Trigger 1, PRZR Press (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 notifications to the NRC, Duty Station Manager, etc.

as asked.

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. 1P-431 will indicate off scale low.

2.

PRZR spray valves close.

3.

PRZR Pressure rises.

4.

Tavg rises.

5.

The following annunciators are received:

a.

47012-0108, PRZR LO PRESS SI CHANNEL ALERT.

b.

47012-0408, PRZR HI/LO PRESS CHANNEL ALERT LEAD/

RO SS LEAD SS C47012-0108, PRZR LO PRESS SI CHANNEL ALERT:

Check PRZR 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:

If the Blue channel is selected on the PRZR Pressure Control Selector Switch, then:

o Place PRZR Press Cont in MANUAL and stabilize o Select 2-1 (WHITE/RED) on channel sel sw o When press returned to normal w/ no deviation from setpoint, then return to automatic.

Verify PRZR Press Rec. not selected to Blue channel.

The SS will enter the following TS LCOs:

3.3.1 Condition A o Reference Table 3.3.1-1 immediately.

3.3.1 Condition E o Place channel in trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR o Be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 3.3.2 Condition A o Reference Table 3.3.2-1 immediately.

3.3.2 Condition D o Place channel in trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR o Be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND o Be in Mode 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months Trip bistables

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

SCENARIO TIME-LINE:

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

1.

After the crew has placed PRZR level control in R-B and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, SI Accumulator Relief Valve Leakage.

2. When contacted by Control Room via hand-held radio:

a.

When directed to set CV-31241 to control 800-825#,

then wait one minute and report completion.

b.

When directed to open NG-1-1, then wait one minute and report completion.

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, inform the crew that you will write a work order and investigate.

5. When the crew has raised pressure in 11 SI Accumulator, then enter Trigger 12 to remove malfunction.

Plant Response:

1.

11 SI Accumulator pressure lowers.

2.

The following annunciator will be received:

a. 47018-0203, 11 ACCUMULATOR HI/LO PRESS RO /

LEAD /

SS SS C47018-0203, 11 SI ACCUMULATOR HI/LO PRESS:

Check pressure high or low.

If pressure is low, then raise pressure per 1C18.

1C18, ENGINEERED SAFEGUARDS SYTEM UNIT 1:

In the Gas House, set CV-31241 to control at 800 to 825 psig.

Open NG-1-1.

Verify CV-31242 is closed using 1HC-945 at 0 position.

Enter TS LCO 3.6.3 Conditions A & B.

Open CV-31441 using CS-46219.

Open CV-31440 using CS-46212.

When accumulator pressure reaches 750 psig, then close CV-31440.

Close CV-31441.

Exit TS LCO 3.6.3 Conditions A & B.

The SS will enter the following TS LCO:

3.5.1 Condition B:

o Restore accumulator to OPERABLE status in 24 HOURS.

NOTE:

SI Accumulator malfunction takes approx. 5 minutes to alarm. Consider entering trigger while crew is completing previous event.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

EVENTS 5, 6, 7, &

8 EVENTS 5, 6, 7, &

8 cont.

Booth Operator / Communicator:

1. When the crew has raised pressure in the 11 SI Accumulator and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 3, LBLOCA.

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 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.

Plant Response:

1. RCS pressure lowers.

2. Pressurizer Level lowers.

3. RCS Leak rate rises.

4. Containment Pressure rises.

CRITICAL TASKS RO /

LEAD /

SS 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify reactor is tripped.

Verify main turbine.

Verify both Safeguards buses energized.

Verify SI actuated due to inability to maintain pressurizer level above 5%.

Perform Attachment L (see SEG page 15).

Check AFW Status.

Check RCS Tavg trending to 547°F.

Check PRZR PORVs and Spray valves closed.

Stop both RCPs.

Determine SGs are NOT faulted.

Determine SG tubes are NOT ruptured.

Determine RCS is NOT intact due to Containment pressure rising.

Go to 1E-1.

1E-1, LOSS OF REACTOR OR SECONDARY COOLANT:

STOP both RCPs.

Determine SGs are NOT faulted.

Check intact SG levels.

Control feed flow to maintain WR 50% - 64%.

Check secondary radiation is normal.

Check power to PRZR PORV block valves available.

Check PRZR PORVs are closed.

Check at least one PRZR PORV block valve is open.

Reset SI and Containment Isolation.

Establish Instrument Air to Containment.

Check charging pumps powered from offsite power.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

EVENTS 5, 6, 7, &

8 cont.

Manually start at least one CC Pump before the end of the scenario.

Transfer to cold leg recirculation and establish ECCS recirculation flow before an ORANGE or RED path in Core Cooling CSF occurs.

Booth Operator / Communicator:

1. 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.

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

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

4. 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.

5. When called as the Auxiliary Building Operator to open RD-4-6 and 2RD-4-2, report that these valves are open.

6. When requested to perform Attachment K, then wait 2 minutes and perform the following:

a. Enter Trigger 13, Att. K Out-Plant Actions.

b. Inform CR when all actions are complete Check at least one charging pump is running.

Determine SI should NOT be terminated.

Determine RHR pumps should NOT be stopped.

Check if DGs and SG CL pumps should be stopped.

Determine Train A available for recirc.

Start all CTMT dome recirc fans.

Open one train of CR alt outside air dampers.

Align CFCU CLG water rad monitors.

Stop SFP ventilation.

Notify ABO to perform 1ES-1.2 Att. K.

When RWST level less than 33%, then GO TO 1ES-1.2.

1ES-1.2, TRANSFER TO RECIRCULATION:

Notify ABO to perform ATTACHMENT K.

Reset SI.

Reset Containment Spray.

Stop safeguards pumps for train going to recirc.

Close RWST to RHR isolation valve.

Close SI Test Line to RWST MV-32202 & MV-32203 Verify RHR to Reactor Vessel Injection valve alignment: MV-32064 & MV-32065 OPEN Align CC to RHR HX for RHR train going to recirc.

Check CTMT level greater than 2.25 feet.

Check if RHR suction can be aligned to CTMT sump.

Check if second CS pump can be stopped.

Stop SFP Ventilation System.

Place selected RHR in recirculation operation:

o Verify Sump B to RHR isolation valves are FULL OPEN.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

EVENTS 5, 6, 7, &

8 cont.

