Text

2016 Monticello Nuclear Generating Plant Initial License Examination Proposed Simulator Scenarios
	ML17142A425
Person / Time
Site:	Monticello
Issue date:	05/18/2017
From:	David Reeser; NRC/RGN-III/DRS/OLB
To:	; NRC/RGN-III/DRS/OLB
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Appendix D Scenario Outline Form ES-D-1 Facility: MONTICELLO Scenario No.: 1 Op-Test No.: 2016-301 Examiners: Operators:

Initial Conditions: 100% Power; There are 4 control rods with slow scram times (38-47, 42-43, 46-39, and 50-31); HPCI is in PTL due to inadvertent initiation the previous shift.

Turnover: 12 EDG Monthly Surveillance test in progress, ready to unload.

Event Malfunction Event Event No. No. Type* Description 1 N (BOP) EDG 12 Monthly Surveillance Test

The BOP will unload and shutdown 12 EDG 2 C (BOP) The Main Seal Oil Pump (MSOP) will trip and the Emergency Seal Oil Pump (ESOP) will fail to auto start. The BOP will take action to start the ESOP.

3 C/TS (SRO) #10 Transformer Lockout

CRS will address TS for a loss of an offsite power source (1AR) 4 C (OATC) CRD Flow Control Valve Fails Open resulting in CR 26-27 drifting in 1 notch.

OATC will discover the flow control valve failure and swap CRD flow control valves 5 R (OATC) Crew will be directed by Nuclear Engineering to perform a power reduction to 97-98% with Recirc flow and then fully withdraw the drifted control rod.

6 C (OATC) When withdrawing the drifted control rod it will become TS (SRO) uncoupled. The OATC will take actions for an uncoupled control rod and the CRS will evaluate TSs.

7 M Station Power Transfer - Scram w/electrical ATWS C (BOP)

A 2R Lockout will occur requiring the crew to scram on degrading condenser vacuum

An ATWS will occur, the OATC will be successful with ARI (CT) 8 C-(POST) A steam leak will occur in the HPCI room. HPCI will fail to auto-isolate requiring the crew to manually isolate HPCI when a max-safe temperature is received (CT).

9 C-(POST) A 1R Lockout will occur causing a LOOP, 11 EDG-ESW pump and 12 EDG will fail to auto start. The BOP will be required to: manually start or cross-connect 11 EDG-ESW with Service Water; OR manually start and ensure loading of 12 EDG. (CT)

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

QF107502 Rev. 4 (FP-T-SAT-75)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-40E SEG TITLE: 2016 ILT NRC SCENARIO 1 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME: 45-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 2 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Guide Requirements This Scenario evaluation has been written for the 2016 ILT NRC Goal of Exam. Once this exam is complete and exam security is relaxed, Training: this SEG should be appropriate to use for the following activities:

Future ILT NRC / Audit Exam Evaluations

SRO Certification Evaluations

LOR Crew development

1. Demonstrate the ability to predict and/or monitor changes in Learning parameters associated with operating system controls for the Objectives: appropriate tasks.

2. Demonstrate the ability to correctly use procedures to correct, control, or mitigate the consequences of normal and abnormal operations for the appropriate tasks.

3. Demonstrate the ability to monitor automatic operations of the systems to ensure proper operation for the appropriate tasks.

4. Demonstrate the ability to manually operate and/or monitor systems in the control room in accordance with approved procedures for the appropriate tasks.

5. Demonstrate the ability to complete administrative requirements, as necessary, in order to operate the plant for the appropriate tasks.

6. Demonstrate knowledge of and ability to implement shift supervision duties as they relate to crew operations for the appropriate tasks.

7. Given a degrading or improving plant condition or event, demonstrate the ability to: (CRS)

a. Evaluate trends that may result in equipment damage or reduction in plant safety.

b. Ensure proper diagnosis of plant problems by monitoring and interpreting data (information from panel indications).

c. Evaluate and diagnose challenges to Critical Plant Parameters.

d. Evaluate events and accidents.

1. Completion of the MT-ILT Training Program, or Prerequisites: 2. Completion of the SRO Certification Program, or

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 3 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0

1. Full Scope Simulator Training 2. MTF-7100-051 (Attendance Record) or LMS Equivalent Resources: 3. 3139 (Control Room Shift Turnover Checklist)

4. 3140 (Shift Supervisors Office Shift Turnover Checklist)

5. Lead Instructor - Crew Turnover Brief paperwork

1. 0187-02B (12 EDG/12 ESW MONTHLY PUMP AND VALVE TEST)

References:

2. 8-A-22 (NO. 1 GEN H2 SYSTEM TROUBLE)

3. 83-B-6 (EMERG SEAL OIL PUMP RUNNING)

