Text

Form 3.3-2 Proposed Operating Test Simulator Scenario Guides
	ML23012A137
Person / Time
Site:	Monticello
Issue date:	09/28/2022
From:	; Nuclear Management Co, Xcel Energy
To:	; NRC/RGN-III/DORS/OB
	Iskierka-Boggs T
Shared Package
ML21188A292	List: L-MT-22-023, 75-Day Exam Package; ML23012A009; ML23012A012; ML23012A134; ML23012A136; ML23012A137; ML23012A139; ML23012A143;
References
	Download: ML23012A137 (1)
	v • d • e

Rev. 1 (3/8/2021)

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-62E SEG TITLE:

2022 ILT NRC SCENARIO 1 REV. #

0 PROGRAM:

INITIAL LICENSE TRAINING FL-ILT COURSE:

NRC SIMULATOR EVALUATION N/A TOTAL TIME: 60-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor (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 2022 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 Required Personal Protective Equipment None

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Training Resources:

1.

Full Scope Simulator

2.

QF104016, Attendance Record or LMS Equivalent

3.

3139, Control Room Shift Turnover Checklist

4.

3140, Shift Supervisors Office Shift Turnover Checklist

References:

1.

Test 0010, Reactor Scram Functional Test

2.

TS 3.3.1.1 RPS Instrumentation

3.

5-B-40, FW Control Valve Locked

4.

C.4-B.05.07.A, Loss Of Reactor Water Level Control

5.

B.05.07-05-G.2, Restoring Feedwater Level Control To Automatic

6.

7-A-20, Offgas Annunciator

7.

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

8.

C.4-G, Inadvertent ECCS Initiation

9.

C-03-A-41, AC Interlock

10. TS LCO 3.5.1

11. 8-A-34, 1-Bus 345 KV Low Freq

12. C.4-F, Rapid Power Reduction

13. C.4-B.06.02.04.A, Stator Cooling Water Failure

14. C.4.K, Immediate Reactor Shutdown

15. C.5-1100, RPV Control

16. C.5-2007, Failure To Scram

17. C.5-3301, Defeat MSIV Low-Low Level Isolation

18. C.5-3205, Prevent Core Spray Injection

19. C.5-3101, Alternate Rod Insertion

20. B.03.05-05.G.1, SBLC Manual Initiation

21. Torus Cooling Hard Cards Commitments: None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2022 ILT NRC Exam Process (NUREG 1021 & FP-T-SAT-72)

FL-ILT, ILT 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-212-101 Supervise the Reactor Manual Scram Functional Test 5-7 MT-SRO-299-351 Apply administrative requirements for Tech Spec Section 3.3 and bases to containment systems.

5 MT-SRO-299-353 Apply administrative requirements for Tech Spec Section 3.5 and bases to containment systems.

5 MT-SRO-315-120 Supervise response to a loss of reactor water level control 5-7 MT-SRO-315-127 Supervise response to decreasing condenser vacuum 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-315.126 Supervise response to a stator cooling water failure 5-7 MT-SRO-315-164 Supervise immediate reactor shutdown 5-7 MT-SRO-304-213 Implement the bases for RPV Control 5-7 MT-SRO-304-201 Implement the response for a failure to 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 level controlled below -33 and RPV blowdown not required.

5-7 MT-SRO-314-111 Supervise defeat of RPV low-low level isolation for MSIV closure 5-7 MT-SRO-314-108 Supervise terminate and prevent 5-7 MT-SRO-314-101 Supervise alternate rod insertion 5-7 RO Tasks:

MT-CRO-212-101 Perform the Reactor Scram Functional Test 1-4 MT-CRO-200-164 Perform the procedure for loss of reactor water level control 1-4 MT-CRO-259-110 Restore feedwater level control to automatic 1-4 MT-CRO-200-172 Perform the procedure for decreasing condenser vacuum 1-4 MT-CRO-200-204 Perform the procedure for an inadvertent ECCS initiation 1-4 MT-CRO-200-203 Perform the procedure for rapid power reduction 1-4 MT-CRO-200-171 Perform the procedure for a stator cooling water failure 1-4 MT-CRO-200-208 Perform the procedure for immediate reactor shutdown 1-4 MT-CRO-212-105 Manually Initiate the ATWS System 1-4 MT-CRO-314-104 Perform actions associated with Failure to Scram 1-4 MT-CRO-314-129 Perform 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 MT-CRO-314-115 Defeat RPV Low-Low Level Isolation for MSIV Closure 1-4 MT-CRO-314-112 Perform actions to Terminate and Prevent injection 1-4 MT-CRO-314-105 Perform actions associated with Alternate Rod Insertion 1-4 MT-CRO-211-106 Manually Initiate Standby Liquid Control System 1-4

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. B RPS Scram Pushbutton failure

2. Main Feed Regulating Valve Lockup

3. SJAE Failure

4. RHR pump inadvertent initiation After EOP Entry:

1. 1st SBLC Pump fails to start Abnormal Events:

1. Loss of Reactor Water Level Control

2. Degrading Condenser Vacuum

3. Inadvertent ECCS Initiation

4. Loss of Stator Water Cooling Major Transients:

1. Hydraulic ATWS

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Critical Tasks:

1. CT-45:

Critical Task Statement: 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 -36.

Safety Significance: To prevent or mitigate the consequences of any large irregular neutron flux oscillations induced by neutronic/thermal-hydraulic instabilities, RPV water level is lowered sufficiently below the elevation of the feedwater sparger nozzles. This places the feedwater spargers in the steam space providing effective heating of the relatively cold feedwater and eliminating the potential for high core inlet subcooling. For conditions that are susceptible to oscillations, the initiation and growth of oscillations is principally dependent upon the subcooling at the core inlet; the greater the subcooling, the more likely oscillations will commence and increase in magnitude.

Applicability: C.5-2007 conditions where power remains above 4.0% following the tripping of both recirc pumps.

Performance Indicator: When an ATWS occurs and reactor power remains above 4.0% then perform RPV level reduction to at least -36. If the ATWS occurs at 100% power with NO Control Rod movement coincident with a Group 1 isolation, then level reduction must commence within 90 seconds following MSIV closure.

Distinguishable Cue: APRMs indicate reactor power above 4.0% with RPV level indicated above -36 on Panel C-05: CRS directs systems to be prevented per C.5-3205.

Performance Feedback: APRMs indicate lowering power as level is lowered to -36.

2. CT-47:

Critical Task Statement: During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained in C.5-3101 to achieve reactor shutdown under all conditions (all rods inserted to at least 02).

Safety Significance: Achieving Rx shutdown is one of the primary goals of C.5-2007.

Applicability: C.5-2007 conditions with a critical reactor where one or more of the methods contained within C.5-3101 would be successful in achieving reactor shutdown.

Performance Indicator: Performance of actions in C.5-3101 is successful in shutting down the Reactor under all conditions without boron.

Distinguishable Cue: Failure of control rods to insert from a reactor scram and direction from the CRS to perform C.5-3101.

Performance Feedback: All rods in condition indicated from the RWM and Full Core Display on Panel C-05.

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SCENARIO OVERVIEW:

Event 1: Perform Reactor Scram Functional Test - 0010

The BOP operator will perform Test 0010. During the performance of Part D, the B RPS manual scram pushbutton will fail to work. The CRS will evaluate TSs for a faulty pushbutton. The BOP will insert a half scram from panel C-17.

Event 2: MFRV A Lockup

The A MFRV will lockup. The OATC will take manual control of the B MFRV and further action to unlock the A MFRV and restore RPV Water Level Control to automatic.

Event 3: SJAE Steam Supply PCV Fails Closed

The A SJAE steam supply PCV will fail closed. The BOP will coordinate with the TB operator and will take manual action to restore steam and reset the air ejector.

Event 4: Rapid Power Reduction for Degrading Main Condenser Vacuum

While the BOP is restoring the SJAE, degrading condenser vacuum will force the OATC to reduce Recirc flow to maintain condenser vacuum.

Event 5: Inadvertent Initiation of 14 RHR pump

The #14 RHR pump will inadvertently start. The BOP will take manual action to secure the pump. The CRS will evaluate Tech Specs for an inoperable RHR Pump coincident with HPCI OOS.

Event 6: 11 Stator Water Cooling Pump trip requiring a manual scram.

With 12 Stator Water Cooling pump OOS, the 11 Stator Water Cooling pump will trip resulting in a complete loss of Stator Water Cooling requiring a manual scram.

Event 7: Hydraulic ATWS (CT x 2)

When the reactor is scrammed, multiple control rods will fail to insert. The crew will take action IAW C.5-2007 (Failure to Scram) to lower power and insert control rods.

Event 8: SBLC Pump start failure

When the OATC initiates SBLC, the first pump will fail to start. The OATC will start the remaining pump.

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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: RUN

b. Present Power Level: 100%

c. XCEL System Condition: Green

d. Plant CDF & LERF: Green

e. Electrical lineup - 2R supplying

f.

