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Dua 2017 Ile - Administered Exam Scenarios
	ML17214A214
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Site:	Duane Arnold
Issue date:	06/14/2017
From:	Bielby M; Operations Branch III
To:	; NextEra Energy Duane Arnold
	Bielby M
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SIMULATOR EXERCISE GUIDE SEG SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG 203 LMS Rev. Date: N/A SEG TITLE: NRC INITIAL LICENSE EXAM, SCENARIO #1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~90 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective: This Evaluation Scenario Guide evaluates the Operators ability to:

Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Objectives: Evaluation Guide, no tasks are trained. Evaluated tasks are listed on page 3.

Prerequisites: None Training Resources: A. Simulator B. Evaluation team C. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G. Simulator Video recording equipment

References:

A. ARP 1C05A Rev. 82 B. ARP 1C08B Rev. 113 C. AOP 410 Rev. 29 D. ARP 1C08A Rev, 90 E. ARP 1C23A Rev. 19 F. ARP 1C23B Rev. 23 G. OI 734 Rev. 59 H. AOP 644, Rev. 17 I. AOP 255.1, Rev. 46 J. AOP 255.2, Rev. 43 K. EOP 2 Rev. 18 L. EOP 1 Rev. 20 M. ED Rev. 11 N. OP-AA-102-1003 Rev. 18 O. IPOI 3 Rev. 152 P. OI 856.1, Rev. 48 Q. OI 304.1, Rev. 84 R. OI 304.2, Rev. 96 S. OI 304.2 QRC 1, Rev. 0 Protected Content: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 14.16 Remove the Startup Transformer (1X3) from service 15.10 Transfer Essential Bus from Startup to Standby Transformer 45.21 Reset A/B or Startup Feed Regulating Valve Lockup 93.22 Perform the Immediate Operator Responses to a Reactor Scram 94.15 Respond to Loss of River Water Supply 95.21 Perform Defeat 11 95.44 Perform actions of RC/L of EOP 1 95.45 Perform initial EOP 1 actions (RC) 95.46 Perform actions of RC/P of EOP 1 95.63 Perform DW/T leg of EOP 2 95.64 Perform PC/P leg of EOP 2 95.74 Perform ALC leg of EOP 1 when Injection Systems are lined up and available 95.76 Perform ALC with 1 Core Spray and 1 other ECCS pump available.

95.80 Perform an Emergency Depressurization Using SRVs.

Senior Reactor Operator 1.02 Determine operability for TS required components 4.21 Direct Crew Actions to Perform the Immediate Operator Responses to a Reactor Scram 5.04 Direct Crew Responses to Loss of 1A3 5.08 Direct Crew Response to Loss of 4160V Nonessential Power Condition 5.15 Direct Crew Response to Loss of River Water Supply 6.21 Direct Crew Response to Perform EOP Defeat 11 6.44 Direct Crew Response for performance of the RC/L leg of EOP 1 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.46 Direct Crew Response for performance of RC/P leg of EOP 1 6.63 Direct Crew Response for performance of the DW/T leg of EOP 2 6.64 Direct Crew Response for performance of the PC/P leg of EOP 2 6.74 Direct Crew Response to Perform ALC leg of EOP 1 when Injection Systems are lined up 6.76 Direct Crew Response to Perform ALC with 1 core spray and 1 other ECCS pump available 6.78 Direct Crew Response for performance of Emergency Depressurization UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev. 0 Initial development for 2017 Initial development for N/A See Cover NRC LOIT Examination 2017 NRC LOIT See Cover Examination Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS Event # Description When the crew assumes the shift reactor power is approximately 80% following A Feed pump vibration analysis. On the last shift, repairs were made to the B FRV due to internal fault that caused the B FRV to lock.

1. Once the crew takes the shift they will be required to reset the B FRV lockup using ARP 1C05A (F-1) section 4.

2. RE will request the crew to raise Reactor Power by 5% using control rods and hold prior to continuing raising power to 100%.

3. Once the crew has reset the B FRV lockup and raised power to approximately 85%, the crew will respond to B FRV failing downscale. The crew will enter AOP 644 and AOP 255.2 due to the feedwater transient and subsequent power fluctuation.

