Text

Initial License Exam Administered Scenarios
	ML21019A573
Person / Time
Site:	Monticello
Issue date:	11/03/2020
From:	Chuck Zoia; Operations Branch III
To:	; Nuclear Management Co
	Zoia C
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ML19127A318	List: ML21019A572; ML21019A573; ML21019A574;
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Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 1 Op-Test No.: 2020-301 Examiners: ____________________________ Operators:

Initial Conditions: 100% Power 1AR XFMR is OOS for an oil leak Two non-adjacent control rods declared slow Turnover: Swap Stator Water Cooling Pumps Critical Tasks:

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

CT-30: When Drywell pressure reaches 12 psig then initiate drywell sprays within 22 minutes.

Event No.

Malf No.

Event Type*

Event Description 1

N/A N - BOP The BOP will place 12 SWC Pump in service for vibration data and place the 11 SWC Pump in standby IAW with the Ops Manual.

2 NI12C I - OATC NP2 APRM #3 will fail downscale. The OATC will take action to bypass the APRM.

3A AP01H C - BOP NP2 SRV H will stick open mechanically; the BOP will take immediate actions causing SRV H to partially close.

3B R - OATC TS - CRS NP2 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.

4 HP07 C - BOP TS - CRS 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.

5 AP01H CT-6 SRV H will re-open mechanically and will not close requiring the OATC to insert a manual reactor scram prior to torus temperature reaching 110°F.

6 PC09H M - Crew CT-30 NP2 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.

7 03-A166-02 Post/C - OATC 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.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (NP2) - Not on previous 2 NRC Exams: >2 events

Rev. 0 (12/14/2018)

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

SIMULATOR EXERCISE GUIDE (SEG)

SITE: 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2020 ILT NRC 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 Objectives:

1.

Demonstrate the ability to predict and/or monitor changes in 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 Resources:

1. Full Scope Simulator

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

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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 Method:

The following methods are acceptable methods for examinee 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 Experience:

Not Applicable to Evaluation Scenarios Related PRA Information:

Initiating Event with Core Damage Frequency:

None Important Components:

None Important Operator Actions with Task Number:

None

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

MT-SRO-299-353 Apply Admin requirements to TS Section 3.5 and Bases to ECCS and RCIC 5-7 MT-SRO-299-351 Apply administrative requirements for Tech Spec Section 3.3 and Bases to Instrumentation 5-7 MT-SRO-299-362 Apply administrative requirements of Technical Requirements Manual (TRM) 5-7 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 MT-SRO-304-233 Implement the response for high containment pressure requiring drywell sprays maintaining safe region PSP with no blowdown required.

5-7 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 MT-CRO-304-146 Perform the actions for high containment pressure requiring drywell sprays maintaining safe region PSP with no blowdown required.

1-4

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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 within 22 minutes.

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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 3A: SRV H Stuck Open Mechanically - BOP

SRV H will stick open mechanically; the BOP will take immediate actions causing SRV H to partially close.

Event 3B: SRV H Stuck Open Mechanically - OATC/CRS 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.

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NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

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, 152 hours0.00176 days 0.0422 hours 2.513228e-4 weeks 5.7836e-5 months to 200°F

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 Inst

a. Reset the simulator to IC-281 (PW: bucks1) and 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.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

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 control boards prior to starting the shift brief.

Crew Performs walk down of control boards and reviews 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.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1

5.

SWAPPING STATOR WATER COOLING PUMPS SWAPPING STATOR WATER COOLING PUMPS BOOTH

a.

When contacted as the TBO, state that you are standing by to swap SWC Pumps and roll play as follows:

BOP Performs B.06.02.04-05.E.1, Swapping Stator Cooling Pumps Part B 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 TRIGGER 2.

OATC Acknowledges the alarm and informs the CRS that APRM

3 has failed downscale.

Key Parameter Response: APRM #3 Reads fully Downscale Enters ARP 5-A-06 Key Expected Alarms: 5-A-06, APRM Downscale/Trouble, 5-A-03, Rod Withdraw Block, 5-A-22, APRM UPSC/INOP Trip Determines that APRM #3 has failed downscale due to a Critical Self-Test Fault.

Automatic Actions: Control Rod Withdrawal Block Places 7B-S3, APRM Bypass Switch in #3 position to bypass APRM #3.

Floor

b.

If asked about the status of APRMs 1, 2 and 4; state they all read normal.

Enters ARP 5-A-22 Determines that APRM #3 has failed downscale.

Booth

c.

Acknowledge any investigation / notification requests to Engineering, Maintenance and Plant Management.

Informs CRS to evaluate TS 3.3.1.1, 3.3.2.1 and TRM 3.3.2.1

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES NOTE: For ILT Exam scenarios, this is NOT an evaluated TS Call for the CRS since the LCOs remain met. Once the APRM is bypassed, the lead evaluator may move on to Event 3.

CRS Evaluates LCO 3.3.1.1, 3.3.2.1, and TRM 3.3.2.1 as MET Event 3A 7.

SRV H FAILS OPEN MECHANICALLY SRV H FAILS OPEN MECHANICALLY Booth Operator

a.

When directed by the Lead Evaluator, Insert TRIGGER 3 and verify Malfunction AP01H goes active.

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

BOP Implements C.4-B.03.03.A, Stuck Open SRV 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 the SRV H switch to Close. This will partially close the SRV but it will remain slightly open and require additional actions to be performed.

Notifies CRS Subsequent Actions:

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

NOTE: Steam Line C will still show a slightly lower steam flow, tailpipe temp will remain high and the amber light will remain on.

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

Event 3B

c.

Verify TRIGGER 13 activates when 11 RECIRC pump speed is reduced. This will cause the SRV to close.

CRS Directs C.4-F, Rapid Power Reduction OATC Performs at least a 10% power reduction IAW C.4-F.

Recognizes that H SRV is closed.

Booth Operator

d.

Acknowledge any investigation / notification requests to Engineering, Maintenance and Plant Management CRS May establish new power and/or pressure band.

CRS Declares LCO 3.3.6.3 as NOT met (Div 2 Bypassed)

Condition A applies to restore channels in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

e.

If form 3038 is requested for SRV tailpipe monitoring, state that the WEC SRO will attain.

Declares LCO 3.6.1.5 as NOT met (HS in Close)

Condition A applies to restore LL-SET valve in 14 days.

Event 4

8.

HPCI STEAM LEAK HPCI STEAM LEAK BOOTH INST

a.

When directed insert Trigger 4 and verify that HP07 activates.

Key Parameter Response: Rising radiation levels and temperatures in the Reactor Building.

CRS Directs HPCI isolated IAW C.4-B.04.01.D, Group 4 Isolation Key Expected Alarms: 3-B-56, High Area Temp Steam Leak, 4-A-11, Reactor Building Hi Radiation Crew BOP Evacuates the Reactor Building 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 INST When contacted as engineering, maintenance or plant management, state that the appropriate investigations and/or notifications will be initiated.

Initiates and investigation.

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.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

9.

SRV RE-OPENS MECHANICALLY REQUIRING A MANUAL REACTOR SCRAM SRV RE-OPENS MECHANICALLY REQUIRING A MANUAL REACTOR SCRAM Booth Inst

a. When directed by the lead evaluator, 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 back 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 closed then insert a manual reactor scram prior to Tours water temperature reaching 110°F.

Potentially recommends reducing reactor power further IAW C.4-F depending on size of initial power reduction.

Recommends Reactor Scram.

CRS Directs Reactor Scram IAW C.4-K, Immediate Reactor Shutdown Booth Inst Verify that TRIGGER 6 inserts when the MODE Switch is placed in shutdown. This will insert Malfunction PC09H and cause an H SRV line break above the waterline in the Torus.

