ML17142A425

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
Shared Package
ML15274A423	List: ML17142A415 ML17142A423 ML17142A425 ML17142A427 ML17142A429 ML17142A430 ML17156A043 ML17156A045
References
Download: ML17142A425 (103)

Text

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 <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> 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

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

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

6. 2167 (Plant Startup) & 2300 (Reactivity Adjustment)

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0

1. FORM 2167 (PLANT STARTUP)

References:

2. 2300 REACTIVITY MANEUVERING STEPS

3. B.01.03-05.H.3 (ELEVATING DRIVE PRESSURE TO WITHDRAW A CONTROL ROD)

4. B.06.05-05.D.3 (STARTUP 12 CONDENSATE PUMP WITH 11 CONDENSATE PUMP RUNNING)

5. B.01.04-05 (UNSTABLE SPEED CONTROL ON ONE PUMP)

6. LCO 3.4.1 (RECIRCULATION LOOPS OPERATING)

7. 8-B-32 (NO. 103 480V LDCTR MCC FEEDER TRIP)

8. C.4-B.09.07.C (LOSS OF POWER TO LC-103 OR ITS MCCs)

9. LCO 3.8.1(OFFSITE SOURCES)

10. 3-A-9 (AUTO BLOWDOWN RELIEF VLV LEAKING)

11. C.4-B.03.03.B (RELIEF VALVE LEAKING)

12. B.03.04-05.H.5/H.6 (PLACING A/B LOOP RHR TORUS COOLING IN SERVICE DURING ABNORMAL AND EMERGENCY CONDITIONS WITH NORMAL OFF-SITE POWER AVAILABLE)

13. B.03.01-05.G.4/G.5 (CORE SPRAY A/B LOOP TORUS MIXING MODE)

14. 5-A-46 (SRV OPEN)

15. C.4-B.03.03.A (STUCK OPEN RELIEF VALVE)

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

17. C.4-K (IMMEDIATE REACTOR SHUTDOWN)

18. C.4-A (REACTOR SCRAM)

19. C.5-1100 (RPV CONTROL)

20. C.5-1200 (PRIMARY CONTAINMENT CONTROL)

21. C.5-3503 (DEFEAT DW COOLER TRIPS)

22. C.5-3502 (CONTAINMENT SPRAY)

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:

Initiating Event with Core Damage Frequency:

Related PRA None Information: Important Components / Accident Class:

None Important Operator Actions with Task Number:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 4 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

SS200.133 Direct a reactor startup to full power 5-7 SS299.352 Apply administrative requirements for TS 3.4 and Bases 5-7 SS315.143 Supervise response to a loss of LC-103 or its MCCs 5-7 SS299.356 Apply administrative requirements for TS 3.8 and Bases 5-7 SS315.110 Supervise response to a relief valve leaking 5-7 SS315.109 Supervise response to a stuck open relief valve 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 SS304.194 Implement primary containment control 5-7 SS314.120 Supervise defeat drywell cooler trips 5-7 SS314.119 Supervise containment spray 5-7 RO Tasks:

CR200.103 Perform a Startup Checklist 1-4 CR200.127 Perform a power ascension after the reactor is on line 1-4 CR201.122 Elevating drive pressure to withdraw a control rod 1-4 CR256.113 Start 12 Condensate pump with 11 Pump running 1-4 CR202.114 Respond to unstable speed control on one pump 1-4 CR299.354 Apply TS 3.4 and Bases 5 CR200.187 Perform procedure for a loss of power to LC-103 or its MCCs 1-4 CR299.358 Apply TS 3.8 and Bases 5 CR200.155 Perform the procedure for a relief valve leaking 1-4 Place RHR in Torus Cooling during abnormal or emergency conditions 1-4 CR203.117 with normal off-site power available CR209.115 Place Core spray in Torus mixing mode 1-4 CR200.154 Perform the procedure for a stuck open relief valve 1-4 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 CR304.103 Perform actions associated with Primary Containment Control 1-4 CR314.124 Defeat drywell cooler trips 1-4 CR314.123 Perform actions associated with containment spray 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 5 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Stuck control rod

2. Recirc speed control failure

3. Loss of LC-103

4. SRV leaking

5. SRV stuck open After EOP Entry:

1. Drywell spray failure Abnormal Events:

1. Loss of LC-103

2. Leaking SRV

3. Stuck Open SRV Major Transients:

1. Unisolable Steam leak in the Drywell requiring Containment Sprays Critical Tasks:

1. CT-6 When an SRV is stuck open and can NOT be closed then insert a manual reactor scram prior to Torus water temperature reaching 110°F.

2. CT-30 When Drywell pressure reaches 12 psig, then initiate Drywell sprays to prevent Emergency Depressurization.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO OVERVIEW:

Event 1: Raise reactor power with Control Rods to ~40%

• OATC will continue the A2R5 startup sequence to raise power to 40%. The control rod that is withdrawn will be stuck at position 12. The OATC will take action to free the stuck rod.

Event 2: Place the second Main Condensate Pump in service

• BOP will place the second Main Condensate Pump in service.

Event 3: 12 Recirc Runaway

• The OATC will continue raising power with Recirc pumps to ~45%. The 12 Recirc pump will runaway requiring the OATC to lock the scoop tube. The CRS will evaluate TS 3.4.1.

Event 4: Loss of MCC-131

• Loss of LC-103 feeder breaker to MCC-131. BOP will manually 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).

Event 5: Leaking SRV D

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

Event 6: Stuck Open SRV D

• SRV D will fail full open and will not close when 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. Temperatures in the Drywell will rise requiring the crew to initiate Drywell Sprays.

Event 7: Drywell Spray failure

• The BOP will be required to initiate Drywell Sprays when Drywell pressure exceeds 12 psig (CT). The LPCI Initiation Bypass will fail for the first division of RHR, requiring the BOP to use the opposite division.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) 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: RUN

b. Present Power Level: 38%

c. XCEL System Condition: Green

d. Plant CDF: Green LERF: Green

e. Plant Fire LERF: Green

f. Electrical lineup - 2R supplying

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

h. Generator Output: ~231 MWe

i. Staffing: Normal Weekday Dayshift

j. Planned Shift Activities:

1) Raise reactor power to 40%

2) Place 2nd Main Condensate Pump in service

3) Raise reactor power to 45%

k. The following equipment is OOS:

1) The following control rods have been declared slow a) 38-47, 42-43, 46-39, 50-31 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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

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

2. SIMULATOR SET UP BOOTH b. Reset the simulator to IC-292 (PW: rpb2) 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).

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

d. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) Form 2300 & 2167 marked up for raising power and starting the 2nd Main Condensate Pump.

a) Step 173 of Form 2167 (PLANT STARTUP)

Revision 93.

3) A2R5 Roller Tape and Binder appropriately marked up to Step 30

4) B.06.05-05.D.3, Steps 1-6 complete.

e. ENSURE Cross Flow is DISABLED on as follows:

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

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

f. Verify the status board is updated IAW Section 1

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 9 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

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

3. SIMULATOR PRE-BRIEF:

FLOOR a. REVIEW the scenario initial conditions as listed in INST 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.

4. SHIFT BRIEF Role Play as necessary. Turbine Building status: Crew Conduct and participate in the Shift Brief 1). 4 Condensate Demins are in service.

2). A vessel d/p is highest @ 5.2 psid.

3). Ready to start 12 Condensate pump 4). 11 RFP is in service, 12 RFP is in warmup 5). All other systems in TB are normal.

Role Play as necessary. Extra out plant operator.

1) Nothing to add.

Role Play as necessary. Rx Building status:

1) All system in the Reactor Building are normal CRS Crew assumes the duty.

for plant startup.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 1 5. RAISE REACTOR POWER TO 40% WITH RODS

a. Provide the following: CRS Performs a Reactivity Manipulation Brief Booth 1) 2300 (Reactivity Adjustment) SS200.133 CRS directs the OATC to raise reactor power to 40% with Operator CR200.103 A2R5 Step 30 control rods IAW 2300 Reactivity Maneuvering Steps and Form 2167 (Plant Startup) Step 173.

2) Nuclear Engineer Reactivity Maneuvering Steps BOP Provide a Peer Check

3) A2R5 Roller Tape and Binder appropriately OATC Withdraws control rods continuing with Step 30 of the marked up to Step 30 A2R5 Startup sequence.