4. 8-A-3 (345 KV & 115 KV YARD TROUBLE)

5. LCO 3.8.1 (OFFSITE SOURCES)

6. 5-A-27 (ROD DRIFT)

7. C.4-B.01.03.C (CONTROL ROD DRIFTING)

8. B.01.03-05.E.4 (PLACING THE STANDBY CRD FLOW CONTROL VALVE INTO SERVICE)

9. C.4-F (RAPID POWER REDUCTION)

10. 5-A-11 (ROD OVERTRAVEL)

11. LCO 3.1.3 (CONTROL RODS)

12. 8-B-02 (NO. 2R XFMR LOCKOUT)

13. 5-B-20 (CONDENSER LO VACUUM SCRAM TRIP)

14. C.4.K (IMMEDIATE REACTOR SHUTDOWN)

15. C.4-A (REACTOR SCRAM)

16. C.5-1100 (RPV CONTROL)

17. C.5-2007 (FAILURE TO SCRAM)

18. C.5-3301 (DEFEAT MSIV LOW-LOW LEVEL ISOLATION)

19. C.5-3101 (ALTERNATE ROD INSERTION)

20. 8-C-04 (NO. 1R RES TRANS LOCKOUT)

21. C.4-B.09.02.B (LOSS OF NORMAL OFFSITE POWER)

22. B.08.01.02-05.H.3 (TRANSFER EDG COOLING FROM EDG-ESW TO SERVICE WATER)

23. 3-B-56 (HIGH AREA TEMP STEAM LEAK)

24. C.4-B.04.01.D (GROUP 4 ISOLATION)

25. C.5-1300 (SECONDARY CONTAINMENT CONTROL)

1. None Commitments:

The following methods are acceptable methods for examinee evaluation:

Evaluation

2016 ILT NRC Exam Process (NUREG 1021 & FP-T-SAT-72)

Method:

MT-ILT (MNGP ILT Program Description)

M-9700 (SRO Certification Program Description)

FP-T-SAT-73 (Licensed Operator Requalification Program)

Not Applicable to Evaluation Scenarios Operating Experience:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 4 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Initiating Event with Core Damage Frequency:

Related PRA Information:

Important Components / Accident Class:

Important Operator Actions with Task Number:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 5 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

SS299.356 Apply Admin requirements for TS 3.8 and Bases. 5-7 SS315.167 Direct the response to a control rod drifting 5-7 SS315.159 Supervise rapid power reduction 5-7 SS299.349 Apply admin requirements to TS 3.1 and Bases 5-7 SS315.164 Supervise immediate reactor shutdown 5-7 SS315.101 Supervise response to a reactor scram 5-7 SS304.193 Implement RPV Control 5-7 SS304.201 Implement the response for a failure to scram 5-7 SS314.111 Supervise defeat of RPV Low-Low Level Isolation for MSIV closure 5-7 SS314.101 Supervise alternate rod insertion 5-7 SS315.137 Supervise response to a loss of normal off-site power 5-7 SS315.115 Supervise response to a Group 4 isolation 5-7 RO Tasks:

CR299.358 Apply TS 3.8 and Bases 5 CR200.226 Respond to a control rod drifting 1-4 CR201.111 Place the standby CRD Flow Control Valve in service 1-4 CR200.203 Perform the procedure for rapid power reduction 1-4 CR299.351 Apply TS 3.1 and Bases 5 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR200.146 Perform the procedure for a reactor scram 1-4 CR304.102 Perform actions associated with RPV Control 1-4 CR314.104 Perform actions associated with failure to scram 1-4 CR314.115 Defeat RPV Low-Low Level Isolation for MSIV closure 1-4 CR314.105 Perform actions associated with alternate rod insertion 1-4 CR200.181 Perform the procedure for loss of normal off-site power 1-4 CR200.160 Perform the procedure for a Group 4 isolation 1-4 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 6 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Main Seal Oil Pump trip

2. #10 Transformer Lockout

3. CRD Flow Control Valve fails OPEN causing rod to drift

4. Uncoupled Control Rod

5. Station Power Transfer with electrical ATWS After EOP Entry:

1. Loss of All Offsite Power

2. 11 EDG-ESW pump fails to start

3. 12 EDG fails to start

4. HPCI Steam Line rupture Abnormal Events:

1. Control Rod Drift

2. Loss of All Offsite Power

3. Group 4 Isolation Major Transients:

1. Loss of All Offsite Power with EDG failures Critical Tasks:

1. CT-47: During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained within C.5-3101 to achieve reactor shutdown under all conditions.

2. CT-34: When a system fails to isolate, manually isolate the system prior to exceeding max safe operating values in two areas.