NOTE The operator will have to perform the following to align safeguards components for SI:

CS #

COMPONENT DESIRED CONDITION (Normally Aligned in Att. L) 46064 MV-32115, 122 SFP HX INLT HDR MV B CLOSED DEHC 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) 46425 12 MDAFW PUMP RUNNING 46178 11 SI PUMP RUNNING 46179 12 SI PUMP RUNNING 46036 11 CC PUMP RUNNING 46037 12 CC PUMP RUNNING 46029 11 CC HX OUTL XOVR ISOL CLOSED 46032 12 CC HX OUTL XOVR ISOL CLOSED o

Start RHR Pump.

o Check for low head recirc:

RCS pressure less than 275 psig [575psig]

RHR flow greater than 1000 gpm Stop RHR & charging pumps aligned to RWST 1E-0 Attachment L: SI Alignment Verification:

Verify Safeguards Component Alignment o See table on page 16 Close MV-32115, 122 SFP HX INLT HDR MV B Check Cooling Water Header Pressures 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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EMERGENCY PLAN CLASSIFICATION SITE AREA EMERGENCY - FS1 due to loss of RCS barrier from LOCA and loss of CTMT barrier from CTMT Isolation actuation failure.

Check status of Spent Fuel Cooling Check Status of Notifications Notify SS Of Any Discrepancies END Once the crew has placed one train of RHR in Low Head Recirculation, 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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 INPUT

SUMMARY

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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 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 RYLC.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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 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-242.

___ 3.

If IC-242 is not available, then perform the following:

a. Reset the Simulator to IC-8 and place in RUN.

b. Place the following equipment in the listed condition:

1) CS-46424, 11 TD AFWP, to PULL TO LOCK.

2) CS-46438, 11 TD AFWP, to MANUAL.

___ 4.

Place the simulator in RUN.

___ 5.

If available, run schedule file PI-ILT-NRC-1802S.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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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 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-242.

___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: 10, 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: 4.0%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 217 ppm.

b. RCS H2 - 25 cc/kg.

c. Turbine Reference Value and Mode - 0.

___ 2.

Shift Reactivity Guidance placard:

a. BA: 0.67 gallons

b. RMU: 67 gallons

c. Dilutions: per reactivity plan

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

___1.

CS-46424, 11 TDAFWP

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 22 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

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 - LEFM).

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 0.2 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.

Procedure checklist completed. See following page.

Peer Check performed for simulator setup.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 23 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

PROCEDURE CHECKLIST:

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

/

C47012-0108, PRZR LO PRESS SI CHANNEL ALERT

/

C47018-0203, 11 ACCUMULATOR HI/LO PRESS

/

1C1.4, UNIT 1 POWER OPERATION

/

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

/

1C12.5, UNIT 1 BORATION CONCENTRATION CONTROL

/

1C14 AOP1, LOSS OF COMPONENT COOLING

/

1C18, ENGINEERED SAFEGUARDS SYSTEM UNIT 1

/

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

/

1E-0, REACTOR TRIP OR SAFETY INJECTION

/

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

/

1E-1, LOSS OF REACTOR OR SECONDARY COOLANT

/

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

SUMMARY

/

1ES-1.2, TRANSFER TO RECIRCULATION

/

EAL Board

/

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

/

LAMINATE COPY OF 1C5, SECTION 5.5

/

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

/

REACTIVITY BRIEFING SHEET - EOC

/

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 3.5.1

/

T.S. LCO BASES 3.5.1

/

T.S. LCO 3.6.3

/

T.S. LCO BASES 3.6.3 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 24 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

Post-Scenario Checklist EOOS computer is cleared of information added during the scenario.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___ 1.

CS-46425, 12 MD AFWP Magnetic placards removed:

___ 1.

NONE Remove Yellow Caution Tags from the following equipment:

___ 1.

CS-46424, 11 TD AFWP 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 25 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:

DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

1. N51 and N52 displays are OOS.

TS LCO 3.3.3 Condition A was entered with 23 days remaining.

TS LCO 3.3.3 Condition D was entered with 5 days remaining.

N51 and N52 counts can be viewed in ERCS.

2. 11 TD AFW Pump is OOS for corrective maintenance on the pump.

TS LCO 3.7.5 Condition B was entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining.

PROTECTED EQUIPMENT 12 MDAFW Pump RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure: EOC Power: 60%

Boron: (CB): 217 ppm Temperature: 554°F Pressure: 2235 psig Xenon: Xe Eq Rods: D @ 178 Generator: 336 MW One 40 GPM Letdown Orifice is in service.

Backup Pressurizer Heaters are ON.

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 Place 2nd Letdown orifice in service per 1C12.1.

o Raise reactor power to 70% per 1C1.4 and provided reactivity plan.

Reactor was operating at 100% power for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to load decrease.

No fuel has been moved.

After turnover, place 2nd letdown orifice in service and perform load increase.

NEW PROCEDURES / INSTRUCTIONS Once reactor power is at 70%, maintain 70% per TSO request.

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.

Reactivity Plan

1. Load INCREASE from 50% to 60%.

2. Current conditions:

Power level:

50% (272 MW)

Xenon:

Equilibrium Control Rod Position:

Bank D @ 168 steps Boron Concentration:

1539 ppm Core Exposure:

1000 MWD/MTU

3. Reactivity Plan:

Target:

Turbine Load: MW (60%)

Rate:

0.50% /minute Control Mode:

FSP control with Rod Control in MANUAL Boration/Dilution:

350 gallon ALT DILUTION (batch)

Final Control Rod Position:

Bank D @ 178 steps

4. Reactivity Prediction:

Change in Power Defect:

-150 pcm (Figure C1-7A)

Differential Boron Worth:

-6.05 pcm/ppm (Figure C1-11A)

Differential Rod Worth:

-4.01 pcm/step (Figure C1-4A)

Calculated RCS PPM change: +18 ppm (110 pcm ÷ -6.05 pcm/ppm)

Calculated Rod Step change: 10 steps (+40 pcm ÷ -4.01 pcm/step)

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 27 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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 Jason Snyder SS / SRO SS Jim Kapsh RO / RO LEAD Mike Helland RO / RO RO

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 30 of 30 PI-ILT-NRC-1802S, 2018 ILT NRC SIMULATOR EVALUATION #2, 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.

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 (1802 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

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 3 Op-Test No.: PI-ILT-NRC-1803 Facility: PRAIRIE ISLAND Examiners:

Operators: Shift Supervisor Lead Reactor Operator Reactor Operator Initial Conditions:

Reactor Power at 100%, Boron Concentration is 828 ppm, RCS temperature 560°, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 218, Generator power at 580 Mw.