Fuel Pool Status: Green, 194 hours0.00225 days 0.0539 hours 3.207672e-4 weeks 7.3817e-5 months to 200°F

g. Generator Output: ~690 MWe

h. Staffing: Weekend Night Shift

i.

Planned Shift Activities: 0010 Rx Scram Functional

j.

The following equipment is OOS:

1) HPCI for Aux Oil Pump replacement - TS 3.5.1 was entered yesterday at 0600 a) Condition I.1 is complete b) Condition I.2 is due in 13 days c)

RCIC, ADS and #13 Battery are protected

2) 12 Stator Water Cooling Pump for motor replacement. 11 Stator Water Cooling Pump is protected.

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

2.

SIMULATOR SET UP Booth

a. Reset the simulator to IC-281 (PW: crappie1) 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. Verify Manual Trigger 50 is inserted for simulator initial conditions and preloaded malfunctions.

c. Tag out 12 Stator Water Cooling Pump as follows:

1) Verify handswitch has been placed in PTL.

2) Hang CAUTION (yellow) card on hand switch.

3) Verify the GREEN light is OFF.

d. Align HPCI as follows:

1) Place Aux Oil Pump in PTL, verify Green light is off and affix caution tag

2) Verify HPCI steam line is depressurized

e. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) Marked up copy of Test 0010 with RPS keys

f.

Verify the status board is updated IAW Section 1 and the current Offgas System Status

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

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). B vessel d/p is highest @ 5.7 psid.

3). 12 SWC Pump is OOS, 11 SWC Pump is protected. All other equipment in TB is normal

b.

Role Play as necessary. Extra out plant operator, Chemistry, RP and Security as requested.

1) Nothing to add.

c.

Role Play as necessary. Rx Building status:

1) HPCI is OOS, RCIC is protected, all other 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.

REACTOR SCRAM FUNCTIONAL TEST REACTOR SCRAM FUNCTIONAL TEST BOP Performs Test 0010, Reactor Scram Functional Test PART A Pushes Reactor Scram A pushbutton Checks Reactor Scram A pushbutton red light ON Checks RPS A Scram Solenoid lights 1, 2, 3 and 4 are OFF Checks 5-B-12 Reactor Manual Scram Channel A is in alarm.

Check RPS029 displays TRIP Resets half scram Verifies pushbutton red light OFF, scram solenoid lights are ON, 5-B-12 and RPS029 are reset.

PART B On C-15, inserts Key 52 and RPS A-1 to trip, returns Key 52 to normal and removes key.

Checks RPS A Scram Solenoid lights 1, 2, 3 and 4 are OFF Checks 5-B-4 Reactor Auto Scram Channel A is in alarm.

Resets half scram Verifies scram solenoid lights are ON and 5-B-4 is reset.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES PART C BOP On C-15, inserts Key 53 and RPS A-2 to trip, returns Key 53 to normal and removes key.

Checks RPS A Scram Solenoid lights 1, 2, 3 and 4 are OFF Checks 5-B-4 Reactor Auto Scram Channel A is in alarm.

Resets half scram Verifies scram solenoid lights are ON and 5-B-4 is reset.

PART D Pushes Reactor Scram B pushbutton Checks Reactor Scram B pushbutton red light ON Booth

a.

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

o Recognizes that the Reactor Scram pushbutton did not insert a half scram and notifies the CRS.

CRS Notifies BOP to stop the test and evaluates TS 3.3.1.1 RPS Instrumentation Function 11 Manual Scram as NOT MET.

Condition A - Place channel/trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Condition C - Restore Function 11 - RPS B trip capability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Booth NOTE: If the crew stalls in taking this action, call in as the SM and direct that a half scram be inserted on RPS B1 or B2 using the C-17 key switches.

BOP Using Key 54 or 55 inserts a B1 or B2 auto scram signal on C-17

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

6.

MFRV A LOCK Booth

a.

When directed by the lead instructor, insert Trigger 2 and verify FW20A actives and deletes.

Key Parameter Response: Red RESET light lit for A MFRV Key Expected Alarm: 5-B-40, FW Control Valve Locked OATC Responds to annunciator and informs CRS Auto Actions: None Enters C.4-B.05.07.A, Loss of Reactor Water Level Control Booth

b.

When contacted as the TBO to inspect for air leakage, wait one minute and report there is no air leakage at the A MFRV.

Places both MFRVs in Manual to maintain level Calls TBO to verify no major air leakage at the valve

c.

A MFRV will unlock on the first attempt Depress and holds reset button for A MFRV ~ 3 seconds

d.

When contacted as Engineering and/or Maintenance wait 2 minutes and report that Panel C-305 (DFLC) in the Cable Spreading Room was bumped by engineers doing walk downs.

Everything appears to be functioning properly.

OATC Restores RPV Water Level Control to automatic using B.05.07-05-G.2, Restoring Feedwater Level Control to Automatic Part A Places Master Level Controller in MANUAL.

Adjusts Master Level Controller such that demand signal matches demand signal of selected MFRV.

Places selected MFRV in AUTO and adjusts Master Level Controller set point into the GREEN band.

Places Master Level Controller to AUTO.

Part C Slowly adjusts remaining MFRV until demand signal for MFRV and Master Controller are matched.

Places remaining MFRV in AUTO.

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

7.

SJAE PRESSURE CONTROL VALVE FAILS CLOSED - AIR IN-LEAKAGE - DEGRADING CONDENSER VACUUM Booth

a. When directed by the lead evaluator, INSERT TRIGGER 3.

Key Parameter Response: 11 SJAE Inlet pressure lowers to 0 psig and Condenser vacuum begins to degrade.

Key Expected Alarms: 7-A-20, Offgas Annunciator BOP Responds to 7-A-20, Offgas Annunciator and notifies the CRS Auto Actions: None Recognizes loss of 11 SJAE Pressure and degrading Main Condenser Vacuum Event 4

8.

RAPID POWER REDUCTION Booth

a. When the OATC lowers Recirc flow, verify Trigger 13 activates to delete MC03 once power is 650 MWe. This removes the air in-leakage.

CRS Directs C.4-F, Rapid Power Reduction OATC Lowers reactor power by lowering recirc flow until condenser vacuum is stabilized (Screen 656)

Event 3 Cont

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

CRS BOP Directs C.4-B.06.03.A, Decreasing Condenser Vacuum Trips HWC by placing HS-4149 on C-252A to OFF Booth

c.

When directed to open the MVP Suction Valves, insert TRIGGER 23, verify MC06 activates and wait one minute to report the valves are open.

Opens MVP suction valves OG-22-1 & OG-22-2 Notices PI-1246 indicates 0 psig and attempts to take manual control NOTE: Manual control will be unsuccessful from the control room.

Directs TBO to take manual control of the failed PCV and restore it to 120-130 psig Booth

d. When directed to manually restore pressure, insert TRIGGER 33, verify MC01 activates.

Resets AO-1085B by pressing PB-1085

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

9.

14 RHR PUMP INADVERTENT INITIATION Booth

a. When directed by the lead evaluator, INSERT MANUAL TRIGGER 5 Key Parameter Response: 14 RHR pump indicates running Key Expected Alarms: C-03-A-41 (AC INTERLOCK)

Auto Actions: None BOP Recognizes 14 RHR pump is running and informs CRS.

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

CRS Directs the BOP to secure 14 RHR Pump IAW C.4-G BOP Secures 14 RHR pump IAW C.4-G:

Places 14 RHR pump switch in Pull-To-Lock Informs CRS to Evaluate TS 3.5.1.

CRS Evaluates TS 3.5.1:

Evaluates TS 3.5.1 Condition A as NOT MET.

o Restore 14 RHR Pump in 30 Days Evaluates TS 3.5.1 Condition J as NOT MET o Restore HPCI or 14 RHR pump 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 6

10. 11 STATOR WATER COOLING PUMP TRIP Booth

a.

When directed by the Lead Examiner, insert Manual Trigger 6.

Key Parameter Response: Speed Load Changer setpoint lowering.

Key Expected Alarms: 8-A-17, No. 1 Generator Cooling Water Failure BOP Responds to ARP 8-A-17 and recognizes entry into C.4-B.06.02.04.A, Stator Cooling Water Failure Auto Actions: Bypass Valves open and Turbine Trip Recommends inserting a manual scram CRS Directs a reactor scram IAW C.4.K, Immediate Reactor Shutdown NOTE: The OATC may only depress the A pushbutton since a half scram is already inserted on RPS B.

OATC Depresses pushbuttons for REACTOR SCRAM A and B and places the Mode Switch in SHUTDOWN NOTE: Trigger 16 will activate on the scram. This will insert a Turbine Master Trip. This is inserted to raise the amount of heat load being added to the Torus.

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

11. HYDRAULIC ATWS OATC Provides a Scram Report Reactor Scram, Mode Switch is in Shutdown, all rods are NOT in, Reactor power is >4%, EOP Entry CRS Enters EOP 1100 RPV Control, transitions to EOP 2007, Failure to Scram, and directs the following:

BOP Inhibits ADS C.5-3301, Defeat MSIV Low-Low Level Isolation Places 4 Key switches to BYP on C-15/17.