OATC Scrams the RX IAW C.4-K, Immediate Reactor Shutdown OATC Takes actions IAW C.4-A, Reactor Scram PART A:

Depress the scram pushbuttons Place Mode Switch in SHUTDOWN.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 performed depending on when the LOCA is recognized.

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 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 Sprays prior to reaching 12 psig in the DW.

Verifies RHR Pumps running Takes Cont Spray/Cooling LPCI Initiation Bypass (B) to BYPASS Opens MO-2007, 2011, & 2009 (B Loop)

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 drywell spray within 22 minutes.

BOP Initiates Drywell Spray IAW C.5-3502, Containment Sprays:

Removes DW Fans from service

Verifies Recirc Pumps are tripped.

Booth

a.

Verify Trigger 15 activates when DW Sprays are initiated. This will close the SRV.

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.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 water level.

OATC Recognizes that CV-6-13 is closed when RPV 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 discretion of lead instructor/evaluator Crew Remain in simulator for potential questions from evaluator.

c.

End the scenario by placing the simulator in FREEZE.

Crew No discussion of scenario or erasing of procedure marking is allowed.

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SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial /

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 AP01H SAFETY/RELIEF VALVE (RV2-71-H) FAILS OPEN (SRV)

(DELETES IN 1 SECOND) 23 ACTIVE INACTIVE AP03H Auto Blowdown Relief Valve Leak (RV-71H) (SRV) 23 100 0

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

(Deletes in 1 Second) 13 100 0

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)

(DELETES IN 1 SECOND) 15 ACTIVE INACTIVE 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

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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 NIJAPRM (1) < 90 APRM 1 < 90%

13 ZD_HS4C(8)

SRV H to Close 23

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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 PROPS 1st 2nd 1st 2nd 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

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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 PROCEDURES 1st 2nd 1st 2nd 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

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Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Yes No

11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No 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.

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Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial conditions agreed with the reference plant with respect to reactor status, plant configuration, and system operation.

Yes No

2. The simulator operated in real time during conduct of validation.

Yes No

3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes No

4. The simulator permitted use of the reference plants procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes No

5. The simulator did not fail to cause or unexpectedly cause any first principle alarm or primary automatic action.

Yes No

6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plants expected response.

Yes No

7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plants response to the initiating cause.

Yes No

8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes No

10. Simulator fidelity has been demonstrated to be adequate for this scenario.

Yes No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

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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

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 2 Op-Test No.: 2020-301 Examiners: ____________________________ Operators:

Initial Conditions: 40% Power with a Startup in progress 12 Service Water Pump is OOS for motor replacement Two non-adjacent control rods declared slow Turnover: Raise power to 44% with Recirc Pumps and Start the second Condensate Pump.

Critical Tasks:

CT-45: During failure to scram conditions with reactor power above 4.0%, terminated and prevent injection from all sources except SBLC, RCIC and CRD until RPV level lowers to at least -33.

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

Event No.

Malf No.

Event Type*

Event Description 1A N/A C - OATC NP2 Upon commencing the power ascension, a 12 Recirc Pump Scoop Tube LOCK will occur requiring the OATC to reset the scoop tube.

1B R - OATC NP2 OATC will continue and complete power ascension to 44%

using Recirculation pumps IAW 2167 (Plant Startup).

2 N/A N - BOP BOP will start the second condensate pump when power reaches 44% IAW the Ops Manual.

3 C-03-A21 01M06-01 C - BOP TS - CRS The 11 Core Spray inboard will develop a leak that cannot be corrected. The BOP will take action to isolate the 11 Core Spray System. The CRS will evaluate Tech Specs.

4 RC02 C - BOP TS - CRS RCIC will inadvertently start requiring the BOP to shutdown the system. The CRS will evaluate Tech Specs.

5 RW01 C - OATC The RWM will experience an internal fault. The OATC will bypass the RWM.

6 CW02A/B NP2 Both circulating water pumps will trip and condenser vacuum will degrade. The OATC will be required to scram the reactor.

7 PP02 CH18 M - Crew CT-45 CT-47 NP2 Following the scram, an electrical ATWS will occur. The CRS will direct actions via C.5-2007. The BOP will terminate and prevent injection from Condensate and Feed and HPCI. The OATC will use Part A of C.5-3101 and will be successful in inserting the control rods.

8 SL01A SL01B Post/C - OATC NP2 The first SBLC pump that the OATC attempts to start will fail.

The second SBLC pump will start and inject normally (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (NP2) Not on Previous 2 NRC Exams: >2 events

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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 (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2020 ILT NRC 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 Objectives:

1.

Demonstrate the ability to predict and/or monitor changes in 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 Resources:

1. Full Scope Simulator

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

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References:

1.

C.1, Startup Procedure

2.

Form 2167, Plant Startup

3.

Form 2300, Reactivity Adjustment

4.

B.06.05-05.D.3, Startup Of 12 Condensate Pump With 11 Condensate Pump Running

5.

3-A-21, Core Spray System Hi Press Vlv Leakage

6.

TS 3.5.1

7.

4-A-14, RCIC Flow Low

8.

C.4-G, Inadvertent ECCS Initiation

9.

TS 3.5.3

10. C.4-B.06.04.A, Decreased Circulating Water Flow

11. C.4-B.06.03.A, Decreasing Condenser Vacuum

12. C.4-F, Rapid Power Reduction

13. C.4-K, Immediate Reactor Shutdown

14. C.4-A, Reactor Scram

15. C.5-1100, RPV Control

16. C.5-1200, Primary Containment Control

17. C.5-2007, Failure To Scram

18. C.5-3301, Defeating RPV Low-Low Level Isolation For MSIV Closure

19. C.5-3101, Alternate Rod Insertion

20. C.5-3205, Terminate And Prevent

21. B.03.05-05.G.1, SBLC Manual Initiation Hard Card

22. B.03.04-05.H1-8, Torus Cooling Hard Cards Commitments: None Evaluation Method:

The following methods are acceptable methods for examinee 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 Experience:

Not Applicable to Evaluation Scenarios

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Related PRA Information:

Initiating Event with Core Damage Frequency:

None Important Components:

None Important Operator Actions with Task Number:

None

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

MT-SRO-200-128 Supervise increase of reactor power to 100%

5-7 MT-SRO-315-160 Supervise response to inadvertent ECCS initiation 5-7 MT-SRO-315-159 Supervise rapid power reduction 5-7 MT-SRO-299-355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 5-7 MT-SRO-315-129 Supervise response to a decreased circulating water flow 5-7 MT-SRO-315-127 Supervise the response to a decreasing condenser vacuum 5-7 MT-SRO-315-159 Supervise rapid power reduction 5-7 MT-SRO-315-164 Supervise immediate reactor shutdown 5-7 MT-SRO-315-101 Supervise response to a reactor scram 5-7 MT-SRO-304-244 Implement the response during a high power ATWS with heat addition to torus requiring entry into level power control with RPV water level controlled below -33 and RPV blowdown not required.

5-7 RO Tasks:

MT-CRO-200-128 Increase Reactor Power to 100%

1-4 MT-CRO-256-113 Startup 11(12) Condensate Pump with Other 11(12) Pump Running 1-4 MT-CRO-200-204 Perform the procedure for an inadvertent ECCS initiation 1-4 MT-CRO-209-108 Isolate a Core Spray Loop 11(12) 1-4 MT-CRO-299-355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 5

MT-CRO-200-174 Perform the procedure for Decreased Circulating Water Flow 1-4 MT-CRO-200-172 Perform the procedure for Decreasing Condenser Vacuum 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 MT-CRO-304-129 Perform the actions during a high power ATWS with heat addition to torus requiring entry into level power control with RPV level controlled below -33 and RPV blowdown not required.