11 RHR Pump out of service. T.S. LCO 3.5.2 Condition A was entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining. D2, 12 MD AFW Pump, 12 RHR Pump, 12 SI Pump, 12 CC Pump, and 22 CL Wtr Pump are protected.

Turnover:

Swap CRDM Fans IAW TP 1393 and 1C19.2.

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

SWAP CRDM FANS 2

I (ATC, SRO)

TS (SRO)

TAVG YELLOW CHANNEL FAILS HIGH 3

R (ATC)

N (SRO)

RESTORE TAVG TO TREF 4

C (BOP, SRO)

FAULTY GENERATOR AUTOMATIC VOLTAGE REGULATOR 5

C (ATC, SRO)

TS (SRO)

REACTOR VESSEL O-RING LEAKAGE 6

M (ALL)

FAULTED 12 STEAM GENERATOR TO CONTAINMENT 7

C (BOP)

MAIN TURBINE FAILS TO AUTOMATICALLY TRIP 8

C (BOP)

SI TO FEEDWATER/CONDENSATE RELAY SIGNAL FAILURE (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 of 33 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-1803S SEG TITLE:

2018 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 2/11/2018 Instructor Date Reviewed by:

Justin Hasner 6/14/2018 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Justin Hasner 6/14/2018 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Shawn Sarrasin 6/21/2018 Training Supervision Date

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 33 PI-ILT-NRC-1803S, 2018 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.

Guide Requirements Evaluation Objectives:

Evaluate the crews ability to:

1.

Manual Make-up to the VCT per 1C12.5.

2.

Restore Tavg to Tref after automatic rod motion.

Evaluate the crews ability to diagnose and respond to:

3.

Tcold Yellow Channel Instrument failing High per 1C51.4.

4.

Faulty Automatic Generator Voltage Regulator per C47.

5.

Reactor Vessel O-Ring Inner Seal Leakage per C47012-0603 &

1C4 AOP1.

6.

CTMT Narrow Range Pressure Instrument Failure per 1C51.4.

7.

12 Steam Generator Fault to CTMT per 1E-0 & 1E-2.

8.

Failure of Turbine to automatically trip per 1E-0.

9.

Failure of MSIVs to automatically close per 1E-0.

10. SI to FW/Cond relay automatic actuation failure 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:

Containment HELB (8.4%)

Important Components:

11 RHR PMP Important Operator Actions with Task Number:

CRO 301 003 06 01 000 - Operators fail to isolate AFW to affected SG.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 33 PI-ILT-NRC-1803S, 2018 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.

QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1TE-404B, Reactor Coolant Cold Leg Transmitter Yellow Channel, fails HIGH.

2. Automatic Voltage Regulator Failure.

3. Reactor Vessel O-Ring Inner Seal Leakage.

4. 1P-947, CTMT Pressure Yellow Channel, fails HIGH.

After EOP Entry:

1. Main Turbine fails to automatically trip.

2. MSIVs fail to automatically close.

3. SI to FW/Cond relay signal fails to automatically actuate.

Abnormal Events:

1. Instrument Failure Guide.

2. ARP/C Procedure for VR failure.

3. ARP/AOP for Rx vessel O-ring leakage.

Major Transients:

1. Faulted SG inside CTMT.

Critical Tasks:

1. PI-CT-3B: Secure main steam to the main turbine to prevent the intact Steam Generator from reaching DRYOUT conditions.

2. PI-CT-19: Stop feed flow to the faulted Steam Generator before the end of the scenario.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 33 PI-ILT-NRC-1803S, 2018 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.

CRITICAL TASK SHEET Number:

PI-CT-3B Critical Task:

Secure main steam to the main turbine to prevent the intact Steam Generator from reaching DRYOUT conditions.

Safety Significance:

The uncontrolled depressurization can also cause a loss of feed water to the Steam Generators. This leads to 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.

Plant Conditions:

Reactor trip.

Main Turbine fails to automatically trip.

MSIVs fail to automatically close.

At least one of the following:

o Main Turbine can be tripped from the Control Room

-OR-o MSIVs can be closed from the Control Room.

Cues:

Turbine stop valves indicate open.

Turbine control valves indicate throttled open or full open.

RCS temperature rapidly lowering.

Performance Indicator:

Momentarily pressing CS-46427, TURB TRIP.

-OR-Closing both of the following MSIVs:

o CV-31098, A MAIN STM LINE ISOL, using CS-46158 o

CV-31099, B MAIN STM LINE ISOL, using CS-46159.

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:

Rapid RCS cool down stops.

Main Turbine indicates tripped or both MSIVs indicate closed.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 33 PI-ILT-NRC-1803S, 2018 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.

CRITICAL TASK SHEET Number:

PI-CT-19 Critical Task:

Stop feed flow to the faulted Steam Generator before the end of the scenario.

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.

Cues:

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.

Performance Indicator:

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)

Feedback:

AFW flow to the faulted Steam Generator is secured.

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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure: MOC N51 and N52 Displays Power: 100%

11 RHR Pump Boron: (CB): 828 ppm Temperature: 560°F Pressure: 2235 psig Xenon: Xe Free Rods: D @ 218 Generator: 580 MW SEQUENCE OF EVENTS:

Event 1: Manual Makeup to the VCT The crew will perform a 50 gallon manual makeup to the VCT per 1C12.5.

Event 2: Tavg Cold (Yellow) Channel Fails HIGH

Tcold transmitter 1T-404B will fail high and rods will step in.

Tavg yellow channel will read high.

The crew will enter 1C5 AOP1 and 1C7 AOP1.

The crew will place charging in manual.

The crew will place CS-46249, Tavg Defeat Switch, in YELLOW and then PULL OUT.

per 1C51.4

The Shift Supervisor will enter TS LCO 3.3.1 Conditions A & E, TS LCO 3.3.2 Conditions A & D; and TRM 3.3.3 Condition A.

Event 3: Restore Tavg to Tref

The crew will restore Tavg to Tref using rods in 1-2 step increments per 1C51.4.

Event 4: Automatic Voltage Regulator Failure

The AVR will fail to OFF.

The crew will enter C47006 and place VR CONTROL to OFF & control generator voltage between 19k-21k volts.

