Text

Initial License Exam Proposed Scenarios
	ML21019A217
Person / Time
Site:	Monticello
Issue date:	11/03/2020
From:	; NRC/RGN-III/DRS/OLB
To:	; Nuclear Management Co
	Zoia C
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ML19127A317	List: ML21019A175; ML21019A209; ML21019A217; ML21019A220; ML21019A423; ML21019A426; ML21019A433;
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Rev. 0 (12/14/2018)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-53E SEG TITLE: 2020 ILT NRC SCENARIO 1 REV. # 0 PROGRAM: INITIAL LICENSED TRAINING PROGRAM #: MT-ILT COURSE: N/A #: 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.

Rev. 0 (12/14/2018) Page 2 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 Guide Requirements Goal of This Scenario evaluation has been written for the 2020 ILT NRC Training: Exam. Once this exam is complete and exam security is relaxed, this SEG should be appropriate to use for the following activities:

Future ILT NRC / Audit Exam Evaluations

SRO Certification Evaluations

LOR Crew development Learning 1. Demonstrate the ability to predict and/or monitor changes in Objectives: parameters associated with operating system controls for the 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 Prerequisites: 1. Completion of the MT-ILT Training Program, or

2. Completion of the SRO Certification Program, or

3. Currently enrolled in the LOR Training Program Training 1. Full Scope Simulator Resources: 2. QF104016, Training Attendance Sheet or LMS equivalent

3. 3139, Control Room Shift Turnover checklist

4. 3140, Shift Supervision 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.

Rev. 0 (12/14/2018) Page 3 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0

References:

1. B.06.02.04-05.E.1, Swapping Stator Cooling Pumps Part B

2. TS 3.5.1

3. 5-A-03, Rod Withdraw Block

4. 5-A-06, APRM Downscale/Trouble

5. 5-A-22, APRM UPSC/INOP Trip

6. TS 3.3.1.1

7. TS 3.3.2.1

8. TRM 3.3.2.1

9. 5-A-46, SRV Open

10. C.4-B.03.03.A, Stuck Open SRV

11. TS 3.3.6.3

12. TS 3.6.1.5

13. C.4-F, Rapid Power Reduction

14. 3-B-56, High Area Temp Steam Leak

15. 4-A-11, Reactor Building Hi Radiation

16. C.4-B.04.01.D, Group 4 Isolation

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.5-1300 Secondary Containment Control

22. C.5-3502, Containment Sprays

23. C.5-3503, Defeat Drywell Cooler Trips

24. B.03.04-05.H1-8, Torus Cooling Hard Cards

25. C.4-B.05.07.A (Loss of RPV Level Control)

Commitments: None Evaluation The following methods are acceptable methods for examinee Method: evaluation:

2020 ILT NRC Exam Process (NUREG 1021 & FP-T-SAT-72)

FL-ILT, Initial Licensed Training Program Description

FL-Cert, Senior Reactor Operator Certification

FP-T-SAT-73, Licensed Operator Requalification Program Operating Not Applicable to Evaluation Scenarios Experience:

Related PRA Initiating Event with Core Damage Frequency:

Information: None Important Components:

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.

Rev. 0 (12/14/2018) Page 4 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

Apply Admin requirements to TS Section 3.5 and Bases to ECCS and MT-SRO-299-353 5-7 RCIC MT-SRO-299-351 Apply administrative requirements for Tech Spec Section 3.3 and 5-7 Bases to Instrumentation Apply administrative requirements of Technical Requirements Manual MT-SRO-299-362 5-7 (TRM)

MT-SRO-315-109 Supervise the response to a stuck open relief valve 5-7 MT-SRO-315-115 Supervise response to a primary containment isolation - Group 4 5-7 MT-SRO-315-159 Supervise rapid power reduction 5-7 MT-SRO-315-101 Supervise response to reactor scram 5-7 MT-SRO-315-164 Supervise immediate reactor shutdown 5-7 MT-SRO-315-101 Supervise response to a reactor scram 5-7 Implement the response for high containment pressure requiring MT-SRO-304-233 drywell sprays maintaining safe region PSP with no blowdown 5-7 required.

