Text

Ile Administered Dynamic Simulator Scenarios
	ML22236A666
Person / Time
Site:	Prairie Island
Issue date:	08/19/2022
From:	Jim Nance; NRC/RGN-III/DRS/OLB
To:	; Xcel Energy
	Nance J
Shared Package
ML21188A223	List: ML22236A662; ML22236A666; ML22237A158;
References
	Download: ML22236A666 (106)
	v • d • e

Rev. 1 (3/8/2021) Page 1 of 47 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-2201S SEG TITLE:

2022 ILT NRC SIMULATOR EVALUATION #1 REV. #

0 PROGRAM:

LICENSE REQUALIFICATION TRAINING FL-ILT COURSE:

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

Fred Collins 7/26/22 Instructor Date Reviewed by:

Justin Hasner 7/26/22 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Fred Collins 7/26/22 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Jesse Maunu 7/26/22 Training Supervision Date

Rev. 1 (3/8/2021) Page 2 of 47 PI-ILT-NRC-2201S, 2022 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.

Form 3.3-1 Scenario Outline Facility: PRARIE ISLAND Scenario #: 1 Scenario Source:

Op. Test #:

NEW PI-ILT-NRC-2201S Examiners:

Applicants / Operators:

Shift Supervisor (SS)

Balance of Plant (LRO)

At the Controls (RO)

Initial Conditions:

Reactor Power:

100%

Xenon:

Equilibrium Boron Concentration:

1186 PPM Rods:

CBD @ 218 STEPS RCS temperature:

560°F Main Generator:

582 MW RCS pressure:

2235 PSIG Turnover:

Energize all PRZR Backup Heaters per 1C4, Step 5.5.1.

Reduce load to 500 MWe for Flex Power Operation per 1C1.4 Unit 1 Power Operation Critical Tasks:

PI-CT-13: Manually start at least one CC Pump prior to transition to recirculation phase.

PI-CT-18: Trip Reactor Coolant Pumps within 8 minutes of RCP trip criteria being met.

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

Energize PRZR Backup Heaters 2

R (ATC)

N (SS)

Flexible Power Operations to 500 MWe 3

1 C (BOP, SS)

TS (SS)

PRZR PORV 1PCV-431 Leakage 4

2 I (BOP, SS)

TS (SS) 1PT-486 Blue Channel First Stage Pressure Fails Low 5

3 C (BOP, SS)

Loss of Gap / Support Cooling 6

4 M (ALL)

Small Break LOCA 7

5 C (BOP, SS)

MC (BOP)

Component Cooling Pumps Fail to Start Automatically 8

6 C (BOP, SS)

MC (BOP) 12 DD Cooling Water Pump Fails to Start Automatically

Rev. 1 (3/8/2021) Page 3 of 47 PI-ILT-NRC-2201S, 2022 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.

Energize all PRZR Heaters IAW 1C4

2.

When directed, perform a Flexible Power Operations maneuver, in accordance with 1C1.4.

Evaluate the crews ability to diagnose and respond to:

3.

PRZR PORV Leakage IAW C47012.

4.

PT-486 Fails Low IAW C51.

5.

11 Reactor Vessel Support Cooling Fan Trip IAW C47021.

6.

Small Break LOCA IAW 1E-1.

7.

CC Pumps Fail to Start Automatically IAW 1E-0 Att. L.

8.

12 Diesel Driven Cooling Water Pump Failing to Auto Start IAW 1E-0 Att. L.

Training Resources:

1.

Full Scope Simulator

2.

Operations Management Representative

3.

Evaluation Team

4.

Booth Operator (Backup Communicator)

5.

Primary Communicator Related PRA Information:

Initiating Event with Core Damage Frequency:

LOCA Total (22.3%)

Loss of Component Cooling-U1 (6.9%)

Important Components:

1PT-431 - 1 PRZR P XMTR (CHNL III-BLU)

CV-31232 - 1 PRZR PORV A CV 145-121 - 11 CC PMP 145-122 - 12 CC PMP Important Operator Actions with Task Number:

NONE

Rev. 1 (3/8/2021) Page 4 of 47 PI-ILT-NRC-2201S, 2022 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. PRZR PORV Leakage

2. 1PT-486 Fails Low

3. 11 Reactor Vessel Support Cooling Fan Trip After EOP Entry:

1. CC Pumps Fail to Start Automatically

2. 12 Diesel Driven Cooling Water Pump Fails to Start Automatically Abnormal Events:

1. PRZR PORV Leakage

2. 1PT-486 Fails Low

3. 11 Reactor Vessel Support Cooling Fan Trip Major Transients:

1. Small Break LOCA Critical Tasks:

PI-CT-13: Manually start at least one CC Pump prior to transition to recirculation phase.

PI-CT-18: Trip Reactor Coolant Pumps within 8 minutes of RCP trip criteria being met.

Rev. 1 (3/8/2021) Page 5 of 47 PI-ILT-NRC-2201S, 2022 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-13 Critical Task:

Manually start at least one CC Pump prior to transition to Recirculation Phase.

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. A single Component Cooling Water Pump is required by the USAR for recirculation phase to provide adequate Post-LOCA heat removal capabilities.

Initiating Cue:

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 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.

Plant Conditions/

Success Path:

Safety Injection.

Both Component Cooling Water Pumps are NOT running.

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

Measurable Performance Standard:

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.

CC Pump must be started prior to starting an RHR pump for transfer to recirculation.

Rev. 1 (3/8/2021) Page 6 of 47 PI-ILT-NRC-2201S, 2022 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-18 Critical Task:

Trip Reactor Coolant Pumps within 8 minutes of RCP trip criteria being met.

Safety Significance:

Failure to trip the RCPs under the postulated plant conditions lead to core uncovering and to fuel cladding temperatures in excess of 2200°F. Thus, failure to perform the task represents mis-operation or incorrect crew performance in which the crew has failed to prevent degradation of the fuel cladding barrier to fission product release. USAR 4.3.3 references WOG letter to NRC OG-117 1984 in which the WOG determined the postulated trip criteria in the ERG (E-1-C) meets the requirements of NUREG 0737 Item II.K.3.5 (TMI automatic RCP trip functions). It also describes that for the postulated small break LOCA size of 3, the window for adverse conditions is 8-12 minutes. As the break size decreases, the window start time increases. Because it is not realistic for operators to determine exact break size in the early stages of a LOCA, licensee agrees that the start of the window for adverse conditions, at the largest break size for the postulated Small Break LOCA, is an appropriate response time.

Initiating Cue:

Injection flow exists to RCS:

o At least one SI Pump running and flow indicated.

-OR-o At least one RHR Pump running and flow indicated.

RCS Pressure is less than 1275 PSIG [1600 PSIG].

An operator controlled cool down has NOT been initiated.

Performance Feedback:

Indication that all RCPs are stopped.

Both RCP Pump green indicating lights LIT.

Both RCP Pump red indicating lights NOT LIT.

RCP flow decreasing.

Plant Conditions/

Success Path:

Small Break LOCA.

Break size less than 3 inches.

At least one Safety Injection Pump running.

RCPs Running.

RCP trip criteria are met.

Measurable Performance Standard:

Manually stopping RCPs using:

o CS-46255, 11 REACTOR CLNT PUMP.

o CS-46256, 12 REACTOR CLNT PUMP.

Operators must trip running RCPs within 8 minutes of RCP trip criteria being met in the EOPs.

Rev. 1 (3/8/2021) Page 7 of 47 PI-ILT-NRC-2201S, 2022 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 NONE Power:

100%

Boron: (CB):

1186 PPM TAVG:

560°F Pressure:

2235 PSIG Xenon:

Equilibrium Rods:

CBD @ 218 Generator:

582 MW SEQUENCE OF EVENTS:

Event 1: Energize all PRZR Backup Heaters The crew will energize PRZR Backup Heaters per 1C4.

Event 2: Flexible Power Operations to 500 MW Crew will take the duty at approximately 582 MWe.

In response to a request from marketing for Flexible Power Operations, the crew will lower Generator Electric load to 500 MWe.

Event 3: PRZR PORV 1PCV-431 Leakage PORV PCV-431 will develop seat leakage.

PRZR Relief Line temperatures will rise.

The crew will respond per C47012-0506.

The crew will isolate the leakage by closing CS-46263, PRZR Relief Isol MV-32195.

The Shift Supervisor will refer to TS LCO 3.4.11 Condition A.

Event 4: 1PT-486 Blue Channel First Stage Pressure Fails Low C47011-0405 FW Control System Trouble will alarm.

The crew will place steam dump in steam pressure mode per 1C51.3 Instrument failure guide.

The crew will address T.S. 3.3.1 Conditions A & T, and TRM 3.3.4 A.

Event 5: Loss of Gap / Support Cooling 11 RX VSL support cooling fan will trip.

The crew will start 12 RX VSL support cooling fan per C47021-0503.

Events 6: Small Break LOCA PRZR level and RCS pressure will lower.

The crew will manually actuate Safety Injection.

The crew will respond per 1E-0 and 1E-1.

Event 7: Component Cooling pumps fails to start automatically The crew will manually start CC pumps IAW 1E-0. ATT L.

Event 8: 12 DD Cooling Water Pump Fails to Start Automatically 12 Diesel Driven Cooling Water pump will fail to start.

The crew will start the 12 DD CL water pump per Att. L of 1E-0.

Rev. 1 (3/8/2021)

Page 8 of 47 PI-ILT-NRC-2201S, 2022 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 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 SCENARIO TIME-LINE:

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

1. After the crew has assumed the duty, they will energize all PRZR Backup Heaters IAW the pre-job brief.

BOP (N) 1C4 REACTOR COOLANT SYSTEM Place CS-46241, 1 SFGD PRZR BACK-UP HTRS GRP A ON/AUTO/OFF CS, to ON Place CS-46242, 1 SFGD PRZR BACK-UP HTRS GRP B ON/AUTO/OFF CS, to ON Place CS-46244, 1 PRZR BACK-UP HTRS GRP D ON/AUTO/OFF CS, to ON Place CS-46245, 1 PRZR BACK-UP HTRS GRP E ON/AUTO/OFF CS, to ON

Rev. 1 (3/8/2021)

Page 9 of 47 PI-ILT-NRC-2201S, 2022 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 EVT 2 Booth Operator / Communicator:

1.

After energizing all PRZR heaters, the crew will lower generator electric load to 500 MWe per a request from marketing.

Booth Operator:

2.

If contacted as TSO and notified of the Power reduction, acknowledge the report.

Plant Response:

1. Reactor Power lowers.

2. Generator Load lowers.

3. RCS TAVG lowers.

ATC (R)

SS (N) 1C1.4 Unit 1 Power Operation Verify Pre-Job Brief Complete.

Notify the Duty Chemist of the load change.

Notify the TSO of Load Change.

Notify the NRC resident Verify MISO has been notified of the load change.