4. The crew will then respond to control rod 14-15 drifting out. The crew will have to disarm the rod in order for rod motion to stop. AOP 255.1 will be entered to address the drifting rod. The crew will enter LCO 3.1.3 Condition C.

5. Startup Transformer Trouble annunciator will be received and the crew will respond via ARP 1C08A (A-7), Startup XFMR 1X3 Trouble. In-plant personnel will be dispatched to the S/U Transformer to investigate and upon investigation; it will reveal a Sudden Internal Pressure Trip. The crew will take 1X3 out of service per OI 304.2. The crew will enter and exit the appropriate Tech Specs for the Startup Transformer OOS:

T.S. 3.8.1 Condition B for associated SBDG

T.S. 3.8.1 Condition C for both Offsite Circuits inoperable

T.S. 3.8.1 Condition F (three AC sources inoperable)

T.S. 3.0.3 (per 3.8.1F)

The crew will enter, and remain in, the appropriate Tech Spec for the Startup Transformer OOS:

T.S. 3.8.1 Condition A for Startup XFMR Offsite Circuit

6. A small steam leak will occur in the Drywell. The crew will enter EOP 2, Primary Containment Control. The crew will enter AOP 573 to address rising Drywell pressure. The crew will eventually enter EOP 1, Reactor Control and insert a manual scram prior to exceeding 2# in the Drywell.

After the scram is inserted and after Drywell pressure exceeds 2#, HPCI will fail to start due to the HPCI aux oil pump tripping. At the same time a lockout of 1A3 will occur causing the loss of A Core Spray pump and A and C RHR pumps. The leak in the drywell will require the crew to initiate sprays to prevent drywell air temperature from exceeding 280°F. (CRITICAL)

7. As RPV water level continues to lower, the crew will enter EOP 1 ALC leg. The crew will ensure the appropriate injection subsystems and systems are available and lined up as Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG RPV level lowers.

8. The crew will enter ED after RPV level reaches 15 and prior to -25 in the RPV.

(CRITICAL)

9. The crew will recognize that the LPCI inject valve MO-1905 will not automatically open with a 450 psig signal. Operator action at 1C03 will open MO-1905 and RHR will be used to restore and maintain RPV level in the directed control band. (CRITICAL)

When RPV level is being restored 170-211 the scenario will be terminated.

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Facility: Duane Arnold Energy Center Scenario No.: _____1___ Op-Test No.: 17-1 Examiners: Chuck Zoia Operators: SRO-U (2), SRO-I (7), RO (3)

Mike Bielby _____________________________

Randy Baker _____________________________

Initial Conditions/Turnover:

When the crew assumes the shift reactor power is approximately 80% following A Feed pump vibration analysis. On the last shift, repairs were made to the B FRV due to internal fault that caused the B FRV to lock.

Once the crew takes the shift they will be required to reset the B FRV lockup using ARP 1C05A (F-1) section 4.

RE will request the crew to raise Reactor Power by 5% using control rods and hold prior to continuing raising power to 100%.

Event Malf. Event Event No. No. Type* Description 1 N ATC Reset B FRV N SRO 2 R ATC Raise power with rods R SRO 3 FW12B I ATC B FRV fails downscale I SRO 4 RD0602 C ATC Control Rod drift out 19 TS SRO Tech Spec (3.1.3) 5 AN1C08 C BOP Remove S/U Transformer from service A(7)

TS SRO Tech Spec Entry (3.8.1) 6 RR15A M ALL LOCA in Drywell 7 M ALL Alternate Level Control 8 M ALL Emergency Depressurization required 9 STRH0 C BOP MO-1905 fails to open 1,

STRH0 C SRO 2

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS

1. Set NRC Exam Security for the Simulator per QF-1071-08

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist.

3. Load the saved IC (in folder with this ESG) to a SNAPSHOT ______

a. Reset to that SNAPSHOT.

b. Place the Simulator in RUN OR

4. Reset to IC 23, place the simulator in RUN and perform the following:

a. Raise power to approximately 80%

b. Insert fw16b and remove to lockup FRV B

c. Insert event triggers, malfunctions, overrides and remotes per the tables below.