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 -36.

OATC Prevents injection from Condensate & Feedwater by placing the FRV Controllers in Manual and closing MFRVs until RPV level is below -36 and sets the level band -150 to -36 NOTE: HPCI is OOS and already prevented BOP C.5-3205, Prevent Core Spray Injection Place the A/B CS INJECTION BYPASS Switch to BYPASS Close MO-1751/1752 Injection Outboards Place A/B CS Pump switches to PTL Close MO-1753/1754 Injection Inboards Prevents LPCI injection as follows Open Knife switches (C-03): 10A-S31A/B Verify LPCI OBD Valves are closed, MO-2012/13

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

12. HYDRAULIC ATWS (Cont)

OATC Initiate ATWS C.5-3101 (Alternate Rod Insertion)

Verifies Recirc pumps are at minimum speed and trips the pumps NOTE: ARI will NOT work for this scenario.

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

Event 8

13. SBLC PUMP START FAILURE Key Parameter Response: The first SBLC Pump that is attempted to be started will not start.

CRS Directs Boron Injection using the SBLC Hard Card, B.03.05-05.G.1, SBLC Manual Initiation.

Key Expected Alarms: None Auto Actions: None OATC Places 11A-S1 SBLC System Selector Switch to SYS 1 or SYS 2 Recognizes that the selected SBLC Pump running light is not ON and discharge pressure does not rise.

Places 11A-S1 SBLC System Selector Switch to SYS 1 or SYS 2 depending on which one was attempted first.

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES CT-47 During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained in C.5-3101 to achieve reactor shutdown under all conditions (all rods inserted to at least 02).

NOTE: C.5-3101 Part C and/or Part D may be performed.

If only one part is performed, the actions from the other part are not applicable.

OATC Performs PART C (INCREASE COOLING WATER DIFFERENTIAL PRESSURE AND USE RMCS)

Bypasses RWM Starts all available CRD Pumps Fully open the CRD Flow Control Valve o Place FC 3-301 in MAN o Adjust output of FC 3-301 to 100%

Opens MO-3-20 (Drive Pressure to CRD)

Booth

a. When requested to close these valves, activate Trigger 17 and verify CH34 goes active. Wait 1 minute and report them as closed.

Directs Reactor Building Operator to CLOSE CRD-168, CRD-79-1 & CRD-79-2 NOTE: The scenario is set up such that all control rods will drift in if Part C is utilized.

When control rods no longer drift in, Drive rods using RMCS Establish Drive Pressure as high as possible below 400 psig by one or more of the following:

o Throttle closed the CRD Flow Control Valve o Throttle closed Open MO-3-20 Drive Pressure to CRD Booth

b. If requested to close CRD-14, activate Trigger 27 and verify CH22 is modified to 0.

o Directs the Reactor Bldg Operator to CLOSE CRD-14 to raise drive pressure Select and insert rods in non-peripheral core regions with few or no rods inserted Attempt to achieve a Black and White pattern

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Performs PART D (RESCRAM CONTROL RODS)

NOTE: C.5-3101 Part C and/or Part D may be performed.

If only one part is performed, the actions from the other part are not applicable Evacuate personnel from the RB 896 Floor and the Equipment Drain tank Room Booth

c. When requested to deenergize the ARI valves insert Trigger 37, this modifies RR18 is to Open.

Wait 1 minute and report the ATWS 125 VDC Breakers Open.

Directs the in-Plant operator to deenergize the ATWS 125 VDC Valves by opening D-21 & D-11.

NOTE: These contacts are modeled in the simulator. The jumpers are included with the C.5-3101 procedure.

Installs jumpers to bypass all automatic scram signals in C-15 & C-17 Resets the scram Booth

d. If requested to open CRD-14, modify Remote Function CH22 is to 100, wait 1 minute and report CRD-14 Open.

Directs the Reactor Bldg Operator to open CRD-14 Verifies SDV Vent and drain valves Open NOTE: This may take up to 7 minutes.

When Annunciator C-05-B-21 clears, closes the SDV vent and drain valves Booth

e. IF THE SCRAM IS RESET and a Manual Reactor Scram is inserted for Part D, INSERT MANUAL TRIGGER 7 to deleted CH16 allowing the control rods to insert.

Inserts a Manual Reactor Scram Verifies all control rods fully inserted and informs the CRS

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

14. HYDRAULIC ATWS LEVEL LEG ACTIONS Cont For level control, the CRS should direct condensate and feedwater injection re-established and used to maintain level in the desired band.

BOP Maintains -150 to-36 level band Should be using Condensate & Feedwater as necessary to maintain established level band from the beginning of the ATWS.

CRS Once all control rods are inserted, Exits C.5-2007 and returns to C.5-1100 (RPV Control).

Directs OATC to restore RPV level to +9-48 using condensate and feedwater.

OATC Restores RPV level to +9-48 using condensate and feedwater

15. HYDRAULIC ATWS PRESSURE LEG ACTIONS CRS/

BOP Stabilize RPV pressure below 930 psig using the Bypass Valves and/or SRVs (LL-SET).

Once conditions are stable, the bypass valves can be ordered control pressure 800-1000 psig

16. SCENARIO TERMINATION

a.

The scenario may be terminated as follows:

1) ALL rods are inserted.

2) RPV level and pressure are being restored following the all rods in condition.

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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(This table may be modified based on site simulator)

SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial /

Value MALFUNCTIONS (Allow Tracking Off)

FW20A LOSS OF AIR TO FEED REG VALVE A DELETES IN 1 SECOND 2

ACTIVE INACTIVE MC04B SJAE PRESS CTRL VALVE CV-1242 FAILS CLOSED 3

ACTIVE INACTIVE MC03 CONDENSER AIR INLEAKAGE 3

3 0

MC03 CONDENSER AIR INLEAKAGE DELETES IN 1 SECOND 13 0

0 EG02A 11 STATOR WATER COOLING PUMP TRIP 6

ACTIVE INACTIVE CH16 FAILURE TO SCRAM 50 ACTIVE INACTIVE CH16 FAILURE TO SCRAM DELETES IN 1 SECOND 7

ACTIVE INACTIVE SL01A

11 SBLC PUMP TRIP 50 ACTIVE INACTIVE SLO1B

12 SBLC PUMP TRIP 50 ACTIVE INACTIVE SL01A

11 SBLC PUMP TRIP (DELETES IN 1 SECOND) 47 ACTIVE INACTIVE SLO1B

12 SBLC PUMP TRIP (DELETES IN 1 SECOND) 48 ACTIVE INACTIVE TC02 Turbine Master Trip 16 00:01:00 ACTIVE INACTIVE REMOTES MC06 MVP SUCTION VALVES OG-22-1/OG-22-2 23 00:00:30 100 0

MC01 MS-24-1 11 SJAE PCV BYPASS 33 00:00:30 38 0

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SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial /

Value CH34 CRD-168 - CST Return Valve 17 CLOSE 00:00:00 CH22 CRD-14 Accumulator Charging Water Isolation Valve 27 0

100 RR18 ATWS 125VDC Breakers 37 OPEN CLOSE OVERRIDES 05-DS089-02 12 Stator Liquid Pump - GREEN LAMP 50 OFF ON 01-S070-04 14 RHR PUMP START (DELETES IN 1 SECOND) 5 TRUE FALSE 03-S36-06 B MANUAL SCRAM PUSHBUTTON 50 FALSE FALSE 01-ds148-02 HPCI Aux Oil Pump - Green Lamp 50 OFF ON Event Trigger Definitions:

Code Description Event Trigger ZAMWDIG < 0.65 DELETES CONDENSER AIR INLEAKAGE WHEN < 650 MWE 13 zd_s1shd Mode Switch to Shutdown 16 ZD_SLSS2

12 SBLC PUMP SWITCH TO START 47 ZD_SLSS1

11 SBLC PUMP SWITCH TO START 48

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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:

New Create for the 2022 ILT NRC Exam

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PROP CHECKLIST (for exam scenarios only)

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 Caution Tag on 12 SWC Pump Caution Tag on HPCI Aux Pump PE Box on 11 SWC Pump PE sign on RCIC Any Critical Parameter signs used on the panels PROCEDURE CHECKLIST (for exam scenarios only)

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 Test 0010, Reactor Scram Functional Test TS 3.3.1.1 RPS Instrumentation 5-B-40, FW Control Valve Locked C.4-B.05.07.A, Loss Of Reactor Water Level Control B.05.07-05-G.2, Restoring Feedwater Level Control To Automatic 7-A-20, Offgas Annunciator C.4-B.06.03.A, Decreasing Condenser Vacuum C.4-G, Inadvertent ECCS Initiation C-03-A-41, AC Interlock TS LCO 3.5.1 8-A-34, 1-Bus 345 KV Low Freq C.4-F, Rapid Power Reduction C.4-B.06.02.04.A, Stator Cooling Water Failure C.4.K, Immediate Reactor Shutdown C.5-1100, RPV Control C.5-2007, Failure To Scram C.5-3301, Defeat MSIV Low-Low Level Isolation C.5-3205, Prevent Core Spray Injection C.5-3101, Alternate Rod Insertion B.03.05-05.G.1, SBLC Manual Initiation

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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 Jeremy Jackson SRO Cert CRS Steve Stokes SRO Cert BOP Joe Yarbrough SRO Cert OATC

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-63E SEG TITLE:

2022 ILT NRC SCENARIO 2 REV. #

0 PROGRAM:

INITIAL LICENSE TRAINING FL-ILT COURSE:

NRC SIMULATOR EVALUATION N/A TOTAL TIME: 60-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor (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 2022 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 Required Personal Protective Equipment None

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Training Resources:

1.