RO Tasks:

MT-CRO-245-121 Startup the Stator Cooling System 1-4 MT-CRO-299-355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 5 MT-CRO-299-353 Apply Tech Spec Section 3.3 and Bases to Instrumentation 1-4 MT-CRO-299-364 Apply Requirements of Technical Requirements Manual (TRM) 1-4 MT-CRO-200-154 Perform the procedure for a stuck open relief valve 1-4 MT-CRO-200-160 Perform the procedure for primary containment Group 4 isolation 1-4 MT-CRO-200-203 Perform the procedure for rapid power reduction 1-4 MT-CRO-200-208 Perform the procedure for immediate reactor shutdown 1-4 MT-CRO-200-146 Perform the procedure for a Reactor Scram 1-4 Perform the actions for high containment pressure requiring drywell 1-4 MT-CRO-304-146 sprays maintaining safe region PSP with no blowdown required.

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

Rev. 0 (12/14/2018) Page 5 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. APRM #3 fails downscale

2. SRV H stuck mechanically open

3. HPCI steam leak

4. SRV H re-opens mechanically

5. SRV H Tailpipe break requiring DW spray After EOP Entry:

1. Low Flow Feedwater Regulating Valve fails in automatic Abnormal Events:

1. HPCI steam leak

2. Stuck open SRV

3. Loss of RPV level control Major Transients:

1. SRV Tailpipe break requiring DW spray Critical Tasks:

1. CT-6: When an SRV is stuck open and can NOT be closed then insert a manual reactor scram.

2. CT-30: When drywell pressure reaches 12 psig then initiate drywell spray.

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

Rev. 0 (12/14/2018) Page 6 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO OVERVIEW:

Initial Conditions: 100% power with 1AR Transformer OOS Event 1: Swap Stator Water Cooling (SWC) Pumps

The BOP will place 12 SWC Pump in service for vibration data and place the 11 SWC Pump in standby IAW with the B Manual.

Event 2: APRM #3 Fails Downscale

APRM #3 will fail downscale. The OATC will take action to bypass the APRM.

Event 3: SRV H Stuck Open Mechanically

SRV H will stick open mechanically; the BOP will take immediate actions causing SRV H to partially close. The OATC will reduce power which will result in SRV H fully closing. CRS will evaluate Tech Specs for an inoperable Low Low Set SRV.

Event 4: HPCI steam leak with Group 4 failure

HPCI will develop a steam leak causing room temperatures and radiation levels to rise. The Group 4 automatic isolation will fail requiring the BOP to manually isolate the system. The CRS will evaluate Tech Specs for HPCI inoperable.

Event 5: SRV H Re-opens requiring a Rx Scram

SRV H will re-open mechanically and will not close requiring the OATC to insert a manual reactor scram.

Event 6: SRV H Tailpipe Steam Leak requiring DW Spray

Following the scram, SRV H tailpipe will rupture above the waterline in the Torus.

The CRS will direct DW Sprays when DW pressure exceeds 12 psig. SRV H will close once the DW sprays are initiated.

Event 7: Low Flow Feedwater Regulating Valve (LFRV) fails in automatic

Following the scram the LFRV will not function in automatic level control. The OATC will be required to control RPV level in manual for the remainder of the scenario.

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

Rev. 0 (08/02/2018) Page 7 of 23 ILT-SS-53E, 2020 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: Green

e. Plant Fire LERF: Green

f. Electrical lineup - 2R.

g. Fuel Pool Status: Green, 88 hours0.00102 days 0.0244 hours 1.455026e-4 weeks 3.3484e-5 months to boil

h. Generator Output: ~690 MWe

i. Staffing: Normal Weekday Dayshift

j. Planned Shift Activities: Swap SWC Pumps

k. The following equipment is OOS:

1) 1AR Transformer

l. Two Non-Adjacent Control Rods have been declared SLOW (10-11 & 10-43)

2. SIMULATOR SET UP Booth a. Reset the simulator to IC-281 (PW: bucks1) and Inst place 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.

1) Turnover checklists (3139 & 3140)

c. Place a CAUTION tag on the 1AR Supply Breakers to 15 and 16 Buses.