Event 5: Reactor Vessel O-Ring Inner Seal Leakage

A 4 gpm leak will develop due to failure in the reactor vessel inner o-ring.

The crew will respond per the ARP and close the flange leak-off isolation.

Event 6: Containment Pressure Yellow Channel (Narrow) Fails High

The crew will respond to C47018-0105 and 1C51.4.

The crew will verify Containment Spray is not actuated.

The crew will enter TS LCO 3.3.2 Conditions A, D, & E.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 33 PI-ILT-NRC-1803S, 2018 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.

Event 7: 12 Steam Generator Fault to CTMT:

12 SG pressure will lower, CTMT pressure and humidity will rise.

The crew will manually actuate Safety Injection per 1E-0.

The crew will isolate 12 SG per 1E-2.

The crew will enter 1E-1 and determine SI can be terminated.

The crew will stop SI & RHR pumps per 1ES-0.2.

Event 8: Main Turbine Automatic Trip Failure

After the reactor trips, the main turbine will fail to automatically trip.

The crew will manually trip the turbine from the control board or manually close MSIVs to stop steam flow.

Event 9: SI to FW / Cond Relay Signal Failure The crew will manually align Feedwater and Condensate system components per 1E-0, Att. L.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 33 PI-ILT-NRC-1803S, 2018 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.

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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 33 PI-ILT-NRC-1803S, 2018 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.

EVENT 1 Booth Operator / Communicator:

1. After the crew has assumed the duty, they will perform a manual makeup to the VCT per 1C12.5.

2. If contacted as the Duty Chemist, acknowledge the order to obtain a boron concentration sample of blender flow.

Plant Response:

1. VCT level and pressure rise.

LEAD 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL Using Boron Addition Program or Figure 1, Blended Flow Nomograph, estimate the setting for 1HC-110, BA TO BLENDER FLOW CONT, to obtain the desired blended flow concentration.

If boration of greater than 50 gallons of Boric Acid, then monitor BAST level changes to ensure the proper amount of acid is being added.

Verify the boric acid and reactor makeup flow controllers are in AUTO.

Place CS-46300, MAKE-UP MODE SELECTOR, in MANUAL.

Align the desired Manual Makeup flowpath:

o To add makeup to the VCT Inlet, OPEN CV-31201, BA BLENDER TO VCT INLT, using CS-46454.

Set 1HC-110 auto setpoint dial to setting determined in step 5.5.1.

If desired, then place 1HC-110 in MANUAL and adjust output for desired flowrate.

If desired or if greater than 4000 ppm blended flow is desired, then place 1HC-111 to MANUAL and adjust for desired output.

Set the batch integrators near their maximum settings or to calculated volumes.

o 1YIC, BA TO BLENDER BATCH INTEGRATOR (1.9) o 1YIC-111, RX M-U WTR TO BLENDER BATCH INTEGRATOR (48)

Momentarily place CS-46457, BORIC ACID MAKE-UP CONTROL, to START to initiate manual makeup.

For boration of greater than 50 gallons, monitor BAST level change to ensure the proper amount of boric acid is added.

If adding boric acid, then verify desired boric acid flow rate on one of the following:

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES If adding reactor makeup water, then verify desired makeup water flow rate on one of the following:

o 1FR-110, RX M-U WATER FLOW (green pen) o 1F0140A, 11 RX M-U WTR TO BA BLNDR F For large quantity makeups, if the pump for the BAST on straight recirc also switches to FAST speed, then adjust the recirc valve for the BAST on straight recirc to 50% OPEN:

For large quantity makeups, direct the Chemist to obtain boron concentration sample of blender flow from the applicable location:

When the desired quantity of makeup has been added, then perform one of the following:

o Manually stop the makeup by placing CS-46457 to STOP.

o Verify automatic makeup stopped as indicated by CS-46457 green light lit.

If the recirc valve for the BAST on straight recirc was adjusted to 50% OPEN, then return the recirc valve for the BAST on straight recirc to 0%.

Verify CS-46454 is in AUTO.

Verify CS-46302 is in AUTO.

Verify 1HC-111 is in AUTO.

Verify 1HC-110 is in AUTO.

Return RCS makeup to automatic control as follows:

o Place CS-46300 in AUTO.

o Momentarily place CS-46457 to START.

o Reset Boric Acid Integrator.

o Reset RMU Integrator.

Check for expected response of VCT level and pressure, reactor power and/or count rate, RCS temperature, and RCP seal injection flow.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 33 PI-ILT-NRC-1803S, 2018 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.

EVENT 2 Booth Operator / Communicator:

1.

After the crew has performed a manual makeup to the VCT, and/or at the discretion of the Lead Evaluator, enter:

Trigger 1, Tavg Yellow Channel fails HIGH

2.

If contacted as I&C to trip bistables, inform the crew two I&C Technicians will be available in 90 minutes.

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, inform the crew that you will write a work order and assign an I&C Supervisor to investigate Plant Response:

1.

Tavg will indicate high.

2.

Control rods will step IN.

3.

Charging pump in auto will go to maximum.

4.

The following annunciators will be received:

a.

47012-0104, REACTOR COOLANT SYSTEM HI TAVG.

b.

47012-0304, REACTOR COOLANT SYSTEM TAVG DEVIATION.

c.

47012-0604, REACTOR COOLANT SYSTEM T DEVIATION

d.

47013-0205, OTT ROD STOP TURBINE RUNBACK CHANNEL ALERT

e.

47013-0305, AUCTIONEERED TAVG-TREF DEVIATION RO /

LEAD /

SS C7 AOP1, PLANT STABILIZATION Check generator load stable.

Place rod bank selector switch to manual.

Check rod motion stopped.

Go to 1C5 AOP1, step 4.

1C5 AOP1, UNCONTROLLED ROD MOTION Check for failed instrument.

Go to 1C51.4 C47012-0304, REACTOR COOLANT SYSTEM TAVG DEVIATION:

Check Tavg deviation by comparing channels.

Determine Tavg is failed high.

Refer to 1C51.4.

Verify steam flow/feed flow balance.

1C51.4, TAVG LOOP 1A 1T-404 - HIGH:

Place rod control in manual and maintain Tavg at Tref.

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

If necessary, then take manual control of steam dump.

Select yellow channel on Tavg defeat switch and pull out. (CS-46249)

Return the following to AUTO: Rod control, charging pump speed control, steam dump control.