Full Scope Simulator

2.

QF104016, Attendance Record or LMS Equivalent

3.

3139, Control Room Shift Turnover Checklist

4.

3140, Shift Supervisors Office Shift Turnover Checklist

5.

Lead Instructor - Crew Turnover Brief paperwork

References:

1.

B.05.07-05.D.4, Place Remaining B MFRV CV-6-12B In Service

2.

B.05.07-05.E.2 Part B (TRANSFER TO 3 ELEMENT CONTROL)

3.

B.01.04-05.E.1 Changing Recirc Flow

4.

2167, Plant Startup

5.

2300, Reactivity Adjustment

6.

5-A-27, Rod Drift

7.

C.4-B.01.03.C, Control Rod Drifting

8.

TS 3.1.3

9.

C.4-G, Inadvertent ECCS Initiation

10. TS 3.5.3

11. C.4-B.05.14.A, Earthquake

12. C.4-B.08.01.01.A, Loss Of Service Water

13. C.4-K, Immediate Reactor Shutdown

14. C.4-A, Reactor Scram

15. C.5-1100, RPV Control

16. C.4-B.09.02.B, Loss Of Normal Offsite Power

17. C.4-H Restoration Of Plant Loads

18. B.03.02-05, HPCI Manual Initiation

19. C.5-3302, Alternate Pressure Control Commitments: None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2022 ILT NRC Exam Process (NUREG 1021 & FP-T-SAT-72)

FL-ILT, ILT 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-200-133 Direct reactor startup to full power.

5 MT-SRO-315-167 Direct the response to a control rod drifting 5-7 MT-SRO-299.349 Apply admin requirements for TS Section 3.1and Bases 5-7 MT-SRO-315-160 Supervise response to inadvertent ECCS initiation 5-7 MT-SRO-299-353 Apply admin requirements for TS Section 3.5 and Bases 5-7 MT-SRO-315-125 Supervise response to earthquake 5-7 MT-SRO-315-131 Supervise response to a loss of service water 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-315-137 Supervise response to a loss of normal offsite power 5-7 MT-SRO-304-225 Implement the response for a small break LOC with RPV level maintained above the TAF using high pressure systems.

5-7 MT-SRO-314-112 Supervise alternate pressure control 5-7 RO Tasks:

MT-CRO-259-103 Place remaining MFRV B in service.

1-4 MT-CRO-200-127 Perform a power ascension after the reactor is on line 1-4 MT-CRO-200-226 Respond to a drifting control rod 1-4 MT-CRO-200-204 Perform the procedure for an inadvertent ECCS initiation 1-4 MT-CRO-200-170 Perform the procedure for an earthquake.

1-4 MT-CRO-200-176 Perform the procedure for loss of service water 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-200-181 Perform the procedure for a Loss of Normal Offsite Power 1-4 MT-CRO-206-108 Manually initiate HPCI 1-4 MT-CRO-304-138 Perform actions for a small break LOCA with RPV level maintained above the TAF using high pressure injection.

1-4 MT-CRO-314-116 Perform actions associated with alternate pressure control 1-4

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Scoop Tube lock

2. Rod Drift IN

3. RCIC initiation

4. Service Water Pump trip After EOP Entry:

1. HPCI and RCIC auto start failure

2. EDG-ESW Pump auto start failure Abnormal Events:

1. Control Rod Drifting

2. Inadvertent ECCS initiation

3. Earthquake

4. Loss of Service Water Major Transients:

1. Small LOCA with a LOOP requiring Alternate Pressure/Level Control

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Critical Tasks:

1. CT-10 Critical Task Statement: Manually scram the reactor within 5 minutes if a design basis earthquake has occurred and has been verified by:

All three Panel C-06 earthquake annunciators in alarm And One of the following:

o Actually having felt the indications OR o By confirmation from outside agencies.

Safety Significance: If a design basis earthquake has occurred as indicated by all three alarms and has been verified, plant operation should not continue. A Reactor Scram is required because the plant systems are not analyzed for operation at or above the design basis earthquake levels. Safety system degradation may occur from continued operation with these conditions that could challenge the ability to protect the health and safety of the public.

Applicability: Design basis earthquake has occurred.

Performance Indicator: Upon confirmation that a design basis earthquake exists, AND with indications in the Control Room of degradation to plant safety, manually scram the Reactor.

Distinguishable Cue: Annunciators 6-C-8 (Earthquake), 6-C-13 (Operational Basis Earthquake), and 6-C-18 (Design Basis Earthquake) in alarm and report from PI or the US Geological Survey National Earthquake Information Center.

Performance Feedback: Normal control rod insertion from the manual reactor scram.

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

126 (TAF).

Safety Significance: Submergence is the preferred method for cooling the core. All fuel nodes are then assumed to be covered with water and heat is removed by boiling heat transfer.

Applicability: C.5-1100 conditions where injection systems could otherwise maintain RPV level above -126.

Performance Indicator: When an injection system has failed to automatically start from a valid initiation signal, manually start systems as required and commence injection to avoid RPV level lowering below -126.

Distinguishable Cue: Annunciator 3-A-38 (Reactor Low Low Level) and/or 5-B-28 (Drywell Hi Press Scram Trip) is in alarm and other indications exist on the panels that the injection system should have automatically started.

Performance Feedback: Performance of procedure actions results in the system injecting into the RPV and RPV level is rising.

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SCENARIO OVERVIEW:

Event 1: Place the second Main Feedwater Reg Valve in service

BOP will place the remaining B MFRV in service using the B manual procedure as directed by 2167 (Plant Startup).

Event 2: Raise Reactor power with Recirc flow for Startup

The OATC will continue with the startup by raising recirc flow so reactor power rises from 40% to 45%.

Event 3: Recirc Pump Scoop Tube Lock

When reactor power is ~43% the scoop tube on the B Recirc Pump will lock. The OATC will take action to unlock the scoop tube.

Event 4: Control Rod Drift IN

Control Rod 14-27 will experience a seal failure causing it to drift in from position 48.

The OATC will manually insert and disarm the control rod. The CRS will evaluate Tech Specs for an inoperable control rod.

Event 5: Inadvertent RCIC initiation

RCIC will inadvertently auto initiate. The BOP will take manual action to secure the system. The CRS will evaluate Tech Specs for RCIC inoperable.

Event 6: Multiple earthquakes requiring a Reactor Scram (CT)

An Operational Basis earthquake will cause 11 Service Water pump to trip. The 12 Service water pump will fail to auto start requiring the BOP to manually start it. Shortly after 12 Service Water pump is started and verified running, a Design Basis earthquake will occur requiring a manual reactor scram (CT).

Event 7: Small LOCA and LOOP requiring Alternate RPV Level Control (CT)

Following the scram, a small LOCA and LOOP will occur. HPCI will fail to automatically start on an ECCS initiation and RCIC will be terminated from Event 5. The OATC will manually start HPCI and/or restore RCIC to maintain RPV level above TAF.

Event 8: 11 EDG-ESW Pump fails to Auto Start.

Following the LOCA and/or LOOP, the 11 EDG-ESW Pump will fail to automatically start. The BOP will manually start 11 EDG-ESW Pump from C-08

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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: RUN

b. Present Power Level: ~38%

c. XCEL System Condition: Green

d. Plant CDF: Green

e. Electrical lineup - 2R.

f.

Fuel Pool Status: Green, 194 hours0.00225 days 0.0539 hours 3.207672e-4 weeks 7.3817e-5 months to 200°F

g. Generator Output: ~236 MWe

h. Staffing: Weekday Startup Dayshift

i.

Planned Shift Activities: Place second MFRV in service and raise reactor power for startup.

j.

The following equipment is OOS:

1) 12 Steam Packing Exhauster

2) 12 Stator Water Cooling Pump for motor replacement

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

2.

SIMULATOR SET UP Booth

a. Reset the simulator to IC-282 (PW: crappie2) and place in RUN. Verify the correct malfunctions, remotes, overrides and event triggers are loaded as listed in the Simulator Input Summary page(s).

Insert Trigger 50.

b. Align 12 SPE as follows:

1) Place Caution Tag on 12 SPE handswitch

c. Align Stator Water Cooling as follows:

1) Place Caution Tag on 12 SWC Pump

2) Place PE switch cover on 11 SWC Pump

d. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) Reactivity Maneuvering Steps and Marked up 2300.