5. RUN Schedule File ESG_1.sch and LEAVE IT RUNNING

6. Verify Malfunctions

7. Verify Remotes

8. Verify Overrides

9. Ensure MOL pull sheet is in the 1C05B hanging file.

10. Ensure EOOS has the same system status lineup as the start of the simulator scenario.

11. Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

12. After going to run, to insert the B FRV lockup perform the following:

a. Insert fw16b to lockup FRV B

b. Remove fw16b in order to allow for the crew to reset

13. Provide appropriate shift turnover documentation.

a. Markup ARP 1C05A (F-1) as follows:

(1) Circle/slash the following sections/steps:

a) Section 1.0 - Step 1.4 b) Section 2.0 - Step 2.1 c) Section 3.0 - Steps 3.1, 3.2 (a), Note, 3.7, 3.10 (2) ONLY circle the following sections/steps:

a) Section 3.0 - 3.3, 4.1 (3) N/A the following sections/steps:

a) Section 3.0 - 3.4, 3.5, 3.6, 3.8, 3.9

b. Place a maintenance and testing border around 1C05A (F-1)

c. Mark up MOL insert/withdrawl sheet to appropriate step Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 1,7,9,13 Manually Activated Manually Activated 5 ZLOHPHS2256(2) == 1 HS-2256(2) AUX OIL PUMP 1P-218 LITES (RED) TO ON 11 ZLOCSHS2103(4) == 1 Pump 1P-211A (Red) to Red 15 ZLOPCHS4310(2) == 1 CV-4310 open MALFUNCTIONS:

Time Malf. No. Malfunction Title ET Delay Ramp Initial Value Final Value 1C08A (A-07) STARTUP XFMR 1X3 Setup AN1C08A(7) 1 CRYWOLF ON TROUBLE RECIRC LOOP RUPT - DESIGN BASES Setup RR15A 9 15:00 0 0.05 LOCA AT 100% - LOOP A Setup ED08C 4.16 KV/480V BUS FAULT - BUS 1A3 11 2 SEC INACTIVE ACTIVE LPCI A INJECT VALVE FAILS TO AUTO Setup STRH01 ACTIVE ACTIVE OPEN - MO-2003 LPCI B INJECT VALVE FAILS TO AUTO Setup STRH02 ACTIVE ACTIVE OPEN - MO-1905 Setup HP12 HPCI Aux Oil Pump 1P218 Trip 5 INACTIVE ACTIVE FW REG VALVE CONTROLLER FAILURE Setup FW12B 7 7:00 AS IS 0 (AUTO)- FWRV B CONTROL ROD DRIVES OUT- ROD 14-Setup RD011415 13 INACTIVE ACTIVE 15 REMOTES:

Time Malf. No. Malfunction Title ET Delay Ramp Initial Value Final Value HS-2256(1) AUX OIL PUMP 1P-218 LITES Setup DO-HP-032 5 INACTIVE ACTIVE (GREEN)

HS-2256(2) AUX OIL PUMP 1P-218 LITES Setup DO-HP-033 5 INACTIVE ACTIVE (RED)

SCHEDULE FILES:

ESG_1

@Time Event Action Description Setup 15 Modify malfunction rr15a to 2.0 in 900 RECIRC LOOP RUPT - DESIGN BASES LOCA AT 100% - LOOP A Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG SHIFT TURNOVER INFORMATION

Monday, Day Shift

Warm summer day, 77 degrees F, Severe Weather possibility later today

Approx. 80% Rx Pwr with corresponding MWe, MWth and core flow.

Protected train- A

Technical Specification Action statements in effect.

o DAEC is in compliance with all LCOs

Plant PRA/PSA Status including CDF/LERF & color o CDF: 1.32 x 10-6, GREEN, 1 Year to Yellow ICDP o LERF 3.27 x 10-7, GREEN, 1 Year to Yellow ILERP

Evolutions in progress or planned for upcoming shift:

o Repairs to an internal fault of the B FRV controller are complete. Upon conclusion of turnover, the ATC operator is to reset the lockup on B FRV.

o Power was lowered to perform A feed pump vibration analysis. A feed pump vibration analysis was completed on the last shift. The crew has been instructed to raise power.

o REs have requested the crew to raise Reactor Power by 5% using control rods and hold prior to continuing raising power to 100%.