Refer to TS LCOs 3.3.1, 3.3.2, TRM 3.3.3.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

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

3.3.2 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.

TRM 3.3.3 Condition A:

o Place the inoperable channel in trip in 6 HOURS.

Note: The crew may leave charging control in manual until PRZR level returns to normal operating band. It is not necessary to wait for charging to be in auto before moving on to the next event.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

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

1.

After the crew has Tavg yellow channel in defeat and addressed TS, the crew will restore Tavg to Tref per 1C51.4.

RO /

SS 1C51.4, TAVG LOOP 1A 1T-404 - HIGH:

Place rod control in manual and maintain Tavg at Tref.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

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

1.

After the crew has restored Tavg to Tref and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 2, Automatic Voltage Regulator Failure.

2.

If contacted as Turbine Building to investigate Voltage Regulator and/or Exciter, then wait 5 minutes and report back that everything appears normal.

3.

If contacted as TSO, then acknowledge VR trip and manual control, then direct the Control Room operator to adjust voltage regulator to RECEIVE 50 MVARs.

4.

If contacted as Engineering or Maintenance to investigate the gas high temp alarm, then acknowledge direction and inform CR you will get back to them.

5.

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.

Plant Response:

1. Voltage regulator trips and shifts to manual.

2. VR Base Adj. returns to pre-position setting.

3. The following annunciators are received:

a. 47006-0106, 1G GENERATOR REGULATOR TRIPPED.

b. 47006-0206, 1G GENERATOR REGULATOR FORCING.

c. 47007-0401, GEN OR EXCTR COLD GAS OR HOT GAS HI TEMP.

LEAD C47006-0106, 1G GENERATOR REGULATOR TRIPPED:

Place CS-46368, GEN REGULATOR CONTROL, to OFF.

Control generator voltage between 19000 and 21000 volts with base adjuster using CS-46366, GEN EXCITER BASE ADJ, per C22.6.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

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

1.

After the crew has completed actions in C47006-0106 and/or at the discretion of the Lead Evaluator, then enter:

Trigger 3, Reactor Vessel O-Ring Inner Seal Leakage.

2.

If contacted as Containment Entry Team, inform CR that RCS loop drain valves are verified NOT leaking by checking line temperatures with thermal imaging camera.

3.

When contacted as CTMT Entry Team, acknowledge the order to close RC-9-2, wait 1 minute, enter Trigger 13, and report that RC-9-2 is CLOSED.

4.

When contacted as CTMT Entry Team, acknowledge the order to open RC-9-1, wait 1 minute, enter Trigger 14, and report that RC-9-1 is OPEN.

Plant Response:

1. The following annunciators are received:

a. 47012-0603, REACTOR VESSEL FLANGE LEAKOFF HI TEMP

b. 47018-0605, REACTOR COOLANT DRAIN TANK TEMP/PRESSURE/LEVEL LEAD C47012-0603, REACTOR VESSEL FLANGE LEAKOFF HI TEMP Check leakoff temperature.

Close CV-31324, 11 REAC VSL FLG LEAK-OFF ISOL, using CS-46267.

Enter containment per F2, RADIATION SAFETY, and check that the RCS loop drain valves are not leaking.

(Check line temperatures.

If the RCS loop valves are the source of the high temperatures, then Close the loop drain valves.

Reopen CV-31324 using CS-46267.

If the inner seal is the source of the leak, then verify that the outer seal does not leak:

o CLOSE RC-9-2, REAC VESSEL FLANGE INNER SEAL LEAK-OFF o OPEN RC-9-1, REAC VESSEL FLANGE OUTER SEAL LEAK-OFF o REOPEN CV-31324 using CS-46267.

Monitor flange leakoff temperature.

Time compression will be used to simulate containment entry per F2, Radiation Safety.

Inform the SS that a CTMT Entry Team has been briefed per F2, has entered Containment, and is standing by with a radio awaiting instructions.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 6 Booth Operator / Communicator:

1. After the FP pumps have been stopped, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 4, Containment Pressure Yellow Channel Fails High.

Plant Response:

1. CTMT Pressure instrument 1P-947 reads off-scale high.

2. The following annunciators are received:

f.

47018-0105, CONTAINMENT HI-HI PRESS CHANNEL ALERT

g.

47018-0205, CONTAINMENT HIGH PRESS CHANNEL ALERT LEAD SS C47018 - 0105, CONTAINMENT HI-HI PRESS CHANNEL ALERT

a. Check CTMT pressure channels.

b. If channel failed, refer to 1C51.

1C51.4, CONTAINMENT PRESSURE 1P-947 - HIGH Refer to TS LCO 3.3.2 Cond. A and Functions 1C, 2C.

The SS will enter the following TS LCOs:

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 3.3.2 Condition E:

o Place inoperable channels in trip in 6 HOURS AND o Verify 1 channel per pair OPERABLE in 6 HOURS OR o Be in MODE 3 in 12 HOURS AND o Be in MODE 4 in 18 HOURS

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 33 PI-ILT-NRC-1803S, 2018 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.

EVENTS 7, 8, & 9 Booth Operator / Communicator:

1. When the crew has determined the location of the leak and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 5, 12 SG Fault Inside 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. 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 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.

Plant Response:

3. Reactor and turbine trip.

4. 12 SG pressure lowers rapidly.

5. CTMT humidity rises.

6. RCS & PRZR pressure lower RO /

LEAD /

SS 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify the reactor is tripped.

Verify the main turbine is tripped.

Verify both Safeguards buses energized.

Manually actuate SI.

Perform Attachment L (see pages 12 & 13).

Check AFW Status.

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:

Check 12 MSIV and bypass valves are closed.

Identify 12 SG as the faulted generator.

Isolate the following from 12 SG:

o main feedwater o AFW flow o Close steam supply from 12 SG to 11 TD AFWP.

o Verify SG PORV is closed.

o Verify SGB isolation valve is closed.

o Dispatch operator to close TD-4-1.

Check CST levels greater than 12,500 gallons.

Check secondary radiation normal.

Go to 1E-1.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 33 PI-ILT-NRC-1803S, 2018 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.

EVENTS 7, 8, & 9 cont.

CRITICAL TASKS Secure main steam to the main turbine to prevent the intact Steam Generator from reaching DRYOUT conditions Stop feed flow to the faulted Steam Generator before the end of the scenario.

Booth Operator / Communicator:

1. 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.

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

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

4. 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.