3) Provide Procedure Form 2167 Plant Startup Revision 105 page 104 for performance of steps 173 and 174. Step 173.c is N/A

4) Procedure C.1 open for reference

e. Verify the status board is updated IAW Section 1 and Offgas System Status is updated.

f.

Adjust Main Turbine Lube Oil Cooler outlet temperature as necessary to maintain 110-115°F

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

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

a.

Performs walk down of control boards and reviews turnover checklists.

4.

SHIFT BRIEF

a.

Turbine Building status:

Crew Conduct and participate in the Shift Brief 1). 4 Cond Demins in service, B vessel is highest @ 5.2 psid.

2). 12 SWC Pump is out of service. 11 SWC Pump and Lower 4kV are protected.

3). 12 Steam Packing Exhauster is OOS.

b.

Reactor Building Status: Normal for startup

c.

Security, Chemistry & RP: Nothing to add

d.

Extra out plant operator - Standing by to place B MFRV in service.

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 2ND B MFRV IN SERVICE Booth

a. If contacted as the extra out plant operator, report that you are standing by locally to verify proper operation of the regulating valves.

BOP Performs B.05.07-05.D.4, Place Remaining B MFRV CV-6-12B In Service as directed by 2167, Plant Startup Step 173.a.

Opens MO-1134 (HP FW Line B Block Valve)

Verifies MTS-6-84B bias is set at Zero Slowly opens B MFRV using MTS-6-84B.

When MTS-6-84B output matches demand then places MTS-6-84B in AUTO.

Performs B.05.07-05.E.2 Part B (TRANSFER TO 3 ELEMENT CONTROL)

Place Master controller to Manual Depress 3EL pushbutton Place Master controller back to automatic

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

6.

RAISE REACTOR POWER TO 45%

Booth

a.

Provide the following as needed:

CRS directs the OATC to raise Recirc speed to achieve 45% reactor power IAW 2300 Reactivity Maneuvering Steps and Form 2167, Plant Startup Step 174.

1) Nuclear Engineer Reactivity Maneuvering Steps with 2300, Reactivity Adjustment OATC Raises Recirc Speed to raise power IAW B.01.04-05.E.1 Changing Recirc Flow

2) 2167, Plant Startup page 104 marked to perform step 174.

Maintains Flow parameters approximately equal

b.

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 NOTE: It is NOT necessary for the OATC to raise power all the way to 45%. Once a sufficient evaluation of the reactivity manipulation has been performed, the lead evaluator may move on to Event 4.

APRMs & Core Thermal Limits

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

7.

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 Recognizes Spurious Scoop Tube Lock on B Recirc Pump Booth

a.

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 Resets the scoop tube lock Booth

b.

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 Completes raising power to 45% with Recirc Flow IAW Event 2.

Booth

c.

Once the scoop tube is reset, call CRS as the Operations Manager to continue with the power increase to 45%.

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

8.

CONTROL ROD 14-27 DRIFTS IN Booth

a.

When directed by the Lead Evaluator, insert TRIGGER 4.

OATC CRO-200-226 OSS-315-167 Acknowledges the alarm and informs the CRS that Control Rod 14-27 is drifting in.

Key Parameter Response: Control Rod 14-27 drifting in Enters C.4-B.01.03.C, Control Rod Drifting Key Expected Alarms: 5-A-27, Rod Drift Places Rod Select Power Switch to OFF and back to ON Automatic Actions: None Reselects Control Rod 14-27 and inserts to position 00 Booth

b.

If the crew does not take action to insert the CR, manually insert Trigger 14 at ~ notch position

20. This will stick the control rod creating unbalanced flux. The stuck rod malfunction will clear when the operator inserts the rod.

Booth

c.

As the Reactor Building Operator; when directed to isolate/disarm Control Rod 14-27, wait 2 minutes and insert TRIGGER 34. Report that the control rod is isolated and disarmed.

CRS/

BOP Directs the Reactor Building Operator to hydraulically isolate and/or electrically disarm HCU 14-27 IAW B.01.03-05.G.2, Hydraulic Control Unit Isolation.

Floor

d. If guidance is requested from Nuclear Engineering on a 2nd control rod drifting, respond that an analysis is currently being performed.

CRS Evaluates LCO 3.1.3-C as NOT MET OSS-299-349 CRO-299-351 Action C.1: Fully insert control rod within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Booth

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

Action C.2: Disarm CRD within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

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

9.

RCIC AUTOMATIC INITIATION RCIC AUTOMATIC INITIATION Booth

a. When directed by the lead evaluator, insert Trigger 5 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 Determines initiation is spurious based on RPV level.

Depresses the RCIC Trip pushbutton Verifies HO-7 closes and RCIC shuts down

b.

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 6

10. OB AND DB EARTHQUAKES Booth

a. When directed by the lead evaluator, INSERT TRIGGER 6.

Key Parameters: Earthquake speakers rumbling Expected Alarms: 06-C-08, Earthquake, 06-C-13, Operational Basis Earthquake and 6-B-22, Service Water Header Low Pressure BOP Enters C.4-B.05.14.A, Earthquake and C.4-B.08.01.01.A, Loss of Service Water Automatic Actions: None, 12 Service Water Pump will fail to auto start Manually starts 12 Service Water Pump NOTE: 06-C-18, Design Basis Earthquake will alarm 10 seconds after 12 Service Water Pump is manually started BOP Announces DB Earthquake and recommends a manual reactor scram.

CRS Directs a reactor scram IAW C.4-K, Immediate Reactor Shutdown CT-10 Manually scram the reactor within 5 minutes if a design basis earthquake has occurred and has been verified by:

OATC Depresses both Scram pushbuttons All three Panel C-06 earthquake annunciators in alarm And One of the following:

o Actually having felt the indications OR o By confirmation from outside agencies.

Time of DBE: ___________

Time of Scram: ___________

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES OATC Takes actions IAW C.4-A, Reactor Scram PART A:

Place Mode Switch in SHUTDOWN.

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

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

Controls Reactor water level between +9 and

+48 inches. When RPV water level starts to increase:

o Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches o Closes both MFRVs o Verify CV-6-13 is closed when RPV level reaches +15 to +20 inches Verify SDV Vent and Drain Valves closed.

Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

Verify Recirc Pumps have run back to minimum

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

Start the Turbine Bearing Lift Pumps Verify Low-Low Set is controlling Reactor Pressure.

At C-25, Place the POST SCRAM switch in ON and verify all available Drywell Recirculation Fans are operating Verify 4500 gpm through each operating Feed Pump Verify Auxiliary Oil Pump running on any non-operating Feed Pump Verify 4100 gpm through each operating Condensate Pump

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

11. SMALL LOCA WITH LOOP Booth

a. Two minutes following the scram a LOOP will occur concurrent with a small LOCA, a HPCI auto start failure and a failure of 11 EDG-ESW Pump to start.

Key Parameter Response: Temporary loss of control room lighting, degrading primary containment parameters and lowering RPV level.

BOP Takes action IAW C.4-B.09.02.B, Loss Of Normal Offsite Power Key Expected Alarms: Various Performs switch lineup on C-08 Key Auto Actions: EDG auto start Verifies proper operation of the EDGs Event 8

12. 11 EDG-ESW PUMP FAILS TO START Booth

a. If the BOP does not start 11 EDG-ESW pump from C-08 AND, if contacted as the TBO to verify proper operation of the EDGs, wait 30 seconds and report that the 11 EDG-ESW pump failed to auto start.

BOP Recognizes that 11 EDG-ESW pump failed to start and manually starts the pump from C-08

b. If directed to crosstie service water to 11 EDG, wait 1 minute and report that SW-228 will NOT open.

Event 7 Cont NOTE: Once Drywell Pressure reaches 1.84 psig, these actions cannot be taken with the LOOP procedure.

Restarts a Service Water Pump Restarts a RBCCW Pump Restarts a CRD Pump Restarts Drywell Cooling.

NOTE: It is not the intent of this scenario to evaluate the restoration of plant loads. These actions could be started if the LOOP actions are completed.

CRS Enters C.4-H Restoration of Plant Loads

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7 Cont NOTE: It is not the intent of this scenario to evaluate primary containment actions. Parameters will be relatively safe and not a priority.

Enters C.5-1200 Primary Containment Control for high DW pressure.

May direct Torus Sprays be initiated OATC Recognizes HPCI failed to automatically start.

CT-21 When systems required to maintain core submergence do not automatically start, manually align injection systems prior to RPV level dropping below -126 (TAF).

Places HPCI in service IAW B.03.02-05, HPCI Manual Initiation hard card NOTE: HPCI may also be started using C.5-3302, Alternate Pressure Control.

Verified high level trip reset Opens CV-2065, HPCI Min Flow Starts HPCI Turbine Gland Seal Condenser Blower Opens MO-2068, HPCI Disch Inbd Isol Opens MO-2067, HPCI Disch Otbd Isol Places HPCI Aux Oil Pump to RUN Opens MO-2036, HPCI Steam Supply Valve Verifies HPCI Turbine speed and flow are rising and HPCI is injecting into the vessel.