1-4

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Scoop Tube Lock

2. Core Spray Valve Leak

3. Inadvertent RCIC Initiation

4. RWM Failure

5. Dual CW Pump Trip

6. Electrical ATWS After EOP Entry:

1. SBLC Pump Failure Abnormal Events:

1. Core Spray Valve Leak

2. Inadvertent ECCS Initiation

3. Dual CW Pump Trip Major Transients:

1. Electrical ATWS Critical Tasks:

1. CT-45: During failure to scram conditions with reactor power above 4.0%,

terminate and prevent injection from all sources except SBLC, RCIC, and CRD until level lowers to at least -33.

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

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SCENARIO OVERVIEW:

INITIAL CONDITIONS: Startup in progress at 41%, 12 SW Pump OOS SEQUENCE OF EVENTS:

Event 1A: #12 Recirc Pump Scoop Tube Lock

Upon commencing power ascension, a spurious scoop tube lock will occur on B Recirc Pump. The OATC will take action to reset the scoop tube.

Event 1B: Raise Power with Recirc

OATC will continue and complete raising reactor power to 44% using Recirculation pumps IAW 2167.

Event 2: Start the 2nd Condensate pump

BOP will start the second condensate pump when power reaches 44% IAW 2167.

Event 3: Core Spray Valve Leak

The 11 Core Spray inboard will develop a leak that cannot be corrected. The BOP will take action to isolate the 11 Core Spray System. The CRS will evaluate Tech Specs.

Event 4: RCIC Inadvertent Initiation

RCIC will inadvertently start requiring the BOP to shutdown the system. The CRS will evaluate Tech Specs.

Event 5: RWM Failure An internal fault will occur with the RWM. The OATC will bypass the RWM.

Event 6: Dual Circulating Water pump trip requiring a Rx Scram

Both circulating water pumps will trip and condenser vacuum will degrade. The OATC will be required to scram the reactor.

Event 7: Electrical ATWS

Following the scram, an electrical ATWS will occur. The CRS will direct actions via C.5-2007. Part A of C.5-3101 will be successful in inserting the control rods.

Event 8: Failure of the first SBLC pump to start

The first SBLC pump that the OATC attempts to start will fail. The second SBLC pump will start and inject normally

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NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

1.

INITIAL CONDITIONS (IC)

a. Mode: 1

b. Present Power Level: 41%

c. XCEL System Condition: Green

d. Plant CDF & LERF: Green

e. Plant Fire LERF: Green

f.

Electrical lineup - 2R.

g. Fuel Pool Status: Green, 152 hours0.00176 days 0.0422 hours 2.513228e-4 weeks 5.7836e-5 months to 200°F

h. Generator Output: ~260 MWe

i.

Staffing: Startup Weekday Dayshift

j.

Planned Shift Activities:

Raise Reactor Power to 44%

Start the 2nd Condensate pump.

k. Steps 1-6 of B.06.05-05 D.3, Startup #12 Condensate Pump with 11 Condensate Pump Running are complete.

l.

The following equipment is OOS:

1) 12 Service Water Pump for motor replacement.

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

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

2.

SIMULATOR SET UP Booth Inst

a. Reset the simulator to IC-282 (PW: bucks2) and place in RUN. Verify the correct malfunctions, remotes, overrides and event triggers are loaded as listed in the Simulator Input Summary page(s).

Booth Inst

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

c. Tag out 12 Service Water Pump as follows:

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

2) Verify its GREEN light is OFF.

d. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) C.1 marked as needed to Part IV. H

3) Form 2300 and Reactivity Maneuvering Steps

4) 2167 Marked up as needed complete through Step 173.

5) B.06.05-05.D.3, Startup of 12 Condensate Pump with 11 Condensate Pump Running marked complete through Step 6.

e. Ensure Cooling Tower fan magnets reflect NO cooling towers are in service.

f.

Verify the status board is updated IAW Section 1

g. Complete the Simulator Setup Checklist

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

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 control boards prior to starting the shift brief.

Crew Performs walk down of control boards and reviews turnover checklists.

4.

SHIFT BRIEF

a.

Role Play as necessary. Turbine Building status:

Crew Conduct and participate in the Shift Brief 1). 4 Condensate Demins are in service.

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

3). 12 SW Pump is OOS 4). Standing by to Start 2nd Condensate Pump.

5). All other systems in TB are normal.

b.

Role Play as necessary. Extra out plant operator.

c.

Role Play as necessary. Rx Building status:

1) All systems are normal for S/U.

CRS Crew assumes the duty.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1B 5.

RAISE REACTOR POWER TO 44%

Booth

a.

Provide the following as needed:

1) Nuclear Engineer Reactivity Maneuvering Steps with 2300, Reactivity Adjustment

2) 2167, Plant Startup marked as needed through step 174.

CRS directs the OATC to raise Recirc speed to achieve 44% reactor power IAW 2300 Reactivity Maneuvering Steps and Form 2167, Plant Startup Step 174.

OATC Raises Recirc Speed to raise power Maintains Flow parameters approximately equal If APRM gain adjustments are requested, open remote NI-18 and SET until gains are +/-2%.

Monitors the following parameters:

Pump Speed

Scoop Tube Positions

APRMs & Core Thermal Limits Recognizes Spurious Scoop Tube Lock on B Recirc Pump Event 1A 12 RECIRC PUMP SCOOP TUBE LOCK Key Parameter Response: None Key Expected Alarms: 4-C-10 (FLUID DRIVE B SCOOP TUBE LOCK)

Automatic Actions: None Booth

b.

When contacted as the RBO state that you bumped panel Z4-12B taking rounds. When asked about the ASD indication, report the ASD indicates a steady 0.000 and the ASD Run pushbutton green light is ON.

OATC Refers to B.01.04-05.H.2 (RESET OF SCOOP TUBE LOCK)

Calls RBO to verify ASD indication Booth

c.

If contacted as System Engineering and/or maintenance. Report that it appears to be a spurious lock from the RBO bumping it and it is ok to reset the lock.

OATC Resets the scoop tube lock Booth

d.

Once the scoop tube is reset, call CRS as the Operations Manager to continue with the plant startup.

OATC Completes raising power to 44% with Recirc Flow

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2

6.

START THE 2ND CONDENSATE PUMP START THE 2ND CONDENSATE PUMP Booth Inst NOTE: Steps 1-6 have been completed. This has been communicated to the crew as part of the Pre-Scenario Brief. Provide B.06.05-05.D.3, Startup of 12 Condensate Pump with 11 Condensate Pump Running marked complete through Step 6.

CRS IAW Step 175 of 2167, Plant Startup, directs the BOP to continue B.06.05-05.D.3, Startup of 12 Condensate Pump with 11 Condensate Pump Running at Step 7.

Starts 12 Condensate Pump Booth Inst

a.

Respond as TBO standing by for pump start.

Directs the TBO to SLOWLY open FW-7-2 Cond Pump Disch.

b.

When directed to open FW-7-2. Wait 1 minute and Insert TRIGGER 1 and ensure FW02 activates.

Raises FC-1095 setpoint to 8500 gpm.

Directs TBO to complete steps 10-15 and inform the control room when complete.

Booth Inst

c.

When directed to complete steps 10-15 of B.06.05-05.D.3. Wait 2 minutes and inform the control room that 10-15 are complete.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3

7.