If desired, place Rod control in Manual &

turn on all PRZR heaters.

Select the desired control mode.

Select the desired demand rate.

Set the target setting.

Initiate reactivity changes using Rods and Boron.

1C12.5, UNIT 1 BORON CONCENTRATION CONTROL Estimate quantity of boric acid required to accomplish the desired concentration change.

If boration of greater than 50 gal, then monitor BAST level changes.

If necessary, calculate boration flow rate.

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

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

Align 1HC-110, BA 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 boration.

Verify desired boric acid flow rate.

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

Reset the boric acid integrator.

Verify 1HC-110, BA TO BLENDER FLOW CONT, is in AUTO.

Perform section 5.5 or 5.9 of 1C12.5 to flush the boric acid to the charging pump suction using RMU in the Alt Dilute mode and return RMU control to auto.

NOTE:

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

Rev. 1 (3/8/2021)

Page 10 of 47 PI-ILT-NRC-2201S, 2022 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 EVT 3 Booth Operator / Communicator:

1.

After the crew has commenced the load reduction, and/or at the discretion of the Lead Evaluator enter:

Trigger 1, B PRZR PORV 1PCV-431 Leakage

{@ 9% severity; Variable: 100% =

8.67lbm/sec @ 2235 PSID =>

Leak is approximately 2 GPM.}

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.

47012-0506, PRZR POWER RELIEF LINE HI TEMP

b.

47012-0606, PRZR SAFETY VALVE LINE A OR B HI TEMP BOP (C)

SS (C)

SS (TS)

C47012-0506, PRZR POWER RELIEF LINE HI TEMP:

Check PRZR relief line temps.

Check PRZR pressure.

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

Identify CV-31231 as the leaking PORV and leave MV-32195 closed.

Refer to 1C4 AOP1.

Refer to Tech Spec LCO 3.4.11.

Crew may choose to restore auto makeup and/or auto rod control.

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 LCOs:

3.4.11 Condition A:

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

Rev. 1 (3/8/2021)

Page 11 of 47 PI-ILT-NRC-2201S, 2022 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 EVT 4 Booth Operator / Communicator:

1.

After the crew has isolated the leaking PRZR PORV and addressed TSs, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, First Stage Pressure 1PI-486 Fails Low

2.

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

3.

If contacted as I&C to trip bistables inform the control room that I&C will be available in 45 minutes.

Plant Response:

1.

Steam Dump arms

2.

The following annunciators will be received:

a.

47011-0405, FW Control System Trouble

b.

47014-0405, Loss of Load Interlock BOP (I)

SS (I)

SS (TS)

C47011-0405, FW CONTROL SYSTEM TROUBLE Verify steam generator level control operating properly in automatic.

Control level in manual for any steam generator which has shifted to manual.

Refer to 1C51 Instrument Failure Guide for any Reactor Protection or Engineered Safeguards system input failure.

1C51.3 Instrument Failure Guide 1PI-486 Low Place steam dump in steam pressure mode and verify valves closed.

Verify SG level control operating properly in automatic The SS will enter the following T.S. LCOs:

3.3.1 Condition A:

Enter the Condition referenced in table 3.3.1-1 for the channel(s) or train(s) 3.3.1 Condition T (function 16.b.2):

Verify interlock is in required state for existing unit conditions - 1 Hour OR Be in Mode 2 - 7 Hours TLCO 3.3.4 Condition A (function 3)

Initiate actions to restore to OPERABLE -

Immediately

Rev. 1 (3/8/2021)

Page 12 of 47 PI-ILT-NRC-2201S, 2022 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 EVT 5 Booth Operator / Communicator:

1.

After the crew has addressed the PT-486 failure and TS, and/or at the discretion of the Lead Evaluator, enter:

Trigger 3, 11 RX VSL Support CLG Fan TRIP

2.

If contacted as the outplant operator to investigate breaker 1L1-Z5, wait 2 minutes and report breaker is tripped. There is no smoke or acrid odor.

3.

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

Plant Response:

1.

11 RX VSL SUPPORT CLG FAN will trip.

2.

The following annunciators will alarm:

a.

47021-0503, REACTOR VESSEL SUPPORT COOLING LO FLOW BOP (C)

SS (C)

C47021-0503, REACTOR VESSEL SUPPORT COOLING LO FLOW Verify a reactor vessel support cooling fan running.

IF no SI signal is present, THEN verify a FCU is running in FAST with the discharge damper aligned to the support.

IF annunciator does not clear, THEN start standby (12) Support Cooling Fan.

Rev. 1 (3/8/2021)

Page 13 of 47 PI-ILT-NRC-2201S, 2022 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 EVTs 6, 7, & 8 Booth Operator/Communicator:

1.

When the crew has started 12 Rx Vessel support Cooling Fan, and/or at the discretion of the Lead Evaluator, enter:

Trigger 4: Small Break LOCA @ 40% severity Variable: 100% ~ 305 lbm/sec @ 2235 PSID

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.

5.

If there is NO examinee in the Unit 2 Lead Position AND 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.

6.

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

7.

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

8.

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.

ATC (M)

BOP(M)

SS (M)

CT 18 ATC 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify the reactor is tripped.

Verify the main turbine is tripped.

Verify both Safeguards buses energized.

Check if SI is actuated.

o Determine SI is required.

o If not actuated, manually actuate SI Perform Attachment L (see SEG page 17)

Check AFW Status.

Check RCS Temperatures trending to 547°F.

Check PRZR PORVs and Spray valves closed.

If RCS pressure is less than 1275 (1600) psig, then STOP both RCPs.

Determine SGs are not faulted.

Determine SG tubes are not ruptured.

Determine RCS is not intact.

Go to 1E-1.

1E-1 LOSS OF REACTOR OR SECONDARY COOLANT Check If RCPs should be stopped Check if SGs are not faulted Check Intact SG Levels Check Secondary Radiation Check PRZR PORVs and Block Valves Reset SI Reset Containment Isolation Establish Instrument Air to Containment Check Power Supply to Charging pumps Check if Charging flow has been established Check if SI flow should be terminated Check if RHR pumps should be stopped

Rev. 1 (3/8/2021)

Page 14 of 47 PI-ILT-NRC-2201S, 2022 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.

EVTS 6, 7 & 8 cont.

Plant Response:

1. RCS pressure and PRZR level lower.

2. Containment Pressure rises.

NOTE:

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

CRITICAL TASKS PI-CT-13: Manually start at least one CC Pump prior to transition to recirculation phase.

PI-CT-18: Trip Reactor Coolant Pumps within 8 minutes of RCP trip criteria being met.

CS #

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

OPEN 46338 STEAM DUMP MODE STM PRESS 46018 11 CFCU SLOW 46019 13 CFCU SLOW (Align due to Malfunctions) 46036 11 CC Pump ON 46037 12 CC Pump ON 46053 12 CLG WTR PUMP (DIESEL)

ON BOP (C)

BOP(MC)

SS (C)

CT 13 BOP BOP (C)

BOP(MC)

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

Verify Safeguards Component Alignment o

See table on page 14 Close MV-32115, 122 SFP HX INLT HDR MV B NOTE: at this severity, the rate of RWST depletion will due to SI flow will slowly rise as RCS pressure lowers. The time to RWST low level is approx. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Check Cooling Water Header Pressures Verify plant announcements complete Check If Main Steam lines 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 END Once the crew has completed 1E-0 Att. L and Critical Tasks, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew training has the duty.

Booth Operator:

Collect SBT data per Attachment 1, if necessary.

Rev. 1 (3/8/2021)

Page 15 of 47 PI-ILT-NRC-2201S, 2022 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

Rev. 1 (3/8/2021) Page 16 of 47 PI-ILT-NRC-2201S, 2022 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:

1st / 2nd

___ / ___ 1. If it is the first scenario of the day, then perform a shutdown and restart of the floor PCs that are connected to the LAN.

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

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

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

a.

NRC Code Placard:

i.

NRC Current Authentication Code HZZY.

ii.

Todays Date.

b.

High Flux at Shutdown Alarm Setpoint placards: 5100 cps.

c.

Feedwater regulating valve position placard set to current values.

d.

Recommended SG Blowdown flow set to current values.

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

a.

Blowdown 46470 SGB To RIVER

b.

H2 in VCT Space

c.

11 BA TANK Lined Up For Service

d.

11 BA PUMP Lined Up to 11 BA Tank

e.

12 BA PUMP Lined Up to 11 BA Tank

f.

CC to SFP MV-32115 In Service

g.

CC to SFP MV-32117 In Service

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

a.

CS-46540, 22 CC WTR PUMP

b.

CS-46572, 121 SFP HX INLT

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

a.

NONE

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

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

Rev. 1 (3/8/2021) Page 17 of 47 PI-ILT-NRC-2201S, 2022 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.

1st / 2nd

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

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

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

a. Reset the simulator to IC-10.

b. Place the simulator in RUN.

c. Place second 40 GPM letdown orifice in service.

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

e. Place simulator in FREEZE.

f. If desired, save to available IC.

g. Go to step 4.

___ / ___ 4. Reset the Simulator to IC-240 and place in RUN.

___ / ___ 5. If available, run schedule file PI-ILT-NRC-2201S.sch as follows:

a.

Locate schedule file.

b.

Open schedule file by double clicking it.

c.

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

d.

Verify the schedule file is running.

___ / ___ 6. If schedule file is NOT available, reset Simulator to IC-240 or IC created in step 3, place in RUN, and insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

___ / ___ 7. If desired, start Scenario Based Testing Data Collection Program per Att 1.

___ / ___ 8. Complete the "Simulator Setup Checklist on next page.

Rev. 1 (3/8/2021) Page 18 of 47 PI-ILT-NRC-2201S, 2022 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:

1st / 2nd

_ _/ _

Simulator Status:

___1.

"Training Load"

___2.

Alarm sound: ON

___3.

Speed: REAL

___4.

Step counters: NOT USED

___5.

Simulator running in IC-10 or IC-240.

___6.

Steps 1 - 8 on previous page complete.

_ _/ _

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

_ _/ _

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

_ _/ _

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

_ _/ _

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

_ _/ _

MOC I sheet displayed on C panel.

_ _/ _

MOC Reactivity Briefing sheet available at Reactor Operator Desk.

_ _/ _

Verify Boric Acid and Reactor Makeup Controllers are set properly:

___ 1.

1HC-110: 25.6%

___ 2.

1HC-111: 44.7%

_ _/ _

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 1186 ppm.

b. RCS H2 - 45 cc/kg.

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

___ 2.

Shift Reactivity Guidance placard:

a. BA: 3.8 gallons

b. RMU: 67 gallons

c. Dilutions @ 20 gal RMU, 1-2 times per shift

___ 3.

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

___ 4.

LCO Timer CLEANED.