Floor NOTE: The crew may decide to un-terminate RCIC for RPV injection OATC Uses C.4-G, Inadvertent ECCS Initiation to restore RCIC Momentarily places MO-2080, RCIC Turb Reset Motor to OPEN Floor NOTE: The BOP may be shifted to containment control; however, it is not the intent of this scenario to evaluate initiating Torus/Drywell Sprays.

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

13. SCENARIO TERMINATION Floor

a.

The scenario may be terminated when RPV level is being restored to the prescribed band with HPCI and/or RCIC.

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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(This table may be modified based on site simulator)

SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial MALFUNCTIONS (Allow Tracking Off)

CH06_058 ROD 14-27 DRIFT IN 4

50 0

CH06_058 ROD 14-27 DRIFT IN 34 0

50 RC02 RCIC AUTO INITIATION 5

ACTIVE INACTIVE SW03A 11 SERVICE WATER PUMP TRIP 6

ACTIVE INACTIVE C-06-C08 EARTHQUAKE 6

CRY-WOLF NORMAL C-06-C13 OPERATIONAL BASIS EARTHQUAKE 6

CRY-WOLF NORMAL C-06-C18 DESIGN BASIS EARTHQUAKE 6

00:01:00 CRY-WOLF NORMAL RR01A SMALL LINE BREAK ON 11 RECIRC 7

00:02:00 5

0 ED12 LOSS OF OFFSITE POWER 7

00:02:00 ACTIVE INACTIVE SW07 STANDBY SERVICE WATER PUMP AUTO START FAILURE 50 ACTIVE INACTIVE HP02 HPCI AUTO START FAILURE 50 ACTIVE INACTIVE CH02_058 CONTROL ROD 14-27 STUCK 14 ACTIVE INACTIVE CH02_058 CONTROL ROD 14-27 STUCK (DELETES IN 1 SECOND) 24 ACTIVE INACTIVE REMOTES CH15_058 CONTROL ROD 14-27 ELEC DISARMED 34 DISARM 00:00:00

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SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial OVERRIDES 02-S35-01 12 RECIRC PUMP SCOOP TUBE LOCK (DELETES IN 1 SECOND) 3 TRUE FALSE 05-DS089-02 12 STATOR LIQUID PUMP GREEN LAMP 50 OFF ON 04-A2DS081-02 12 STEAM PACKING EXHAUSTER - GREEN LAMP 50 OFF ON 05-S106-2 11 EDG-ESW PUMP - AUTO START 50 FALSE TRUE 05-S106-2 11 EDG-ESW PUMP - AUTO START 8

TRUE TRUE FALSE FALSE FALSE FALSE Event Trigger Definitions:

Code Description Event Trigger ZD_MAAUT(2) 12 RECIRC PUMP SPEED TO RAISE 3

ZD_S1SHD MODE SWITCH IN SHUTDOWN 7

ZD_EMSTA(1) 11 EDG-ESW PUMP TO START 8

ZD_CRDIN ROD INSERT SWITCH TO ROD IN 24

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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:

New Create for the 2022 ILT NRC Exam

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PROP CHECKLIST (for exam scenarios only)

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 12 Service Pump Yellow Caution Tag on 12 Steam Packing Exhauster Protected Equipment Box on 11 Stator Water Cooling Pump Any Critical Parameter aids Marked up 2167, Plant Startup Marked up 2300 PROCEDURE CHECKLIST (for exam scenarios only)

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.05.07-05.D.4, Place Remaining B MFRV CV-6-12B In Service B.05.07-05.E.2 Part B (TRANSFER TO 3 ELEMENT CONTROL) 2167, Plant Startup 2300, Reactivity Adjustment 5-A-27, Rod Drift C.4-B.01.03.C, Control Rod Drifting TS 3.1.3 C.4-G, Inadvertent ECCS Initiation TS 3.5.3 C.4-B.05.14.A, Earthquake C.4-B.08.01.01.A, Loss Of Service Water C.4-K, Immediate Reactor Shutdown C.4-A, Reactor Scram C.5-1100, RPV Control C.4-B.09.02.B, Loss Of Normal Offsite Power C.4-H Restoration Of Plant Loads B.03.02-05, HPCI Manual Initiation C.5-3302, Alternate Pressure Control B.01.04-05.E.1 Changing Recirc Flow

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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 Chase Griest CRS / SRO CRS Brad Lanning NPE&RO OATC Andy Wallen NPE&RO BOP

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-64E SEG TITLE:

2022 ILT NRC SCENARIO 3 REV. #

0 PROGRAM:

INITIAL LICENSED TRAINING PROGRAM FL-ILT COURSE:

N/A N/A TOTAL TIME: 60-90 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 2022 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 FL-ILT Training Program, or

2.

Completion of the SRO Certification Program, or

3.

Currently enrolled in the LOR Training Program Required Personal Protective Equipment None

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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

References:

1.

0141 Reactor Building to Torus Vacuum Breaker Operability Check

2.

Tech Spec 3.6.1.6

3.

4-B-20 Recirc Pmp Mtr A Lo Oil Level

4.

B.01.04-05.H.1 Unstable Speed Control On One Pump

5.

C.4-B.05.01.02.A Control Of Neutron Flux Oscillations

6.

C.4-F Rapid Power Reduction

7.

Tech Spec 3.4.1

8.

6-B-32 RBCCW Low Disch Press

9.

C.4-B.02.05.A Loss Of RBCCW Flow

10. B.01.03-05.E.4 Placing the Standby Flow Control Valve into Service

11. C.4-B.01.03.A Loss of CRD Pump Flow

12. C.4-K Reactor Shutdown

13. C.4-A, Reactor Scram

14. C.5-1100, RPV Control

15. C.5-1300, Secondary Containment Control

16. C.5-1100, Emergency RPV Depressurization Commitments: None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2022 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-299-354 Apply administrative requirements for Tech Spec 3.6 and bases to instrumentation.

5-7 MT-SRO-315-119 Supervise response to control of neutron flux oscillations 5-7 MT-SRO-315.159 Supervise rapid power reduction 5-7 MT-SRO-315-107 Supervise response to loss of RBCCW flow 5-7 MT-SRO-315.102 Supervise response to a loss of CRD Pump flow 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-304-239 Implement the response for a primary system leak in secondary containment, exceeding max safe values in 2 or more areas with an RPV blowdown required.

5-7 RO Tasks:

MT-CRO-223-117 Perform the Reactor Building to Torus Vacuum Breaker Op Test 1-4 MT-CRO-202-114 Respond to unstable speed control on one pump 1-4 MT-CRO-200.168 Perform the procedure for control of neutron flux oscillations 1-4 MT-CRO-200.203 Perform the procedure for Rapid Power Reduction 1-4 MT-CRO-200-152 Perform the procedure for a loss of RBCCW flow 1-4 MT-CRO-201.111 Place the Standby CRD Flow Control Valve into Service 1-4 MT-CRO-200.147 Perform the procedure for Loss of CRD Pump flow 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-304-152 Perform actions for a primary system leak in secondary containment, exceeding max safe values in 2 or more areas with an RPV blowdown required.

1-4

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QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Faulted RB-Torus Vacuum Breaker

2. #11 Recirc Pump runback

3. RBCCW Pump trip

4. CRD Flow Control Valve fails closed

5. Remaining CRD Pump Trip After EOP Entry:

1. SDV fails to isolate automatically

2. SRV C fails to open on ED Abnormal Events:

1. Recirc Pump Runback

2. Rapid power reduction

3. Loss of RBCCW flow

4. Loss of CRD Flow Major Transients:

1. Unisolable steam leak in the RCIC room that requires Emergency Depressurization

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Critical Tasks:

1. CT-1 Critical Task Statement: Insert a Manual Reactor Scram within 5 minutes when no CRD pump is running and/or a second CRD accumulator low pressure alarm is received.

Safety Significance: If the accumulators discharge and a scram is required, the rods may not insert into the core at the required scram rate, or at all, depending on reactor pressure.

Therefore, the Operator is instructed to scram the reactor after receipt of the second accumulator low pressure alarm. Failure to do so may result in fuel damage from an unanalyzed rod pattern and higher than normal release to the environment.

Applicability: No CRD pumps running and a second accumulator low pressure alarm is received.

Performance Indicator: With indications of no CRD pumps running and two accumulator low pressure alarms received, Reactor scram is inserted.

Distinguishable Cue: Annunciator 5-B-17 (Charging Water Lo Press) in alarm, no CRD pump running, and at least two accumulator low pressure alarms active.

Performance Feedback: Normal control rod movement from insertion of the manual reactor scram.

2. CT-33 Critical Task Statement: When a primary system is discharging into the secondary containment through an unisolable break, perform an Emergency Depressurization within 15 minutes when max safe operating values are exceeded in two or more areas.