Booth b. If APRM gain adjustments are requested prior to, CR200.127

• Selects Control Rod 14-23 Operator during, or after the power adjustment, open remote NI18 and SET until gains are +2%

• Uses single notch withdrawal from position 12 to 48

• Monitors control rod position, CRDH and APRMs Key Parameter Response: CR 14-23 will not move Recognizes control rod is stuck at position 12 Key Expected Alarms: None CR201.122 Enters B.01.03-05.H.3 (ELEVATING DRIVE PRESSURE TO WITHDRAW A CONTROL ROD)

Auto Actions: None

• Raises Drive pressure in 30 psid increments by closing MO-3-20

c. Acknowledge any requests to Engineering,

• When Drive pressure is >280 psig the control rod Maintenance and Plant Management. will withdraw

d. If required, role play as the Operations Manager

• Continues with startup and withdraws the control and state to continue startup activities. rod until reactor power is ~40%.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 2 6. START 12 CONDENSATE PUMP Booth NOTE: Steps 1-6 have been completed. This has been CRS Directs the BOP to continue B.06.05-05.D.3 (STARTUP Operator communicated to crew as part of the Pre-Scenario Brief. 12 CONDENSATE PUMP WITH 11 CONDENSATE PUMP RUNNING) at Step 7.

Booth a. Respond as TBO standing by for pump start BOP

• Dispatch operator to observe pump start Operator CR256.113

• Starts 12 Condensate Pump Booth b. When requested to open the discharge valve,

• Slowly OPEN FW-7-2 (12 COND PMP DISCH)

Operator Insert Trigger 2, wait 1 minute and report the locally (TBO) valve is open.

Booth

• Raise Condensate Recirc Flow Controller setpoint Operator to achieve a flow of 8500 gpm. Observes rising flow.

c. As the TBO, wait 2 minutes and report D.3 is

• Informs TBO to complete procedure D.3 complete.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 3 7. RAISE POWER TO 45% WITH RECIRCS

a. Provide the following: CRS Performs a Reactivity Manipulation Brief Booth 1) 2300 (Reactivity Adjustment) SS200.133 CRS directs the OATC to raise Recirc speed to achieve Operator CR200.103 45% reactor power IAW 2300 Reactivity maneuvering Steps and Form 2167 (Plant Startup) Step 173.

2) Nuclear Engineer Reactivity Maneuvering Steps BOP

• Provide a Peer Check OATC

• Raises Recirc speed to raise power.

CR200.127

• Maintains Flow parameters approximately equal

b. If APRM gain adjustments are requested prior to,

• Monitors the following parameters:

during, or after the power adjustment, open o Pump Speeds & Scoop Tube positions remote NI18 and SET until gains are +2%

o Reactor Differential pressure

c. When reactor power is ~42% Verify Event o Total Jet Pump Flow Trigger 10 activates and RR09D inserts.

o Reactor Water Level and Feedwater Flow o Reactor Pressure and Steam Flow o APRMs & Core Thermal limits Key Parameter Response: Recirc Pump speed, scoop OATC Recognizes 12 Recirc pump speed rising and locks the tube position and reactor power rising. CR202.114 scoop tube IAW B.01.04-05 (UNSTABLE SPEED CONTROL ON ONE PUMP)

Key Expected Alarms: 5-A-51 (RBM HI/INOP) CRS Evaluates difference in Jet pump flows and evaluates LCO 3.4.1 (RECIRCULATION LOOPS OPERATING)

Auto Actions: Rod Withdraw Block SS299.352 * <70% rated core flow, mismatch needs to be <10%

CR299.354

(~5.7 Mlbm/hr)

• Enters LCO 3.4.1 Condition A (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) if flow mismatch is >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 13 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 4 8. LOSS OF MCC-131 BOOTH a. When directed by the lead evaluator, INST Insert MANUAL TRIGGER 4 and verify ED70 activates.

Key Parameter Response: Loss of voltage to MCC-131 Key Expected Alarms: 8-B-32 (NO. 103 480V LDCTR MCC FEEDER TRIP)

Auto Actions: Main Xfmr Cooling switch to alternate source (MCC-121),

BOP Enters C.4-B.09.07.C (LOSS OF POWER TO LC-103 OR ITS MCCs) and evaluates Table MCC-131

b. As the TBO, wait 2 minutes and report the SS315.143

• Dispatches operator to verify proper operation of following: CR200.187 standby equipment.

1) All MCC-131 equipment transferred power

• Starts 12 Steam Packing Exhauster properly o B.06.01-05.E.15/E.17

2) No Steam Packing Exhauster is running

3) 11 EDG Control Panel C-93 is deenergized

• Verifies 12 SWC Pump auto started

4) The MCC-131 supply breaker tripped on

• Verifies ESOP auto started overload.

CRS Evaluates LCO 3.8.1(AC POWER SOURCES) for loss of power to 11 EDG Control Panel C-93 SS299.356

• Enters LCO 3.8.1 Condition B for one EDG INOP.

CR299.358 o B.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o B.2 will be N/A o B.3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> o B.4 within 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 14 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 9. SRV D LEAKING BOOTH a. When directed by the lead evaluator, INST Insert TRIGGER 5 and verify AP03D activates.

Key Parameter Response: Rising tailpipe temperatures BOP Enters C.4-B.03.03.B (RELIEF VALVE LEAKING)

Key Expected Alarms: 3-A-9 (AUTO BLOWDOWN SS315.110

• If SRV D tailpipe temperature exceeds 210°F then RELIEF VLV LEAKING) CR200.155 mix water in the torus with RHR or Core Spray Auto Actions: None. CR203.117 B.03.04-05.H.5/H.6 (PLACING A/B LOOP RHR TORUS COOLING IN SERVICE DURING ABNORMAL AND EMERGENCY CONDITIONS WITH NORMAL OFF-SITE POWER AVAILABLE)

b. If Torus Cooling is placed in service the CRS

• Sets RHRSW Outlet controller at 20%

should evaluate TS 3.5.1 for inoperable LPCI injection paths.

• Starts RHRSW Pump(s), adjusts flow 3500 gpm/pump

• Starts RHR Pump(s) and opens Torus Cooling Inb

& Otbd valves to achieve 4000 gpm/pump NOTE: With 11 EDG INOP the crew should use Division 1

• Closes HX bypass valve RHR or Division 1 Core Spray to prevent the inoperability of redundant features which would require performance of

• Places Room Air Cooling Unit in service LCO 3.8.1 Condition B.2. BOP B.03.01-05.G.4/G.5 (CORE SPRAY A/B LOOP TORUS CR209.115 MIXING MODE)

Verifies injection inboard valve is closed

c. When directed to check local pump suction Verifies system pressures pressure, state that suction pressure is 20 psig.

Starts a Core Spray pump Opens Torus Test Return valve until flow is ~3000 gpm 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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 6 10. SRV D STUCK OPEN BOOTH a. When directed by the Lead Evaluator, insert SS315.109 INST TRIGGER 6 and verify AP01D activates. CR200.154 Key Parameter Response: MWe lowering, D Main Steam line flow lowers.

Key Expected Alarms: 5-A-46 (SRV OPEN) BOP Enters C.4-B.03.03.A (STUCK OPEN RELIEF VALVE)

Automatic Actions: None Places SRV D handswitch to open then back to normal NOTE: At the lower reactor power and 12 Recirc Pump Enters C.4-F (RAPID POWER REDUCTION) scoop tube locked, the crew may not reduce reactor power CT-6 When an SRV is stuck open and can NOT be closed If SRV remains open then manually scram the reactor then insert a manual reactor scram.

OATC Inserts a manual Reactor scram IAW C.4-K (IMMEDIATE CR200.208 REACTOR SHUTDOWN)

SS315.164 OATC Takes actions IAW C.4-A (REACTOR SCRAM) PART A:

BOOTH b. When the Mode Switch is placed in SHUTDOWN, SS315.101

• Place Mode Switch in SHUTDOWN.

CR200.146 INST verify Event Trigger 7 activates.

o Verify all Control Rods are inserted to or beyond position 04.

• Provides scram script to CRS. Reports RPV less than 9 EOP entry condition.

• Controls Reactor water level +9-48. When RPV water level starts to increase:

o Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches 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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS o Close both Main FW Reg Valves o Verify CV-6-13 is closed when RPV level reaches +15 to +20 inches

• Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

• Verify SDV Vent and Drain Valves closed.