_ _/ _

SEG specific Magnetic Placards in place:

___ 1. NONE

_ _/ _

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

___1. NONE

_ _/ _

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

___ 1. NONE

Rev. 1 (3/8/2021) Page 19 of 47 PI-ILT-NRC-2201S, 2022 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:

1st / 2nd

_ _/ _

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 - 5 min AVG).

_ _/ _

Set Turbine Control HMI Displays as follows:

___ 1.

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

___ 2.

U1 Turb Aux Cont (48088) to Turb Overview

___ 3.

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

___ 4.

DEHC alarms cleared.

_ _/ _

YELLOW turnover sheets 1-6 available.

_ _/ _

All Fire alarms CLEAR.

_ _/ _

Board-mounted EAL Tables are cleaned.

_ _/ _

Headsets turned on as necessary.

_ _/ _

Procedure checklist completed. See following page.

_ _/ _

Peer Check performed for simulator setup.

Rev. 1 (3/8/2021) Page 20 of 47 PI-ILT-NRC-2201S, 2022 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

/

1C1.4, UNIT 1 POWER OPERATION

/

1C4, REACTOR COOLANT SYSTEM

/

1C4 AOP1, REACTOR COOLANT LEAK

/

C47011-0405, FW CONTROL SYSTEM TROUBLE

/

C47012-0506, PRZR POWER RELIEF LINE HI TEMP

/

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

/

C47014-0405, LOSS OF LOAD INTERLOCK

/

C47021-0503, REACTOR VESSEL SUPPORT COOLING LO FLOW

/

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

/

EAL BOARD

/

LAMINATE COPY OF 1C5, SECTION 6.5

/

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

/

LAMINATE COPY OF 1C12.5, SECTION 5.10

/

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

/

REACTIVITY BRIEFING SHEET - MOC

/

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

/

T.S. LCO 3.4.11

/

T.S. LCO BASES 3.4.11

/

T.S. LCO 3.4.14

/

T.S. LCO BASES 3.4.14

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

NOTE: The following procedures will be used during this session. Verify the procedures are free of place keeping marks before starting the session and after the session are complete.

Rev. 1 (3/8/2021) Page 21 of 47 PI-ILT-NRC-2201S, 2022 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 1st / 2nd

_ _/ _

Computer generated PINGP 577 cleared and tab closed.

_ _/ _

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

_ _/ _

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

_ _/ _

Procedure checklist completed. See previous page.

_ _/ _

Remove Pink Status Control Tags from the following equipment:

___1. NONE

_ _/ _

Remove Magnetic placards from Control Boards:

___ 1. EAL Classification Placard from Control Board.

___ 2. RED/WHITE Critical Parameter Cards

_ _/ _

Remove Yellow Caution Tags from the following equipment:

___ 1. NONE

_ _/ _

Board-mounted EAL Table is cleaned.

_ _/ _

All books, note pads, and calculators put away.

End Of Day Checklist 1st / 2nd

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

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

_ _/ _ Instructor station returned to normal with all books, paper, and pens, etc. put away.

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

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

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

_ _/ _ Verify the following placards are erased:

CVCS panel Shift Reactivity Guidance LCO Timer NRC Authentication Code

Rev. 1 (3/8/2021) Page 22 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

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

MOC Pressure:

2235 PSIG Unit 2 is at 100% power.

TPM is set to 5 minute average.

Power:

100%

Xenon:

Equilibrium Boron (CB): 1186 PPM Rods:

CBD @ 218 TAVG:

560°F Generator: 582 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT Energize all PRZR Backup Heaters per 1C4, Step 5.5.1.

Reduce load to 500 MWe for Flex Power Operation per 1C1.4 Unit 1 Power Operation, section 6.4.

Chemistry, the TSO, the NRC resident, and MISO are all informed of the planned load change.

NEW PROCEDURES / INSTRUCTIONS of 6

Rev. 1 (3/8/2021) Page 23 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

PREJOB BRIEF

Prepare a reactivity plan and perform a brief to perform Flex Power Operations down to 500 MWe using 1C1.4, Unit 1 Power Operation, section 6.4.

The 1-hour time you have to get to 500MWe will begin once you have placed the turbine in GO.

Rev. 1 (3/8/2021) Page 24 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 25 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 26 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 27 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 28 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 29 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 30 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 31 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 32 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 33 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 34 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 35 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 36 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 37 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 38 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 39 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 40 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 41 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 42 of 47 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 43 of 47 PI-ILT-NRC-2201S, 2022 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

Rev. 1 (3/8/2021) Page 44 of 47 PI-ILT-NRC-2201S, 2022 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.

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 OE)

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.

Rev. 1 (3/8/2021) Page 45 of 47 PI-ILT-NRC-2201S, 2022 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:

Rev. 1 (3/8/2021) Page 46 of 47 PI-ILT-NRC-2201S, 2022 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 Tim Kohrs SRO SS Mark Girdeen RO LRO Ryan Rhody RO RO

Rev. 1 (3/8/2021) Page 47 of 47 PI-ILT-NRC-2201S, 2022 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 Insert the SBT Locker G3 flash drive into USB port on PITC01, or equivalent if PC has been swapped, and unlock using provided password. (left side Simulator Booth Instructor Station)

START menu or T-Rex IS desktop icon SBT Report File OPEN Select file type.tis o

(FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT Select SBT.tis OPEN or double click Check TAM log & verify no cycling switches Run scenario AFTER SCENARIO For TREX-Lightning SBT:

o FREEZE on Simulator o

Click GREEN arrow to generate report o

Enter the following:

(NAME is not required)

Test Title (22xx SBT ILT Group x Exam)

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 SBT 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 or T-Rex IS desktop icon o

COMPARE IT o

Click + ADD o

Select.csv file from previously saved location o

OPEN or double click o

Click GREEN COMPARE button o

Wait for spreadsheet to populate and then save in desired location o

Verify all 3 files are saved in proper location o

Close spreadsheet, COMPARE IT, and SBT Report For Ovation SBT:

o Run the Copy Ovation SBT Files.bat file on PITCSIM Desktop in Simulator Computer room.

o Copy the three generated files (Alarms, SLIM, Soft) from Ovation SBT folder located on PITC01\\SimData\\X: (left side Simulator Booth Instructor Station) Desktop to the SBT Locker G3 flash drive.

o Rename the files to correspond with SEG and exam activity.

(e.g. 22xx Ovation SBT {Alarms, SLIM, Soft} ILT Group x Exam) o Delete the generated files from the Desktop folder.

Rev. 1 (3/8/2021) Page 1 of 27 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-2202S SEG TITLE:

2022 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:

Fred Collins 7/26/22 Instructor Date Reviewed by:

Justin Hasner 7/26/22 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Fred Collins 7/26/22 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Jesse Maunu 7/26/22 Training Supervision Date

Rev. 1 (3/8/2021) Page 2 of 27 PI-ILT-NRC-2202S, 2022 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.

Form 3.3-1 Scenario Outline Facility: PRARIE ISLAND Scenario #:

2 Scenario Source:

Op. Test #:

NEW PI-ILT-NRC-2202S Examiners:

Applicants / Operators:

Shift Supervisor (SS):

Balance of Plant (LRO):

At the Controls (RO):

Initial Conditions:

Reactor Power:

95%

Boron Concentration:

0 (CDC) PPM RCS temperature:

559.5°F RCS pressure:

2235 PSIG Xenon:

Eq Rods:

CBD @ 225 STEPS Main Generator:

543 MW Turnover:

11 TDAFWP OOS After taking the duty, swap HDT pumps per 1C28.4 and pre-job brief.

Critical Tasks:

PI-CT-2A: Manually insert control rods and/or borate the RCS to prevent an ORANGE or RED path on the Core Cooling CSF.

PI-CT-12A: During an ATWS, establish Auxiliary Feed Water flow to the Steam Generators to prevent an ORANGE or RED path on the CORE COOLING CSF.

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

Swap Auto HDT Pump per 1C28.4 2

1 I (BOP, SS)

R (ATC)

MC (ATC)

TS (SS)

THOT Yellow Channel Fails High 3

2 I (BOP, SS)

TS (SS) 1PT-478, 12 SG Pressure Blue Channel Fails Low 4

3 11 Circ Water Pump High Temp 5

R (BOP)

N (ATC)

C (SS)

Rapid Power Reduction 6

4 M (ALL)

Turbine Trip / ATWS 7

5 C (BOP, SS)

MC (BOP) 12 MDAFWP Fails to Start 8

6 C (BOP, SS)

Normal Boration Fails

Rev. 1 (3/8/2021) Page 3 of 27 PI-ILT-NRC-2202S, 2022 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.

Swap Auto HDT Pump per 1C28.4.

Evaluate the crews ability to diagnose and respond to:

2.

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

3.

12 SG Blue Channel Pressure Fails Low per C47011.

4.

11 Circ Water High Temp per C47001.

5.

Rapid Load Reduction per 1C1.4 AOP1.

6.

Turbine Trip ATWS per 1FR-S.1

7.

Failure of 12 MD AFW Pump to auto start per 1FR-S.1.

8.

Failure of Normal Boration per 1FR-S.1 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:

NONE Important Components:

145-201 11 TD AFW PMP 145-331 12 MD AFW PMP Important Operator Actions with Task Number:

NONE

Rev. 1 (3/8/2021) Page 4 of 27 PI-ILT-NRC-2202S, 2022 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. Yellow Channel THOT Instrument Fails High

2. 12 SG Pressure Blue Channel Fails Low

3. Circ Water Pump HI Temp

4. Turbine Trip After EOP Entry:

1. 12 MDAFWP Auto Start Failure

2. Failure of Normal Boration Abnormal Events:

1. Instrument Failure Guide x2.

2. CW Pump HI Temperature

3. Rapid Load Reduction

4. Turbine Trip Major Transients:

1. ATWS Critical Tasks:

PI-CT-2A: Manually insert control rods and/or borate the RCS to prevent an ORANGE or RED path on the Core Cooling CSF.

PI-CT-12A: During an ATWS, establish Auxiliary Feed Water flow to the Steam Generators to prevent an ORANGE or RED path on the CORE COOLING CSF.

Rev. 1 (3/8/2021) Page 5 of 27 PI-ILT-NRC-2202S, 2022 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-2A Critical Task:

Manually insert control rods and/or borate the RCS to prevent an ORANGE or RED path on the Core Cooling CSF.

Safety Significance:

Negative reactivity must be added, and/or positive reactivity sources must be removed from a core that is observed to be critical when expected to be shutdown.

Plant safeguards systems design basis assumes decay heat and RCP heat only. These safeguards systems cannot perform their safety functions when needed to protect the core during accident conditions if critical core heat is also being added. (e.g. AFW cannot provide sufficient heat removal from SGs if core is still critical)

Initiating Cue:

Reactor trip First Out annunciator lit.

Reactor trip breakers closed.