Comments, problems, operator workarounds, etc.

o NSPEOs available for the shift include:

Aux Operator and Second Assistant One extra NSPEO available in Work Control Radwaste Operator Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 CREW

Reset the B FRV lockup After the crew Booth Communicator CRS has assumed Respond as plant personnel and

Direct crew to reset the B FRV IAW the ARP the shift: respond as necessary ATC (1C05)

Resets the B FRV using ARP 1C05A (F-1) section 4 as follows:

o When the cause of the lockout has been corrected, perform If/when Booth Communicator the following:

contacted as Inform the control room that you are Verify that the controller LED displays for the locked inplant operator standing by at the B FRV Feed Reg Valve are lit.

for B FRV lockup reset: Verify the Feedwater Lockout Relay amber light above the associated Lockout Relay is dim.

After B FRV is Booth Communicator o Reset a locked Feed Reg Valve as follows:

reset and when Inform the control room that nothing At HC-1621 B FEED REG VALVE MANUAL/AUTO contacted: abnormal to report at the B FRV TRANSFER for the locked Feed Reg Valve, perform the following:

Verify or place in MANUAL (M is selected on the A/M pushbutton).

Select Y on the display.

Adjust the Y bias setting to zero.

Obtain the current Feed Reg Valve position using ZI-1621 for the locked Feed Reg Valve.

Using Attachment 1, determine the appropriate M/A station controller output signal V.

At HC-1621, perform the following:

Select V on the display to indicate controller output.

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 ATC (1C05) Cont.

Adjust V to the value obtained from Attachment 1.

Reset the lockout using HSS-1621.

Verify the Feedwater Lockout Relay amber light is no longer lit.

o Transfer CV-1621 to AUTO as follows:

Verify the B FEED REG VALVE CONTROLLER HC-1621 is in MANUAL.

Select 'V' on the display for B FEED REG VALVE CONTROLLER, HC-1621.

Select 'V' on the display for MASTER FEED REG VALVE CONTROLLER, LC-4577.

Match the Feedwater Reg Valve controller top meter display with the MASTER FEED REG VALVE CONTROLLER top meter display by adjusting the potentiometer on HC-1621.

Verify proper response of the Feedwater Regulating valve by monitoring ZI-1621.

Select AUTO on HC-1621.

Select 'S' on the display for B FEED REG VALVE CONTROLLER, HC1621.

Select 'S' on the display for MASTER FEED REG VALVE CONTROLLER, LC-4577.

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 2 Simulator Operator CREW Raise power (NOTE: Insert Override NM02 at

Raise reactor power by 5%

approximately 1 minute intervals during CRS the power change)

Direct and observe reactivity manipulations to achieve a 5% raise in This will ensure that APRM GAFs will reactor power maintain constant through the power change. ATC (1C05)

Raises reactor power by 5% IAW IPOI 3 and OI 856.1 as follows:

o Monitor neutron monitoring instrumentation during control rod movements.

o Verifies the following indications:

If contacted as Booth Communicator

White backlight on the Rod Select pushbutton turns ON organization for

On the Full Core Display, the white XX-XX select light Respond as plant personnel and assistance: corresponding to the rod selected turns ON respond as necessary

On the Four Rod Group Display, the white SELECT light Prior to the next turns ON denoting the position display for the selected Booth Communicator rod.

event, if the BOP is in the Contact the control room as the Aux o Momentarily places the ROD MOVEMENT CONTROL in the vicinity of the Operator informing them that you are OUT-NOTCH position and verifies:

1C05 panel and doing outside-outs.

The green ROD IN light turns ON momentarily and then at the direction turns OFF of the floor instructor:

The red ROD OUT light turns ON after the green ROD IN light turns OFF.

The red ROD OUT light turns OFF

The amber ROD SETTLE light turns ON and then turns OFF

The rod has been withdrawn as indicated on the Four Rod Group Display Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 12 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 3 CREW FRV Failure

Respond to B FRV failure downscale CRS After the crew Simulator Operator

Establish critical parameter monitoring of RPV Water Level has raised Activate ET 7.