CORE SPRAY VALVE LEAKAGE CORE SPRAY VALVE LEAKAGE Booth Inst

a.

When directed by the Lead Evaluator, insert Trigger 3.

b.

Key Parameter Response: PI-14-48A pressure rises to ~460 psig Key Expected Alarms: 3-A-21, Core Spray System Hi Press Vlv Leakage Automatic Actions: None BOP Enters C.6-03-A-21, Core Spray System Hi Steam Press Vlv Leakage Booth Operator

c. When dispatched to vent 11 Core Spray, wait one minute and report CS-25-1, 11 CS Inj Line Vent can not be opened and it feels like the valve stem is broke.

Dispatches RBO to vent 11 Core Spray IAW the B Manual Determines that 11 Core Spray Subsystem must be isolated Closes MO-1751 CRS Evaluates LCO 3.5.1 as NOT MET Enters Conditions B Booth Operator

d.

If contacted as System Engineer or Maintenance, acknowledge report and inform operator you will assemble a troubleshooting team immediately.

Required Actions - Restore in 7 Days

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4

8.

RCIC AUTOMATIC INITIATION RCIC AUTOMATIC INITIATION Booth Inst

a. When directed by the lead evaluator, insert Trigger 4 and verify RC02 activates.

Key Parameter Response: Rising turbine speed and flow Key Expected Alarms: 4-A-14, RCIC Flow Low Automatic Actions: None BOP Enters C.4-G, Inadvertent ECCS Initiation Booth Inst Determines initiation is spurious based on RPV level.

Depresses the RCIC Trip pushbutton Verifies HO-7 closes and RCIC shuts down Acknowledge any investigation / notification requests to the RBO, Engineering, Maintenance and Plant Management.

Initiates investigation CRS Evaluates TSs and determines LCO 3.5.3.A is NOT met A1 - Verify HPCI operable Immediately A2 - Restore RCIC within 14 days

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

9.

RWM FAILURE RWM FAILURE Booth

a. When directed by the lead evaluator, insert Trigger 6 and verify RW01 activates.

Key Parameter Response: None Key Expected Alarms: ARP 5-A-35 RWM ROD BLOCK OATC Enters ARP 5-A-35 RWM ROD BLOCK Automatic Actions: None Verifies RWM mode switch in OPERATE Verifies RWM SELF TEST indicates OK Booth

b. Acknowledge any investigation / notification requests to the RBO, Engineering, Maintenance and Plant Management.

o Identifies that a fault has occurred Note: This TS call is NOT evaluated as reactor power is >

10%.

With power above LPSP informs CRS to evaluate TS 3.3.2.1.

Evaluator Note: Once the RWM is bypassed you may proceed to the next event.

Bypasses the RWM

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6

10. DUAL CIRCULATING WATER PUMP TRIP REQUIRING REACTOR SCRAM DUAL CIRCULATING WATER PUMP TRIP REQUIRING REACTOR SCRAM Booth Inst

a.

When directed by the Lead Evaluator, insert TRIGGER 5 and verify CW02A, and CW02B activate. This will trip 11 CW pump immediately and trip 12 CW after a 1 minute delay.

Key Parameter Response: Trip of both CW pumps and Degrading Vacuum.

BOP Recognizes 11 Circulating Water Pump has tripped.

Key Expected Alarms: 6-C-9, CIRC WTR PP P-100A TRIP, 6-C-10, CIRC WTR PP P-100B Trip, 6-C-14, Circ WTR PP P-100A Overload, 6-C-15, Circ WTR PP P-100B Overload Enters C.4-B.06.04.A, Decreased Circulating Water Flow Automatic Actions: None Enters C.4-B.06.03.A, Decreasing Condenser Vacuum Places 11 CW Pump handswitch in SHUTDOWN and verifies that valves automatically reposition.

Recognizes that 11 CW pump tripped on OVERLOAD and does not attempt to restart.

OATC Attempts to reduce power using C.4-F to stabilize vacuum.

NOTE: Condenser vacuum will degrade rapidly following the trip of the second Circ Water pump. It is not expected for the crew to beat the automatic scram.

BOP Recognizes 12 Circulating Water Pump has tripped, recommends Reactor Scram CRS Directs a Reactor Scram IAW C.4-K, Immediate Reactor Shutdown.

OATC Inserts a MANUAL SCRAM IAW C.4-K.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7

11. HIGH POWER ELECTRICAL ATWS HIGH POWER ELECTRICAL ATWS Booth Inst Key Parameter Response: No Control Rod Movement, Reactor Power >4% after Mode Switch placed in S/D.

OATC Takes C.4-A, Part A actions:

Key Expected Alarms: 5-B-3, Reactor Neutron Monitor Scram Trip

Places Mode Switch to S/D Automatic Actions: None

Verifies control rod position

Verifies SDV Vent and Drain valves close.

Gives Failure to Scram report CRS

Enters EOP C.5-1100, RPV Control, transitions to C.5-2007, Failure to Scram CT-45 During failure to scram conditions with reactor power

>4%, terminate and prevent injection from all sources except SBLC, RCIC and CRD until level lowers to at least -33.

Inhibits ADS Terminates and Prevents Feedwater/Condensate &

HPCI per C.5-3205 and intentionally lowers Reactor Level to <-33.

Prevents Core Spray & LPCI per C.5-3205 Lowers RPV water level until one of the following conditions are met:

o Reactor Level reaches -126 inches o DW pressure <1.84 psig AND all SRVs remain closed.

o Reactor Power <4%

Maintains Reactor water level between -149 and the determined level during Terminate and Prevent using Condensate & Feedwater.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 8

11. SBLC PUMP FAILS TO START SBLC PUMP FAILS TO START Key Parameter Response: The first SBLC Pump will not start.

CRS Directs initiation of SBLC prior to Torus temperature exceeding 110° F Key Expected Alarms: None OATC Attempts to initiate the first SBLC pump. Reports failure of this pump to start and initiates the second pump.

Automatic Actions: None Booth Inst Ensure TRIGGER 7 (#11 SBLC pump) or TRIGGER 17

(#12 SBLC pump) activates when the first SBLC pump is started. This will delete the SBLC pump trip for the alternate SBLC pump to allow start of the 2nd pump.

CRS Directs OATC to perform C.5-3101 CT-47 During Failure to Scram conditions with a critical reactor, inject SBLC or insert control rods using one or more methods contained within C.5-3101 to achieve reactor shutdown under all conditions.

OATC Performs C.5-3101:

Reduces Recirc flow to minimum

Trips Recirc Pumps

Initiates ATWS

Informs CRS ARI was unsuccessful

Refers to Table 1 of C.5-3101 OATC De-Energizes RPS per C.5-3101, Part A by placing all RPS sub channel test switches to TRIP. Observes that all SCRAM BUS lights de-energize and all rods are in:

Informs CRS that all rods have been inserted CRS Once Control Rods are inserted, terminates SBLC injection (if required), transitions back to C.5-1100 and directs the following actions:

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

Maintains RPV level 9-48 inches utilizing Condensate and Feedwater without exceeding Reactor cooldown limits.

CRS If not performed earlier, enters C.5-1200, Primary Containment Control based on Torus temperature >90°F and directs the following:

Starts RHR in Torus Cooling IAW Hard Card

12. SCENARIO TERMINATION SCENARIO TERMINATION Floor Inst

a.

The scenario may be terminated when All Rods are in and Reactor Water Level is being controlled in band.

b.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew Remain in simulator for potential questions from evaluator.

c.

End the scenario by placing the simulator in FREEZE.

Crew No discussion of scenario or erasing of procedure marking is allowed.