Rods not at bottom.

ROD AT BOTTOM lights not lit.

Reactor trip switches fail to generate a reactor trip.

AMSAC/DSS switch fails to insert control rods.

Performance Feedback:

Rods stepping in.

Reactor power lowering.

Negative SUR.

Plant Conditions/

Success Path:

Reactor power is greater than or equal to 70%.

At least one of the following occurs:

o Loss of normal feed water to the Steam Generators.

o Main Turbine Trip.

The reactor fails to automatically trip.

The reactor cannot be manually tripped from the Control Room.

Out-plant operators are unable to trip the reactor locally.

Rods fail to automatically insert.

At least one of the following is drawing steam from the SGs:

o Main Turbine.

o Steam Dumps.

o SG PORVs.

Measurable Performance Standard:

Prior to reaching an ORANGE or RED path in Core Cooling, the crew performs one or both of the following:

Control Rods CS-46280 in a position other than AUTO, and CS-46281 in the IN position.

-AND / OR-Boron injection to RCS at 12 - 15 gpm.

Rev. 1 (3/8/2021) Page 6 of 27 PI-ILT-NRC-2202S, 2022 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-12A Critical Task:

During an ATWS, establish Auxiliary Feed Water flow to the Steam Generators to prevent an ORANGE or RED path on the Core Cooling CSF.

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. Also, failure to maintain an adequate heat sink will result in degradation of the Fuel Clad Barrier and RCS Barrier.

Cues:

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

Both Steam Generators levels lowering.

RCS pressure is above the pressure of all Steam Generators.

Performance Feedback:

Increasing water level in at least one Steam Generator.

Feed water flow into at least one SG.

Plant Conditions/

Success Path:

Reactor power is greater than or equal to 70%.

At least one of the following occurs:

o Loss of normal feed water to the Steam Generators.

o Main Turbine Trip.

The reactor fails to automatically trip.

The reactor cannot be manually tripped from the Control Room.

Out-plant operators are unable to trip the reactor locally.

Rods fail to automatically insert.

SGs are required for heat sinks.

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

o 11 Turbine Driven Auxiliary Feed Water Pump o

12 Motor Driven Auxiliary Feed Water Pump o

21 Motor Driven Auxiliary Feed Water Pump At least one of the following is drawing steam from the SGs:

o Main Turbine.

o Steam Dumps.

o SG PORVs.

Measurable Performance Standard:

Prior to the need to establish bleed and feed, the crew manipulates controls to establish feed water flow into at least one SG with Auxiliary Feed Water Pumps:

o CS-46438, 11 TDAFWP, mode selector switch to MANUAL.

and o

CS-46424, 11 TDAFWP CV-31998, to START.

OR o

CS-46439, 12 MDAFWP, mode selector switch to MANUAL.

and o

CS-46425, 12 MDAFWP, to START NOTE:

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

Rev. 1 (3/8/2021) Page 7 of 27 PI-ILT-NRC-2202S, 2022 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:

CDC 11 TDAFWP Power:

95%

Boron: (CB):

0 PPM TAVG:

559.5°F Pressure:

2235 PSIG Xenon:

Equilibrium Rods:

CBD @ 225 Generator:

543 MW SEQUENCE OF EVENTS:

Event 1: Swap Automatic Heater Drain Tank Pump The crew will place 12 HDT Pump in Automatic and 11 HDT pumps to Manual.

Event 2: THOT Yellow Channel Fails High Rods will step in.

Charging pump speed will go to maximum.

The crew will take manual control of rods and charging.

The crew will select yellow channel TAVG defeat switch and pull out.

The SS will enter T.S. 3.3.1 Cond. A & E; T.S. 3.3.2 Cond. A & D; and T.R.M. 3.3.3 Cond. A Event 3: 1PT-478, 12 SG Pressure Blue Channel Fails Low 1PI-478 B Steam Generator Pressure (Blue) fails LOW.

The crew will place 12 SG PORV in manual per 1C51.3 The SS will enter T.S. 3.3.2 Condition A and T.S. LCO 3.3.2 Condition D Events 4 & 5: 11 Circ Water Pump High Temp / Rapid Load Reduction Crew will receive 11 Circ Water High Temp Alarm.

The crew will determine a rapid load reduction is required per C47001.

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

Event 6: Turbine Trip / ATWS Main Turbine will trip and MFW pumps will lockout.

The reactor will fail to trip automatically and rods will fail to move automatically.

Attempts to trip the reactor from the Control Room will be unsuccessful.

The crew will manually insert control rods per 1FR-S.1.

Event 7: 12 MDAFWP Fails to Start 12 MDAFW pumps will fail to start automatically.

The crew will start 12 MDAFW Pumps per 1FR-S.1.

Event 8: Normal Boration Fails The normal boration method will fail.

The crew will emergency borate the reactor per 1FR-S.1.

Rev. 1 (3/8/2021)

Page 8 of 27 PI-ILT-NRC-2202S, 2022 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.

Rev. 1 (3/8/2021)

Page 9 of 27 PI-ILT-NRC-2202S, 2022 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 EVT 1 Booth Operator / Communicator:

1. After the crew has assumed the duty, they will swap speed control for running HDT Pumps per 1C28.4 and pre-job brief.

BOP (N) 1C28.4, UNIT 1 HEATER DRAINS:

Using ERCS Group Display OP19, trend 11/12/13 HTR DRN PUMPS data, update rate should be 5 seconds.

Adjust the speed control switch for the heater drain pump in MANUAL speed control to balance running HDTP speeds:

o CS-46432, 12 HTR DRN PUMP SPEED Place the pump speed selector switch for the pump to be removed from automatic control to MANUAL:

o CS-46462, 11 HTR DRN PMP SPEED SELECTOR IF necessary, THEN adjust HD PMP speed on the pump taken to manual in step B.:

o CS-46119, 11 HTR DRN PMP SPEED Place the pump speed selector switch for the pump to be left in automatic to AUTO:

o CS-46463, 12 HTR DRN PMP SPEED SELECTOR IF no further HDTP changes are desired, THEN exit this procedure.

Rev. 1 (3/8/2021)

Page 10 of 27 PI-ILT-NRC-2202S, 2022 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 EVT 2 Booth Operator / Communicator:

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

Trigger 1, THOT Yellow Channel 1T-404 Fails High

1.

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

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, inform the crew that you will write a maintenance notification, CAP, work request, and assign an I&C Supervisor to investigate.

Plant Response:

1.

Instrument 1T-404 fails high.

2.

The following annunciator will be received:

a.

47012-0104, REACTOR COOLANT SYSTEM HI TAVG

b.

47012-0304, REACTOR COOLANT SYSTEM TAVG DEVIATION

c.

47012-0504, REACTOR COOLANT SYSTEM OVERTEMP T CHANNEL ALERT

d.

47012-0604, REACTOR COOLANT SYSTEM T DEVIATION

e.

47013-0105, OPT ROD STOP TURBINE RUNBACK CHANNEL ALERT

f.

47013-0107, BANK D ROD WITHDRAWL HI LIMIT

g.

46013-0205, OTT ROD STOP TURBINE RUNBACK CHANNEL ALERT

h.

47013-0305, AUCTIONEERED TAVG-TREF DEVIATION

3.

Rods will step in.

4.

11 Charging pump speed will go to maximum.

BOP (I)

SS (I)

ATC (R)

ATC (MC)

SS (TS) 1C5 AOP1 UNCONTROLLED ROD MOTION Check Generator Electrical Load - Stable Place Rod Bank Selector Switch to Manual Check Rod Motion - Stopped Check for failed instruments - Go to 1C51 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.

Select yellow channel on TAVG defeat switch and pull out.

Return the following to Auto, as required:

Rod Control Steam dump control Charging pump speed control The SS will enter the following TS LCOs:

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

3.3.1 Condition E (functions 6 & 7)

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

3.3.2 Condition A Enter Condition referenced in Table 3.3.2-1 for the channel(s) or train(s) IMMEDIATELY.

3.3.2 Condition D (function 4d)

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

TRM 3.3.3 Condition A Place INOPERABLE channel in trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Rev. 1 (3/8/2021)

Page 11 of 27 PI-ILT-NRC-2202S, 2022 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 EVT 3 Booth Operator:

1.

After the crew has returned control rods to auto and addressed Tech Specs, and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, 12 SG Blue Channel Pressure Fails Low

2.

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

3.

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

4.

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

Plant Response:

1. Pressure indicator 1PI-478 fails low.

2. Steam Flow indicator 1FI-474 indicates low.

3. The following annunciators are received:

a. 47011-0405, FW CONTROL SYSTEM TROUBLE

b. 47011-0304, 12 STM GEN LO-LO PRESS CHANNEL ALERT

c. 47011-0504, 12 STM GEN LO PRESS BOP (I)

SS (I)

SS (TS) 47011-0304, 12 STM GEN LO-LO PRESS CH ALERT If channel failed, then refer to 1C51.

1C51.3, 12 STEAM GENERATOR PRESSURE 1P-478 - LOW Verify SG level control operating properly in automatic.

Take manual control of 12 SG PORV and verify valve is CLOSED.

Refer to T.S. LCO 3.3.2 Condition A & Table 3.3.2-1 Function 1e.

The SS will enter the following TS LCOs:

3.3.2 Condition A Enter Condition referenced in Table 3.3.2-1 for the channel(s) or train(s) IMMEDIATELY.

3.3.2 Condition D (function 1e)

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

Rev. 1 (3/8/2021)

Page 12 of 27 PI-ILT-NRC-2202S, 2022 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 EVTs 4 & 5 Booth Operator / Communicator:

1.

After the crew has addressed TS, and/or at the discretion of the Lead Evaluator enter:

Trigger 3, 11 Circulating Water Pump High Stator Temperature

2. If contacted as the Turbine Building Operator to investigate 11 Circ Water Pump, then wait 3 minutes and report that 11 Circ Water Pump ambient temperature is noticeably higher than the other Circ Water Pumps.

Ventilation and oil levels are all normal.

3. If contacted as the Operations Manager or DSM and asked to contact Electrical Section in support to troubleshooting and repair of 11 Circ Water Pump, then inform the crew you will make necessary phone calls to inform Electrical Section of issue. 5 minutes later all the crew and inform them that Station Electricians have been called to the site and their ETA is about 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . If asked to man the OCC, then agree to man the OCC.

4. If contacted as the TSO and informed about the rapid downpower and status of the plant, then acknowledge the report and ask the crew to update you when more information becomes available.

5. If contacted as Energy Marketing and informed about the power reduction, then acknowledge the report of the downpower.

6. If contacted as the Duty Chemist and informed of the power reduction then, acknowledge the report.

NOTE:

CW pump annunciator takes approx. 5 minutes to alarm after trigger inserted.