3. CT-EDG: Under a loss of all off-site power condition, maintain and/or restore electrical power to an essential bus prior to reaching TAF.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 7 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO OVERVIEW:

Event 1: 12 EDG Monthly Surveillance Test (0187-02B)

BOP will continue Test 0187-02B with steps to unload and shutdown 12 EDG.

Event 2: Trip of Main Seal Oil Pump (MSOP)

After shutting down the 12 EDG, the MSOP will trip and the Emergency Seal Oil Pump (ESOP) will fail to auto start. The BOP will manually start the ESOP.

Event 3: #10 Transformer Lockout

The # 10 Bank Transformer will receive a lockout and the CRS will evaluate TSs for offsite power sources.

Event 4: CRD Flow Control Valve Fails OPEN

11 CRD Flow Control Valve will fail OPEN causing a control rod to drift in one notch. While verifying CRDH parameters the failed flow control valve will be discovered and the OATC will swap to the standby flow control valve.

Event 5/6: Rapid Power Reduction with Uncoupled Control Rod

The OATC will reduce power to 97-98% with recirc flow IAW Nuclear Engineering recommendation and then fully withdraw the drifted control rod. The drifted control rod will be uncoupled requiring the OATC to fully insert the control rod. CRS will evaluate TSs for an inoperable control rod.

Event 7: Station Power Transfer - Electrical ATWS

A 2R Lockout will occur requiring the crew to scram on degrading condenser vacuum. An ATWS will occur; the OATC will be successful with ARI (CT).

Event 8: HPCI Steam Line Rupture

A steam leak will occur in the HPCI room. HPCI will fail to auto-isolate requiring the crew to manually isolate HPCI when a max-safe temperature is received (CT).

Event 9: Loss of Off-Site Power

A 1R Lockout will occur causing a LOOP, 11 EDG-ESW pump and 12 EDG will fail to auto start. The BOP will be required to manually start or cross-connect 11 EDG-ESW with Service Water and/or start 12 EDG (CT).

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 8 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

1. INITIAL CONDITIONS (IC):

a. Mode: 1

b. Present Power Level: 100%

c. XCEL System Condition: Green

d. Plant CDF & LERF: Yellow

e. Plant Fire LERF: Yellow

f. Electrical lineup - 2R.

g. Fuel Pool Status: Green, 125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months to boil

h. Generator Output: ~695 MWe

i. Staffing: Normal Weekday Dayshift

j. Planned Shift Activities: Continue 0187-02B

k. The following equipment is OOS:

1) HPCI for Inadvertent initiation.

a) LCO 3.5.1 is NOT met b) Condition I was entered at 0400 today c) Required Action I.1 is complete and I.2 is due in 14 days d) RCIC and 13 Battery are protected

2) 12 EDG for 0187-02B since 1800 yesterday.

a) LCO 3.8.1 is NOT met

B.1 complete due at 1400 today

B.2 complete

B.3 complete

B.4 due in 7 days Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 9 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS b) 12 EDG ready to unload and secure c) 11 EDG & EDG-ESW protected

3) The following control rods have slow scram times:

a) 38-47, 42-43, 46-39, 50-31

2. SIMULATOR SET UP BOOTH a. Reset the simulator to IC-291 (PW: rpb1) and place INST in RUN. Verify the correct malfunctions, remotes, overrides and event triggers are loaded as listed in the Simulator Input Summary page(s).

b. Insert Manual Trigger 50 to load simulator initial conditions and preloaded malfunctions.

BOOTH c. Verify HPCI OOS but available as follows:

INST

1) Place Aux Oil Pump in PTL with Caution tag

2) Hang PROTECTED EQUIPMENT sign on RCIC

3) Mark up C.4-G appropriately for HPCI

d. Line up 12 EDG as follows:

1) Hang a CAUTION (yellow) card on the pump

2) Verify its GREEN light is OFF.

3) Place a PROTECTED EQUIPMENT sign near 11 EDG and switch box on 11 EDG-ESW pump

e. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 10 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

f. ENSURE Cross Flow is ENABLED on PCS as follows:

1) Verify computer points CFW966-CFW969 are set to ENABLED

g. ENSURE Remote PO03 (CROSSFLOW DISABLED/ENABLED) is set to ENABLED

1) Verify status board is updated IAW Section 1

2) Complete the Simulator Setup Checklist

3. SIMULATOR PRE-BRIEF:

a. REVIEW the scenario initial conditions as listed in Section 1: For examination purposes a Lead Instructor - Crew Turnover Brief has been created.

This should be reviewed with the crew prior to allowing the crew in the simulator.

b. VERIFY the crew performs a walk-down of the Crew Performs walk down of control boards and reviews control boards prior to starting the shift brief. turnover checklists.