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

Rev. 0 (08/02/2018) Page 8 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS

d. ENSURE tiles on Panel C-06 are arranged to reflect NO cooling towers are in service.

1) River temp is 56°F

2) Outside temp is 60°F

e. Verify the status board is updated IAW Section 1

f. Complete the Simulator Setup Checklist

3. SIMULATOR PRE-BRIEF Floor Inst 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.

4. SHIFT BRIEF

a. Shift Chemistry, RP and Security- Nothing to add.

b. 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). 1AR is OOS for an oil leak 4). All other systems in TB are normal.

c. Extra out plant operator - Nothing to add.

d. Rx Building status:

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

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

Rev. 0 (08/02/2018) Page 9 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 1 5. SWAPPING STATOR WATER COOLING PUMPS SWAPPING STATOR WATER COOLING PUMPS BOOTH a. When contacted as the TBO, state that you are BOP Performs B.06.02.04-05.E.1, Swapping Stator Cooling INST standing by to swap SWC Pumps and roll play as Pumps Part B follows:

TBO: State that discharge pressure is 125 psig

Note discharge pressure on PI-7121 (Panel C-83)

Starts 12 SWC Pump TBO: State that discharge pressure is now 130 psig

Verifies discharge pressure on PI-7121 TBO: State that discharge pressure is back to 125 psig.

Stops 11 SWC Pump

Verifies discharge pressure is 115-135 on PI-7121 TBO: State that inlet pressure is 30 psig

Verifies inlet pressure <56 psig on PI-7122 TBO: State that flow is 300 gpm

Verify flow is 285-315 gpm on FIS-7183 Event 2 6. APRM #3 FAILS DOWNSCALE APRM #3 FAILS DOWNSCALE Booth a. When directed by the Lead Evaluator, insert OATC Acknowledges the alarm and informs the CRS that APRM Inst TRIGGER 2. #3 has failed downscale.

Key Parameter Response: APRM #3 Reads fully Enters ARP 5-A-06 Downscale Key Expected Alarms: 5-A-06, APRM

Determines that APRM #3 has failed downscale.

Downscale/Trouble, 5-A-03, Rod Withdraw Block, 5-A-22, APRM UPSC/INOP Trip Automatic Actions: Control Rod Withdrawal Block

Places 7B-S3, APRM Bypass Switch in #3 position to bypass APRM #3.

Enters ARP 5-A-22

Determines that APRM #3 has failed downscale.

Booth b. Acknowledge any investigation / notification

Informs CRS to evaluate TS 3.3.1.1, 3.3.2.1 and Inst requests to Engineering, Maintenance and Plant TRM 3.3.2.1 Management.

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

Rev. 0 (08/02/2018) Page 10 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS NOTE: For ILT Exam scenarios, this is NOT an evaluated CRS Evaluates LCO 3.3.1.1, 3.3.2.1, and TRM 3.3.2.1 as MET TS Call for the CRS since the LCOs remain met. Once the APRM is bypassed, the lead evaluator may move on to Event 3.

Event 3 7. SRV H FAILS OPEN MECHANICALLY SRV H FAILS OPEN MECHANICALLY Booth a. When directed by the Lead Evaluator, Insert Operator TRIGGER 3 and verify Malfunction AP01H goes active.

Key Parameter Response: SRV H Fails Open, Lowering BOP Implements C.4-B.03.03.A, Stuck Open SRV Generator MWe, Lowered C Steam Line Pressure.

Key Expected Alarms: 5-A-46, SRV Open Immediate Actions:

Auto Actions: None

Takes the handswitch to Open and then back to Auto, and then takes handswitch to Close.

Bypasses Div II Lo-Lo Set logic signal.

b. Verify TRIGGER 23 activates when the BOP takes

Notifies CRS the SRV H switch to Close. This will partially close Subsequent Actions:

the SRV but it will remain slightly open and require additional actions to be performed.

Verifies HS-S43, RV Local Control, keylock switch in OFF.

Recognizes H SRV remains partially open and recommends C.4-F.

c. Verify TRIGGER 13 activates when 11 RECIRC CRS Directs C.4-F, Rapid Power Reduction pump speed is reduced. This will cause the SRV OATC Performs a power reduction IAW C.4-F. Recognizes that to close. H SRV is closed.