BOP (R)

ATC (N)

SS (C)

C47001-0203 11 Circ Water Pump Motor High Stator Temp Dispatch an operator to check the condition of the circulating water pump. i.e. air flow and oil level, and compare its ambient temperature with the other circulating water pumps.

Monitor the motor temperatures utilizing the applicable ERCS address point 1T2555A.

Notify electrical section to check pump load and vibration.

If conditions necessitate securing of the pump, then:

Prior to securing pump, if possible, reduce turbine load to less than 350 Mwe per 1C1.4 AOP1, Rapid Power Reduction Unit 1 Verify MV-32005, 1B CDSR CW XOVR MN, is open If condenser vacuum problems are experienced, then reduce turbine load further as necessary If pump is secured, then control circ water temperature as necessary Effect necessary repairs and return the system to normal status 1C1.4 AOP1, Rapid Power Reduction Unit 1 Determine predicted Boron concentration and final rod position.

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

Verify systems in automatic:

Steam Dump SGWL PRZR pressure Rods PRZR level Turn on all PRZR heaters.

Reduce turbine load as follows:

From the On Line Control screen Select desired mode (VPC, FSP, LOAD) from the control mode pop-up Select desired rate of load change from demand rate pop-up Set the target setting to desired Target Select GO to initiate load reduction

Rev. 1 (3/8/2021)

Page 13 of 27 PI-ILT-NRC-2202S, 2022 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 EVTs 4 & 5 cont.

Plant Response:

1.

47001-0203 11 Circ Water Pump Motor Stator High Temp

2.

11 Circulating Water Pump Stator temperature will increase from 100.5 to 150 Celsius over 15 minutes.

3.

The 11 Circ Water Pump Motor Stator High Temp alarm will come in approximately 5 minutes after inserting trigger 3.

4.

11 Circulating Water Pump will lockout when stator temperature reaches 150 Celsius.

1C12.5, UNIT 1 BORON CONCENTRATION CONTROL 5.10 Review precautions in section 5.8.

Verify 1YIC-110, BA TO BLENDER BATCH INTEGRATOR, is reset.

Set 1YIC-110 to quantity desired.

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

If desired, place 1HC-110, BA TO BLENDER FLOW CONT, to MANUAL & adjust output for desired flow.

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

If boron additions of greater than 50 gallons are required, then monitor BAST level changes.

When desired quantity of boron added, verify automatic make-up stopped as indicated by CS-46457 green light LIT.

If additional boration desired, return to step 2.

When boration complete, verify 1HC-110 is in AUTO.

Reset 1YIC-110 integrator.

Perform section 5.9 to flush acid to charging pump suction using ALT DILUTE.

5.9 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.

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.

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.

Rev. 1 (3/8/2021)

Page 14 of 27 PI-ILT-NRC-2202S, 2022 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 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

Rev. 1 (3/8/2021)

Page 15 of 27 PI-ILT-NRC-2202S, 2022 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 EVTs 6, 7, &

8 Booth Operator / Communicator:

1.

When reactor power has been lowered to ~

75%, and/or at the discretion of the Lead Evaluator then enter:

Trigger 4: Turbine Trip / ATWS

2.

If dispatched as the Outplant operator to locally open reactor trip breakers and/or Rod Drive MG Set breakers, then wait until reactor power is <5%, crew has commenced Emergency Boration and/or at the discretion of the Lead Evaluator, enter Trigger 5.

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.

Plant Response:

1.

Main turbine trips.

2.

Rods fail to move in auto.

3.

Manual reactor trip switches and AMSAC/DSS fail to trip the reactor.

4.

MFW pumps will lockout.

5.

12 MDAFW Pump fails to start automatically.

CRITICAL TASKS PI-CT-2A: Manually insert control rods and/or borate the RCS to prevent an ORANGE or RED path on the Core Cooling CSF.

PI-CT-12A: During an ATWS, establish Auxiliary Feed Water flow to the Steam Generators to prevent an ORANGE or RED path on the Core Cooling CSF.

ATC (M)

BOP (M)

SS (M)

CT-2A BOP (C)

SS (C)

CT-12A BOP (C)

BOP (MC)

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

Determine the reactor did NOT automatically trip.

Determine reactor can NOT be tripped manually.

Determine reactor power is > 5%.

Go to 1FR-S.1.

1FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS:

Manually insert control rods.

Determine both turbine stop valves are closed.

Manually start 12 MDAFW pump.

Initiate normal boration to RCS at 12 to 15 gpm.

Crew will initiate Emergency Boration Transfer running Boric Acid Transfer pump to FAST speed.

Open in-service BAST recirc valve to 50% - CV-31195.

Open Emergency Boration valve - MV-32086.

Dispatch operator to locally open reactor trip breakers or locally open rod drive MG set motor and generator breakers.

Check if reactor is subcritical.

When reactor is < 5%, then return to 1E-0.

Check SG Level 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify reactor trip.

Verify turbine trip.

Verify both safeguards buses ENERGIZED.

Determine SI is NOT actuated nor required.

Go to 1ES-0.1.

1ES-0.1, REACTOR TRIP RECOVERY:

Announce Unit1 reactor trip Transfer steam dump to steam pressure mode END Once the crew has completed critical tasks &

transferred steam dump to steam pressure mode, 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.

Rev. 1 (3/8/2021)

Page 16 of 27 PI-ILT-NRC-2202S, 2022 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

Rev. 1 (3/8/2021) Page 17 of 27 PI-ILT-NRC-2202S, 2022 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 HZZY.

ii. Todays Date.

b. High Flux at Shutdown Alarm Setpoint placards: 5100 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.

Rev. 1 (3/8/2021) Page 18 of 27 PI-ILT-NRC-2202S, 2022 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-241 and go to step 4.

___ 3.

If IC-241 is not available, then perform the following:

a. Reset the Simulator to IC-17 and place in RUN.

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

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

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

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

f.

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

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

h. Withdraw CB-D to 225 steps.

___ 4.

Place the simulator in RUN.

___ 5.

If available, run schedule file PI-ILT-NRC-2202S.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

Rev. 1 (3/8/2021) Page 19 of 27 PI-ILT-NRC-2202S, 2022 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-241 or IC-17.

___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 @ 225.

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

CDC 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: 0%

___ 2.

1HC-111: 44.7%

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a.

RCS boron - 5 ppm.

b.

RCS H2 - 45 cc/kg.

c.

Turbine Reference Value and Mode - matched with DEHC.

___ 2.

Shift Reactivity Guidance placard:

a.

BA: 0 gallons

b.

RMU: 67 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. CS-46425, 12 MD AFWP SEG specific or Out of Service Yellow Caution Tags are in place:

___ 1. CS-46424, 11 TD AFWP

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

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

___ 4. CS-46314, 11 TD AFWP TO 11 STM GEN MV-32238 CS-46315, 11 TD AFWP TO 12 STM GEN MV-32239

Rev. 1 (3/8/2021) Page 20 of 27 PI-ILT-NRC-2202S, 2022 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:

Position the following switches as follows:

___a.

CS-46424, 11 TD AFWP to PULLOUT

___b.

CS-46438, 11 TDAFW PUMP AUTO/MANUAL switch to MANUAL 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 - 1 Hour AVG).

Set Turbine Control HMI Displays as follows:

___ 1.

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

___ 2.

U1 Turb Aux Cont (48088) to Turb Overview

___ 3.

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

___ 4.

DEHC alarms cleared.

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

YELLOW turnover sheets 1-6 available.

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

Board-mounted EAL Tables are cleaned.

Headsets turned on as necessary.

Perform one of the following:

Clear web browser history and recent procedures in pdf.

Complete post-scenario checklist.

Procedure checklist completed. See following page.

Ensure Alarm OOS sticker is REMOVED from C47001-0203, 11 CW Pump High Stator Temp annunciator.

Peer Check performed for simulator setup.

Rev. 1 (3/8/2021) Page 21 of 27 PI-ILT-NRC-2202S, 2022 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

/

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

/

1C5 AOP 1, UNCONTROLLED ROD MOTION

/

1C28.4, UNIT 1 HEATER DRAINS

/

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

/

1C51.3, 1P-478 Blue SG Pressure - Low

/

C47001-0203, 11 CIRC WATER PUMP MOTOR HIGH STATOR TEMP

/

C47011-0304, 12 STM GEN LO-LO PRESS CHANNEL ALERT

/

C47011-0405, FW CONTROL SYSTEM TROUBLE

/

C47011-0504, 12 STM GEN LO PRESS

/

1E-0, REACTOR TRIP OR SAFETY INJECTION

/

1ES-0.1, REACTOR TRIP RECOVERY

/

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

SUMMARY

/

EAL Board

/

1FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS

/

LAMINATE COPY OF 1C5, SECTION 6.5

/

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

/

LAMINATE COPY OF 1C12.5, SECTION 5.10

/

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

/

REACTIVITY BRIEFING SHEET - EOC

/

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

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S. LCO 3.3.2

/

T.S. LCO BASES 3.3.2

/

TRM TLCO 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.

Rev. 1 (3/8/2021) Page 22 of 27 PI-ILT-NRC-2202S, 2022 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 Clear web browser history and recent procedures in pdf.

Computer generated PINGP 577 cleared.

Procedure checklist completed. See previous page.

Remove Pink Status Control Tags from the following equipment:

___ 1.

CS-46425, 12 MD AFWP Magnetic placards removed:

___ 1.

NONE Remove Yellow Caution Tags from the following equipment:

___ 1.

CS-46424, 11 TD AFWP

___ 2.

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

___ 3.

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

___ 4.

CS-46314, 11 TD AFWP TO 11 STM GEN MV-32338

___ 5.

CS-46315, 11 TD AFWP TO 12 STM GEN MV-32339 Board-mounted EAL Table is cleaned.

All books, note pads, and calculators put away.

If desired restore Alarm OOS sticker on C47001-0203, 11 CW Pump High Stator Temp annunciator.

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

Rev. 1 (3/8/2021) Page 23 of 27 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

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

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

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

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

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

CDC Pressure:

2235 PSIG Unit 2 is at 100% power.

Power:

95%

Xenon:

Equilibrium Boron (CB): 0 PPM Rods:

CBD @ 225 TAVG:

560°F Generator:

543 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 Place 12 HDT Pump in Auto and 11 HDT Pump in Manual per 1C28.4 step 6.4.2.

After taking the duty, swap HDT pumps per 1C28.4 and pre-job brief.

NEW PROCEDURES / INSTRUCTIONS of 6

Rev. 1 (3/8/2021) Page 24 of 27 PI-ILT-NRC-2202S, 2022 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 site and/or industry experience.

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.