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SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial /

Value MALFUNCTIONS (Allow Tracking Off)

C-03-A21 CORE SPRAY SYSTEM 1 HI PRESS VLV LEAKAGE 3

CRYWOLF NORMAL RC02 RCIC AUTO INITIATION 4

ACTIVE INACTIVE CW02A CIRC WATER PUMP #11 TRIP (OVER LOAD) 5 ACTIVE INACTIVE CW02B CIRC WATER PUMP #12 TRIP (OVER LOAD) 5 00:01:00 ACTIVE INACTIVE PP02 ELECTRICAL ATWS 50 ACTIVE INACTIVE SL01A SBLC PUMP #11 TRIP 50 ACTIVE INACTIVE SL01B SBLC PUMP #12 TRIP 50 ACTIVE INACTIVE SL01A SBLC PUMP #11 TRIP (DELETES IN 1 SECOND) 7 ACTIVE INACTIVE SL01B SBLC PUMP #12 TRIP (DELETES IN 1 SECOND) 17 ACTIVE INACTIVE CH18 ATWS FAILURE - ARI VALVES FAIL TO ENERGIZE 50 ACTIVE INACTIVE RW01 RWM EQUIPMENT FAILURE 6

ACTIVE INACTIVE REMOTES FW02 FW-7-2 CONDENSATE PUMP DISCHARGE VLV 2

00:00:30 100 2

OVERRIDES 04-A1DS108-02 12 SWP - GREEN LAMP 50 OFF ON 01-M06-01 PI-14-48A CS PUMP PRESS 3

93 7.36967 02-S35-01 12 RX RECIRC SCOOP TUBE LOCK (DELETES IN 1 SECOND) 1 00:00:03 TRUE FALSE

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Event Trigger Definitions:

Code Description Event Trigger ZD_MAAUT(2) 12 RECIRC PUMP SPEED ADJUST TO RAISE 1

ZD_SLSS2 Deletes SBLC 11 TRIP WHEN IN SYS 2 7

ZD_SLSS1 Deletes SBLC 12 TRIP WHEN IN SYS1 17

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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 PROPS 1st 2nd 1st 2nd Yellow Caution Card On 12 SW Pump Yellow Paper Tablets For Examinees NRC Scenario 2 Pre-Brief 3139 Turnover Sheet 3140 Turnover Sheet Reactivity Maneuvering Steps

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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 PROCEDURES 1st 2nd 1st 2nd C.1, Startup Procedure Form 2167, Plant Startup Form 2300, Reactivity Adjustment B.06.05-05.D.3, Startup Of 12 Condensate Pump With 11 Condensate Pump Running 3-A-21, Core Spray System Hi Press Vlv Leakage TS 3.5.1 4-A-14, RCIC Flow Low C.4-G, Inadvertent ECCS Initiation TS 3.5.3 C.4-B.06.04.A, Decreased Circulating Water Flow C.4-B.06.03.A, Decreasing Condenser Vacuum C.4-F, Rapid Power Reduction C.4-K, Immediate Reactor Shutdown C.4-A, Reactor Scram C.5-1100, RPV Control C.5-1200, Primary Containment Control C.5-2007, Failure To Scram C.5-3301, Defeating RPV Low-Low Level Isolation For MSIV Closure C.5-3101, Alternate Rod Insertion C.5-3205, Terminate And Prevent B.03.05-05.G.1, SBLC Manual Initiation Hard Card B.03.04-05.H1-8, Torus Cooling Hard Cards

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Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Yes No

11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No 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.

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Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial conditions agreed with the reference plant with respect to reactor status, plant configuration, and system operation.

Yes No

2. The simulator operated in real time during conduct of validation.

Yes No

3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes No

4. The simulator permitted use of the reference plants procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes No

5. The simulator did not fail to cause or unexpectedly cause any first principle alarm or primary automatic action.

Yes No

6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plants expected response.

Yes No

7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plants response to the initiating cause.

Yes No

8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes No

10. Simulator fidelity has been demonstrated to be adequate for this scenario.

Yes No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

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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 Brad Casperson NLPE&RO / RO BOP Cory Broich NPE&RO / RO OATC

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 3 Op-Test No.: 2020-301 Examiners: ____________________________ Operators:

Initial Conditions: 90% Power 1AR XFMR is OOS for an oil leak OPRMs are Inoperable for PMT Turnover: Place the Mechanical Pressure Regulator (MPR) in service.

Critical Tasks:

CT-2: If more than one control rod is drifting then insert a manual reactor scram.

CT-16: Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate (>100°/hr) or a loss of adequate core cooling (<-126).

CT-22: When RPV water level can NOT be maintained >-149, Emergency Depressurize the reactor.

Event No.

Malf No.

Event Type*

Event Description 1

N/A N - BOP NP2 The BOP operator will place MPR in service and secure the EPR IAW the Operations Manual.

2 RR05A C - BOP TS - CRS NP2 11 Recirc pump will trip. The BOP will take actions IAW the abnormal procedure. The CRS will evaluate Tech Specs for single loop operations.

3A 03-S72-01 03-DS107-02 C - OATC When the OATC attempts to insert control rods to exit the analyzed region of the P-F Map, the normal rod insertion switch will fail requiring the OATC to insert rod using the Emergency Rod-In method.

3B R - OATC The OATC will continue and complete the power reduction to approximately 50%

4 C-08-B01 ED03 C - BOP TS - CRS NP2 The 2R trouble alarm will annunciate. Operators will report that there is a severe oil leak on 2R transformer. The BOP will transfer to 1R via the emergency method IAW with the Operations B Manual. The CRS will evaluate Tech Specs for Off-Site sources.

5 CH06-080 CH06-091 C - OATC CT-2 Rods 46-35 and 50-31 will begin to drift into the core. The OATC will Scram the reactor IAW the Control Rod Drift abnormal procedure.

6 HP09A RR01A FW16A/B M - Crew CT-16 CT-22 Following the scram a LOCA will occur. HPCI and RCIC will fail to auto start. When HPCI is started, an Aux Oil Pump lockout will occur rendering HPCI unavailable. RCIC can be manually started will not keep up with the leak. The crew will perform an emergency depressurization on low RPV water level.

7 CS06B Post 12 Core Spray pump will fail to auto start from the ECCS signals.

The OATC or BOP will manually start the pump so its available for low pressure injection (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (NP2) - Not on previous 2 NRC Exams: > 2 events

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-55E SEG TITLE:

2020 ILT NRC SCENARIO 3 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2020 ILT NRC 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 Objectives:

1.

Demonstrate the ability to predict and/or monitor changes in 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 Resources:

1. Full Scope Simulator

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

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References:

1.

B.05.09.-05.E.2, Swapping Pressure Regulators

2.

C.4-B.01.04A, Trip of One Recirc Pump

3.

4-C-01, Recirc A Lockout

4.

C.4-B.05.01.02.A, Control of Neutron Flux Oscillations

5.

B.01.03-05.H.1, Inoperable Control Rods

6.

B.05.05-05.H.1, RMCS Failure

7.

C.4-F, Rapid Power Reduction

8.

TS 3.4.1

9.