CRS May establish new power and/or pressure band.

Booth d. Acknowledge any investigation / notification CRS Declares LCO 3.3.6.3 as NOT met (Div 2 Bypassed)

Operator requests to Engineering, Maintenance and Plant Condition A applies to restore channels in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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

Rev. 0 (08/02/2018) Page 11 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS

e. If form 3038 is requested for SRV tailpipe Declares LCO 3.6.1.5 as NOT met (HS in Close) monitoring, state that the WEC SRO will attain. Condition A applies to restore LL-SET valve in 14 days.

Declares TLCO 3.4.4 (SRV Safety Function) as NOT met Condition A applies to restore within 14 days.

Event 4 8. HPCI STEAM LEAK HPCI STEAM LEAK BOOTH a. When directed insert Trigger 4 and verify that INST HP07 activates.

Key Parameter Response: Rising radiation levels and CRS Directs HPCI isolated IAW C.4-B.04.01.D, Group 4 temperatures in the Reactor Building. Isolation Key Expected Alarms: 3-B-56, High Area Temp Steam Crew Evacuates the Reactor Building Leak, 4-A-11, Reactor Building Hi Radiation BOP Closes the following valves:

Automatic Actions: Group 4 fails to automatically isolate

MO-2034

MO-2035 Verifies rad levels and temperatures are trending down.

BOOTH When contacted as engineering, maintenance or Initiates and investigation.

INST plant management, state that the appropriate investigations and/or notifications will be initiated.

CRS Enters C.5-1300, Secondary Containment Control for one area above max normal radiation Evaluates TS 3.5.1 Condition I NOT met which requires HPCI restoration within 14 days.

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

Rev. 0 (08/02/2018) Page 12 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 9. SRV RE-OPENS MECHANICALLY REQUIRING A SRV RE-OPENS MECHANICALLY REQUIRING A MANUAL REACTOR SCRAM MANUAL REACTOR SCRAM Booth a. When directed by the lead evaluator, Inst INSERT MANUAL TRIGGER 5.

Key Parameter Response: SRV H Fails Open, Lowering Generator MWe, Lowered Steam Line Pressure.

Key Expected Alarms: 5-A-46, SRV Open Auto Actions: None BOP Recognizes H SRV has re-opened:

Immediate Actions:

Takes the handswitch to Open, back to Auto and returns it to Close.

Recognizes further immediate actions have already been taken.

Subsequent Actions:

CT-6 When an SRV is stuck open and can NOT be

Potentially recommends reducing reactor power closed then insert a manual reactor scram prior to further IAW C.4-F depending on size of initial Tours water temperature reaching 110°F. power reduction.

Recommends Reactor Scram.

CRS Directs Reactor Scram IAW C.4-K, Immediate Reactor Shutdown Booth Verify that TRIGGER 6 inserts when the MODE Switch is OATC

Scrams the RX IAW C.4-K, Immediate Reactor Inst placed in shutdown. This will insert Malfunction PC09H and Shutdown cause an H SRV line break above the waterline in the Torus.

OATC Takes actions IAW C.4-A, Reactor Scram PART A:

Depress the scram pushbuttons

Place Mode Switch in SHUTDOWN.

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

Rev. 0 (08/02/2018) Page 13 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS

Verify all Rods are inserted to position 04.

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

Restores RPV water level in band.

Verify SDV Vent and Drain Valves closed.

When RPV water level starts to rise:

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 Use +30 to +40 band when stable o Monitor Reactor Power o Insert SRM and IRM detectors.

Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

o 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.

Verify the Generator Field Breaker Open.

Start the Turbine Aux Oil Pump.

Verify Turbine Exhaust Hood Sprays in service.

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

Rev. 0 (08/02/2018) Page 14 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS

Verify Turbine Stop Valves are closed

Start Turbine Bearing Lift Pumps

Verify Main Steam Pressure Control & Bypass valves are controlling Reactor Pressure.

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

At C-25, Place the POST SCRAM switch in ON performed depending on when the LOCA is recognized. 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 CRS Directs performance of C.5-1100, RPV Control Event 6 10. SRV H LINE BREAK REQUIRING DW SPRAY SRV H LINE BREAK REQUIRING DW SPRAY Key Parameter Response: Rising DW Pressure, Rising DW Temperature, Rising Torus Pressure.