5. When directed as an outplant operator to close TD-4-1, wait 3 minutes, then report to control room that TD-4-1 is CLOSED.

1E-1, LOSS OF REACTOR OR SECONDARY COOLANT:

Determine RCPs are stopped.

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 be stopped.

Go to 1ES-0.2.

1ES-0.2, SI TERMINATION:

Determine SI and CI are reset.

Determine IA is established to CTMT.

Stop 11 & 12 SI pumps.

Stop 11 & 12 RHR pumps.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 33 PI-ILT-NRC-1803S, 2018 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.

EVENTS 7, 8, & 9 cont.

NOTE The operator will have to perform the following to align safeguards components for SI:

CS #

COMPONENT DESIRED CONDITION (Normally Aligned in Att. L) 46064 MV-32115, 122 SFP HX INLT HDR MV B CLOSED DEHC 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) 46410 11 COND PUMP OFF 46411 12 COND PUMP OFF 46412 13 COND PUMP OFF 46437 13 COND PUMP MANUAL 46419 12 FWP OFF 46417 CV-31127, 12 FW RECIRC VLV CLOSED 43062 CV-31127, A FW REG VLV CLOSED 43063 CV-31128, B FW REG VLV CLOSED 1E-0 Attachment L: SI Alignment Verification:

Verify Safeguards Component Alignment o

See table on page 19 Close MV-32115, 122 SFP HX INLT HDR MV B Check Cooling Water Header Pressures 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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 33 PI-ILT-NRC-1803S, 2018 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENTS 7, 8, & 9 cont.

EMERGENCY PLAN CLASSIFICATION The SS will declare an NUE, HU2.1, based on fire alarm in CTMT that cannot be verified within 15 minutes.

END Once the crew has stopped both SI pumps & 12 RHR 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 33 PI-ILT-NRC-1803S, 2018 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 INPUT

SUMMARY

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 22 of 33 PI-ILT-NRC-1803S, 2018 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 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 RYLC.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 23 of 33 PI-ILT-NRC-1803S, 2018 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 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-243.

___ 3.

If IC-243 is not available, then perform the following:

a. Reset the Simulator to IC-10.

___ 4.

Place the simulator in RUN.

___ 5.

If available, run schedule file PI-ILT-NRC-1803S.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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 24 of 33 PI-ILT-NRC-1803S, 2018 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 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-243.

___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 @ 218.

Boric Acid/RMU integrators set to: BA: 0, RMU: 10, 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: 19.8%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 828 ppm.

b. RCS H2 - 25 cc/kg.

c. Turbine Reference Value and Mode - 0.

___ 2.

Shift Reactivity Guidance placard:

a. BA: 2.6 gallons

b. RMU: 67 gallons

c. Dilutions: 10 gal 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 MDAFW PUMP

___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

___6. CS-46930, D2 DIESEL GENERATOR SEG specific or Out of Service Yellow Caution Tags are in place:

___1.

CS-46184, 11 RHR PUMP

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 25 of 33 PI-ILT-NRC-1803S, 2018 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.

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 - LEFM).

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 0.2 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.

Procedure checklist completed. See following page.

Peer Check performed for simulator setup.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 26 of 33 PI-ILT-NRC-1803S, 2018 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.

PROCEDURE CHECKLIST:

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

/

C7 AOP1, PLANT STABILIZATION

/

C22.6, 1(2) GENERATOR AND GENERATOR TRANSFORMER

/

C47006-0106, 1G GENERATOR REGULATOR TRIPPED

/

C47012-0304, REACTOR COOLANT SYSTEM TAVG DEVIATION

/

C47012-0603, REACTOR VESSEL FLANGE LEAKOFF HI TEMP

/

C47018-0105, CONTAINMENT HI-HI PRESS CHANNEL ALERT

/

1C5 AOP1, UNCONTROLLED ROD MOTION

/

1C51.4, CONTAINMENT PRESSURE 1P-947-HIGH

/

1C51.4, TAVG LOOP 1A 1T-404-HIGH

/

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

/

1ES-0.2, SI TERMINATION

/

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, & 5.10

/

REACTIVITY BRIEFING SHEET - MOC

/

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. TRM 3.3.3

/

T.S. TRM BASES 3.3.3 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 27 of 33 PI-ILT-NRC-1803S, 2018 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.

Post-Scenario Checklist EOOS computer is cleared of information added during the scenario.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___ 1.

CS-46425, 12 MDAFW PUMP

___ 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

___ 6.

CS-46930, D2 DIESEL GENERATOR Magnetic placards removed:

___ 1.

EAL Classification Placard Remove Yellow Caution Tags from the following equipment:

___ 1.

CS-46184, 11 RHR 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 28 of 33 PI-ILT-NRC-1803S, 2018 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.

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE:

DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

1. N51 and N52 displays are OOS.

TS LCO 3.3.3 Condition A was entered with 23 days remaining.

TS LCO 3.3.3 Condition D was entered with 5 days remaining.

N51 and N52 counts can be viewed in ERCS.

2. 11 RHR PUMP is Out of Service for Corrective Maintenance.

TS 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 RHR 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 12 RHR PUMP 12 SI PUMP 12 CC WTR PUMP 22 CLG WTR PUMP D2 DSL GEN 22 CC PUMP 121 SFP HX RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure: MOC Power: 100%

Boron: (CB): 828 ppm Temperature: 560°F Pressure: 2235 psig Xenon: Xe Eq Rods: D @ 218 Generator: 580 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 Perform 50-gallon manual makeup to VCT inlet per 1C12.5.

o Reactivity briefing PINGP 1710 provided (Attachment 2).

o Current VCT level is 35%.

After turnover, perform manual makeup to VCT.

NEW PROCEDURES / INSTRUCTIONS

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 29 of 33 PI-ILT-NRC-1803S, 2018 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 30 of 33 PI-ILT-NRC-1803S, 2018 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 31 of 33 PI-ILT-NRC-1803S, 2018 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 Josh Talbot SRO SS Mark Haren RO LEAD Chris Olson RO RO John DuBose SRO OBSERVER Steve Skoyen SM OBSERVER Fredrick Collins NRC Exam Developer Validator Justin Hasner Senior Instructor Validator

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 32 of 33 PI-ILT-NRC-1803S, 2018 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.

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 (1803 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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 33 of 33 PI-ILT-NRC-1803S, 2018 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.