C.6-08-B-01, No.2R XFMR Trouble

10. B.09.06-05.E.1, Transfer of Plant Buses From 2R to 1R -

Emergency Method

11. TS 3.8.1

12. 5-A-27, Rod Drift

13. C.B.01.03.C, Control Rod Drifting

14. C.4-A, Reactor Scram

15. C.5-1100, RPV Control

16. HARD CARD B.02.03-05.D.2, Manual Initiation of RCIC

17. HARD CARD B.03.02-05.D.1, HPCI Manual Initiation

18. C.5-1100, RPV Control

19. C.5-3203, Use of Alternate Injection Systems For RPV Makeup

20. C.5-3204 RPV Makeup With CRD

21. C.5-1200, Primary Containment Control

22. C.5-3502, Containment Sprays

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

24. C.5-2002, Emergency RPV Depressurization

25. B.03.04-05.H, Torus Cooling Hard Cards Commitments: None Evaluation Method:

The following methods are acceptable methods for examinee 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 Experience:

Not Applicable to Evaluation Scenarios

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Related PRA Information:

Initiating Event with Core Damage Frequency:

None Important Components:

None Important Operator Actions with Task Number:

None

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

MT-SRO-315-103 Supervise response to a trip of one recirculation pump 5-7 MT-SRO-299-352 Apply Admin requirements to TS Section 3.4 and Bases to Reactor Coolant System (RCS) 5-7 MT-SRO-315-119 Supervise response to control neutron flux oscillations 5-7 MT-SRO-299-356 Apply administrative requirements for Tech Spec Section 3.8 and Bases to Electrical Power Systems 5-7 MT-SRO-315-167 Direct the Response to a Control Rod Drifting 5-7 MT-SRO-315-101 Supervise response to a reactor scram 5-7 MT-SRO-304-226 Implement the response for a small break LOCA or loss of high pressure injection where RPV level cannot be maintained above TAF and RPV blowdown is required to recover level above TAF.

5-7 RO Tasks:

MT-CRO-249-109 Perform the procedure for swapping pressure regulators 1-4 MT-CRO-200-149 Perform the procedure for one recirculation pump trip 1-4 MT-CRO-299-354 Apply Tech Spec Section 3.4 and Bases to the Reactor Coolant System (RCS) 5 MT-CRO-200-168 Perform the procedure for Control of Neutron Flux Oscillations 1-4 MT-CRO-201-141 Respond to RMCS Failure 1-4 MT-CRO-262-133 Perform the procedure for Transfer of Plant Buses From 2R to 1R using the Emergency Method 1-4 MT-CRO-299-358 Apply Tech Spec Section 3.8 and Bases to Electrical Power Systems 1-4 MT-CRO-200-226 Respond to a drifting Control Rod 1-4 MT-CRO-200-146 Perform the procedure for a Reactor Scram 1-4 MT-CRO-304-139 Perform actions for a small break LOCA or loss of high pressure injection where RPV level cannot be maintained above TAF and RPV blowdown is required to recover level above TAF.

1-4

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 12 Recirculation Pump Trip

2. 2R Transformer Oil Leak

3. Normal Control Rod insertion failure

4. Multiple Control Rods Drifting After EOP Entry:

1. Core Spray Pump fails to Auto Start Abnormal Events:

1. Recirc Pump Trip

2. Manual Transfer to 1R Transformer

3. Drifting Control Rods Major Transients:

1. LOCA with loss of High Pressure Feed Critical Tasks:

1. CT-2: If more than one control rod is drifting then insert a manual reactor scram.

2. CT-16: Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate (>100°/hr) or a loss of adequate core cooling (<-126).

3. CT-22: When RPV water level can NOT be maintained >-149, Emergency Depressurize the reactor.

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SCENARIO OVERVIEW:

INITIAL CONDITIONS: 90% power with 1AR and OPRMs OOS SEQUENCE OF EVENTS:

Event 1: Place the MPR in Service

The BOP operator will place MPR in service and secure the EPR IAW the Operations Manual.

Event 2: 12 Recirc Pump Trip

11 Recirc pump will trip. The BOP and OATC will take actions IAW the abnormal procedure. The CRS will evaluate Tech Specs for single loop operations.

Event 3A: Normal Control Rod Insertion Failure When the OATC attempts to insert control rods to exit the unanalyzed region of the P-F Map, the normal rod insertion switch will fail requiring the OATC to insert rod using the Emergency Rod-In method.

Event 3B: Rapid Power Reduction With Control Rods

The OATC will continue and complete the power reduction to approximately 50%.

Event 4: Emergency Manual Transfer to 1R

The 2R trouble alarm will annunciate. Operators will report that there is a severe oil leak on 2R transformer. The BOP will transfer to 1R via the emergency method IAW with the Operations B Manual. The CRS will evaluate Tech Specs for Off-Site sources.

Event 5: Multiple Control Rods Drifting Requiring Reactor Scram

Rods 46-35 and 50-31 will begin to drift into the core. The OATC will Scram the reactor IAW the Control Rod Drift abnormal procedure and enter C.4-A.

Event 6: LOCA with a loss of High Pressure Feed

Following the scram a LOCA will occur. HPCI and RCIC will fail to auto start. When HPCI is started, an Aux Oil Pump lockout will occur rendering HPCI unavailable.

RCIC can be manually started will not keep up with the leak. The crew will perform an emergency depressurization on low RPV water level.

Event 7: 12 Core Spray Pump Fails to Auto Start

The 12 Core Spray pump will fail to auto start from the ECCS signals. The OATC or BOP will manually start the pump so its available for low pressure injection.

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NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

1.

INITIAL CONDITIONS (IC)

a. Mode: 1

b. Present Power Level: 90%

c. XCEL System Condition: Green

d. Plant CDF & LERF: Green

e. Plant Fire LERF: Green

f.

Electrical lineup - 2R.

g. Fuel Pool Status: Green, 152 hours0.00176 days 0.0422 hours 2.513228e-4 weeks 5.7836e-5 months to 200°F

h. Generator Output: ~611 MWe

i.

Staffing: Normal Weekday Dayshift

j.

Planned Shift Activities: Place the MPR in service for EPR maintenance.

k. The following equipment is OOS:

1) 1AR Transformer for an oil leak a) LCO and TLCO 3.8.1 remain MET

2) OPRM Inoperable for Post-Maintenance Testing a) LCO 3.3.1.1 Conditions A, B, C and D NOT met, I.1 complete, I.2 required with 120 Days.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

2.

SIMULATOR SET UP Booth Inst

a. Reset the simulator to IC-283 (PW: bucks3) and 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.

c. Tag out 1AR as follows:

Booth Inst

1) Verify 1AR to 15 & 16 Bus supply breakers are in PTL.

2) Hang a CAUTION (yellow) card on 1AR to 15 &

16 Bus supply breakers.

3) Verify GREEN lights are OFF for 1AR to 15 &

16 Bus supply breakers.

d. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

e. Ensure Cooling tower magnets reflect NO cooling towers in service.

f.

Verify the status board is updated IAW Section 1

g. Complete the Simulator Setup Checklist

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

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 control boards prior to starting the shift brief.

Crew Performs walk down of control boards and reviews turnover checklists.

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

3). All other systems in TB are normal.

b.

Role Play as necessary. Extra out plant operator.

1) 1AR tagged out for an Oil Leak.

c.

Role Play as necessary. Rx Building status:

1) All systems in the Rx Bldg are normal.

CRS Crew assumes the duty.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1

5.

PLACE THE MPR IN SERVICE PLACE THE MPR IN SERVICE BOP Performs B.05.09.-05.E.2, Swapping Pressure Regulators Place MPR to LOWER until Mech Press Regulator Controlling, Yes light (red), is ON.

Place 90/CS, Elec Press Regulator, to RAISE until Elec Press Regulator Controlling, No light (green),

is ON.

Verify MPR setpoint adjusted to maintain Reactor Dome Pressure vs. Steam flow IAW C.2-06.

Using 90/CS, ADJUST EPR setpoint 10%-12%

lower than Turb MPR Relay Piston Position.

Event 2

6.