Key Expected Alarms: 3-B-54, Containment Spray Permissive, 3-B-53, Drywell Hi Press, 4-B-35, Drywell-Torus Hi Press CRS Directs performance of C.5-1200, PC Control BOP Places Torus Sprays in service IAW C.5-3502, Containment Sprays:

NOTE: Its not anticipated that the crew will establish Torus

Verifies RHR Pumps running Sprays prior to reaching 12 psig in the DW.

Takes Cont Spray/Cooling LPCI Initiation Bypass (B) to BYPASS

Opens MO-2007, 2011, & 2009 (B Loop)

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

Rev. 0 (08/02/2018) Page 15 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS

Verifies LPCI Inject Outboard Valves are closed; MO-2012 and MO-2013.

Initiates Containment Cooling

RHRSW Outlet valve controller set 20%

Place HX Bypass in CLOSE

ECCS Load Shed to MANUAL OVERRIDE

Start RHRSW Pump(s)

Adjust flow to 3500 gpm per pump BOP Start all available drywell cooling IAW C.5-3503, Defeat Drywell Cooler Trips

Place all D/W fan control switches to OFF

Open Knife switch KS3100

Verify fan inlet dampers are in AUTO

Place all D/W fan control switches to ON

OPEN associated fan disch dampers CT-30 When drywell pressure reaches 12 psig then initiate BOP Initiates Drywell Spray IAW C.5-3502, Containment drywell spray. Sprays:

Booth a. Verify Trigger 15 activates when DW Sprays are

Removes DW Fans from service Oper initiated. This will close the SRV.

Verifies Recirc Pumps are tripped.

Open Drywell Spray Outboard MO-2021

Open Drywell Spray Inboard MO-2023

Close Torus Cooling MO-2009 CRS Directs BOP to secure DW Spray at 2 psig.

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

Rev. 0 (08/02/2018) Page 16 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SCENARIO TIME-LINE CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 7 11. LFRV FAIL TO OPERATE IN AUTOMATIC LFRV FAIL TO OPERATE IN AUTOMATIC May enter C.4-B.05.07.A, Loss of RPV Level Control Key Parameters: LFRV fails to open and restore RPV OATC Recognizes that CV-6-13 is closed when RPV level water level. reaches is less than +15 inches Expected Alarms: None Recognizes that there is no feed flow, RPV level doesnt rise and the LFRV does not open.

Automatic Actions: None

Places LFRV back in Manual

Restores RPV level in manual control

12. SCENARIO TERMINATION SCENARIO TERMINATION Floor Inst a. The scenario may be terminated when the DW has been sprayed, DW pressure is under control and RPV level is in band in manual control.

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.

Rev. 0 (08/02/2018) Page 17 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 SIMULATOR INPUT

SUMMARY

Event Initial /

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

NI12C APRM CHANNEL #3 DOWNSCALE 2 ACTIVE INACTIVE AP01H SAFETY/RELIEF VALVE (RV2-71-H) FAILS OPEN (SRV) 3 ACTIVE INACTIVE SAFETY/RELIEF VALVE (RV2-71-H) FAILS OPEN (SRV)

AP01H 23 ACTIVE INACTIVE (DELETES IN 1 SECOND)

AP03H Auto Blowdown Relief Valve Leak (RV-71H) (SRV) 23 100 0 Auto Blowdown Relief Valve Leak (RV-71H) (SRV)

AP03H 13 100 0 (Deletes in 1 Second)

HP07 HPCI STEAM LEAK 4 00:02:00 10 0 HP08 FAILURE OF HPCI TO AUTO ISOLATE 50 ACTIVE INACTIVE PC09H SAFETY/RELIEF VALVE RV2-71H LINE BREAK (SRV) 6 00:01:00 ACTIVE INACTIVE AP01H SAFETY/RELIEF VALVE (RV2-71-H) FAILS OPEN (SRV) 5 ACTIVE INACTIVE AP01H SAFETY/RELIEF VALVE (RV2-71-H) FAILS OPEN (SRV) 15 INACTIVE ACTIVE (DELETES IN 1 SECOND)