Rev. 1 (3/8/2021) Page 25 of 27 PI-ILT-NRC-2202S, 2022 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:

Rev. 1 (3/8/2021) Page 26 of 27 PI-ILT-NRC-2202S, 2022 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 Bruce Fauver SRO SS Jason Fox RO LRO Jamie Henthorn RO RO

Rev. 1 (3/8/2021) Page 27 of 27 PI-ILT-NRC-2202S, 2022 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 Insert the SBT Locker G3 flash drive into USB port on PITC01, or equivalent if PC has been swapped, and unlock using provided password. (left side Simulator Booth Instructor Station)

START menu or T-Rex IS desktop icon SBT Report File OPEN Select file type.tis o

(FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT Select SBT.tis OPEN or double click Check TAM log & verify no cycling switches Run scenario AFTER SCENARIO For TREX-Lightning SBT:

o FREEZE on Simulator o

Click GREEN arrow to generate report o

Enter the following:

(NAME is not required)

Test Title (22xx SBT ILT Group x Exam)

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 SBT 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 or T-Rex IS desktop icon o

COMPARE IT o

Click + ADD o

Select.csv file from previously saved location o

OPEN or double click o

Click GREEN COMPARE button o

Wait for spreadsheet to populate and then save in desired location o

Verify all 3 files are saved in proper location o

Close spreadsheet, COMPARE IT, and SBT Report For Ovation SBT:

o Run the Copy Ovation SBT Files.bat file on PITCSIM Desktop in Simulator Computer room.

o Copy the three generated files (Alarms, SLIM, Soft) from Ovation SBT folder located on PITC01\\SimData\\X: (left side Simulator Booth Instructor Station) Desktop to the SBT Locker G3 flash drive.

o Rename the files to correspond with SEG and exam activity.

(e.g. 22xx Ovation SBT {Alarms, SLIM, Soft} ILT Group x Exam) o Delete the generated files from the Desktop folder.

Rev. 1 (3/8/2021) Page 1 of 32 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-2205S SEG TITLE:

2022 ILT NRC SIMULATOR EVALUATION #5 REV. #

0 PROGRAM:

INITIAL LICENSE OPERATOR TRAINING FL-ILT COURSE:

INITIAL LICENSE OPERATOR TRAINING PI-ILT TOTAL TIME: 2.0 HOUR Developed by:

Fred Collins 7/26/22 Instructor Date Reviewed by:

Justin Hasner 7/26/22 Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Fred Collins 7/26/22 Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Jesse Maunu 7/26/22 Training Supervision Date

Rev. 1 (3/8/2021) Page 2 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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.

Form 3.3-1 Scenario Outline Facility: PRARIE ISLAND Scenario #:

5 Scenario Source:

Op. Test #:

NEW PI-ILT-NRC-2205S Examiners:

Applicants / Operators:

Shift Supervisor (SS)

Balance of Plant (LRO)

At the Controls (RO)

Initial Conditions:

Reactor Power:

100%

Xenon:

Equilibrium Boron Concentration:

1186 PPM Rods:

CBD @ 218 STEPS RCS temperature:

560°F Main Generator:

582 MW RCS pressure:

2235 PSIG Turnover:

12 CS Pump OOS Swap reactor makeup pumps per C13.1 Reduce load from 100% to 90% per 1C1.4 Unit 1 Power Operation Critical Tasks:

PI-CT-15: Manually actuate containment cooling as necessary to prevent pressure from exceeding 46 PSIG.

PI-CT-19: Stop feed flow to the faulted Steam Generator prior to an ORANGE/RED Path in Containment CSF.

Event No.

Malf.

No.

Event Type*

Event Description 1

N (BOP)

Swap RX make up pumps 2

R (ATC)

MC (ATC)

N (SS)

Lower reactor power to 90%

3 1

TS (SS) 11 SG Steam Flow Red channel fails high 4

2 I (ATC, BOP, SS)

MC (ATC)

TS (SS)

PRZR Level Blue channel (controlling) fails high 5

3 C (BOP, SS)

B Condenser Air In-Leakage 6

4 M (ALL) 12 SG faulted to CTMT 7

5 C (BOP, SS)

D1 fails to automatically start 8

6 C (BOP, SS)

MC (BOP)

BKR 8H-16 fails to open

Rev. 1 (3/8/2021) Page 3 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 RMU Pumps per C13.1.

2.

Perform a load reduction from 100% to 90% power per 1C1.4.

Evaluate the crews ability to diagnose and respond to:

3.

11 SG Steam Flow Red Channel Fails High per 1C51.1.

4.

Blue channel (controlling) PRZR Level Fails High per 1C51.3.

5.

B Condenser Air In-Leakage per C26.

6.

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

7.

D1 Fails to Auto Start per 1E-0 ATT L.

8.

BKR 8H-16 Fails to Open per 1E-0 ATT L.

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 (12.8%)

Important Components:

11 CS PMP Important Operator Actions with Task Number:

Operators fail to isolate AFW to affected SG (PI-CRO-301-003 - Faulted Steam Generator Isolation)

Rev. 1 (3/8/2021) Page 4 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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. 11 SG Steam Flow Red Channel Fails High

2. Blue Channel (Controlling) PRZR Level Fails High.

3. B Condenser Air In-Leakage.

After EOP Entry:

1. 11 CS pump fails to start automatically.

2. CFCUs fail to start in SLOW after SI.

Abnormal Events:

1. Instrument Failure Guide Steam Flow Failure.

2. Instrument Failure Guide PRZR Level Failure.

3. ARP for Condenser Air In-Leakage.

Major Transients:

1. Faulted 12 SG inside CTMT.

Critical Tasks:

1. PI-CT-15: Manually actuate containment cooling as necessary to prevent containment pressure from exceeding 46 PSIG.

2. PI-CT-19: Stop feed flow to the faulted Steam Generator prior to an ORANGE/RED Path in Containment CSF.

Rev. 1 (3/8/2021) Page 5 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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-15 Critical Task:

Manually actuate containment cooling as necessary to prevent containment pressure from exceeding 46 PSIG.

Safety Significance:

Failure to actuate sufficient containment cooling during a high energy release into containment will result in containment pressure exceeding the design limit of 46 PSIG. Exceeding this limit will result in a loss of the Containment Barrier.

Initiating Cue:

Containment pressure is rising.

Containment cooling equipment fails to start, actuate, or align to their safeguards alignment.

Performance Feedback:

Containment pressure lowering or stable below 46 PSIG.

Plant Conditions/

Success Path:

At least one of the following accidents:

o LOCA into Containment.

o Un-isolable Steam Line Break into Containment.

Containment pressure will exceed 46 PSIG if no operator action is taken to start available containment cooling equipment.

o Sufficient containment cooling equipment is available to start from the Control Room to prevent containment pressure from exceeding 46 PSIG.

Measurable Performance Standard:

Starting, actuating, or aligning the following equipment, as necessary, to establish sufficient containment cooling to prevent containment pressure from exceeding 46 PSIG:

o One of the following Containment Fan Coil Units (CFCUs):

CS-46018, 11 CFCU, to SLOW CS-46019, 13 CFCU, to SLOW Cooling Water / Chilled Water supply to CFCUs. (n/a for this scenario)

Containment Spray System CS-46008, 11 CS PUMP, to START

Rev. 1 (3/8/2021) Page 6 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 prior to an ORANGE/RED Path in Containment CSF.

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 as well as challenging minimum feedwater flow to the intact Steam Generator.

Initiating Cue:

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

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

Performance Feedback:

AFW flow to the faulted Steam Generator is secured.

Feed Water Flow to the faulted Steam Generator is secured.

Plant Conditions/

Success Path:

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.

Measurable Performance Standard:

Stop feed flow to the faulted Steam Generator by Closing/Securing the following valves and/or pumps aligned to the faulted Steam Generator (as necessary):

o AFW Pump Discharge Valve(s)

CS-46317, 12 MDAFWP TO 12 SG MV-32382, to CLOSE CS-46315, 11 TDAFWP TO 12 SG MV-32239, to CLOSE o

AFW Pump(s) (n/a for this scenario) o Main and Bypass Feed Water valve(s) (n/a for this scenario) o MFW Pump(s) (n/a for this scenario)

Rev. 1 (3/8/2021) Page 7 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 12 CS Pump Power: 100%

Boron: (CB): 1186 ppm Temperature: 560°F Pressure: 2235 psig Xenon: Eq Rods: D @ 218 Generator: 582 MW SEQUENCE OF EVENTS:

Event 1: Swap RMU Pumps The crew start 12 RMU Pump and stop 11 RMU Pump per C13.1 Event 2: Reduce Reactor Power to 90%

The crew will place rods in manual.

The crew will perform borations per 1C12.5.

The crew will operate the turbine to reduce load.

Event 3: 11 SG Steam Flow Red Channel Fails High 1FI-464 Fails High.

The crew will respond to C47011-0405 & C51.1.

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

Event 4: Blue Channel PRZR Level Fails High Charging will go to minimum and backup heaters will energize.

The crew will select 2-1 (White-Red) on PRZR Level control.

The crew will return PRZR heaters and charging pump speed to auto.

The SS will enter TS LCO 3.3.1 Condition A and K.

Event 5: B Condenser Air In-Leakage B condenser will develop in-leakage, resulting in lowering vacuum and rising condenser vacuum D/P.

The crew will place the standby air ejector in service on the B condenser.

Event 6: 12 Steam Generator Fault to CTMT:

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

The reactor will trip and SI will actuate.

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

The 11 CS pump will fail to start automatically and CFCUs will fail to start in slow.

The crew will respond to high CNTMT pressure per 1FR-Z.1.

Event 7: D1 Fails to Auto Start D1 fails to auto start.

The crew will start D1 EDG per 1E-0 ATT L.

Event 8: BKR 8H-16 Fails to Open 8H16, 345 KV Substation Breaker, will fail to open automatically after the turbine trip.

The crew will open 8H-16 per 1E-0 ATT L.

Rev. 1 (3/8/2021)

Page 8 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 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

Rev. 1 (3/8/2021)

Page 9 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 EVT 1 After the crew has assumed the duty and/or at the discretion of the Lead Evaluator, direct the crew to swap RMU Pumps.

Booth Operator / Communicator:

1.

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

BOP (N)

C13.1, REACTOR MAKEUP SYSTEM Verify the standby reactor makeup tank is NOT aligned for degasification.

Start the oncoming Reactor Makeup Pump:

CS-46117, 12 RX M-U PMP START/STOP CS Stop the off-going Reactor Makeup Pump:

CS-46116, 11 RX M-U PMP START/STOP CS Check 47022-0601, UNIT 1 REACTOR MAKEUP LO PRESS, is NOT LIT.

Rev. 1 (3/8/2021)

Page 10 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 EVT 2 Booth Operator / Communicator:

1. After the crew has swapped RMU Pumps and/or at the discretion of the lead evaluator, then:

As the Shift Manager, direct the Unit 1 SS to reduce Unit 1 Reactor Power to 90%.