FLOOR 4. SHIFT BRIEF INST

c. Role Play as necessary. Turbine Building status: Crew Conduct and participate in the Shift Brief 1). 5 Condensate Demins are in service.

2). C vessel d/p is highest @ 5.4 psid.

3). 0187-02B in progress for 12 EDG. 11 EDG &

EDG-ESW and 13 Battery are protected. All other systems in TB are normal.

d. Role Play as necessary. Extra out plant operator -

Nothing to add.

e. Role Play as necessary. Rx Building status:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 11 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

1) HPCI is OOS, troubleshooting in progress, RCIC is protected.

2) All other systems in the Rx Bldg are normal. CRS Crew assumes the duty.

Event 1 5. CONTINUE 0187-02B 12 EDG MONTHLY BOOTH a. When contacted as the Turbine Building Operator CRS Directs BOP to continue 0187-02B (12 EDG/12 ESW INST (TBO), respond appropriately that you are standing MONTHLY PUMP AND VALVE TEST) at Step 73a.3) by for EDG shutdown.

Makes 4KV Breaker cycling announcement

Lowers 12 EDG speed and loading to <2250 kW

Lowers 12 EDG speed and loading to 200-300 kW

Opens 12 EDG output breaker BOOTH b. When directed to set speed droop to zero, Insert

Directs TBO to adjust speed droop to zero INST Trigger 8

Adjusts 12 EDG frequency to 60.4-60.6 Hz BOOTH c. When directed to set speed droop to the scribe

Directs TBO to adjust speed droop to scribe mark INST mark, Set remote DG11 back to IN.

d. The OATC and BOP should swap and perform IV

Adjusts 12 EDG voltage to ~4350 V and perform IV BOOTH e. KS 36 must be placed in CLOSE before moving

Places 12 EDG Control Switch to STOP INST to Event 2.

FLOOR f. Perform CV as the Floor Instructor

Places Knife Switch 36 back to CLOSE with INST Concurrent Verification Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 12 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 2 6. MAIN SEAL OIL PUMP (MSOP) TRIP BOOTH a. When directed by the lead evaluator Insert INST TRIGGER 2.

Parameter response: MSOP trips Expected alarms: 8-A-22 (NO. 1 GEN H2 SYSTEM BOP

BOP responds to alarm and sends TBO to TROUBLE) investigate.

Automatic actions: Emergency Seal Oil Pump (ESOP)

BOP may recognize that MSOP pump is off and fails to AUTO start when the MSOP trips. ESOP failed to auto start BOOTH b. When directed to investigate the trouble alarm, INST wait 1 minute and state that Alarm 83-B-6 (EMERG SEAL OIL PUMP RUNNING) is in alarm but the ESOP is NOT running. Nothing appears to be wrong with the ESOP.

c. If asked as the TBO, report that Seal oil pressure CRS

Directs the BOP to start the ESOP from C-08.

locally is 52 psig.

BOOTH d. When asked to investigate cause of MSOP trip, INST wait 1 minute and state that breaker B3101 has tripped on overload.

e. Once the ESOP is started, if asked, report that seal oil pressure is 82 psig.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 13 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 3 7. #10 TRANSFORMER LOCKOUT BOOTH a. When directed by the lead instructor, Insert INST Trigger 3 and verify ED08, ED127 and ED128 activate.

Parameter response: 1AR XFMR voltage 0 VAC Expected alarms: 8-A-3 (345 KV & 115 KV YARD BOP

Acknowledges alarm and dispatches operator to 345 TROUBLE) KV House to investigate.

Automatic actions: None

Identifies 1AR voltage has been lost BOOTH b. When sent to investigate, wait 2 minutes and INST report that Panel 5P4 Annunciator Point 79 (10 TR LOCKOUT) is in alarm.

CRS Evaluates LCO 3.8.1 & TLCO 3.8.1 (OFFSITE SS299.356 SOURCES) as still met since 2R and 1R XFMRs are still CR299.358 available.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 14 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 4 8. CRD FLOW CONTROL VALVE FAILS OPEN BOOTH a. When directed by the lead instructor, Insert INST Trigger 4 and verify CH07A and CH06_061 activate (CH06_061 will delete in 3 seconds).

Parameter response: CRDH Drive pressure rises and SS315.167 cooling water header flow rises. CR 26-27 drifts in one CR200.226 notch.

BOOTH Expected alarms: 5-A-27 (ROD DRIFT) OATC Enters C.4-B.01.03.C (CONTROL ROD DRIFTING)

INST Automatic actions: None

Rod Select Power Switch to OFF and back to ON BOOTH b. As the RBO, if asked to investigate CRDH or after

Recognizes the rod is no longer drifting INST the C.4 page announcement, wait 1 minute and

Verifies CRD system operating parameters and report unusual high flow noise from the A CRD determines the Flow Control valve has failed open Flow Control valve.