• Verify Recirc Pumps have run back to minimum CRS Enters C.5-1100 (RPV CONTROL)

SS304.193

• Directs OATC to restore and maintain RPV level CR304.102

+9 to +48 using Condensate and Feedwater NOTE: This pressure band may be lower when the crew

• Directs BOP to restore and maintain RPV pressure realizes that the SRV has closed. 800-1000 psig using the Bypass valves CRS Enters C.5-1200 (PRIMARY CONTAINMENT CONTROL)

NOTE: This action may be performed as part of placing

• Directs BOP to place Torus Cooling in service Torus Spray in service.

BOP Takes actions IAW C.4-A (Reactor Scram) PART B:

• Plant page that a Reactor Scram has occurred.

• Open Main Generator output breakers 8N7 & 8N8.

• Trip the Main Turbine.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS NOTE: The remaining BOP actions in C.4-A may NOT be

• Verify the Generator Field Breaker Open.

performed depending on when the steam leak is recognized.

• Start the Turbine Aux Oil Pump.

• Verify Turbine Exhaust Hood Sprays in service.

• Verify Turbine Stop Valves are closed

• Start the Turbine Bearing Lift Pumps

• Verify Main Steam Pressure Control and Bypass Valves are controlling Reactor Pressure.

Event 7 10. STEAM LINE RUPTURE IN THE DRYWELL

a. The malfunctions for the stream line rupture will SS304.194 insert when the Mode Switch is taken to CR304.103 SHUTDOWN Key Parameter Response: Rising DW pressure and temperature.

Key Expected Alarms: 3-B-54 (CONTAINMENT SPRAY BOP When DW pressure reaches 1.84 psig, announces EOP PERMISSIVE), 4-B-35 (DRYWELL-TORUS HI PRESS) entry conditions Auto Actions: ECCS Initiation CRS Enters C.5-1200 (PRIMARY CONTAINMENT CONTROL)

NOTE: The LPCI Initiation Bypass will not work for the first BOP Starts all available Drywell Cooling IAW C.5-3503 Division of RHR that is used for Containment Sprays SS314.120 (DEFEAT DW COOLER TRIPS)

CR314.124 BOOTH Places RHR in Torus Sprays IAW C.5-3502 INST Manually delete the override for the 2nd Division of RHR (CONTAINMENT SPRAY) that is placed in service. SS314.119 CR314.123

• Bypass 2/3 Core Height interlock

• Bypass LPCI initiation 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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

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

• Announces failure of LPCI Initiation Bypass

• Opens Torus Cooling/Spray valves on the opposite division of RHR

• Recognizes that DW pressure is still rising once Torus sprays are in service.

• Verifies Recirc Pumps are tripped

• Places all Drywell Fan controls switches in OFF BOP

• Places RHR in DW Sprays IAW C.5-3502 (CONTAINMENT SPRAY)

Opens DW Spray INBOARD CT-30 When Drywell pressure reaches 12 psig, then initiate

• Opens DW Spray OUTBOARD Drywell sprays to prevent Emergency Depressurization.

• Before Drywell and Torus Pressure reach 0 psig, terminate drywell sprays.

14. SCENARIO TERMINATION FLOOR The scenario may be terminated when Drywell sprays have Crew: Remain in simulator for potential questions from evaluator.

INST been initiated and Drywell pressure is <12 psig.

The scenario may be also terminated at the discretion of Crew:

• No discussion of scenario or erasing of procedure lead instructor/evaluator marking is allowed.

End the scenario by placing the simulator in FREEZE.

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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SIMULATOR INPUT

SUMMARY

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

RR09D 12 Recirc Pump Runaway 10 60 0 AP03D D SRV Leaking 5 00:05:00 70 0 AP01D D SRV Stuck OPEN 6 Active InActive AP01D D SRV Stuck OPEN (Deletes in 1 Second) 7 Active InActive MS04A Main Steam Line Rupture in the Drywell 7 00:02:00 00:03:00 100 0 CH02_045 Control Rod 14-23 Stuck 50 Active InActive CH02_045 Control Rod 14-23 Stuck (Deletes in 1 Second) 1 Active InActive REMOTES FW02 FW-7-2 Condensate Pump Discharge Valve 50 10 10 FW02 FW-7-2 Condensate Pump Discharge Valve 2 100 10 ED70 MCC-131 Supply Breaker 4 OPEN 00:00:00 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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 Event Code Description Trigger Delay(s) Ramp Final Value OVERRIDES 01-D103-01 Div 2 Containment Spray LPCI Bypass 50 False False 01-S089-01 Div 1 Containment Spray LPCI Bypass 50 False False Event Trigger Definitions:

Code Description Event Trigger ZACHDRWP>.7 Drive Water Header Pressure > 280 psid 1 ZD_S1SHD Mode Switch to SHUTDOWN 7 nijaprm(1)>42 ZD_MAAUT(2) Power >42% and 12 Recirc in Raise 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 21 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) 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 22 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

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

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 23 of 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

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

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 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 24 ILT-SS-41E (2016 ILT NRC Scenario 2) Rev. 0 SMAR: SMAR: SMAR: SMAR:

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.: NRC Scenario 3 Op-Test No.: 2016-301 Examiners: ____________________________ Operators: _____________________________

____________________________ _____________________________

____________________________ _____________________________

Initial Conditions:

100% Power 1AR Transformer OOS Turnover:

OATC to perform 0010 (RX SCRAM FUNCTIONAL) Parts A & B for PMT Event Malfunction Event Event No. No. Type Description 1 03-S37-01 N (OATC) OATC will perform 0010. When performing Part A the RPS C (OATC) 1/2 Scram will fail to reset. OATC must recognize that Part 03-S37-02 B can NOT be performed or a full scram would result.

2 RW01 & C (OATC) A Self-Test fault will occur on the RWM causing a rod TS (SRO) block. The OATC will bypass the RWM and the CRS will C-05-A03 evaluate Tech Specs.

3 HP01 C (BOP) HPCI will inadvertently initiate resulting in reactor power TS (SRO) exceeding 100%. The BOP will perform a rapid shutdown of HPCI (CT) and the CRS will evaluate Tech Specs.

4 MC03 & C (BOP) The inlet PCV to 11 SJAE will fail closed. The BOP will R (OATC) take action to restore the SJAE and the OATC will reduce MC04B reactor power to stabilize condenser vacuum.

5 ED12 M (CREW) A small Feedwater leak will occur causing both Feedwater pumps to trip resulting in a reactor scram.

6 C (POST-OATC) With the loss of Feedwater and A FW leak, RPV level will RC01 lower. RCIC will fail to automatically start and require manual start the system to restore RPV water level (CT).

HPCI can also be returned to service to restore level.

(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-42E SEG TITLE: 2016 ILT NRC SCENARIO 3 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) 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

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. Form 2300 and Reactivity Maneuvering steps 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0

1. 0010 (REACTOR SCRAM FUNCTIONAL TEST)

References:

2. 5-A-3 (ROD WITHDRAW BLOCK)

3. 5-A-35 (RWM ROD BLOCK)

4. TECH SPEC 3.3.2.1

5. 5-B-24 (REACTOR WATER LEVEL HI/LO)

6. C.4-G (INADVERTENT ECCS INITIATION)

7. TS LCO 3.5.1

8. 7-A-20 (OFFGAS ANNUNCIATOR)

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

10. C.4-B.06.03.A (DECREASING CONDENSER VACUUM)

11. C.4-A (REACTOR SCRAM)

12. 5-B-45 (DRYWELL HI/LO PRESSURE)

13. 3-A-38 (REACTOR LOW LOW LEVEL)

14. C.5-1100 (RPV CONTROL)

15. C.5-3204 (RPV MAKEUP WITH CRD)

16. B.02.03-05.D.02 (MANUAL INITIATION OF RCIC)

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:

Initiating Event with Core Damage Frequency:

Related PRA None Information:

Important Components / Accident Class:

None Important Operator Actions with Task Number:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 4 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

SS299.351 Apply administrative requirements for Tech Spec Section 3.3 5-7 and Bases to Instrumentation SS315.160 Supervise response to inadvertent ECCS initiation 5-7 SS299.355 Apply administrative requirements for Tech Spec Section 3.5 5-7 and Bases to ECCS and RCIC SS315.159 Supervise rapid power reduction 5-7 SS315.127 Supervise response to a decreasing condenser vacuum 5-7 SS315.101 Supervise response to a reactor scram 5-7 SS304.225 Implement the response for a small break LOCA with RPV level maintained above the TAF using high pressure injection and/or 5-7 alternate coolant injection systems and containment SS314.107 Supervise RPV makeup with CRD 5-7 RO Tasks:

CR299.353 Apply Tech Spec Section 3.3 and Bases to Instrumentation 5 CR200.204 Perform the procedure for an inadvertent ECCS initiation 1-4 CR299.355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 5 CR200.203 Perform the procedure for rapid power reduction 1-4 CR200.172 Perform the procedure for Decreasing Condenser Vacuum 1-4 CR200.146 Perform the procedure for a Reactor Scram 1-4 CR304.138 Perform actions for a small break LOCA with RPV level 1-4 maintained above the TAF using high pressure injection and/or alternate coolant injection systems and containment CR314.111 Perform actions associated with RPV Makeup With CRD 1-4 CR217.107 Manually Initiate RCIC 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 5 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. RPS Scram reset failure

2. RWM failure

3. Inadvertent HPCI start

4. SJAE Failure

5. Feedwater break After EOP Entry:

1. RCIC Auto Initiation Failure Abnormal Events:

1. Loss of Condenser Vacuum

2. Inadvertent ECCS Initiation Major Transients:

1. Feedwater break Critical Tasks:

1. CT-14: When HPCI inadvertently initiates, restore reactor power to within the license limit.

2. CT-21: When systems required to maintain core submergence do not automatically start, manually align the systems prior to RPV level dropping below -126.

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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO OVERVIEW:

SEQUENCE OF EVENTS:

Event 1: Reactor Scram Functional Test

• The OATC will manual scram on RPS A, the half scram will not reset and the test will be halted because performing Part B will result in a Full Scram Event 2: RWM Failure

• The RWM will experience a self-test fault. This will require the OATC to bypass the RWM and the CRS to evaluate Tech Specs.

Event 3: Inadvertent HPCI Initiation

• HPCI will inadvertently initiate causing reactor power to rise above 100%. The BOP will perform a rapid shutdown of HPCI (CT) and the CRS will evaluate Tech Specs.

Event 4: SJAE Failure

• The 11 SJAE Inlet PCV will fail closed. This will require the BOP to take actions to restore the SJAE and the OATC will reduce reactor power to stabilize condenser vacuum.

Event 5: Feedwater leak with Loss of Feed pumps

• A Feedwater leak will occur in the drywell causing both Feed pumps to trip. The OATC will insert a scram on lowering RPV water level.

Event 6: RCIC Fails to Auto Initiate

• The loss of feedwater will lower RPV water level. HPCI is in PTL and RCIC will fail to auto initiate. The OATC will be required to manually initiate RCIC and HPCI to restore RPV water level (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 7 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) 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: RUN

b. Present Power Level: 100%

c. XCEL System Condition: Green

d. Plant CDF and LERF: Green

e. Electrical lineup - 2R

f. Fuel Pool Status: Green, 105.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to boil

g. Generator Output: ~684 MWe

h. Staffing: Normal weekday night shift.

i. Planned Shift Activities: 0010 (Reactor Scram Functional Test Parts A & B for PMT

j. The following equipment is OOS:

1) 1AR Transformer for an Oil Leak

2. SIMULATOR SET UP BOOTH a. Reset the simulator to IC-293 (PW: rpb3) 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 30 to load simulator initial conditions and preloaded malfunctions.

c. Tag out both of the 1AR Transformer hand switches 152-511/CS & 152-610/CS as follows:

1) Verify both hand switches are in PTL.

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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

2) Hang CAUTION (yellow) cards on both hand switches

3) Verify the GREEN lights are OFF on both hand switches.

d. Ensure the following are provided for the crew:

e. Turnover checklists (3139 & 3140)

f. Marked up copy of 0010 (Rx Scram Functional Test) ready to perform Parts A & B and RPS Keys.

g. Attain SHEMP password for Event 1

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

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

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

i. Verify the status board is updated IAW Section 1

j. Complete the Simulator Setup Checklist

3. SIMULATOR PRE-BRIEF:

FLOOR a. REVIEW the scenario initial conditions as listed in INST 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.

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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

4. SHIFT BRIEF

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

2). A vessel d/p is highest @ 6.4 psid.

3). 1AR Transformer is tagged out for an oil leak

b. Role Play as necessary. Extra out plant operator.

1) Nothing to add.

c. Role Play as necessary. Rx Building status:

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

Event 1 5. 0010 (REACTOR SCRAM FUNCTIONAL TEST)

a. The RPS reset failure is inserted as part of the CRS May perform refocus brief prior to start of 0010 initial scenario setup OATC

• Pushes Reactor Scram A Pushbutton

• Checks pushbutton RED light is ON

• Checks CRD Scram Solenoids 1, 2, 3 & 4 lights are OFF

b. Respond appropriately as maintenance,

• Checks 5-B-12 is in alarm engineering and/or management to start the necessary investigations and make the

• Checks RPS029 displays TRIP appropriate notifications.

• Toggles Scram Reset Switch

c. If asked to check the A RPS MG Set, state that it

• Recognizes 1/2 Scram will not reset and Part B can appears to be operating normal. NOT be completed CRS Stops performance of 0010 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 2 6. RWM FAILURE BOOTH a. When directed by the Lead Evaluator, insert INST Manual Trigger 1 and verify RW01 and C-05-A03 activate.

Key Parameter Response: Rod Withdraw Permitted White light goes out on C-05 Key Expected Alarms: 5-A-3 (ROD WITHDRAW BLOCK) OATC Takes action IAW 5-A-35 (RWM ROD BLOCK) and 5-A-35 (RWM ROD BLOCK)

• Verifies RWM Mode switch is in OPERATE Auto Actions: None

• Verifies RWM SELF TEST indicates FAULT

b. Respond appropriately as maintenance,

• With Rx Pwr > LPSP engineering and/or management to start the o Evaluates Tech Spec 3.3.2.1 as still MET CRS necessary investigations and make the o Bypasses the RWM appropriate notifications. OATC Event 3 7. INADVERTENT HPCI INITIATION BOOTH a. When directed by the Lead Examiner, insert INST Manual Trigger 3 and verify HP01 activates.

Key Parameter Response: HPCI Turbine speed increasing, valves repositioning and RPV water level rising.

Key Expected Alarms: 5-B-24 (REACTOR WATER OATC Takes action IAW 5-B-24 LEVEL HI/LO)

• Sets Master LC-6-83 setpoint to 30 inches Auto Actions: None BOP Takes action IAW C.4-G (INADVERTENT ECCS INITIATION)

• Based on DW pressure and RPV water level indications, determines that initiation is spurious.

• Places HPCI Aux Oil Pump to RUN 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS CT-14 When HPCI inadvertently initiates, restore reactor

• Depresses HPCI Turbine TRIP pushbutton while power to within the license limit. performing the following:

o Verifies turbine has stopped o Places HPCI Aux Oil Pump to PTL

b. Respond appropriately as maintenance, o Waits 5 seconds to release the TRIP engineering and/or management to start the pushbutton necessary investigations and make the appropriate notifications.

CRS Evaluates TS LCO 3.5.1 as NOT MET

• Condition I.1 - Verify RCIC Operable immediately.

• Condition I.2 - Restore HPCI within 14 days.

Event 4 8. SJAE PRESSURE CONTROL VALVE FAILS CLOSED - AIR IN-LEAKAGE - DEGRADING CONDENSER VACUUM Booth a. When directed by the lead evaluator, Operator INSERT MANUAL TRIGGER 5 and verify MC03

& MC04B go active.

Key Parameter Response: 11 SJAE Inlet pressure lowers SS315.127 to 0 psig and Condenser vacuum begins to degrade. CR200.172 Key Expected Alarms: 7-A-20 (Offgas Annunciator) BOP

• Responds to 7-A-20 (Offgas Annunciator) and notifies the CRS Auto Actions: None

• Recognizes loss of 11 SJAE Pressure and degrading Main Condenser Vacuum CRS Directs C.4-F (Rapid Power Reduction)

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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Booth b. When the OATC lowers Recirc flow, verify MC03 OATC

• Lowers reactor power by lowering recirc flow until Operator deletes when MWe is <600 MWe. This will SS315.159 condenser vacuum is stabilized remove the air in-leakage and allow vacuum to CR200.203 stabilize.

c. Acknowledge any investigation / notification CRS Directs C.4-B.06.03.A (Decreasing Condenser Vacuum) requests to Engineering, Maintenance and Plant Management.