Safety Significance: Should secondary containment temperatures, radiation levels or area water levels exceed their maximum safe operating values in more than one area, the RPV must be depressurized to preclude further degradation. RPV depressurization places the primary system in its lowest possible energy state, rejects heat to the suppression pool in preference to outside the containment, and reduces the driving head and flow of primary systems that are unisolated and discharging into the secondary containment. The criteria of two or more areas specified identifies the rise in secondary containment parameters as a wide-spread problem which may pose a direct and immediate threat to secondary containment integrity, equipment located in the secondary containment, and continued safe operation of the plant.

Applicability: C.5-1300 conditions when the plant is at power and a primary system is discharging into the secondary containment which can NOT be isolated resulting in two or more areas above max safe.

Performance Indicator: Upon confirmation that max safe operating values were exceeded in two or more areas, perform an emergency depressurization. This includes the opening of ADS valves. An alternative strategy would be to anticipate the blowdown by fully opening turbine bypass valves. If the blowdown is avoided by performing an anticipation of the blowdown then this would be considered successfully meeting the critical task.

Distinguishable Cue: Indications from SPDS and from back panel recorders/monitors show two areas above max safe.

Performance Feedback: RPV pressure lowering with ADS valves open.

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SCENARIO OVERVIEW:

Event 1: Perform Test 0141 (RB/Torus Vacuum Breaker Operability Check)

BOP will perform Test 0141. The second vacuum breaker tested will fail open. The CRS will evaluate Tech Specs for an inoperable vacuum breaker.

Event 2: #11 Recirc Pump Runback

11 Recirc pump will runback to ~30% speed. The OATC may attempt to insert a scoop tube lock but it will be unsuccessful. The CRS will evaluate TSs for mismatched recirc flows.

Event 3: Insert Control Rods to exit Unanalyzed Region of P-F Map The recirc pump runback will place the plant in the unanalyzed region of the P-F map. The OATC will insert rods to exit this region.

Event 4: RBCCW Pump Trip

#11 RBCCW pump will trip and the #12 RBCCW pump will fail to auto start. The BOP will manually start #12 RBCCW Pump.

Event 5: CRD Flow Control valve fails closed

The A CRD Flow Control valve will fail closed. The OATC will take manual control and swap to the standby B CRD Control valve.

Event 6: Loss of all CRD flow (CT)

Once the standby CRD flow control valve is in service, the remaining 11 CRD Pump will trip requiring the crew to insert a manual reactor scram.

Event 7: Unisolable RCIC steam line break requiring a Blowdown (CT)

Following the scram a steam line break will occur in the RCIC room. Temperatures and radiation levels will rise and eventually reach two Max Safe values. The crew will be forced to perform and Emergency Depressurization.

Event 8: SDV fails to automatically isolate

When the reactor is scrammed, the SDV will fail to automatically isolate. The OATC will manually isolate the SDV.

Event 9: SRV C fails to open on ED When ED is initiated, the C SRV will fail to open. The BOP will open an additional SRV until 3 SRVs are verified open.

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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, 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months to 200°F

h. Generator Output: ~607 MWe

i.

Staffing: Normal Weekday Dayshift

j.

Planned Shift Activities: Test 0141 (RB/Torus Vacuum Breaker Operability Check)

k. The following equipment is OOS:

1) 12 CRD Pump for motor replacement

2) 12 Service Water Pump for motor replacement

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

2.

SIMULATOR SET UP Booth

a. Reset the simulator to IC-283 (PW: crappie3) 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. Verify Manual Trigger 50 inserted for simulator initial conditions and preloaded malfunctions.

c. Tag out 12 CRD Pump as follows:

1) Place Caution tag on 12 CRD Pump.

2) Place protected equipment cover on 11 CRD Pump

3) Verify GREEN light is OFF for 12 CRD Pump

d. Tag out 12 Service Water Pump as follows:

1) Place Caution tag on 12 Service Water Pump

2) Verify 12 Service Water Pump green lamp off

e. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) Copy of Test 0141 initiated and ready to perform.

f.

Ensure Cooling tower magnets reflect NO cooling towers in service.

g. Verify the status board is updated IAW Section 1

h. 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

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). 12 Service Water Pump is OOS 4). All other systems in TB are normal.

b.

Role Play as necessary. Chemistry, RP and Extra out plant operator.

1) Nothing to add

c.

Role Play as necessary. Rx Building status:

1) 12 CRD Pump is OOS, 11 CRD Pump is protected, all other 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.

RB/TORUS VACUUM BREAKER TEST RB/TORUS VACUUM BREAKER TEST BOP Performs Test 0141, Reactor Building to Torus Vacuum Breaker Operability Check Floor DPIS readings for Step 1 are provided.

Verifies DPIS-2572 (-0.21) and DPIS-2573 (-0.16) are reading less than 0. (Step 1) Completed by I&C.

Booth

a.

Report that DWV-8-2 is closed Verifies locally DWV-8-2 is CLOSED (Step 2)

b.

Using a stopwatch, report AO-2379 is open 15 seconds after the HS taken to open.

Opens AO-2379

c.

At 15 seconds, report AO-2379 is closed (Crew times this)

Closes AO-2379

d.

Report that DWV-8-1 is closed Verifies locally DWV-8-1 is CLOSED (Step 4)

e.

When AO-2380 is taken to OPEN, verify Event Trigger 1 goes active. This prevents AO-2380 from closing.

Opens AO-2380

f.

Using a stopwatch, report AO-2380 is open 15 seconds after the HS taken to open.

NOTE: AO-2380 should auto close when the switch is released but it wont.

BOP Closes AO-2380 Booth

g.

Report as the RBO that the valve did NOT close and remains full open.

Reports to the CRS that AO-2380 will NOT close.

h.

If notified as Engineering about IST requirements, acknowledge the notification CRS Evaluates Tech Spec LCO 3.6.1.6 as NOT met and enters Condition A.

i.

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

A.1 is a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action to close the Vacuum Breaker.

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

6.

11 RECIRC PUMP RUNBACK 11 RECIRC PUMP RUNBACK Booth

a.

When directed by the Lead Evaluator, insert TRIGGER 2.

Key Parameter Response: Lowering speed on the 11 Recirc Pump and Reactor power lowering.

Key Expected Alarms: 4-B-20 Recirc Pmp Mtr A Lo Oil Level, C.6-REC002 Computer Point.

OATC Notices 11 Recirc Pump speed lowering Automatic Actions: None Takes actions IAW B.01.04-05.H.1 Unstable Speed Control On One Pump NOTE: Locking the scoop tube will be unsuccessful in this scenario.

Notifies CRS Attempts to lock the scoop tube Booth

b.

When contacted as the RBO, wait one minute and report that there is no apparent cause for the Recirc Pump Runback.

CRS Enters C.4-B.05.01.02.A Control Of Neutron Flux Oscillations OATC Determines plant is operating in the Unanalyzed Region of the P-F map Booth

c.

When contacted as engineering, maintenance or plant management, state that the appropriate investigations and/or notifications will be initiated.

CRS Evaluates TS LCO 3.4.1 as NOT met.

Condition A applies for mismatched Recirc flows 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to match flows or establish single loop operations

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

7.

INSERT CONTROL RODS INSERT CONTROL RODS Takes action IAW C.4-F Rapid Power Reduction NOTE: Based on validation, the crew should establish a power band near 60%.

Selects Rapid Power Reduction menu on the RWM.

Inserts control rods to exit Unanalyzed Region Monitors CRDH parameters, Rx Power and control rod positions.

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

8.

11 RBCCW PUMP TRIP 11 RBCCW PUMP TRIP Booth

a.

When directed by the Lead Evaluator, Insert TRIGGER 4 and verify Malfunction SW01A goes active.

Key Parameter Response: 11 RBCCW Pump will trip and its green control power light will extinguish. 12 RBCCW Pump white standby light will also extinguish.

BOP Implements C.4-B.02.05.A Loss Of RBCCW Flow Key Expected Alarms: 6-B-32 RBCCW Low Disch Press Key Expected Alarms: None Observes that 12 RBCCW Pump failed to start and manually starts the pump (IA).

Auto Actions: None, 12 RBCCW Pump will fail to auto start.

Observes that 12 RBCCW Pump failed to start and manually starts the pump (IA).

Verifies that system parameters are restored to normal.

Notifies CRS

b.

If dispatched as the RBO, wait one minute and report that 12 RBCCW pump is running normally and there is no apparent reason for the trip.

c.

If dispatched as the TBO, wait one minute and report that #11 RBCCW pump breaker tripped on overload.

d.

When contacted as engineering, maintenance or plant management, state that the appropriate investigations and/or notifications will be initiated.

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

9.

A CRD FLOW CONTROL VALVE FAILS CLOSED A CRD FLOW CONTROL VALVE FAILS CLOSED Booth

a.

When directed by the Lead Evaluator, insert TRIGGER 5 and verify CH07B goes active.

Key Parameter Response: Reduced CRD cooling water flow Key Expected Alarms: 5-B-41, CRD HI Temperature OATC Responds to annunciator and informs CRS Automatic Actions: None Recognizes CRD FCV failure Booth

b.

If directed to investigate CRD temperatures, wait 1 minute and report that many CRD temperatures are rising and that CRD 26-15 is in alarm. The highest reading alarm is 255°F.