Direct entering AOP 644 power, reset the B FRV, This will activate FW12B for failure of B

May direct entering AOP 255.2 FRV and at the ATC (1C05) direction of the

Assuming manual control of a malfunctioning system Floor Instructor:

o B FEED REG VALVE MANUAL/AUTO TRANSFER HC-1621

Take manual control of the B Feedwater controller HC-1621 to restore reactor water level If contacted as Booth Communicator

May perform the following actions: (if entered AOP 255.2) organization for Respond as plant personnel and assistance: o Place one APRM recorder in each trip system to fast speed to respond as necessary monitor for APRM undamped oscillations greater than normal.

o Verify proper operation/indication of other systems and/or If contacted as Booth Communicator indications operators to Acknowledge communication inspect the B o Verify control rod positions are correct for the established FRV locally: sequence, by using Rod Position Log.

o Verify thermal limits on the Official 3D Case.

Two minutes o When power is stabilized, plot location on the Stability Power /

after being sent Booth Communicator Flow Map.

to investigate Inform control room that nothing B FRV: abnormal is seen at the FRV Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 13 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 4 Simulator Operator CREW Rod Drift Activate ET 13.

Respond to control rod 14-15 drifting in IAW ARP 1C05A (D-6).

This will activate RD011415 with will cause CRS control rod 14-15 to drift out.

Direct entering AOP 255.1 If contacted as

May direct (re-)entering AOP 255.2 organization for Booth Communicator

Notify the Reactor Engineer of the abnormal rod pattern.

assistance: Respond as plant personnel and respond as necessary

Comply with the Technical Specification requirements for Control Rod Operability LCO 3.1.3 Condition C ATC (1C05)

Two minutes Booth Communicator after contacted

Place the C11A-S3 EMERG IN/NOTCH OVERRIDE SELECT switch Inform control room that further as RE: on 1C05 in the EMERG ROD IN position momentarily to abort the rod analysis is required and will contact sequence timer.

control room when have more information

If any control rod still indicates movement, place and hold the C11A-S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position.

Two minutes Booth Communicator

Run an OFFICIAL 3D CASE for abnormal reactor power/control rod after sent to Inform control room that nothing distributions.

HCU: abnormal is seen at the HCU

Verify control rod positions are correct for the established sequence, by using Rod Position Log.

One minute Simulator Operator

When power is stabilized, plot location on the Stability Power / Flow after contacted DELETE MALF. RD011415 Map.

to isolate rod

When Rod motion has been stopped and/or position indication has AND 14-15: been restored clear the alarm by momentarily taking C11A-S7 Rod Booth Communicator Drift Alarm Reset/Test switch to RESET.

Inform the control room that time BOP compression has been used and that

Contact in-plant operator to close the Insert Isolation the Insert and Withdrawal Isolations for (V-18-1008) AND Withdrawal Isolation (V-18-1275) for Rod 14-15.

rod 14-15 are closed.

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 5 Simulator Operator CREW Loss of 1X3 Insert ET1

Implement actions of ARP 1C08A (A-7) Startup XFMR 1X3 Trouble.

This inserts AN1C08A(7), S/U Xfmr trouble CRS alarm.

Direct taking out 1X3 out of service per OI 304.2 (or OI 304.2 QRC)

When

Using OI 304.2 section TRANSFERRING ESSENTIAL BUS 1A3[4]

contacted to Booth Communicator FROM STARTUP TO STANDBY TRANSFORMER:

investigate 1X3 Acknowledge request.

If in Mode 1,2, or 3, verify the following Tech Spec conditions are alarm:

entered and exited:

Booth Communicator

T.S. 3.8.1 Condition A for Standby XFMR Offsite Circuit 2 min. after told to investigate Inform Control Room there is a Sudden

T.S. 3.8.1 Condition B for associated SBDG Internal Pressure Trip Alarm in and you

If the Startup XFMR Offsite Circuit is currently inoperable, then enter 1X3 alarm:

are leaving the area. and exit the following additional Tech Spec conditions:

T.S. 3.8.1 Condition C for both Offsite Circuits inoperable When

T.S. 3.8.1 Condition F (three AC sources inoperable)

Booth Communicator contacted as

T.S. 3.0.3 (per 3.8.1F)

ITC Midwest: Acknowledge notification.