BOP

• Monitors SPDS Screen 656

• Trips HWC by placing HS-4149 on C-252A to OFF

• Notifies RP of changing Rad conditions Booth d. If directed as the TBO to open the MVP Suction

• Opens MVP suction valves OG-22-1 & OG-22-2 Operator Valves, insert MANUAL TRIGGER 7, verify MC06 activates and wait one minute to report the valves are open.

NOTE: Manual control will be unsuccessful.

• Notices PI-1246 indicates 0 psig and attempts to take manual control Booth e. When directed as the TBO to manually restore

• Contacts TBO to take manual control of the failed PCV Operator pressure, insert MANUAL TRIGGER 9, verify and restore it to 120-130 psig MC01 activates and wait for the 30 second ramp

• Resets AO-1085B by pressing PB-1085 to report that pressure is restored.

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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 9. FEEDWATER LEAK WITH LOSS OF FEED PUMPS

a. When directed by the Lead Examiner, insert MANUAL TRIGGER 10.

Key Parameter Response: Rising DW pressure and temperature, and Feed Pump trips.

Key Expected Alarms: 5-B-45 (DW HI/LO PRESSURE 6-A-11/12 (RCT FEEDPUMP P-2A/B OVERLOAD)

Auto Actions: Reactor scram at RPV level +9, Failure of OATC C.4-A (REACTOR SCRAM) actions:

RCIC to auto start at Low-Low Level (-47)

CR200.146

• Place Mode Switch in SHUTDOWN.

• Verifies all Control Rods are inserted to or beyond position 04

• Provides scram script to CRS and reports EOP entry condition RPV level less than 9

• Reports loss of RFPs and rapidly lowering RPV level BOP Takes actions IAW C.4-A (Reactor Scram) PART B:

• Plant page that a Reactor Scram has occurred.

• Open Main Generator output breakers 8N7 & 8N8.

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

• Trip the Main Turbine.

be performed depending on when the Feedwater leak is recognized.

• Verify the Generator Field Breaker Open.

• Start the Turbine Aux Oil 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 14 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

• Verify Turbine Exhaust Hood Sprays in service.

• Start the Turbine Bearing Lift Pumps

• Verify Main Steam Pressure Control or Low-Low Set is controlling Reactor Pressure.

• At C-25, Place the POST SCRAM switch in ON

• Verify 3300 gpm through each operating Feed Pump

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

• Verify 3000 gpm through each operating Condensate Pump Event 6 10. FAILURE OF HPCI/RCIC TO AUTO INJECT CRS Directs performance of C.5-1100 (RPV Control)

OATC

• Recognizes the trip of both Feed Pumps on OVERLOAD NOTE: With the leak on the A Feedwater line, RCIC CRS Directs RPV level control using HPCI and/or RCIC injection will have little effect in raising RPV water level.

NOTE: Due to the inadvertent initiation, HPCI can be OATC When directed by the CRS, places HPCI Aux Oil Pump to place in service using C.4-G. AUTO and verifies HPCI restarts.

CT-21 When system required to maintain core OATC Places RCIC in service using the Hard Card submergence do not automatically start, manually align the systems (specifically HPCI) prior to RPV

• Verifies RCIC in AUTO at 400 gpm level dropping below -126

• Opens MO-2096 NOTE: This critical task is still met if the OATC manually

• Starts Barometric Cdsr Vacuum Pump starts HPCI prior to reaching -47

• Opens MO-2107 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

• Opens MO-2106

• Opens MO-2078

• Verifies CV-2848/2849 and 2082A/B Closed

• Verifies RCIC speed rising

• Verifies RCIC pump flow at ~400 gpm NOTE: Performing C.5-3204 and/or C.5-3203 are optional OATC/ Starts 12 CRD pump IAW C.5-3204 (RPV MAKEUP WITH as they will have minimal effect in raising RPV water level. BOP CRD)

• Verifies 11 & 12 CRD Pump running

a. When directed to close CRD-168 as the RBO,

• Directs RBO to close CRD-168 insert MANUAL TRIGGER 13 and verify CH34 activates. After one minute report the valve OATC/

• Starts a SBLC pump for injection IAW C.5-3203 closed. BOP (Use Of Alternate Injection Systems For RPV Makeup) o Verifies injection o Adequately monitors and reports RPV level and Pressure, both values and trends.

11. PRIMARY CONTAINMENT CONTROL BOP Reports Drywell pressure rising

• Reports EOP entry conditions.

o DW pressure, DW Temp and Torus temp CRS Directs performance of C.5-1200 (PC Control)

• Start all available Torus cooling at 90°F NOTE: Drywell parameters will allow these to be performed

• May start Torus Sprays/Cooling but are not required as Drywell Conditions will improve on their own.

• May start Drywell Cooling 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

• Performs C.5 1200 actions

• Places Torus Sprays in service IAW C.5-3502 (Containment Sprays):

o Verifies RHR Pumps running o Takes Cont Spray/Cooling LPCI Initiation Bypass (B) to BYPASS o Opens MO-2007, 2011, & 2009 (B Loop) o Verifies LPCI Inject Outboard Valves are closed; MO-2012 and MO-2013.

BOP

• Initiates Containment Cooling o RHRSW Outlet valve controller set 20%

o Place HX Bypass in CLOSE o ECCS Load Shed to MANUAL OVERRIDE o Start RHRSW Pump(s) o Adjust flow to 3500 gpm per pump

• Start all available drywell cooling IAW C.5-3503 (Defeat Drywell Cooler Trips) o Place all D/W fan control switches to OFF o Open Knife switch KS3100 o Verify fan inlet dampers are in AUTO o Place all D/W fan control switches to ON o OPEN associated fan disch dampers 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

12. SCENARIO TERMINATION

a. The scenario may be terminated when actions are taken to start HPCI/RCIC and restore RPV water level.

b. The scenario may be also terminated at the Crew

• Remain in simulator for potential questions from discretion of lead instructor/evaluator evaluator.

c. End the scenario by placing the simulator in Crew

• No discussion of scenario or erasing of procedure FREEZE. 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 18 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SIMULATOR INPUT

SUMMARY

Event Initial /

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

RW01 RWM EQUIP FAILURE 1 Active InActive C-05-A03 ROD WITDRAWAL BLOCK 1 Active InActive HP01 HPCI AUTO INITIATION 3 Active Inactive MC03 CONDENSER AIR IN-LEAKAGE 5 2 0 MC04B SJAE PCV CV-1242 FAILS CLOSED 5 Active Inactive MC03 CONDENSER AIR IN-LEAKAGE (DELETES IN 1 SECOND) 29 Active Inactive RW01 RWM EQUIP FAILURE (DELETES IN 1 SECOND) 28 Active InActive C-05-A03 ROD WITDRAWAL BLOCK (DELETES IN 1 SECOND) 28 Active InActive FW26A FEEDWATER LINE BREAK INSIDE DW 10 1 0 FW16A 11 RFP TRIP 10 00:00:10 Active InActive FW16B 12 RFP TRIP 10 00:00:15 Active InActive C-06-A11 11 RFP OVERLOAD 10 00:00:10 Active InActive C-06-A12 12 RFP OVERLOAD 10 00:00:15 Active InActive RC01 RCIC AUTO START FAILURE 30 Active InActive 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 SIMULATOR INPUT

SUMMARY

Event Initial /

Code Description Trigger Delay(s) Ramp Final Value REMOTES ED08 1AR XFMR PRI Supply BKR 1N2 30 None None OPEN CLOSED MCO6 MVP SUCTION VALVES OG-22-1/2 7 100 0 MC01 MS-24-1 #11 SJAE PCV BYPASS 9 38 0 CH34 CRD-168 CH HEADER TO CST RETURN LINE 13 CLOSE 0 HP05 HPCI HIGH DW INITIATION BYPASS 11 INSTLD REMOVED HP06 HPCI LOW-LOW LEVEL INITIATION BYPASS 11 INSTLD REMOVED OVERRIDES 05-DS016-02 1AR XFMR TO 15 BUS GREEN LAMP 30 Off ON 05-DS022-02 1AR XFMR TO 16 BUS GREEN LAMP 30 Off ON 03-S37-01 SCRAM LOGIC RESET - GP 1&4 30 FALSE FALSE 03-S37-02 SCRAM LOGIC RESET - GP 2&3 30 FALSE FALSE 03-DS105-02 Rod Out Permit White Lamp 1 OFF ON 03-DS105-02 Rod Out Permit White Lamp (Deletes in 1 second) 28 OFF ON Event Trigger Definitions:

Code Description Event Trigger ZD_AMWDIG < 0.6 MWe Indication < 600 29 ZD_RWMBP RWM to BYPASS 28 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 23 ILT-SS-42E (2016 ILT NRC Scenario 3) 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 21 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

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

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 22 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

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

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 23 of 23 ILT-SS-42E (2016 ILT NRC Scenario 3) Rev. 0 Comments:

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

Validation Personnel Name Job Title / Qualification Validation Position Jason Pearce SM / SRO CRS Greg Pagel NPE&RO / RO OATC Brad Casperson 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.: NRC Scenario 4(SPARE) Op-Test No.: 2016-301 Examiners: ____________________________ Operators: _____________________________

____________________________ _____________________________

____________________________ _____________________________

Initial Conditions:

100% Power 4 Control Rods have been declared SLOW (38-47, 42-43, 46-39, and 50-31)

HPCI OOS Turnover:

Restore HPCI Event Malfunction Event Type* Event No. No. Description 1 None N (BOP) BOP will restore HPCI to standby by opening steam line isolation valves.

2 C-05-B20 I (OATC) A low condenser vacuum switch will fail with RPS failing TS (SRO) to insert a 1/2 scram. The OATC will need to insert a 1/2 scram and the CRS will address Technical Specifications 3 AP07 I (BOP) The ADS timer will inadvertently initiate requiring the BOP TS (SRO) to inhibit it. The CRS will address TSs.

4 04-A2S70-04 C (BOP) The EPR will fail upscale automatically placing the MPR R (OATC) in service. The BOP will be unsuccessful lowering reactor power and pressure with the MPR requiring the OATC to reduce recirc flow to stay below 100% power.

5 NI14C/NI13C I (OATC) APRM 3 will fail Upscale due to an INOP condition. The TS (SRO) OATC will bypass APRM 3 and the CRS will evaluate TSs.

6 04-A2S59-02 M (CREW) The MPR will fail in the lowering direction requiring a manual scram. When the reactor is scrammed an CH22A/B unisolable Torus Leak will occur eventually requiring the crew to Emergency Depressurize on low Torus water level.

7 C (POST) When performing actions for the ED, one SRV will fail to AP08D open. This will require the BOP to open other SRVs until a total of 3 are verified open.

(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-43E SEG TITLE: 2016 ILT NRC SCENARIO 4 (SPARE) REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME: 60-90 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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) 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

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 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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0

1. B.03.02-05.G.04 (Opening HPCI Steam Line Isolation Valves MO-

References:

2034 and MO-2035)

2. C05-A-22 (APRM UPSC/INOP Trip)

3. C05-A-3 (Rod Withdraw Block)

4. C05-A14 (APRM ALARM)

5. LCO 3.3.1.1, LCO 3.3.2.1 and TLCO 3.3.2.1

6. 3-A-25 (Auto Blowdown Timer Activated)

7. C.4-G (Inadvertent ECCS Initiation)

8. LCO 3.3.5.1 & LCO 3.5.1

9. C07-B-15 (EPR Trouble)

10. C.4-B.05.09-B (Main Steam Pressure Regulator Failure Causing Increased Pressure)

11. B.04.01-05.E.01 (Changing Recirculation Flow) hard card

12. 5-B-16 (Reactor Press Hi/Low)

13. C.4-B.05.09.A (Main Steam Pressure Regulator Failure Causing Reduction in Main Steamline Pressure)

14. C.4-A (Reactor Scram)

15. C.5-1100 (RPV Control)

16. C.5-1200 (Primary Containment Control)

17. C.5-2002 (Emergency Depressurization)

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:

Initiating Event with Core Damage Frequency:

Related PRA None Information:

Important Components / Accident Class:

None Important Operator Actions with Task Number:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 4 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

Apply administrative requirements for Tech Spec Section 3.3 and Bases to SS299.351 5-7 Instrumentation SS315.160 Supervise response to inadvertent ECCS initiation 5-7 Apply administrative requirements for Tech Spec Section 3.5 and Bases to SS299.353 5-7 ECCS and RCIC Supervise response to increasing pressure caused by main steam pressure SS315.123 5-7 regulator failure SS315.159 Supervise rapid power reduction 5-7 Supervise response to decreasing pressure caused by main steam pressure SS315.122 5-7 regulator failure SS315.164 Supervise immediate reactor shutdown 5-7 SS315.101 Supervise response to a reactor scram 5-7 SS304.196 Implement secondary containment control 5-7 SS304.194 Implement primary containment control 5-7 SS304.198 Implement emergency RPV depressurization 5-7 RO Tasks:

CR206.116 Opening HPCI Steam Line Isolation Valves MO-2034 and MO-2035 1-4 CR299.353 Apply Tech Spec Section 3.3 and Bases to Instrumentation 5 CR200.204 Perform the procedure for an inadvertent ECCS initiation 1-4 CR299.355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 5 Perform the procedure for a main steam press regulator failure causing 1-4 CR200.167 increasing pressure CR200.108 Changing recirculation flow 1-4 Perform the procedure for a main steam press regulator failure causing a 1-4 CR200.166 reduction in main steam pressure CR200.203 Perform the procedure for rapid power reduction 1-4 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR200.146 Perform the procedure for a Reactor Scram 1-4 CR304.105 Perform action associated with Secondary Containment Control 1-4 Perform action for a loss of inventory in the torus requiring RPV blowdown or 1-4 CR304.145 anticipation of blowdown and depressurizing to the main condenser CR314.101 Perform action associated with Emergency RPV Depressurization 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 5 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Condenser Vacuum Switch failure

2. Inadvertent ADS timer initiation

3. EPR upscale failure with MPR lock

4. APRM upscale failure

5. MPR fails downscale

6. Torus Leak After EOP Entry:

1. ADS Valve failure Abnormal Events:

1. Inadvertent ECCS initiation

2. Main Steam Pressure Regulator Failure Causing Increased Pressure

3. Main Steam Pressure Regulator Failure Causing Reduction in Main Steam Line Pressure Major Transients:

1. Unisolable leak from Torus resulting in a RPV blowdown Critical Tasks:

1. CT-16 Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate or a loss of adequate core cooling.

2. CT-26 When torus water level can NOT be maintained above -3.3, executes Emergency Depressurization per C.5-2002.

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO OVERVIEW:

Event 1: Restore HPCI to standby

• BOP will restore HPCI to standby by opening HPCI Steam Line Isolation Valves MO-2034 and MO-2035 IAW B.03.02-05.G.4.

Event 2: Condenser Vacuum switch Failure

• Condenser Low-Vacuum switch fails. The annunciator alarms but the Channel A RPS logic fails to trip, which requires the OATC to insert a 1/2 scram on RPS A. The CRS will evaluate Tech Specs for the inoperable switch.

Event 3: ADS Timer Failure

• The ADS timer will inadvertently initiate. This will require the CRS to direct that the ADS system be placed in Inhibit IAW C.4-G prior to the timer counting down.

• The CRS will evaluate Tech Specs for ADS being in Inhibit and declare the ADS function for all 3 ADS valves inoperable. This requires entry into LCO 3.5.1.

Event 4: EPR Upscale Failure with MPR Locking in Position

• The EPR will fail upscale, resulting in the MPR taking over at a higher CTP and the crew will need to lower reactor pressure.

• When the crew attempts to utilize the MPR to lower reactor pressure, the MPR will lock in place, forcing the OATC to reduce reactor power with Recirc Pumps.

Event 5: APRM UPSCALE/INOP Failure

• APRM 3 will experience an Upscale/INOP failure. The OATC will bypass the APRM and the CRS will evaluate Technical Specifications.

Event 6: MPR Downscale Failure with Reactor Scram

• The MPR will fail downscale and the crew will need to take action to scram the reactor prior to the automatic setpoint of 840 psig with the mode switch in RUN.

• Reactor pressure control will be restored to the MPR following the placement of the mode switch to the SHUTDOWN position.

Event 7: Unisolable Torus leak

• Following the scram, an unisolable torus leak will occur. The crew will be required to perform an emergency depressurization.