RECIRC PUMP TRIP RECIRC PUMP TRIP Booth Inst

a.

When directed by the Lead Evaluator, insert TRIGGER 2 and verify that RR05B goes active.

OATC Acknowledges the alarm and informs the CRS that 12 Recirc Pump has Tripped Key Parameter Response: Recirc Speed Drops, Reactor Power Drops.

OATC Enters C.4-B.01.04A, Trip Of One Recirc Pump &

C.4-B.05.01.02.A, Control Of Neutron Flux Oscillations Key Expected Alarms: 4-C-02, Recirc B Lockout Adjusts Master Reactor Level Controller to 30 Automatic Actions: None Closes B RCP discharge valve Opens discharge valve after being closed for 5 minutes.

NOTE: Crew must subtract B JP Flow (FI-2-3-92B) from A JP Flow (FI-2-3-92A) when the B Recirc Pump trips to obtain accurate core flow. SPDS and the Core Flow Recorder will be inaccurate since it CANNOT distinguish reverse flow.

Evaluates Power to Flow map. Commences Control Rod insertions IAW C.4-F, Rapid Power Reduction to obtain margin to unanalyzed region and Region 2.

BOP Makes C.4 page announcement, and informs System Engineer.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Booth Inst

b.

If dispatched as Outplant Operator to report status of B Recirc MG-SET, wait 1 minute and REPORT nothing abnormal can be identified.

CRS Evaluates LCO 3.4.1 as NOT MET, Condition A applies.

Required Action A.1: Restore flow or place the plant in Single Loop Operation within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Booth Inst

c.

Acknowledge any investigation / notification requests to Engineering, Maintenance and Plant Management.

Event 3A 7.

RMCS NORMAL ROD INSERTION FAILURE RMCS NORMAL ROD INSERTION FAILURE Booth Inst While the OATC is inserting the control rods, the Rod Insert Switch will fail to respond on the second rod. Verify Event Trigger 3 activates 2 seconds after the second rod begins to insert.

Key Parameter Response: The green rod in light will extinguish and the control rod will stop inserting and settle at position 04.

OATC B.01.03-05.H.1, Inoperable Control Rods Step 2. If the Control Rod is NOT at position 00, then attempt to insert the control rod using the following:

Key Expected Alarms: None Place Rod Out Notch Override Switch in EMERG ROD IN.

Auto Actions: None B.05.05-05.H.1, RMCS Failure Step 3. If RMCS failure detected and normal rod insertion capability is lost then place Rod Out Notch Override Switch in EMERG ROD IN.

Event 3B RAPID POWER REDUCTION WITH CONTROL RODS NOTE: The crew is also allowed to use EMERG ROD IN based on entry into C.4-F, Rapid Power Reduction.

These procedures may NOT be used.

OATC Continues power reduction using Emergency Rod In to the directed power band.

NOTE: Based on validation, the crew should establish a power band near ~50%.

Restores RPV water level to the normal band after the power reduction.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4

8.

2R XFMR TROUBLE 2R XFMR TROUBLE Booth Operator

a.

When directed by the Lead Evaluator, Insert TRIGGER 4 and verify C-08B-1 annunciates.

Key Parameter Response: None Key Expected Alarms: 8-B-1, No. 2R XFMR Trouble and Low Oil Level alarm on the PCS.

BOP Implements C.6-08-B-01, No.2R XFMR Trouble Initiates Investigation of 2R Trouble Auto Actions: None Booth Operator

b.

When directed to investigate 2R the XFMR, wait 1 minute and that there is a large oil leak and loud humming coming from 2R the XFMR.

CLEAR all personnel from area near 2R Initiates Manual Transfer to 1R IAW B.09.06-05 Xfer BUS 13 to 1R (Close 152-302/ Trip 152-301)

Booth Operator

c.

Acknowledge any investigation / notification requests to Engineering, Maintenance and Plant Management Xfer BUS 14 to 1R (Close 152-402/ Trip 152-401)

Xfer BUS 11 to 1R (Close 152-407/ Trip 152-101)

Xfer BUS 12 to 1R (Close 152-207/ Trip 152-201)

OPENs 16/C-31, Knife Switch 16 Booth Operator

d.

Acknowledge the order to trip 3N4. This would take 10-15 Minutes. Toggling the 3N4 Remote has no effect on the scenario therefore is NOT required.

DISPATCHs an Operator to PLACE 3N4/CS, 3N4 34.5 OCB Control Switch to TRIP.

NOTE: Intention is to have the Crew transfer the busses; once the Tech Spec call is complete the scenario can be moved forward to the next event.

CRS Evaluates Tech Spec 3.8.1 as NOT MET:

A.1: Perform SR 3.8.1.1 on 1R in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

A.2: Not Applicable A.3: Restore required offsite circuit to OPERABLE Status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

9.

MULTIPLE CONTROL RODS DRIFTING REQUIRING REACTOR SCRAM MULTIPLE CONTROL RODS DRIFTING REQUIRING REACTOR SCRAM Booth Inst

a. When directed by the lead evaluator, INSERT MANUAL TRIGGER 5 and verify CH06_080 and CH06_091 go active.

Key Parameter Response: Rod 46-35 and 50-31 start to drift into the core.

Key Expected Alarms: 5-A-27, Rod Drift Auto Actions: None OATC Informs the CRS of control rods drifting and SCRAMS the reactor IAW C.4-B.01.03.C Immediate Actions.

CT-2 If more than one control rod is drifting then insert a manual reactor scram prior to both control rods drifting fully into the core.

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

Depress the scram pushbuttons Place Mode Switch in SHUTDOWN.

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

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 Pump has 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 performed depending on when the LOCA is recognized.

Verify the Generator Field Breaker Open.

Start the Turbine Aux Oil Pump.

Verify Turbine Exhaust Hood Sprays in service.

Verify Turbine Stop Valves are closed Start Turbine Bearing Lift Pumps Verify Main Steam Pressure Control & Bypass valves are controlling Reactor Pressure.

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 CRS Directs performance of C.5-1100, RPV Control

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6

10. LOCA WITH LOSS OF HIGH PRESSURE FEED LOCA WITH LOSS OF HIGH PRESSURE FEED BOOTH

a.

When the Mode Switch is placed in Shutdown, verify that Event Trigger 6 activates. This will initiate the Feed Pump trips, HPCI/RCIC auto start failures and LOCA.

b.

If directed to investigate, report that there is no apparent cause for the loss of the Feed Pumps.

OATC Notifies CRS that Feed Pumps have tripped on overload and are not available.

CRS Directs RPV level control using RCIC/HPCI NOTE: RCIC will be allowed to inject, however, it needs to be started manually and it will not keep up with the leak.

OATC Manually starts RCIC using Hard Card B.02.03-05.D.2, Manual Initiation of RCIC NOTE: HPCI will fail to auto start. When a manual start is attempted, verify that Event Trigger 16 activates. This will cause a lockout of the HPCI Aux Oil Pump.

OATC/

BOP Manually starts HPCI using Hard Card B.03.02-05.D.1, HPCI Manual Initiation CT-16:

Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate (>100°/hr) or a loss of adequate core cooling (<-126).

Recognizes that the HPCI Aux Oil Pump has failed.

Inhibits ADS Maximizes CRD using C.5-3204 RPV Makeup With CRD BOOTH

c.

If directed to close CRD-14, open remote CH22 and change the status to CLOSE.