Resets the Rod Drift alarm CRS Directs swapping CRD Flow Control Valves BOOTH c. When directed to report to the CRD FCV station to OATC Performs B.01.03-05.E.4 (PLACING THE STANDBY INST support shift of FCV, report you are standing by. CR201.111 CRD FLOW CONTROL VALVE INTO SERVICE)

BOOTH d. When directed to OPEN CRD-18-2 and CRD Directs RBO to OPEN CRD-18-2 & CRD-16-2 INST 2, WAIT 1 minute then Insert Trigger 9 and report

Places CRD Flow Controller in MANUAL this action to the Control room.

Closes CV-3-19A with the flow controller BOOTH e. Verify CH07A deletes when the flow controller is

Places the CRD Flow Selector to the B position INST placed in Manual (Event Trigger 7)

Slowly opens CV-3-19B to 60-62 gpm

Places CRD Flow Control in auto BOOTH f. When directed to CLOSE CRD-16-1 and

Closes CRD-16-1 & CRD-18-1 INST CRD-18-1 WAIT 1 minute & Insert Trigger 10.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 15 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 9. POWER REDUCTION BOOTH a. When directed by the Lead Evaluator, call the OATC

Lowers Recirc flow until reactor power is INST CRS as the Operations Manager. State that time SS315.159 approximately 97-98%. May refer to Hard Card.

compression is in effect and the Nuclear Engineer CR200.203

Selects CR 26-27 and single notch withdraws it to recommends a power reduction to 97-98% with 48 Recirc pumps and then fully withdrawing CR 26-27 and performing a coupling check.

Floor b. Provide Reactivity Maneuvering sheet to crew INST Event 6 10. UNCOUPLED CONTROL ROD

a. The uncoupled control rod malfunction is inserted as part of initial Setup trigger 50.

Parameter response: Rod Position goes blank Notifies CRS and recouples CR as follows:

Expected alarms: 5-A-11 (ROD OVERTRAVEL)

Insert CR until position 46 is observed Automatic actions: None

Verifies 5-A-11 resets

Resets CR Drift Alarm

Continuously withdraws CR to position 48 for coupling check

b. As the Nuclear Engineer, concur with the request

Repeats previous steps as CR is NOT recoupled to bypass the RWM

Inserts CR to 00 as its still uncoupled

c. When directed to electrically disarm control rod

Directs RBO to electrically disarm the CR 26-27, wait 1 minute and Insert Trigger 14.

CRS Evaluates LCO 3.1.6 (ROD PATTERN CONTROL) and SS299.349 LCO 3.1.3 (CONTROL RODS) as NOT met for CR 26-27 CR299.351 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 16 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 7 11. STATION POWER TRANSFER -

SCRAM W/ ELECTRICAL ATWS BOOTH a. When directed by the lead instructor, Insert INST Trigger 5.

Key Parameter response: Loss of power to 12 Bus, Dual BOP Announces 2R Lockout and/or Station Power Transfer Recirc Pump trip, Dual Circ Water Pump trip, rapidly

Recognizes rapidly degrading condenser vacuum degrading condenser vacuum.

Key Expected alarms: 8-B-02 (NO. 2R XFMR LOCKOUT), 5-B-20 (CONDENSER LO VACUUM SCRAM TRIP)

Automatic actions: Failure of Manual and Automatic CRS Directs a reactor scram IAW C.4.K (IMMEDIATE scram SS315.164 REACTOR SHUTDOWN)

OATC Depresses pushbuttons for REACTOR SCRAM A and B CR200.208 and places the Mode Switch in SHUTDOWN OATC Provides a Scram Report SS304.201

Reactor Scram, Mode Switch is in Shutdown, no CR314.104 rod motion, Reactor power is >4%, EOP Entry CRS Enters EOP 1100 RPV Control, transitions to EOP 2007 (FAILURE TO SCRAM) and directs the following:

NOTE: The CRS may wait to direct this action as time BOP o Inhibit ADS permits.

NOTE: This action may not be taken based on the loss of BOP C.5-3301 (DEFEAT MSIV LOW-LOW LEVEL Circ Water pumps SS314.111 ISOLATION)

CR314.115

Places 4 Key switches to BYPASS on C-15/17.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 17 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS CT-47 During failure to scram conditions with a critical OATC Performs C.5-3101 (ALTERNATE ROD INSERTION) reactor, insert control rods using one or more CR314.105 methods contained within C.5-3101 to achieve reactor shutdown under all conditions.

SS314.101

Verifies Recirc pumps are at minimum speed and trips the pumps NOTE: ARI will work for this scenario. CR212.105

Arms and Actuates A/B ATWS and determines ARI is having success.