Sends Reactor Building Operator to investigate CRD temperature recorder.

Acknowledge any investigation/notification request to Engineering, Maintenance and Plant MNGR.

CRS Directs performance of B.01.03-05.E.4, Placing The Standby CRD Flow Control Valve Into Service When directed to report to the CRD FCV station to support shift of FCV wait 1 minute and report you are standing by.

OATC Coordinates with Reactor Building Operator and performs the following:

c. When directed to OPEN CRD-18-2 and CRD-16-2, WAIT 1 minute then use TRIGGER 15 and verify CH17 goes to OPEN and inform the CR.

Directs RBO to OPEN CRD-18-2 & CRD-16-2 (Steps 1.a and 1.b)

Places CRD Flow Selector to the B position.

Slowly opens CV-3-19B to 60-62 gpm Places CRD Flow Control in Auto When directed to CLOSE CRD-16-1 and CRD 1, WAIT 1 minute, then use TRIGGER 25 and verify CH16 goes to CLOSE and inform the CR.

Directs RBO to close CRD-16-1 & CRD-18-1 (Steps 1.h and 1.i)

Acknowledges 5-B-41 clear and informs CRS

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

10. COMPLETE LOSS OF CRD FLOW COMPLETE LOSS OF CRD FLOW Booth

a. When directed by the lead evaluator, insert TRIGGER 6 Key Parameter Response: 11 CRD Pump trips and CRDH pressures and flow lowering Key Expected Alarms: 5-B-17, Charging Water Lo Press, 5-B-25 CRD Pump 3-16A Breaker Tripped, 5-B-26 CRD Pump 3-16A OL OATC Announces 11 CRD Pump trip and complete loss of CRDH Flow Automatic Actions: None CRS Directs the OATC to insert a reactor scram IAW C.4-K (Immediate Reactor Shutdown)

CT-1 Insert a Manual Reactor Scram within 5 minutes when no CRD pump is running and/or a second CRD accumulator low pressure alarm is received.

OATC Takes action IAW C.4-A Reactor Scram Depresses both scram pushbuttons NOTE: The crew may not wait for the 2nd accumulator alarm to insert the scram since CRD Pumps cant be restored.

Time CRD Pumps lost: _____________

Time Rx Scram inserted: ______________

Place Mode Switch in SHUTDOWN Verify all Rods are inserted to position 04.

Provides scram script to CRS.

Restores RPV water level in band.

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

11. SDV VENT AND DRAIN VALVES FAIL TO CLOSE SDV VENT AND DRAIN VALVES FAIL TO CLOSE Key Parameter Response: SDV vent and drain valves remain open.

OATC C.4-A Reactor Scram Immediate Actions.

Verify SDV Vent and Drain Valves closed Key Expected Alarms: None Manually closes the SDV vent and drain valves Automatic Actions: None, SDV fails to auto isolate.

Event 6 Cont OATC 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 +9 to +48 C.5-1100 level band 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

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6 Cont 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 RCIC leak 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 7

12. RCIC STEAM LEAK WITH FUEL FAILURE RCIC STEAM LEAK WITH FUEL FAILURE Booth Key Parameter Response: Rising RB radiation levels and rising RCIC room temps CRS Directs C.4-B.02.04.A, Steam Leaks Outside Primary Containment and RB Evacuation.

Key Expected Alarms: 3-B-56, High Area Temp Steam Leak, 4-A-11, Reactor Building High Radiation Directs BOP to isolate RCIC per C.4-B.04.01.E, Primary Containment Isolation - Group 5 or C.4-B.02.04.A.

Automatic Actions: None, RCIC fails to isolate BOP Attempts to isolate RCIC and reports MO-2075 and MO-2076 will not close.

BOP Monitors RB area radiation and temperature levels on SPDS and the back panels.

CRS Enters C.5-1300 and determines location and magnitude of radiation conditions in the Reactor Building.

CRS May order opening of Main Turbine Bypass valves in anticipation of Emergency Depressurization.

BOP Monitors and reports temperature and radiation levels in the Reactor Building and promptly reports receipt of second max safe radiation level.

CT-33 When a primary system is discharging into the secondary containment through an unisolable break, perform an Emergency Depressurization within 15 minutes when max safe operating values are exceeded in two or more areas.

Max Safe Rad: 1 R/hr in RCIC and TIP rooms Max Safe Temp: 212°F in RCIS and TIP rooms CRS Enters Emergency Depressurization Verifies Torus level > -5.9 ft.

Directs opening of all 3 ADS SRVs.

Time when 2 Max Safe values reached: _______

Time when 3 ADS valves are placed in OPEN:_______

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SCENARIO TIME-LINE SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 9

13. SRV C FAILS TO OPEN ON ED SRV C FAILS TO OPEN ON ED Key Parameter Response: SRV remains closed when handswitch is taken to open.

CRS Directs Emergency Depressurization IAW C.5-1100 RPV Control Key Expected Alarms: None Automatic Actions: None, RCIC fails to isolate BOP Opens A, C and D SRVs Reports to CRS that C SRV failed to open CRS Directs opening of additional SRVs until 3 are verified open.

Opens an additional SRV until 3 SRVs are verified open.

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

14. SCENARIO TERMINATION SCENARIO TERMINATION Floor Inst

a.

The scenario may be terminated once 3 ADS valves are open and RPV level is in auto 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)

SW01A 11 RBCCW PUMP TRIP 4

ACTIVE INACTIVE CH07B CRD FLOW CONTROL VALVE CV-19A) FAILS CLOSE 5

ACTIVE INACTIVE RC07 RCIC STEAM LINE LEAK 7

00:02:00 00:03:00 100 0

RC08 FAILURE OF RCIC TO AUTO ISOLATE 50 ACTIVE ACTIVE RX01 FUEL FAILURE 6

2 0

CH22 SDV VENT AND DRAIN VALVES FAIL OPEN 50 ACTIVE INACTIVE CH22 SDV VENT AND DRAIN VALVES FAIL OPEN (DELETES IN 1 SECOND) 8 ACTIVE INACTIVE CH08A 11 CRD Pump Trip 6

ACTIVE INACTIVE C-05-B26 11 CRD Pump OL 6

CRYWOLF NORMAL SW08 STANDBY RBCCW PUMP AUTO START FAILURE 50 ACTIVE INACTIVE REMOTES CH17 B FLOW CONTROL STATION CRD-16-2, CRD-18-2 15 OPEN CLOSE CH16 A FLOW CONTROL STATION CRD-16-1, CRD-18-1 25 CLOSE 00:00:00

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SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s)

Ramp Final Initial /

Value OVERRIDES 02-A11P1-U 11 RECIRC PUMP - LOWER 2

TRUE FALSE 02-S31-01 11 SCOOP TUBE LOCK PUSHBUTTON 50 FALSE FALSE 02-S74-02 TORUS VAC RELIEF AO-2380 - OPEN 1

TRUE FALSE 02-S74-01 TORUS VAC RELIEF AO-2380 - CLOSE 1

00:00:15 FALSE FALSE 02-DS162-02 AO-2380 - GREEN LAMP 1

00:00:15 OFF ON 02-DS-163-02 AO-2380 - RED LAMP 1

ON OFF 03-DS083-02 12 CRD PUMP GREEN LAMP 50 OFF ON 04-A1DS108-02 12 SERVICE WATER PUMP GREEN LAMP 50 OFF ON 02-S82-01 MO-2075 HANDSWITCH TO CLOSE 50 FALSE FALSE 02-S62-01 MO-2076 HANDSWITCH TO CLOSE 50 FALSE FALSE 01-S053-01 SRV C HANDSWTICH 50 FALSE FALSE Event Trigger Definitions:

Code Description Event Trigger ZD_PC80O INITIATES AO-2380 FAILURE WHEN HANDSWITCH IS TAKEN TO OPEN 1

ZD_S1SHD MODE SWITCH TO SHUTDOWN 7

ZD_CSDVI SDV IN ISOLATE 8

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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 2022 ILT NRC Exam

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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 Caution tag for 12 CRD Pump PE cover on 11 CRD Pump Caution tag for 12 SWP

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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 0141 Reactor Building to Torus Vacuum Breaker Operability Check Tech Spec 3.6.1.6 4-B-20 Recirc Pmp Mtr A Lo Oil Level B.01.04-05.H.1 Unstable Speed Control On One Pump C.4-B.05.01.02.A Control Of Neutron Flux Oscillations C.4-F Rapid Power Reduction Tech Spec 3.4.1 6-B-32 RBCCW Low Disch Press C.4-B.02.05.A Loss Of RBCCW Flow B.01.03-05.E.4 Placing the Standby Flow Control Valve into Service C.4-B.01.03.A Loss of CRD Pump Flow C.4-K Reactor Shutdown C.4-A, Reactor Scram C.5-1100, RPV Control C.5-1300, Secondary Containment Control C.5-1100, Emergency RPV Depressurization

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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 Mike Munoz CRS / SRO CRS Dan Olson NPLE&RO / RO OATC Andy Wallen NPE&RO / RO BOP

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