REMOTES ED08 1AR XFMR PRI SUPPLY BKR 1N2 50 OPEN CLOSE OVERRIDES 05-DS016-02 1AR XFMR TO 15 BUS - GREEN LAMP 50 OFF 0 05-DS022-02 1AR XFMR TO 16 BUS - GREEN LAMP 50 OFF 0 03-A166-02 CV-6-13 LFRV - AUTO 50 FALSE UNK Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (08/02/2018) Page 18 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 Event Trigger Definitions:

Code Description Event Trigger ZD_S1SHD Mode Switch to Shutdown 6 ZD_ZS9P(1) + ZD_ZS9P(2) MO-2020 or MO-2021 Handswitch to Open 15 ZD_MAMAN(1) 11 Recirc to Lower 13 ZD_HS4C(8) SRV H to Close 23 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (08/02/2018) Page 19 of 23 ILT-SS-53E, 2020 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 2020 ILT NRC Exam PROP CHECKLIST The following props will be used during this scenario. Verify the props are properly place kept, erased or removed as appropriate before and after the scenario. This list should include marked up placards, equipment tags, protected equipment signs and boxes, etc. First and second checkers, initial below.

BEFORE AFTER 1st 2nd 1st 2nd PROPS Yellow Caution tag on 1AR to 15 & 16 Bus breakers 3139 Turnover Sheet 3140 Turnover Sheet NRC Scenario 1 Pre-Brief Yellow Paper Tablets For Examinees Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (08/02/2018) Page 20 of 23 ILT-SS-53E, 2020 ILT NRC Scenario 1 Rev. 0 PROCEDURE CHECKLIST The following procedures will be used during this scenario. Verify the procedures are free of place keeping marks before and after the scenario is administered. This procedures list should match the procedures listed in the front matter references section. First and second checkers, initial below.

BEFORE AFTER 1 st 2 nd 1 st 2nd PROCEDURES B.06.02.04-05.E.1, Swapping Stator Cooling Pumps Part B TS 3.5.1 5-A-03, Rod Withdraw Block 5-A-06, APRM Downscale/Trouble 5-A-22, APRM UPSC/INOP Trip TS 3.3.1.1 TS 3.3.2.1 TRM 3.3.2.1 5-A-46, SRV Open C.4-B.03.03.A, Stuck Open SRV TS 3.3.6.3 TS 3.6.1.5 C.4-F, Rapid Power Reduction 3-B-56, High Area Temp Steam Leak 4-A-11, Reactor Building Hi Radiation C.4-B.04.01.D, Group 4 Isolation C.4-K, Immediate Reactor Shutdown C.4-A, Reactor Scram C.5-1100, RPV Control C.5-1200, Primary Containment Control C.5-1300 Secondary Containment Control C.5-3502, Containment Sprays C.5-3503, Defeat Drywell Cooler Trips B.03.04-05.H1-8, Torus Cooling Hard Cards C.4-B.05.07.A Loss of RPV Level Control Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (08/02/2018) Page 21 of 23 ILT-SS-53E, 2020 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.

Rev. 0 (08/02/2018) Page 22 of 23 ILT-SS-53E, 2020 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.

Rev. 0 (08/02/2018) Page 23 of 23 ILT-SS-53E, 2020 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 Dave Bernstrom CRS / SRO CRS Cory Broich NPE&RO / RO OATC Brad Casperson NPLE&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.

Rev. 0 (12/14/2018)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-54E SEG TITLE: 2020 ILT NRC SCENARIO 2 REV. # 0 PROGRAM: INITIAL LICENSED TRAINING PROGRAM #: MT-ILT COURSE: N/A #: 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.

Rev. 0 (12/14/2018) Page 2 of 25 ILT-SS-50E, 2020 ILT NRC Scenario 2 Rev. 0 Guide Requirements Goal of This Scenario evaluation has been written for the 2020 ILT NRC Training: Exam. Once this exam is complete and exam security is relaxed, this SEG should be appropriate to use for the following activities:

Future ILT NRC / Audit Exam Evaluations

SRO Certification Evaluations

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