Event 8: D SRV fails to open for the Blowdown

• The BOP will recognize that the D SRV failed to open for the ED and open additional SRVs until a total of 3 are verified open.

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) 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: RUN

b. Present Power Level: 100%

c. XCEL System Condition: Green

d. Plant CDF: Green

e. Electrical lineup - 2R.

f. Fuel Pool Status: Green, 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> to boil

g. Generator Output: ~685 MWe

h. Staffing: Normal Weekday Dayshift

i. Planned Shift Activities: Restore HPCI to standby

j. The following equipment is OOS:

1) HPCI, ready to restore

2) 3.5.1 I entered yesterday at 0600 a) I.1 Complete, I.2 due in 14 days.

2. SIMULATOR SET UP BOOTH a. Reset the simulator to IC-294 (PW: rpb4) 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. Aligns HPCI as follows:

1) Ensure MO-2034 and MO-2035 are closed

2) Ensure HPCI steam line is depressurized

c. Ensure the following are provided for the crew:

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

d. Turnover checklists (3139 & 3140)

e. ENSURE Cross Flow is ENABLED on as follows:

1) Verify CFW966-CFW969 are set to ENABLED

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

f. Verify the status board is updated IAW Section 1

g. Complete the Simulator Setup Checklist

3. SIMULATOR PRE-BRIEF FLOOR a. REVIEW the scenario initial conditions as listed in INST 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.

4. SHIFT BRIEF Turbine Building status: Crew Conduct and participate in the Shift Brief 1). 5 Cond Demins are in service, E vessel d/p is highest @ 5.2 psid.

2). All systems in Turbine building are normal.

Extra out plant operator - Nothing to add.

Rx Building status:

1) HPCI ready to be restored, all other systems in CRS Crew assumes the duty.

the Rx Bldg are normal.

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 1 5. RESTORE HPCI TO STANDBY Booth a. ENSURE SIMULATOR SOUND IS OFF FOR BOP Performs B.03.02-05.G.4 (OPENING HPCI STEAM LINE Operator THIS EVOLUTION. ISOLATION VALVES MO-2034 AND MO-2035)

Notifies RP of changing radiation conditions Booth b. Role play as the RBO, wait one minute and state Isolate LS-23-90 (HPCI STM DRN HI LVL BYP)

Operator I-HPCI-R-6 and 7 are closed (Step 2)

NOTE: The simulator does NOT model these isolation Opens CV-2043 is in OPEN valves and the Alarm will still be received. The annunciator Verifies CV-2046A/B are OPEN tile light is overridden but the sound is not. Maintain the simulator sound OFF for the duration of this evolution.

Opens MO-2035 NOTE: Opening MO-2034 too fast could cause a high JOGs open MO-2034 and verifies full open steam flow isolation or water hammer

c. Role play as the RBO, wait one minute and state Unisolates LS-23-90 (HPCI STM DRN HI LVL BYP)

I-HPCI-R-6 and 7 are open

d. Role play as necessary, wait one minute and Notifies I&C to seal wire I-HPCI-R-6/7 report these steps are complete Verifies I-HPCI-R-6/7 are IVed open Verify CV-2043 is in AUTO Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 10 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 2 6. Condenser Vacuum Switch Failure BOOTH a. When directed by the lead evaluator, INST Insert MANUAL TRIGGER 3.

b. Verify C-05-B20 MALFUNCTION (Annunciator) goes active:

Key Parameter Response: None Key Expected Alarms: 5-B-20 (CONDENSER LOW OATC Responds to annunciator and reports to the CRS VACUUM SCRAM TRIP)

Auto Actions: None, RPS A fails to trip. Crew Recognize 1/2 scram should have occurred and did NOT

c. Evaluator prompt when the operator goes around CRS Evaluates TLCO 3.3.1.1 as NOT met & enters Condition A back to C-15 and C-17; 5A-K2A: Relay finger tabs back without contact

d. 5A-K2B, C, & D: Relay finger tabs forward with SS299.362

• Required Action A.2: Place associated trip system CR299.364 contact in Trip in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• Provides crew brief

• Directs 1/2 scram be inserted on A RPS EVALUATOR NOTE: If the crew decides to wait the 12 OATC Inserts 1/2 scram by depressing A manual scram hours to place channel in trip, inform them that time pushbutton or by the A.1 RPS Key switch compression is in effect and 11.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> have passed and the malfunction has not been resolved.

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 3 7. ADS TIMER FAILURE Booth When directed by the Lead Evaluator, insert BOP Acknowledges the alarm and informs the CRS that the Operator MANUAL TRIGGER 7 and verify AP07 is active: ADS timer is timing down Key Parameter Response: ADS timer timing down and Audible Alarm Key Expected Alarms: 3-A-25 (AUTO BLOWDOWN Crew Verifies plant parameters do not require ADS initiation TIMER ACTIVATED) (DW pressure and Reactor level are in the normal band).

Automatic Actions: After the ADS timer times out, an CRS Directs the BOP to perform actions of C.4-G ADS actuation will occur, resulting in the depressurization SS315.160 (INADVERTENT ECCS INITIATION) of the RPV.

Booth a. If Inhibit switches are NOT placed in BOP Places ADS Inhibit switches to INHIBIT and informs the Operator INHIBIT, Then insert Manual Trigger 8 to activate CR200.204 CRS that ADS is inhibited.

AP02. This will open the ADS valves. DELETE AP02 if the switches are then placed in INHIBIT.

CT-16 Inhibit ADS to avoid auto initiation that would result in CRS Evaluates LCO 3.3.5.1 as NOT MET a violation of cooldown rate or a loss of adequate core cooling.

Booth b. If contacted as System Engineer, acknowledge

• Enters Conditions G Operator report and inform operator you will assemble a troubleshooting team immediately.

• Required Actions - Declare ADS Valves inoperable within one hour CRS Evaluates LCO 3.5.1 as NOT MET once ADS valves are declared inoperable.

• Enters Condition K & L.

• Condition L requires the plant to be placed in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

QF107502 Rev. 4 (FP-T-SAT-75) Page 12 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 4 8. EPR Upscale Failure with MPR Locking in Position Booth a. When directed by the lead evaluator, Operator INSERT MANUAL TRIGGER 9 and verify Override 04-A2S70-04 goes active.

Key Parameter Response: RPV Pressure rises which BOP

• Notifies the CRS also raises Core Thermal Power Key Expected Alarms: C07-B-15 (EPR TROUBLE)

• Verifies that the MPR assumes steam pressure control Auto Actions: The MPR begins to control pressure

• Depress the EPR STOP Pushbutton

• Recognizes that the EPR TROUBLE annunciator does not reset CRS Performs C.4-B.05.09-B (MAIN STEAM PRESSURE SS315.123 REGULATOR FAILURE CAUSING INCREASED BOP PRESSURE)

CR200.167 BOP/ATC

• Monitor Reactor Pressure

• Identifies that Reactor pressure increased slightly when the EPR failed BOP

• Attempts to adjust the MPR to lower RPV pressure but will be unsuccessful and informs CRS.

Booth b. Role Play plant support personnel as necessary to BOP

• Initiate an investigation Operator acknowledge report. CRS CRS

• Directs OATC to reduce Rx Power IAW C.4-F (RAPID POWER REDUCTION).

NOTE: It is not the intent of this portion of the SEG to OATC

• Lowers power to restore reactor power within thermal evaluate Tech Specs. limits.

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 9. APRM 3 UPSCALE FAILURE BOOTH a. When directed by the lead evaluator, insert MANUAL TRIGGER 1, and verify INST NI13C/14C activate.

Key Parameter Response: APRM Channel #3 High or INOP Red indicating light lit; APRM Channel #3 recorder upscale high Key Expected Alarms: 05-A-22 (APRM UPSC/INOP Trip), OATC Responds to C05-A-3, 14 & 22 and notifies CRS.

05-A-3 (Rod Withdraw Block), 05-A-14 (APRM Alarm)

Automatic Actions: 1/2 Vote trip for APRM 3 on all 2 out of

• Determines the trip signal by pressing the APRM 4 Vote Logic Channels, Rod Withdraw Block or APRM ODA TRIP STATUS softkey

• Determines that APRM Channel 3 is upscale and Inoperable FLOOR b. When operator goes to Panel C-37 to observe

• Verifies each 2 of 4 Voter Module APRM status of 2 of 4 Voter Modules #1, 2 & 4, inform UPSC/INOP INPUT SATUS LEDs is ON for APRM INST him these voters indicate the same as Voter #3 and a Rod Block has initiated.