Notifies CRS that all control rods are inserted OATC Continues actions IAW C.4-A (REACTOR SCRAM)

PART A:

Controls Reactor water level between +11 and

+46 inches.

When RPV water level starts to increase:

Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches

Close both Main FW Reg Valves o Verify CV-6-13 controls RPV level when it reaches +15 to +20 inches o Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

OATC

Range down on IRMs as necessary.

o Verify SDV Vent and Drain Valves closed.

BOP Takes actions IAW C.4-A (REACTOR SCRAM) PART B:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 18 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

Plant page that a Reactor Scram has occurred.

Open Main Generator output breakers 8N7 &

8N8.

Trip the Main Turbine.

Verify the Generator Field Breaker Open.

NOTE: The remaining BOP actions in C.4-A may NOT be

Start the Turbine Aux Oil Pump.

performed depending on when the LOOP occurs.

Verify Turbine Exhaust Hood Sprays in service.

Verify Turbine Stop Valves are closed

Start Turbine Bearing Lift Pumps NOTE: Circ water pumps will need to be restarted for

Verify Main Steam Pressure Control & Bypass condenser vacuum or LL-SET will be used for pressure valves are controlling Reactor Pressure.

control.

At C-25, Place the POST SCRAM switch in ON and verify all available Drywell Recirculation Fans are operating

Verify 4500 gpm through each operating Pump

Verify AC Auxiliary Oil Pump running on any non-operating Feed Pump

Verify 4100 gpm through each operating Condensate Pump Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 19 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 8 12. HPCI STEAM LEAK BOOTH a. Verify HP07 activates 5 minutes after the scram.

INST SS315.115 Key Parameter response: Rising temperatures and Rad levels in the HPCI room. CR200.160 Key Expected alarms: 3-B-56 (HIGH AREA TEMP BOP Goes to back panel C-11 & C-21to check temperatures STEAM LEAK)

Automatic actions: HPCI will fail to automatically isolate Recognizes rising temperatures and radiation levels in on high temperature. the HPCI room and evacuates the Reactor Building BOOTH b. Two minutes after HPCI leak is initiated, report as CRS Enters C.5-1300 (SECONDARY CONTAINMENT INST maintenance that there is a steam leak in the CONTROL)

HPCI room and all personnel have left the room.

Isolate all discharges into the area CT-34 When a system fails to isolate, manually isolate the BOP Manually closes MO-2034 & MO-2035 (HPCI STEAM system prior to exceeding max safe operating values LINE ISOLATION VALVES) in two areas.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 20 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

13. LOSS OF ALL OFF-SITE POWER

a. One minute after HPCI is isolated, verify ED04C activates. This will cause a 1R lockout.

Key Parameter response: Loss of off-site power to Busses 11-16 and a temporary loss of control room lighting.

Key Expected alarms: 8-C-4 (NO. 1R TRANS LOCKOUT)

Automatic actions: 11 EDG will automatically load onto 15 Bus but 11 EDG-ESW Pump will fail to automatically start. 12 EDG will fail to automatically start and 16 Bus will remain deenergized.

Performs switch lineup for loss of Busses 11-14 NOTE: With a Loss of Offsite Power and 16 Bus

Performs switch lineup for no 1AR voltage to 15 &

deenergized, ONLY 11 Service Water Pump is available 16 Bus and must be manually restarted.

Recognizes that 11 EDG-ESW pump failed to auto start

b. If 11 Service Water pump is NOT restarted and

Performs one of the following:

you are directed to cross-tie service water to 11 o Manually starts 11 EDG-ESW pump or EDG-ESW, wait 30 seconds and report that o Restarts 11 Service Water pump and NONE of the Service Water pumps are running. dispatches the TBO to cross-tie Service Water to 11 EDG-ESW IAW B.08.01.02-

c. Once 11 Service Water pump is running and you 05.H.3 (TRANSFER EDG COOLING are directed to cross-tie service water to 11 EDG- FROM EDG-ESW TO SERVICE WATER)

ESW, wait 30 seconds and Insert Trigger 16. o Starts 12 EDG from C-08 or directs a local start.

CT-EDG Under a loss of all off-site power condition, maintain and/or restore electrical power to an essential bus prior to reaching TAF.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 21 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

Performs switch lineup for loss of bus 16 Booth NOTE: 12 EDG can be manually started by the crew.

Places 12 EDG O/P breaker in PTL Malfunction DG02B will auto delete on Event Trigger 26 if INST

Verifies 11 Service Water Pump is running started from C-08. If directed by the crew to start the 12 EDG locally, manually delete malfunction DG02B. Both BOP

Starts 11 RBCCW Pump options will allow 12 EDG to auto load onto 16 bus from the EBT.