2. If contacted as the duty chemist, acknowledge Unit 1 power will be reduced from 100% to 90%.

Plant Response:

1. Reactor Power lowers.

2. Generator Load lowers.

3. RCS Tavg lowers.

ATC (R)

SS (N) 1C1.4, UNIT 1 POWER OPERATION Place CS-46280, ROD BANK SELECTOR, in MANUAL.

Using the On Line Control screen:

o Select FSP.

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 a boration of the RCS per 1C12.5.

When Tave shows a decrease, then select the Go control using the On Line Control screen.

Adjust the boration rate or perform batch borations per 1C12.5 to maintain Tave and Tref with the desired 1.5°F band.

1C12.5, UNIT 1 BORON CONCENTRATION CONTROL Place CS-46300, MAKE-UP MODE SELECTOR, to BORATE.

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

Align 1HC-110, BA TO BLENDER FLOW CONT, auto setpoint dial to the flow rate desired.

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

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

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, or manually stop the makeup by placing CS-46457 to STOP.

Reset the Boric Acid Integrator Verify 1HC-110 is in auto.

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

Set 1YIC-111 to desired quantity.

If desired, place CS-46454 to CLOSE during ALT DIL.

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

Verify desired makeup water flow rate.

When desired quantity of RMU water has been added, then verify automatic makeup has stopped.

Verify CS-46454 is selected to AUTO.

Rev. 1 (3/8/2021)

Page 11 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 Place CS-46300 in AUTO, Momentarily place CS-46457 to START.

Reset 1YIC-111.

Rev. 1 (3/8/2021)

Page 12 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 EVT 3 Booth Operator / Communicator:

1.

After the crew has swapped Reactor Makeup Pumps and has started the downpower, and/or at the discretion of the Lead Evaluator, enter:

Trigger 1, 11 SG Steam Flow Red Channel Fails High

2.

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

3.

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

4.

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

Plant Response:

1. 1FI-464 fails high.

2. The following annunciators will be received:

a. 47011-0201 11 STM GEN HI-HI STM FLOW

b. 47011-0203 11 STM GEN ISOLATION CHANNEL ALERT.

c. 47011-0405 FW CONTROL SYSTEM TROUBLE SS (TS)

C47011-0201 11 STM GEN HI-HI STM FLOW Check steam flow channels IF channel failed, THEN refer to 1C51, Instrument Failure Guide.

1C51.1 11 SG STEAM FLOW 1F-464 - HIGH Verify SG level control operating properly in automatic.

Refer to the following Technical Specification requirements:

o T.S. LCO 3.3.2 Condition A and Table 3.3.2-1 Functions 4d, 4e The SS will enter the following TS LCOs:

3.3.2 Condition A:

o Enter conditions referenced in Table 3.3.1-1 IMMEDIATELY.

3.3.2 Condition D (functions 4d & 4e):

o Place channel in trip in 6 HOURS OR o In accordance with the Risk Informed Completion Time Program

Rev. 1 (3/8/2021)

Page 13 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 EVT 4 Booth Operator / Communicator:

1.

After the crew has addressed T.S. and/or at the discretion of the Lead Evaluator, enter:

Trigger 2, PRZR Level Blue Channel 1L-428 Fails High

2.

If contacted as an I&C Supervisor 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 maintenance notification, CAP, work request, and assign an I&C Supervisor to investigate.

Plant Response:

1.

1LT-428 Fails High

2.

Charging will go to minimum

3.

Backup Heaters in auto will energize

4.

The following annunciators will be received:

a.

47012-0307, PZR HI LVL CHANNEL ALERT

b.

47012-0507, PZR LEVEL DEVIATION

c.

47015-0203, CHARGING PUMP IN AUTO TROUBLE ATC (I)

ATC (MC)

BOP (I)

SS (I)

SS (TS)

C47012-0307, PRZR HI LVL CHANNEL ALERT Check pressurizer level Control level in manual Refer to 1C51, Instrument Failure Guide 1C51.3, INSTRUMENT FAILURE GUIDE 1LT-428 -

HIGH:

If the Blue channel is selected on the PRZR Level Control Selector Switch, Then:

Control PRZR heaters manually Place charging pump speed control in Manual and adjust pressurizer level to setpoint Select position 2-1 (White-Red) on PRZR Level Control Selector switch.

Return pressurizer heaters to Auto Return one charging pump speed control to Auto Ensure pressurizer level recorder not selected to Blue 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 (function 9):

o Place channel in trip in 6 HOURS

Rev. 1 (3/8/2021)

Page 14 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 EVT 5 Booth Operator/Communicator:

After the crew has selected 2-1 (White-Red) on PRZR Level Control Selector switch &

addressed T.S.s, and/or at the discretion of the Lead Evaluator then enter:

Trigger 3: B Condenser Air Leak

1. If asked to check for local leaks, then wait 2 minutes and report that a loud whistling sound can be heard near the 'B' condenser, but that the exact location cannot be determined

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, inform the crew that you will write a maintenance notification, CAP, work request, and assign an I&C Supervisor to investigate.

Plant Response:

1. The following indications will be observed:

1) B condenser vacuum will decrease

2) MWe decrease slightly

3) The condenser p indicator will increase

4) ERCS alarm Hi Air Ejector Air Flow AR 34

5) 47009-0501, 1A CONDENSER HOTWELL HI LVL

6) 47008-0409, TURBINE CONTROL SYSTEM ALARM

2. If the standby air ejectors are not placed in service, condenser vacuum decreases to the Cond Lo Vacuum alarm in ~16 minutes.

3. If standby air ejector is placed in service on B condenser, 1B vacuum will stabilize at ~ 26.4 Hg.

BOP (C)

SS (C)

ERCS AR-34 (C47041), 11(21) AIR EJECTOR AIR LEAKAGE FLOW Open the associated Air Ejector After Condenser drain valve:

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

o

[SV-33342, AIR ECJTR LOOP SEAL DRN, using CS-46800.]

Maintain loop seal drain open unitl all concerns are addressed.

If alarm is associated with a loss of condenser vacuum, refer to C26, AIR REMOVAL SYSTEM, to restore condenser vacuum.

C47008-0209, CONDENSER LO-LO VACCUUM Verify: gland seal steam pressure, vacuum breakers closed, air ejectors functioning, and Circulating Water flow.

The crew places the standby set of air ejectors in service per C26, Air Removal System.

C26, AIR REMOVAL SYSTEM Open MV-32328, STBY AIR EJCTR STM SPLY, using CS-46402.

Open MV-32358, STBY SECONDARY AIR EJCTR SUCT, using CS-46400.

Open MV-32347, STBY PRIMARY AIR ELCTR SUCT FROM B CDSR, using CS-46399.

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

Rev. 1 (3/8/2021)

Page 15 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 EVTs 6, 7, &

8 Booth Operator / Communicator:

1. When the SS has placed STBY Air Ejector in service, and/or at the discretion of the Lead Evaluator, then enter:

Trigger 4, 12 SG Fault Inside CTMT.

2. When the reactor trip breakers open, then verify:

Auto Trigger 5 is entered to cause a loss of CTMT Cooling.

3. Upon 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.

4. Upon 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.

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

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

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

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

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

ATC (M)

BOP (M)

SS (M)

CT-19 CT-15 1E-0, REACTOR TRIP OR SAFETY INJECTION:

Verify the reactor is tripped.

Verify the turbine tripped.

Verify both Safeguards buses energized.

Verify SI is actuated.

Perform Attachment L (see SEG page 16)

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.

o Close 12 MSIV 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 12 TD AFWP.

o Verify 12 SG PORV is closed.

o Verify 12 SGB isolation valve is closed.

o Dispatch operator to close TD-4-1.

Verify 12 SG MSIV and bypass valves are closed.

Check CST levels greater than 12,500 gallons.

Check secondary radiation normal.

Go to 1E-1.

1FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE:

Verify CI valves closed.

Check CS ACTUATED.

Verify CS pumps running.

Verify FCUs running slow to the dome.

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

Determine RCPs do not need to be 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.

Rev. 1 (3/8/2021)

Page 16 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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

10. If dispatched to close TD-4-1, 12 SG MS DRN TO TRAP 3, wait four minutes and report TD-4-1 is closed.

11. If dispatched to turn on BKR 111J-3 (MCC 1K1A2), VCT TO CHG PMPS ISOL MV-32061, wait 2 minutes, insert remote VC155 to ON. Report back that the breaker is on.

Plant Response:

1. 12 SG pressure lowers rapidly.

2. RCS & PRZR pressure lower.

3. Containment Pressure rises.

4. 11 CS Pump & all CFCUs fail to start.

CS #

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

OPEN 46338 STEAM DUMP MODE STM PRESS (Align due to Malfunctions) 46008 11 CNTMT SPRAY PUMP*

ON 46018 11 CFCU SLOW 46019 13 CFCU SLOW 46935 D1 EDG START 46381 8-H-16, 345 kV SUBSTATION BREAKER OPEN

11 Containment Spray Pump will only be started if containment pressure exceeds 23 psi.

CRITICAL TASKS PI-CT-15: Manually actuate containment cooling as necessary to prevent pressure from exceeding 46 psig.

PI-CT-19: Stop feed flow to the faulted Steam Generator prior to an ORANGE/RED Path in Containment CSF.

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

CT-15 SS (C)

BOP (C)

SS (C)

BOP (C)

BOP (MC)

Check offsite power available to charging pumps.

Determine if SI pumps can or cannot be stopped.

(May transition to 1ES-0.2)

Stop RHR pumps.

1E-0 Attachment L: SI Alignment Verification:

Verify Safeguards Component Alignment o

See table on page 16 Close MV-32115, 122 SFP HX INLT HDR MV B Check Cooling Water Header Pressures Verify plant announcements complete Check If Main Steamlines Are required to be isolated Verify SI & RHR Flow Check RCP Cooling Verify Generator Breakers - OPEN Verify All Heater Drain Pumps - STOPPED Open turbine drain valves Verify Main Feedwater Alignment Verify All Condensate Pumps - STOPPED Place Steam Dump in "STM PRESS" Mode Verify Unit 1 Cooling Water/Chilled Water Alignment Verify 11 Safeguards Screenhouse Ventilation lineup Verify Control Room Ventilation Alignment Verify Unit 2 Cooling/Chilled Water Alignment Verify 21 Safeguards Screenhouse Ventilation lineup Verify 11 and 12 Battery Charger Operation is normal Verify Battery Room temps less than 84°F Check status of Spent Fuel Cooling Check Status Of Notifications Notify SS Of Any Discrepancies EXAMINER NOTE:

Close B MSL if not already closed.

Rev. 1 (3/8/2021)

Page 17 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 stopped ECCS pumps, completed critical tasks and completed faulted portions of ATT L, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew training has the duty.

Booth Operator:

Collect SBT data per Attachment 1, if necessary.