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 4 Op-Test No.: PI-ILT-NRC-1804 Facility: PRAIRIE ISLAND Examiners:

Operators: Shift Supervisor Lead Reactor Operator Reactor Operator Initial Conditions:

Reactor Power at 90%, Boron Concentration at 858 ppm, RCS temperature at 558°, RCS pressure at 2235 psig, Xenon at equilibrium, Bank D rods at 208, Generator Power at 525 Mw.

D2 Diesel Generator is out of service. T.S. LCO 3.8.1 Condition B was entered with 9 days remaining. D1 Diesel Generator has been evaluated for common cause failure and has been determined to be OPERABLE. D1, 11 TD AFW Pump, 11 RHR Pump, 11 SI Pump, 11 CC Pump, 12 CL WTR Pump, 121 CR Air Supply Fan, 121 CR Chiller & Pump, and 121 CR Clean up Fan are protected. SP 1118 was completed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago and is due in 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Turnover:

Swap 11 & 12 EH oil pumps.

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

SWAP EH OIL PUMPS 2

I (ATC, SRO)

TS(SRO)

PRZR LEVEL WHITE CHANNEL FAILS LOW 3

I(ATC, SRO)

TS(SRO)

FIRST STAGE PRESSURE FAILS LOW 4

R(ATC)

N(SRO)

RESTORE TAVG TO TREF 5

M(ALL)

LOSS OF ALL AC 6

C(BOP)

D1 FAILS TO AUTO START 7

C(ATC) 11 TD AFW PUMP FAILS TO AUTO START (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 of 26 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-1804S SEG TITLE:

2018 ILT NRC SIMULATOR EVALUATION #4 REV. #

0 PROGRAM:

INITIAL LICENSE OPERATOR TRAINING FL-ILT COURSE:

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

Developed by:

Fredrick Collins 2/11/2018 Instructor Date Reviewed by:

Justin Hasner 6/14/2018 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Justin Hasner 6/14/218 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Shawn Sarrasin Training Supervision Date

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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 Level Instrument failing low per 1C51.2.

3.

First Stage Pressure Instrument failing low per 1C5 AOP1 and 1C51.2.

4.

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

5.

Failure of D1 EDG to automatically start per 1ECA-0.0.

6.

Failure of 11 TD AFW Pump to automatically 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:

11 TD AFW PMP D1 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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1L-427, White Channel Pressurizer Level Transmitter, fails LOW.

2. 1PT-485, Turbine First Stage Pressure Transmitter, fails LOW.

After EOP Entry:

1. D1 Emergency Diesel Generator fails to start automatically.

2. 11 TD AFW Pump fails to start automatically.

Abnormal Events:

1. Instrument Failure Guide.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

SCENARIO OVERVIEW:

INITIAL CONDITIONS:

EQUIPMENT OOS Exposure: MOC N51 and N52 Displays Power: 90% power Boron: (CB): 858 ppm Temperature: 558°F Pressure: 2235 psig Xenon: Xe Free Rods: D @ 208 Generator: 525 MW SEQUENCE OF EVENTS:

Event 1: Swap Running EH Oil Pumps

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 2: 1L-427, White Interlock Channel Pressurizer Level, fails LOW.

PRZR Level White (Interlock) Channel 1L-427 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: First Stage Pressure Instrument fails LOW

Rods will automatically step in.

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

The crew will perform actions per 1C51.2.

The SS will enter TS LCO 3.3.1 Conditions A and R.

Event 4: 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.

D2 is out of service and Bus 25 will lock out. The crew will have to manually start D1 and place D1 EDG on Bus 15 to restore power to a U1 safeguards bus.

Event 5: D1 fails to start automatically

The crew will manually start D1 per 1ECA-0.0.

Event 6: 11 TD AFW pump fails to start automatically

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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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 loading and unloading properly.

LEAD /

SS 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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 1, PRZR Level Intlk (White) Channel fails LOW.

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

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

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

5. 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.

6. 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. Letdown automatically secures.

2. PRZR heaters de-energize.

3. PRZR level rises.

4. Annunciator 47012-0607 will alarm LEAD /

RO SS LEAD /

RO SS 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.

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 K:

o Place channel in trip in 6 HOURS.

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

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

SCENARIO TIME-LINE:

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

1.

After the crew has restored letdown and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, 1ST Stage Pressure Instrument Failure.

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

4.

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

Plant Response:

1.

Control Rods automatically step IN.

2.

Tavg will lower due to rod movement.

3.

The following annunciators will alarm:

a.

47011-0405, FW CONTROL SYSTEM TROUBLE.

b.

47013-0305, AUCTIONEERED TAVG-TREF DEVIATION, PRZR SAFETY VALVE LINE A OR B HI TEMP RO SS LEAD /

RO SS C7 AOP 1, PLANT STABILIZATION Check generator load stable.

Place rod bank selector switch to manual.

Check rod motion stopped.

Go to 1C5 AOP1, step 4.

1C5 AOP1, UNCONTROLLED ROD MOTION Check for failed instrument.

Go to 1C51.2.

1C51.2, TURBINE 1ST STAGE PRESSURE 1P-485-LOW Place rod control in manual.

Control Tave at value appropriate for power level.

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.

The SS will enter the following TS LCOs:

3.3.1 Condition A o Reference Table 3.3.1-1 Function 16.b.2 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 Reference TRM Table 3.3.4-1 Function 3 o Trip Bistables (no six hour requirement).

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

EVENTS 4, 5, & 6 EVENTS 4, 5, & 6 cont.

Booth Operator / Communicator:

1. When the crew restored Tavg to Tref and addressed Tech Specs OR commenced a rapid load reduction, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 4, Loss of All AC.

2. Wait 1 minute and 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 the D1 Local Alarm, report that it is due to C55300-0105, Stand-By Lube Oil System Trouble alarm.

5. 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.

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

a.

FW134 - 11 AFW Pump to 11 SG (MV-32238)

b.

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

c.

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

d.

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

NOTE

7. 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.

CRITICAL TASKS Energize at least one AC emergency bus when safeguards equipment is required to perform its safety RO /

LEAD /

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

Verify the Main Turbine is tripped.

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.

o Start 11 TDAFW Pump.

Announce Unit 1 reactor trip.

Determine CL header pressure greater than 25 psig.

Determine Bus 15 IS available.

Start D1 diesel generator.

Place BKR 15-2 MAN/AUTO switch to MANUAL Place synchroscope select switch to D1 Close BKR 15-2.