Starts 11 CRD Pump

Performs switch line up for loss of Condensate, Feed and Circ Water pumps

Restores Drywell cooling as required

Verifies 11 EDG meets load limitations.

d. Based on initial scenario conditions, HPCI could CRS Enters C.5-1100 (RPV CONTROL) Level Leg and directs also be used to restore RPV level. However, HPCI OATC to place RCIC in service IAW the Hard Card to will be lost once the steam leak occurs. restore and maintain RPV level +9 to +48 OATC

Verifies flow control in Auto at 400 gpm

Opens MO-2096

Starts Barometric Cdsr Vacuum Pump

Opens MO-2107

Opens MO-2106

Opens MO-2078 NOTE: If main condenser available, and -47 RPV Level

Verifies RCIC turbine comes up to speed and was not reached and the Main Turbine Aux Oil pump injects Lockout is reset, pressure control can be restored with the Bypass Valves 800-1000 psig. CRS Enters C.5-1100 (RPV CONTROL) Pressure Leg and directs a pressure band of 900-1056 psig using LL-SET.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 22 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

14. SCENARIO TERMINATION

a. The scenario may be terminated when:

11 EDG has cooling supplying 15 Bus or 12 EDG is restarted supplying 16 Bus and

HPCI is isolated

RPV water level is being controlled

b. The scenario may be also terminated at the discretion of lead instructor/evaluator FLOOR c. End the scenario by placing the simulator in Crew

Remain in simulator for potential questions from INST FREEZE. evaluator

No discussion of scenario or erasing of procedure marking is allowed Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 23 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SIMULATOR INPUT

SUMMARY

Event Initial /

Code Description Trigger Delay(s) Ramp Final Value MALFUNCTIONS (Allow Tracking Off)

C-08-A22 NO 1 GEN H2 SYSTEM TROUBLE 2 Active InActive C-08-A03 345 KV _ 115 KV YARD TROUBLE 3 Active InActive CH07A CRD Flow Control Valve CV-19A fails OPEN 4 Active InActive CH07A CRD Flow Control Valve CV-19A fails OPEN (Deletes in 1 second) 17 Active InActive CH06_061 Control Rod 26-27 Drift IN (Deletes in 3 seconds) 4 00:00:05 100 0 CH03_061 Control Rod 26-27 Uncoupled 4 00:00:02 Active InActive ED04D Loss of 2R XFMR 5 Active InActive PP02 ELECTRICAL ATWS 5 Active InActive DG02B #12 EDG Start Failure 5 Active InActive DG02B #12 EDG Start Failure (Deletes in 1 second) 26 Active InActive ED04C Loss of 1R XFMR 15 00:01:00 Active InActive HP01 HPCI AUTO-INITIATION 50 Active Active HP01 HPCI AUTO-INITIATION (Deletes in 1 second) 15 Active Active HP08 Failure of HPCI to Auto Isolate 50 Active Active HP07 HPCI Steam Leak 6 00:05:00 Active InActive REMOTES ED08 1AR XFMR PRI SUPPLY BKR 1N2 3 OPEN CLOSE ED127 345 KV 10 TR DISC 3 OPEN CLOSE ED128 115 KV 10 TR DISC 3 OPEN CLOSE CH17 CRD-18-2 & 16-2 9 OPEN CLOSE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 24 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 SIMULATOR INPUT

SUMMARY

Event Initial /

Code Description Trigger Delay(s) Ramp Final Value CH16 CRD-18-1 & 16-1 10 CLOSE 00:00:00 CH15_061 Control Rod 26-27 Electrically Disarmed 14 DISARM 00:00:00 DG11 12 EDG Speed Droop 8 OUT IN SW09 SW-228 & SW 229 to OPEN 16 OPEN CLOSE CH18 ATWS - ARI Fails to Energize 20 Active InActive CH18 ATWS - ARI Fails to Energize 21 Active InActive CH18 ATWS - ARI Fails to Energize 22 Active InActive Event Initial /

Code Description Trigger Delay(s) Ramp Final Value OVERRIDES 05-S050-01 MSOP Handswitch RUN position 2 FALSE TRUE 05-S071-02 ESOP in AUTO 50 FALSE FALSE 05-S071-03 ESOP in STOP 50 TRUE TRUE 05-S071-02 ESOP in AUTO 12 TRUE FALSE 05-S071-03 ESOP in STOP 12 FALSE TRUE 05-S106-02 11 ESW Pump - AUTO 50 FALSE FALSE 05-S106-03 11 ESW Pump - STOP 50 TRUE TRUE 05-S106-02 11 ESW Pump - AUTO 7 TRUE FALSE 05-S106-03 11 ESW Pump - STOP 7 FALSE TRUE 03-S36-06 B Manual Scram Pushbutton 5 FALSE FALSE 05-DS032-02 MSOP GREEN Light 2 OFF OFF Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 25 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Event Trigger Definitions:

Code Description Event Trigger ZD_SESOP ESOP Handswitch to START 12 ZD_EMSTA(1) 11 EDG-ESW Pump to START 7 ZD_S1SHD Mode Switch to SHUTDOWN 6 ZD_HS3CL HPCI MO-2035 to CLOSE 15 ZD_CNMAN CRDH Flow Controller to MANUAL 17 rrpdome > 1075 RPV Steam Dome pressure >1075 psig 20 ZD_S5amn A ARI Pushbutton depressed 21 ZD_S5bmn B ARI Pushbutton depressed 22 ZD_SDG2 12 EDG Control Switch to START 26 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 26 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Attach the following site-specific information as necessary:

Simulator Set-up Checklist (before and after training)

Pre-evaluation Brief Guide (for evaluations only)

Post-evaluation Critique (for evaluations only)

Turnover Log Historical Record:

1. New Create for the 2016 ILT NRC Exam Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 27 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

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

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

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

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

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

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

7. The scenario guide includes responses for anticipated communications to Yes No 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.

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

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

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

11. For evaluations, it has been verified that without operator action the critical Yes No tasks will be failed.

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 28 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

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

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

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

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

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

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

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

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

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

10. Simulator fidelity has been demonstrated to be adequate for this Yes No scenario.

Discrepancies noted (Check none or list items found) None SMAR = Simulator Action Request SMAR: SMAR: SMAR: SMAR:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 29 of 29 ILT-SS-40E (2016 ILT NRC Scenario 1) Rev. 0 Comments:

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

Validation Personnel Name Job Title / Qualification Validation Position Jason Pearce SM / SRO CRS Greg Pagel NPE&RO / RO OATC Troy Teige NLPE&RO / RO BOP Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Appendix D Scenario Outline Form ES-D-1 Facility: MONTICELLO Scenario No.: 2 Op-Test No.: 2016-301 Examiners: Operators:

Initial Conditions: Plant Start-up in progress (38% power) following an outage; There are 4 control rods with slow scram times (38-47, 42-43, 46-39, 50-31).

Turnover: Continue the start-up, raise power to 40% using single notch control rod withdrawal starting at Step 30 of ASR5. At 40%, place 12 Condensate pump in service. Once 12 Condensate pump is in service, raise power to 45% using Recirc flow.

Event Malfunction Event Event Description No. No. Type

1. R (OATC) Operator will raise power from 38% to 40% using control rods.

I (OATC) While withdrawing a control rod from 12 to 48, the control rod will be stuck at 12. The OATC will raise drive pressure to free the control rod. Crew will continue with startup activities.

2. N (BOP) When power is ~40%, BOP will place 12 Condensate Pump in service

3. R (OATC) OATC will raise power to 45% with Recirc flow. When raising C (OATC) power to 45%, a 12 Recirc Pump Speed Controller failure will TS (SRO) occur. The OATC will lock B Scoop Tube. The CRS will evaluate LCO 3.4.1 flow mismatch > 10% between loops.

4. C (BOP) Loss of LC-103 feeder breaker to MCC-131. BOP will manually TS (CRS) start 12 Steam Packing Exhauster and verify auto actions. The CRS will evaluate TSs for loss of power to #11 EDG control panel (LCO 3.8.1).

5. C (BOP) SRV D will begin leaking. Tailpipe temperature will rise requiring the BOP to place B RHR in the Torus Cooling Mode.

6. M (CREW) SRV D will fail full open and will not close when immediate actions are taken. The OATC will insert a manual scram (CT).

The SRV will close following the scram. Following the insertion of the scram, a large steam leak will occur in the Drywell.

Pressure and Temperature in the Drywell will rise requiring the crew to initiate Drywell Sprays.

7. C - (POST) When DW pressure CANNOT be maintained below 12 psig, the CRS will direct Drywell Sprays (CT). The LPCI Initiation Bypass will fail for the first Division of RHR that is used for Containment Sprays. The crew will be forced to use the opposite Division of RHR.

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

QF107502 Rev. 4 (FP-T-SAT-75)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-41E SEG TITLE: 2016 ILT NRC SCENARIO 2 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME: 45-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 2 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 Guide Requirements This Scenario evaluation has been written for the 2016 ILT NRC Goal of Exam. Once this exam is complete and exam security is relaxed, Training: this SEG should be appropriate to use for the following activities:

Future ILT NRC / Audit Exam Evaluations

SRO Certification Evaluations

LOR Crew development