Starts 12 CRD Pump Directs RBO to close CRD-14 OATC/

BOP Starts SBLC injection IAW C.5-3203, Use of Alternate Injection System for RPV Makeup Verifies injection OATC/

BOP Monitors and reports RPV level and Pressure, both values and trends.

o Reports Drywell pressure rising o Reports EOP entry conditions.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6 Cont

11. LOCA IN PRIMARY CONTAINMENT (DRYWELL)

LOCA IN PRIMARY CONTAINMENT (DRYWELL)

NOTE: With the crew prioritizing RPV water level actions, Containment Spray/Cooling actions may be minimized or not taken at all.

CRS Directs performance of C.5-1200 (PC Control)

BOP /

OATC Places Torus Sprays in service IAW C.5-3502, Containment Sprays:

Verifies RHR Pumps running 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.

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

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 BOP /

OATC 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

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Initiates Drywell Spray IAW C.5-3502, Containment Sprays:

o Open Drywell Spray Outboard MO-2021 o Open Drywell Spray Inboard MO-2023 o Close Torus Cooling MO-2009 Event 7

12. FAILURE OF 12 CORE SPRAY PUMP TO AUTO START FAILURE OF 12 CORE SPRAY PUMP TO AUTO START CRS Verifies that Condensate, B Core Spray, B LPCI are realigned for injection.

OATC Recognizes that B Core Spray Pump failed to start OATC Manually starts B Core Spray Pump When RPV level is < -126 inches and prior to -149 inches, directs performance of C.5-2002, Emergency RPV Depressurization Event 6 (CONT)

13. ALTERNATE RPV LEVEL CONTROL /

EMERGENCY BLOWDOWN ALTERNATE RPV LEVEL CONTROL / EMERGENCY BLOWDOWN CRS SS304.226 CR304.139 Verifies Torus level > -5.9 ft.

CT-22 When RPV water level can NOT be maintained

>-149, Emergency Depressurize the reactor.

Directs opening of all 3 ADS SRVs.

BOP /

OATC Monitor and report RPV level values and trends Controls RPV injection from RHR.

Opens Knife Switch to Bypass LPCI 5 Minute Timer using C.5-3208

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Throttles MO-2013.

May divert LPCI flow using B.03.04-05.H, Torus Cooling Hard Cards Controls RPV injection from Core Spray.

Throttles MO-1754 Controls RPV injection from the Condensate system.

14. SCENARIO TERMINATION SCENARIO TERMINATION Floor Inst

a.

The scenario may be terminated when Reactor Water level is being recovered and controlled with Low Pressure injection systems.

b.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew Remain in simulator for potential questions from evaluator.

c.

End the scenario by placing the simulator in FREEZE.

Crew No discussion of scenario or erasing of procedure marking is allowed.

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SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial /

Value MALFUNCTIONS (Allow Tracking Off)

RR05A RX RECIRC PUMP #11 LOCKOUT 2

ACTIVE INACTIVE C-08-B01 NO 2R XFMR TROUBLE 4

CRY_WOLF NORMAL ED03 2R XFMR LOW OIL LEVEL MAIN TANK 4

NORMAL NORMAL CH06-080 CONTROL ROD (50-31) SCRAM OUTLET VALVE LEAKING (DRIFT IN) 5 00:00:10 60 0

CH06-091 CONTROL ROD (46-35) SCRAM OUTLET VALVE LEAKING (DRIFT IN) 5 60 0

HP02 HPCI AUTO-START FAILURE 6

00:02:00 ACTIVE INACTIVE RC01 RCIC AUTO-START FAILURE 6

00:02:00 ACTIVE INACTIVE HP09A HPCI AUX OIL PUMP OVERLOAD 16 ACTIVE INACTIVE RR01A SMALL LINE BREAK ON RX RECIRC #11 6

00:02:00 36 0

FW16A REACTOR FEEDPUMP #11 TRIP 6

00:02:15 ACTIVE INACTIVE C-06-A12 RCT FEEDPUMP P-2A OVERLOAD 6

00:02:15 CRYWOLF NORMAL FW16B REACTOR FEEDPUMP #12 TRIP 6

00:02:30 ACTIVE INACTIVE C-06-A12 RCT FEEDPUMP P-2B OVERLOAD 6

00:02:30 CRYWOLF NORMAL CS06B 12 CORE SPRAY PUMP AUTO START FAILURE 50 ACTIVE INACTIVE REMOTES ED08 1AR XFMR PRI SUPPLY BKR 1N2 50 OPEN CLOSE

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OVERRIDES 05-DS016-02 A530P30-03 1AR XFMR to 15 BUS - GREEN LAMP

[ZL_B511G]

50 OFF ON 05-DS022-02 A530P30-37 1AR XFMR to 15 BUS - GREEN LAMP

[ZL_B610G]

50 OFF ON 03-S72-01 CONTROL ROD IN 3

00:00:02 FALSE FALSE 03-DS107-02 ROD IN - GREEN LAMP 3

00:00:02 OFF OFF Event Trigger Definitions:

Code Description Event Trigger ZD_CRDIN &

ZL_CRPSL(63)

ROD INSERT SWITCH TO IN WITH CONTROL ROD 34-27 SELECTED 3

ZD_S1SHD MODE SWITCH TO SHUTDOWN 6

ZD_H17ST MO-2036 TO OPEN 16

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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 PROPS 1st 2nd 1st 2nd Yellow Caution Card On 1ar To 15 Bus Yellow Caution Card On 1ar To 16 Bus Green Push Pins On Electrical One Line For 1AR OOS Yellow Paper Tablets For Examinees Audit Scenario 3 Pre-Brief Turnover 3139 Turnover 3140

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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 PROCEDURES 1st 2nd 1st 2nd B.05.09.-05.E.2, Swapping Pressure Regulators C.4-B.01.04A, Trip of One Recirc Pump 4-C-01, Recirc A Lockout C.4-B.05.01.02.A, Control Of Neutron Flux Oscillations B.01.03-05.H.1, Inoperable Control Rods B.05.05-05.H.1, RMCS Failure C.4-F, Rapid Power Reduction TS 3.4.1 C.6-08-B-01, No.2R XFMR Trouble B.09.06-05.E.1, Transfer of Plant Buses from 2R to 1R -

Emergency Method TS 3.8.1 5-A-27, Rod Drift C.B.01.03.C, Control Rod Drifting C.4-A, Reactor Scram C.5-1100, RPV Control HARD CARD B.02.03-05.D.2, Manual Initiation of RCIC HARD CARD B.03.02-05.D.1, PCI Manual Initiation C.5-1100, RPV Control C.5-3203, Use of Alternate Injection Systems for RPV Makeup C.5-3204 RPV Makeup With CRD C.5-1200, Primary Containment Control C.5-3502, Containment Sprays C.5-3503, Defeat Drywell Cooler Trips C.5-2002, Emergency RPV Depressurization B.03.04-05.H, Torus Cooling Hard Cards

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Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Yes No

11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No 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.

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Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial conditions agreed with the reference plant with respect to reactor status, plant configuration, and system operation.

Yes No

2. The simulator operated in real time during conduct of validation.

Yes No

3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes No

4. The simulator permitted use of the reference plants procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes No

5. The simulator did not fail to cause or unexpectedly cause any first principle alarm or primary automatic action.

Yes No

6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plants expected response.

Yes No

7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plants response to the initiating cause.

Yes No

8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes No

10. Simulator fidelity has been demonstrated to be adequate for this scenario.

Yes No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

Rev. 0 (08/02/2018)

Page 26 of 26 ILT-SS-55E, 2020 ILT NRC Scenario 3 Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Comments:

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

Validation Personnel Name Job Title / Qualification Validation Position Dave Bernstrom CRS / SRO CRS Cory Broich NPE&RO / RO OATC Brad Casperson NPLE&RO / RO BOP

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