Determine that the final Tech Spec determination:

T.S. 3.8.1 Condition A If contacted as

Notify ITC Midwest that the Startup Transformer (1X3) has been removed the Booth Communicator from service.

organization for Acknowledge request.

assistance:

Record the time ITC Midwest was notified that the Startup Transformer was removed from service in the Operating Log.

BOP (1C08)

Send an Operator locally to 1X3 Alarm Cubicle to determine the cause of the alarm.

With the aid of Table 1, take the appropriate Corrective Action.

Take 1X3 out of service per OI 304.1 and OI 304.2, (or OI 304.2 QRC)

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 5 BOP (1C08)

One minute

Using OI 304.2 QRC1:

after contacted Booth Communicator

Transfer 1A3 to the Standby Transformer by performing the following:

to verify switchgear Inform the control room that the

Place BUS 1A3 TRANSFER switch in MANUAL.

switchgear rooms are clear.

rooms clear:

Insert the handle in the SYNCHRONIZE switch for 4KV BREAKER 1A301 STANDBY TRANSFORMER TO BUS 1A3, and place in the ON position.

If/When contacted as Booth Communicator

Verify that the synchroscope indicates near 12 oclock and not organization: Acknowledge information/requests moving with both white (differential phase voltage) indicating lights OFF.

Place the control switch 4KV BREAKER 1A301 STNDBY TRANSFORMER TO BUS 1A3 momentarily to the CLOSE position.

Verify BUS 1A3 STANDBY AMPERES greater than zero amps.

Place the control switch 4KV BREAKER 1A302 STARTUP TRANSFORMER TO BUS 1A3 momentarily in the TRIP position.

Place the SYNCHRONIZE switch for 4KV BREAKER 1A301 STANDBY TRANSFORMER TO BUS 1A3 in the OFF position.

Place BUS 1A3 TRANSFER switch in AUTO.

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 5 BOP (1C08)

Using OI 304.2 QRC1:

Transfer 1A4 to the Standby Transformer by performing the following:

Place BUS 1A4 TRANSFER switch in MANUAL.

Insert the handle in the SYNCHRONIZE switch for 4KV BREAKER 1A401 STANDBY TRANSFORMER TO BUS 1A4, and place in the ON position.

Verify that the synchroscope indicates near 12 oclock and not moving with both white (differential phase voltage) indicating lights OFF.

Place the control switch 4KV BREAKER 1A401 STNDBY TRANSFORMER TO BUS 1A4 momentarily to the CLOSE position.

Verify BUS 1A4 STANDBY AMPERES greater than zero amps.

Place the control switch 4KV BREAKER 1A402 STARTUP TRANSFORMER TO BUS 1A4 momentarily in the TRIP position.

Place the SYNCHRONIZE switch for 4KV BREAKER 1A401 STANDBY TRANSFORMER TO BUS 1A4 in the OFF position.

Place BUS 1A4 TRANSFER switch in AUTO.

Remove Startup Transformer 1X3 from service by performing the following:

Place the STARTUP TRANSFORMER J BREAKER (OCB 5550) control switch momentarily in the TRIP position.

Place the STARTUP TRANSFORMER K BREAKER (OCB 5560) control switch momentarily in the TRIP position.

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 6 Simulator Operator CREW Insert ET 9

Respond to a coolant leak in containment.

This will start a drywell leak. CRS

Directs enter AOP 573 After the crew Simulator Operator BOP (1C03/1C24) takes HS-4310 Verify ET 15 goes ACTIVE

Monitor outside barometric pressure utilizing Computer Point M000 to to Auto Open: determine if weather conditions are causing a change in indicated This will increase the size of the leak leading the crew to scram. drywell pressure.

Verify RIM-9184A and RIM-9184B, NW and South Drywell Area Hi Range Rad Monitors, are reading less than 20R/hr.

Start one train of the Standby Gas Treatment System.

Position switches at 1C03 as follows:

o HS-4303 Outbd Drywell Vent Isol CV-4303 Auto Open o HS-4310 Inbd DW Vent Bypass Isol CV-4310 Auto Open o HS-4302 Inbd Drywell Vent Isol CV-4302 Auto Open Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 18 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 6 CREW

Implements EOP 1, RPV Control mitigation strategies.