Verify Bus 15 energized.

Start one charging pump.

Return to 1E-0, step 3.

1E-0, REACTOR TRIP OR SAFETY INJECTION Determine Bus 15 energized.

Determine SI is NOT actuated nor required.

Transition to 1ES-0.1.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

EVENTS 4, 5, & 6 cont.

function or prior to ORANGE or RED path on Core Cooling CSF.

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

Plant Response:

1. Reactor and turbine trip.

2. Bus 15 de-energizes.

3. Bus 25 LOCKS OUT.

4. Multiple annunciators associated with loss of power.

EMERGENCY PLAN CLASSIFICATION

ALERT - SA5.1 due to Safeguards Buses being reduced to a single source for greater than 15 minutes and a failure of D1 would result in SBO.

NOTE: If Bus 15 is not re-energized within 15 minutes, SITE AREA EMERGENCY-SS1.1 will be declared.

Notify TBO to perform Att. J.

Determine AFW flow to SGs greater than 200 gpm.

Determine all control rods NOT fully inserted.

o Borate 400 gallons due to CBD stuck rod G11

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES END Once the crew has restored power to Bus 15, transitioned to 1ES-0.1, and begun a 400 gallon boration, 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 INPUT

SUMMARY

SIMULATOR EVENT

SUMMARY

Event ID Description Code 4

RESTORE BKR 15-2 HWZDGU4869!=1

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 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 RYLC.

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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 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-244.

___ 3.

If IC-244 is not available, then perform the following:

a. Reset the Simulator to IC-21.

b. Place CS-46930, D2 DIESEL GENERATOR, in PULL TO LOCK.

c. Place CS-46921, BUS 16 SOURCE FROM D2, in PULL TO LOCK

d. Place CS-46911, D2 DSL GEN EXCITER CONTROL SEL SW, in MANUAL.

___ 4.

Place the simulator in RUN.

___ 5.

If available, run schedule file PI-ILT-NRC-1804S.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-1804.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

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 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-244.

___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 @ 208.

Boric Acid/RMU integrators set to: BA: 0, RMU: 10, 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: 19.8%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 858 ppm.

b. RCS H2 - 25 cc/kg.

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

___ 2.

Shift Reactivity Guidance placard:

a. BA: gallons

b. RMU: 0 gallons

c. Dilutions: 10 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.

D2 DSL GEN OOS signs on the G, A, C, & E panels.

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

___1. CS-46424, 11 TD AFWP

___2. CS-46184, 11 RHR PUMP

___3. CS-46178, 11 SI PUMP

___4. CS-46053, 12 CLG WTR PUMP

___5. CS-46067, 121 CR AIR SUPPLY FAN

___6. CS-46068, 121 CR CHILLER & PUMP

___7. CS-46066, 121 CR CLEAN UP FAN

___8. CS-46935, D1 DIESEL GENERATOR SEG specific or Out of Service Yellow Caution Tags are in place:

___1.

CS-46930, D2 DIESEL GENERATOR, to PULL TO LOCK.

___2.

CS-46921, BUS 16 SOURCE FROM D2 to PULL TO LOCK.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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 - LEFM).

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 0.2 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.

Procedure checklist completed. See following page.

Peer Check performed for simulator setup.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

PROCEDURE CHECKLIST:

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

/

C7 AOP1, PLANT STABILIZATION

/

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

/

1C5 AOP1, UNCONTROLLED ROD MOTION

/

1C23, UNIT 1 TURBINE CONTROL SYSTEM

/

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

/

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

/

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

/

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

/

SWI O-50, REACTIVITY MANAGEMENT

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S. TRM 3.3.4

/

T.S. TRM BASES 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.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

Post-Scenario Checklist EOOS computer is cleared of information added during the scenario.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___ 1.

CS-46424, 11 TDAFWP

___ 2.

CS-46184, 11 RHR PUMP

___ 3.

CS-46178, 11 SI PUMP

___ 4.

CS-46053, 12 CLG WTR PUMP

___ 5.

CS-46067, 121 CR AIR SUPPLY FAN

___ 6.

CS-46068, 121 CR CHILLER & PUMP

___ 7.

CS-46066, 121 CR CLEAN UP FAN

___ 8.

CS-46935, D1 DIESEL GENERATOR Magnetic placards removed:

___ 1.

D2 DSL GEN OOS signs on the G, A, C, and E panels.

___ 2.

EAL Classification Placard from Control Board.

Remove Yellow Caution Tags from the following equipment:

___ 1.

CS-46930, D2 DIESEL GENERATOR

___ 2.

CS-46921, BUS 16 SOURCE FROM D2 Board-mounted EAL Table is cleaned.

All books, note pads, and calculators put away.

Verify SYNCHROSCOPE handle on Unit 1 G Panel restored.

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 22 of 26 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:

DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

1. N51 and N52 displays are OOS.

TS LCO 3.3.3 Condition A was entered with 23 days remaining.

TS LCO 3.3.3 Condition D was entered with 5 days remaining.

N51 and N52 counts can be viewed in ERCS.

2. D2 DIESEL GENERATOR is out of service for corrective maintenance.

TS 3.8.1 Condition B was entered with 9 days remaining.

Expected return to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D1 DIESEL GENERATOR has been evaluated for common cause failure and has been determined to be OPERABLE PROTECTED EQUIPMENT 11 TD AFW PUMP 11 RHR PUMP 11 SI PUMP 11 CC PUMP 12 CLG WATER PUMP 121 CR CLEAN UP FAN D1 DIESEL GENERATOR SFP COOLING 121 CR AIR SUPPLY FAN 121 CR CHILLER & PUMP RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure: MOC Power: 90%

Boron: (CB): 858 ppm Temperature: 558°F Pressure: 2235 psig Xenon: Xe Free prior to startup Rods: D @ 208 Generator: 525 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 Reactor power is at 90% power following load increase. Holding at 90% per TSO request. Xe at equilibrium.

SP 1118 was performed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago and is due again in 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 23 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 24 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 25 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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 John DuBose SRO SS Mark Haren RO LEAD Chris Olson RO RO Fredrick Collins NRC Exam Developer Floor Instructor Justin Hasner Senior Ops Instructor Booth Driver

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 26 of 26 PI-ILT-NRC-1804S, 2018 ILT NRC SIMULATOR EVALUATION #4, 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.

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 (1804 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

ML22179A321

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML22179A321

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search