Module #3 for APRM Channel #3. Voter Modules 1, 2 & 4 are not modeled.

• Determines the INOP signal by pressing the APRM or APRM ODA INOP STATUS softkey; Critical Self-Test Fault BOOTH c. Role Play as plant management and support

• Notifies Plant Engineering.

personnel as necessary to acknowledge report.

INST CRS Evaluates LCO 3.3.1.1 and TLCO 3.3.2.1 as still MET SS299.351

• These LCOs only require 3 of 4 APRMs to be CR299.353 operable.

• Directs OATC to bypass APRM Channel #3.

• Bypasses APRM 3 as directed by the CRS.

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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 6 10. MPR Downscale Failure with Reactor Scram Booth a. After crew brief or when directed by the Floor Crew Identifies Reactor pressure lowering, reports Reactor low Operator Instructor, INSERT MANUAL TRIGGER 11 and pressure alarm and refers to appropriate ARP.

verify override 04-A2S59-01 activates.

Key Parameters: Reactor pressure lowers, Reactor power lowers Expected Alarms: 5-B-16 (REACTOR PRESS HI/LOW) BOP Determines MPR setpoint is lowering. Reports this to CRS.

Automatic Actions: Group 1 Isolation at 840 psig with CRS Enters C.4-B.05.09.A (MAIN STEAM PRESSURE Mode Switch in RUN SS315.122 REGULATOR FAILURE CAUSING REDUCTION IN MAIN SS315.101 STEAMLINE PRESSURE) and directs manual Reactor scram.

OATC Inserts a manual Reactor scram.

CR200.166 SS315.164 OATC Takes actions IAW C.4-A (REACTOR SCRAM) PART A:

Booth b. When the Mode switch is placed in SHUTDOWN, SS315.101

• Place Mode Switch in SHUTDOWN.

CR200.146 Operator verify EVENT TRIGGER 27 activates o Verify all Control Rods are inserted to or beyond position 04.

• Provides scram script to CRS. Reports RPV less than 9 EOP entry condition.

• Controls Reactor water level between +9 and +48 inches. When RPV water level starts to increase:

o Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches 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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS o Close both Main FW Reg Valves o Close MO-1133 and MO-1134 (HP Feedwater Line Block valves o Verify CV-6-13 is closed when RPV level reaches +15 to +20 inches

• Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

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

• Verify SDV Vent and Drain Valves closed.

performed depending on when the Torus leak is recognized.

• Verify Recirc Pumps have run back to minimum BOP Takes actions IAW C.4-A (Reactor Scram) PART B:

• Plant page that a Reactor Scram has occurred.

• Open Main Generator output breakers 8N7 & 8N8.

• Trip the Main Turbine.

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

• Verify the Generator Field Breaker Open.

performed depending on when the Torus leak is recognized.

• Start the Turbine Aux Oil Pump.

• Verify Turbine Exhaust Hood Sprays in service.

• Start the Turbine Bearing Lift Pumps 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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

• Verify Main Steam Pressure Control or Low-Low Set is controlling Reactor Pressure.

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

• Verify 3300 gpm through each operating Feed Pump

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

• Verify 3000 gpm through each operating Condensate Pump Event 6 10. UNISOLABLE TORUS LEAK

a. Verify Event Trigger 27 is active and verify Malfunction PC05 at 100%.

Key Parameter Response: Torus Level on LI-2996 (C-04) or PLR 7251A/B (C-03) lowering Key Expected Alarms: 6-B-9/10 (HIGH WATER LEVEL IN RHR ROOMS) 4-B-4 (TORUS HI-LOW LEVEL), 4-B-19/24 (TORUS VACUUM BREAKERS OPEN) and 5-A-49 (RADWASTE TROUBLE)

Auto Actions: Torus to Drywell Vacuum breakers begin to BOP Respond to 4-B-4, (Suppression Water Level Hi/Low) cycle NOTE: It takes ~19 minutes to reach -3.3 ft which is the

• Check LI-2996 on C-04 or PLR-7251A/B on C-03 decision point for a Reactor Scram and Emergency depressurization

• Identifies and reports the lowering trend 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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

• Reports EOP 1200 Entry Condition when Torus water level (Narrow Range) is < -4 inches

• Monitors and reports Torus water level throughout CRS Enters and directs actions from EOP-1200 (Primary Containment Control)

SS314.115

• Directs performance of C.5-3401 (Torus Water Level Makeup)

b. Role Play the out-plant operator if assigned to BOP

• May direct an in-plant operator to perform perform C.5-3401: Wait 2 minutes and report that CR314.119 C.5-3401 steps for Core Spray and RHR. (May he must find boots and PPE for the water on the choose not to perform due to safety concerns) floor.

c. As the RBO, when torus water level reaches less

• Verifies the HPCI CST Suction, MO-2063 Open than -1ft, report that the leak is from an unisolable weld break in the ring header

• Opens the HPCI Pump Minimum Flow Valve CV-2065

• Verifies the RCIC CST Suction, MO-2102 Open

• Opens the RCIC Pump Minimum Flow Valve CV-2104

12. EMERGENCY DEPRESSURIZATION CRS CRS May anticipate Blowdown per a C.5-1100 Override Statement and direct RPV pressure be lowered using the Turbine Bypass Valves BOP If directed to ANTICIPATE BLOWDOWN and lower RPV pressure using the Turbine Bypass Valves CR304.145

• At C-07, places PRESS REG OVERRIDE in OPEN until both Bypass valves are open Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF107502 Rev. 4 (FP-T-SAT-75) Page 18 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS CT 26 When torus water level can NOT be maintained CRS When it is determined that Torus Water Level can NOT be above -3.3, executes EMERGENCY maintained above -3.3 ft, Blowdown and enter EOP 2002.

DEPRESSURIZATION per C.5-2002 AND opens 3 SRVs before torus water level drops below -3.3 feet.

• Enters and directs EOP-2002 (Blowdown)

• Verifies Torus level > -5.9 ft.

• Directs that 3 ADS SRVs be opened BOP Perform Emergency Depressurization Booth a. Verify AP08D and 01-DS124-02 are active.

• Attempts to open all 3 ADS SRVs.

Operator These will prevent D SRV from opening.

• Recognizes that D SRV failed to open

• Opens additional SRVs until a total of 3 are open CRS Enters EOP-1300 (Secondary Containment Control)

15. SCENARIO TERMINATION FLOOR The scenario may be terminated when Emergency INST Depressurization has been performed.

The scenario may be also terminated at the discretion of Crew:

• Remain in simulator for potential questions from lead instructor/evaluator evaluator.

End the scenario by placing the simulator in FREEZE. Crew:

• 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 19 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 SIMULATOR INPUT

SUMMARY

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

C-05-B20 CONDENSER LOW VACUUM SCRAM TRIP 3 Active InActive AP07 ACTUATION OF ADS TIMER 7 Active InActive AP02 INADVERTANT APRS ACTUATION 8 Active InActive AP08D D SRV STUCK CLOSED 27 Active InActive PC05 TORUS DRAIN 27 Active InActive NI14C APRM 3 INOP 6 Active InActive NI13C APRM 3 Fullscale 6 Active InActive REMOTES OVERRIDES 04-A2S70-04 EPR STOP PUSHBUTTON 9 TRUE FALSE 04-A2S59-01 MPR HANDSWITCH - LOWER 9 FALSE FALSE 04-A2S59-02 MPR HADSWITCH - RAISE 9 FALSE FALSE 04-A2S59-01 MPR HANDSWITCH - LOWER 11 TRUE FALSE 04-A2S59-01 MPR HANDSWITCH - LOWER 27 FALSE TRUE 01-DS124-02 D SRV RED LIGHT - OFF 27 OFF OFF 01-AO3P1-B10 (3-B-10) HPCI TURBINE INLET HI DRAIN POT LEVEL OFF OFF Event Trigger Definitions:

Code Description Event Trigger ZD_S1SHD MODE SWITCH TO SHUTDOWN 27 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 23 MT-ILT-43E (2016 ILT NRC Scenario 4) 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 21 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

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

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 22 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

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

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 23 of 23 MT-ILT-43E (2016 ILT NRC Scenario 4) 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 OATC Brad Casperson NLPE&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.