CRS

Direct Crew Response to manually Insert a Scram Before Drywell Pressure reaches 2 psig.

Directs scramming the reactor and performing IPOI 5, Scram.

Directs RC/L band of 170-211 using the directed control system, RCIC.

Directs installation of Defeat 11 - Containment N2 Supply Isolation Defeat

Directs RC/P of 800-1055 psig using directed control system

Direct Crew Response to Establish a Cooldown of the RPV at a Rate of

<100F/hr ATC (1C05)

Prior to exceeding 2 psig Drywell Pressure, insert and perform Immediate Operator Responses to a Reactor Scram

Scrams the reactor and performs IPOI 5, Scram.

Restores and maintains RPV level 170-211 using directed control system.

Monitors and controls RPV pressure 800-1055 psig using directed control system.

BOP (1C35)

Installs Defeat 11 - Containment N2 Supply Isolation Defeat Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 19 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 6 CREW

Implements the mitigation strategies of EOP 2, Primary Containment After Drywell Simulator Operator Control Pressure Verify ET 5 AND 11 goes active CRS exceeds 2 psig:

Performs a crew update of entry into EOP 2 due to Drywell Pressure.

This will insert HP12 to trip the HPCI Aux Oil Pump and ED08C to Lockout Bus 1A3

Obtains containment parameters.

May direct installation of Defeat 4 - Drywell Cooler Isolation Defeat If contacted to Booth Communicator

Directs spraying the torus after confirmation that torus pressure is greater investigate 1P-Acknowledge request. than 2 psig.

218 breaker (1D41-13):

Directs spraying the drywell before drywell temperature reaches 280F.

(CRITICAL)

Two minutes Booth Communicator

Verifies torus water level less than 13.5 ft.

after sent to Inform control room that 1D41-13 HPCI

Verifies plot of drywell temperature and drywell pressure on the DWSIL investigate Aux. Oil Pump 1P218 is tripped and has curve allows drywell sprays.

1D41-13: an acrid odor, no smoke or fire.

Verifies recirculation pumps are secured.

Directs maximizing torus cooling.

If contacted to

Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in T/L (T/L-3 investigate 1A3 Booth Communicator and T/L 10), T/T (T/T-6), DW/T (DW/T-6) and PC/P (PC/P-7) legs Lockout: Acknowledge request.

Directs entering AOP 301 for Loss of 1A3 BOP (1C03/1C08/1C23)

Two minutes Booth Communicator after sent to

Installs Defeat 4 - Drywell Cooler Isolation Defeat 1A3: Inform control room that 1A3 has a

Utilizes OI 149 QRC to spray the torus.

ground fault indication.

Utilizes OI 149 QRC to spray the drywell.

Utilizes OI 149 QRC to establish torus cooling.

Place A SBDG in Pull-to-Lock Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 7 CREW ALC

Implements the mitigation strategies of the ALC contingency of EOP 1 CRS

Directs ADS lockout.

Directs RPV level bands as RPV level lowers

Directs maximizing injection with CRD in accordance with AIP 407.

Directs injection with SBLC in accordance with AIP 406.

Ensures injections subsystems can be lined up for injection.

Directs to close MSIVs at approximately 100 RPV Water Level

Waits for RPV level to drop to +15

Ensures at least one injection subsystem lined up with a pump running.

Before RPV level reaches -25 performs an Emergency Depressurization.

BOP (1C03)

Lockouts ADS.

ATC (1C05)

Attempts to restore and maintain RPV level above +15 o Maximizes injection with CRD in accordance with AIP 407.

o Injects with SBLC in accordance with AIP 406.

Shuts MSIVs Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 21 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 8/9 CREW Emergency

After RPV level reaches +15 enters and implements the mitigation Depress.: strategies of EOP ED. (CRITICAL)

Places handswitch of the first SRV to OPEN prior to RPV level reaching

-25 CRS

Direct Crew Response for performance of EOP 1 ALC and ED

Verifies all control rods inserted to at least position 00.

Verifies torus water level above 4.5 feet

Direct Crew Response to Perform an Emergency Depressurization Using SRVs

Directs opening 4 ADS SRVs ATC (1C03)

Perform an Emergency Depressurization Using SRVs.