Rev. 1 (3/8/2021)

Page 18 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 5

RX TRIP - LOSS OF CTMT COOLING ZRPG439(1)==1 6

11 CFCU to SLOW HWZCHOFCF(1)==1 7

13 CFCU to SLOW HWZCHOFCF(3)==1

Rev. 1 (3/8/2021) Page 19 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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:

1st / 2nd

___ / ___ 1. If it is the first scenario of the day, then perform a shutdown and restart of the floor PCs that are connected to the LAN.

___ / ___ 2. Log in on floor PCs.

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

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

a.

NRC Code Placard:

i.

NRC Current Authentication Code HZZY.

ii.

Todays Date.

b.

High Flux at Shutdown Alarm Setpoint placards: 5100 cps.

c.

Feedwater regulating valve position placard set to current values.

d.

Recommended SG Blowdown flow set to current values.

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

a.

Blowdown 46470 SGB To 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

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

a.

CS-46540, 22 CC WTR PUMP

b.

CS-46572, 121 SFP HX INLT

___ / ___ 7. Verify that copy machine and printers are loaded with YELLOW BORDER paper.

___ / ___ 8. Pens/Notepads/Markers available on the simulator.

Rev. 1 (3/8/2021) Page 20 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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.

1st / 2nd

___ / ___ 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 and place in RUN.

___ / ___ 3. If IC-244 is not available, then perform the following:

a. Reset the Simulator to IC-10 and place in RUN.

b. Energize all PRZR Backup Heaters.

c. Place both 40 GPM LTDN orifices in service.

___ / ___ 4. Place the following equipment in the listed condition:

a. CS-46009, 12 CS PUMP, to PULL TO LOCK

___ / ___ 5. If available, run schedule file PI-ILT-NRC-2205S.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 available, run event file PI-ILT-NRC-2205S.evt as follows:

a.

Select open file in the Event application.

b.

Locate event file.

c.

Open event file by double clicking it.

___ / ___ 7. If event file is NOT available, then enter event codes as specified by the Simulator Event Summary.

___ / ___ 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 Att 1.

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

Rev. 1 (3/8/2021) Page 21 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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:

1st / 2nd

_ _/ _

Simulator Status:

_ _/ _

___1.

"Training Load"

___2.

Alarm sound: ON

___3.

Speed: REAL

___4.

Step counters: NOT USED

___5.

Simulator running in IC-244 or IC-10.

___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 Event File/Summary matches Simulator Input Summary page in the SEG.

_ _/ _

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

_ _/ _

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

_ _/ _

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: 26.4%

___ 2.

1HC-111: 44.7%

_ _/ _

Update or Verify SEG specific Control Board Placards:

___ 1.

CVCS panel placard:

a. RCS boron - 1186 ppm.

b. RCS H2 - 45 cc/kg.

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

___ 2.

Shift Reactivity Guidance placard:

a. BA: 3.8 gallons

b. RMU: 67 gallons

c. Dilutions @ 20 gal RMU, 1-2 times per shift.

___ 3.

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

___ 4.

LCO Timer CLEANED.

_ _/ _

SEG specific Magnetic Placards in place:

___ 1. NONE

_ _/ _

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

___1. CS-46008, 11 CNTMT SPRAY PUMP

___2. CS-46018, 11 CNTMT FAN COIL UNIT

___3. CS-46019, 13 CNTMT FAN COIL UNIT

_ _/ _

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

___ 1. CS-46009, 12 CS PUMP

Rev. 1 (3/8/2021) Page 22 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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:

1st / 2nd

_ _/ _

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 - 1 Hour AVG).

_ _/ _

Set Turbine Control HMI Displays as follows:

___ 1.

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

___ 2.

U1 Turb Aux Cont (48088) to Turb Overview

___ 3.

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

___ 4.

DEHC alarms cleared.

_ _/ _

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

_ _/ _

YELLOW turnover sheets 1-6 available.

_ _/ _

All Fire alarms CLEAR.

_ _/ _

Board-mounted EAL Tables are cleaned.

_ _/ _

Headsets turned on as necessary.

_ _/ _

Procedure checklist completed. See following page.

_ _/ _

Peer Check performed for simulator setup.

Rev. 1 (3/8/2021) Page 23 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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

/

1C1.4, UNIT 1 POWER OPERATION

/

/ 1C12.5, UNIT 1 BORON CONCENTRATION CONTROL

/

/ C13.1, REACTOR MAKEUP SYSTEM

/

/ C26, AIR REMOVAL SYSTEM

/

/ 1C51.1, 11 SG STEAM FLOW 1F-464 - HIGH

/

/ 1C51.3, PRZR LEVEL 1LT-428 - HIGH

/

/ C47008-0209, CONDENSER LO-LO VACUUM

/

/ C47011-0201, 11 STM GEN HI-HI STM FLOW

/

C47011-0203, 11 STM GEN ISOLATION CHANNEL ALERT

/

C47011-0405, FW CONTROL SYSTEM TROUBLE

/

C47012-0307, PRZR HI LVL CHANNEL ALERT

/

C47041, ERCS AR 34 AIR ELECTOR LEAKAGE FLOW

/

/ 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

/

1FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE

/

EAL Board

/

LAMINATE COPY OF 1C5, SECTION 6.5

/

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

/

LAMINATE COPY OF 1C12.5, SECTION 5.10

/

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

/

REACTIVITY BRIEFING SHEET - MOC

/

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

/

T.S. LCO 3.3.1

/

T.S. LCO BASES 3.3.1

/

T.S. LCO 3.3.2

/

T.S. LCO BASES 3.3.2 NOTE: The following procedures will be used during this session. Verify the procedures are free of place keeping marks before starting the session and after the session are complete.

Rev. 1 (3/8/2021) Page 24 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 1st / 2nd

_ _/ _

Computer generated PINGP 577 cleared and tab closed.

_ _/ _

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

_ _/ _

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

_ _/ _

Procedure checklist completed. See previous page.

_ _/ _

Remove Pink Status Control Tags from the following equipment:

___ 1.

CS-46008, 11 CNTMT SPRAY PUMP

___ 2.

CS-46018, 11 CNTMT FAN COIL UNIT

___ 3.

CS-46019, 13 CNTMT FAN COIL UNIT

_ _/ _

Remove Magnetic placards from Control Boards:

___ 1.

EAL Classification Placard from Control Board.

___ 2.

RED/WHITE Critical Parameter Cards

_ _/ _

Remove Yellow Caution Tags from the following equipment:

___ 1.

CS-46009, 12 CS PUMP

_ _/ _

Board-mounted EAL Table is cleaned.

_ _/ _

All books, note pads, and calculators put away.

End Of Day Checklist 1st / 2nd

_ _/ _

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

_ _/ _

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

_ _/ _

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

Rev. 1 (3/8/2021) Page 25 of 32 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 12 CONTAINMENT SPRAY Pump is OUT OF SERVICE o T.S. LCO 3.6.5 Condition A was entered with 56 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months remaining.

o Expect the 12 CS pump to be returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

PROTECTED EQUIPMENT 11 CS PUMP 11 CFCU 13 CFCU SFP COOLING 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): 1186 ppm Temperature: 560°F Pressure: 2235 psig Xenon: Equilibrium Rods: D @ 218 Generator: 582 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT Prior to entering the simulator:

o Review the reactivity plan.

o Perform a Pre-Job Brief for load reduction and swapping RMU Pumps.

When directed by the Shift Manager, reduction load per steps 6.2.11 - 6.2.13.F of 1C1.4.

Suspend the load reduction at 90% per step 6.2.13.G of 1C1.4.

Steps 6.2.1 - 6.2.10 of 1C1.4 are complete. Pressurizer heaters are energized and a second 40 gpm letdown orifice is in service.

Dilute 20 gallons 1-2 times per shift for temperature control.

NEW PROCEDURES / INSTRUCTIONS NONE of 6

Rev. 1 (3/8/2021) Page 26 of 32 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 REDUCTION from 100% to 90%.

2. Current conditions:

Power level:

100% (582 MW)

Xenon:

Equilibrium Control Rod Position:

Bank D @ 218 steps Boron Concentration:

1186 ppm Core Exposure:

13000 MWD/MTU

3. Reactivity Plan:

Target:

Turbine Load: 524.4 MW (90%), 472.4 PSIG (FSP)

Rate:

0.50%/minute Control Mode:

FSP control with Rod Control in MANUAL Boration/Dilution:

33.5 gallon BORATION (batch)

Final Control Rod Position:

Bank D @ 208 steps

4. Reactivity Prediction:

Change in Power Defect:

160 pcm (Figure C1-7A)

Differential Boron Worth:

-6.3 pcm/ppm (Figure C1-11A)

Differential Rod Worth:

2.37 pcm/step (Figure C1-4A)

Calculated RCS PPM change: 21.6 ppm (-136.3 pcm ÷ -6.3 pcm/ppm)

Calculated Rod Step change: -10 steps (23.7 pcm ÷ 2.37 pcm/step)

Rev. 1 (3/8/2021) Page 27 of 32 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 28 of 32 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 1 (3/8/2021) Page 29 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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.

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.

Rev. 1 (3/8/2021) Page 30 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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:

Rev. 1 (3/8/2021) Page 31 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 Todd Strain SRO SS Jaimie Henthorn RO RO/ATC Jason Fox RO LEAD/BOP

Rev. 1 (3/8/2021) Page 32 of 32 PI-ILT-NRC-2205S, 2022 ILT NRC SIMULATOR EVALUATION #5, 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 Insert the SBT Locker G3 flash drive into USB port on PITC01, or equivalent if PC has been swapped, using provided password. (left side Simulator Booth Instructor Station)

START menu or T-Rex IS desktop icon SBT Report File OPEN Select file type.tis o

(FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT Select SBT.tis OPEN or double click Check TAM log & verify no cycling switches Run scenario AFTER SCENARIO For TREX-Lightning SBT:

o FREEZE on Simulator o

Click GREEN arrow to generate report o

Enter the following:

(NAME is not required)

Test Title (22xx SBT ILT Group x Exam)

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 SBT 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 or T-Rex IS desktop icon o

COMPARE IT o

Click + ADD o

Select.csv file from previously saved location o

OPEN or double click o

Click GREEN COMPARE button o

Wait for spreadsheet to populate and then save in desired location o

Verify all 3 files are saved in proper location o

Close spreadsheet, COMPARE IT, and SBT Report For Ovation SBT:

o Run the Copy Ovation SBT Files.bat file on PITCSIM Desktop in Simulator Computer room.

o Copy the three generated files (Alarms, SLIM, Soft) from Ovation SBT folder located on PITC01\\SimData\\X: (left side Simulator Booth Instructor Station) Desktop to the SBT Locker G3 flash drive.

o Rename the files to correspond with SEG and exam activity.

(e.g. 22xx Ovation SBT {Alarms, SLIM, Soft} ILT Group x Exam) o Delete the generated files from the Desktop folder.

ML22236A666

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML22236A666

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search