Open 4 ADS SRVs BOP (1C03)

Recognizes MO-1905 does not automatically open at 450 psig and takes action at 1C03 to open MO-1905. (CRITICAL)

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG EVENT 8 CREW EOP 1

Implements mitigation strategies of EOP 1 after EOP ED to restore Implementation adequate core cooling after EOP ED: CRS

Verifies 1 Core Spray pumps and 1 other ECCS pump available for injection

Direct Crew Response to Maximize Injection with Table 2 Systems

Direct to maximize injection with all available Preferred Injection Systems (Table 1A) and Alternate Injection Systems (Table 2A).

Determines RPV level can be restored and maintained above +15 and returns to the normal RPV level control leg of EOP 1

Directs restoring and maintaining RPV level 170-211 using low pressure ECCS systems BOP (1C03)

Verifies low pressure ECCS system (B & D RHR Pumps) start and align to inject into the RPV

Reports 1 Core Spray pumps is injecting and 1 other ECCS pump is injecting.

Throttles RHR injection after level has been restored to 90 on Yarway level indication to restore and maintain RPV level 170-211 When RPV Simulator Operator level is being Place the simulator in FREEZE.

restored and at the direction of the Floor Floor Instructor Instructor: Announce the scenario is complete; please stand by your stations and do not discuss the scenario with your crew.

- - END OF SCENARIO ***

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. B FRV fail downscale

2. Control Rod Drift

3. S/U Xfmr Sudden Internal Pressure Trip After EOP Entry:

1. HPCI Trip on Startup

2. Loss of 1A3 Abnormal Events:

1. AOP 644

2. AOP 255.1 Major Transients:

1. LOCA in DW

2. ALC

3. ED Critical Tasks:

1. #22: BEFORE drywell temperature reaches 280°F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. {BWROG: N/A}

2. #1: IF the reactor is shutdown under all conditions and RPV level drops to +15, THEN perform Emergency RPV Depressurization before RPV level reaches -25".

{BWROG: RPV 1.1}

3. #2: IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. {BWROG: RPV 1.2}

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NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG CREW GRADING ATTACHMENT ESG ___1_____ Rev. ___0___ Date ________________

Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P.

Management Representative/Lead Evaluator ______________/________________

Crew Critical Tasks Task Statement SAT UNSAT

1. BEFORE drywell temperature reaches 280°F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays.

2. IF the reactor is shutdown under all conditions and RPV level drops to

+15, THEN perform Emergency RPV Depressurization before RPV level reaches -25".

3. IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling.

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SIMULATOR EXERCISE GUIDE SEG SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG 204 LMS Rev. Date: N/A SEG TITLE: NRC INITIAL LICENSE EXAM, SCENARIO #2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~90 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal This Evaluation Scenario Guide evaluates the Operators ability to:

Objective: Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Evaluation Guide, no tasks are trained. Evaluated tasks are listed on page 3.

Objectives:

Prerequisites: None Training A. Simulator Resources: B. Evaluation team C. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G. Simulator Video recording equipment

References:

A. OI 644, Rev. 172 B. IPOI 2, Rev. 154 C. OI 264, Rev. 138 D. OI 856.1, Rev. 48 E. OI 856.2, Rev. 9 F. OI 878.8, Rev. 27 G. AOP 255.1, Rev. 46 H. ARP 1C03A, Rev. 58 I. ARP 1C04B, Rev. 81 J. ARP 1C08A, Rev. 92 K. EOP 3, Rev. 22 L. EOP Defeat 11, Rev. 5 M. ARP 1C05B, Rev. 105 N. EOP 1, Rev. 20 O. ATWS, Rev. 23 P. OI 644 QRC 2, Rev. 0 Q. OI 149 QRC 4, Rev. 0 R. OI 734 QRC 1, Rev. 0 S. OI 153 QRC 1, Rev. 4 Protected Content: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 8.11 Manually Delay or Interrupt ADS Auto Initiation 95.21 Perform EOP Defeat 11 95.42 Inject into the RPV with SBLC from the Boron Tank 95.45 Perform Initial EOP 1 Actions 95.50 Perform /L to Control RPV Level during an ATWS 95.51 Perform Power/Level Control 95.55 Perform Initial ATWS Actions 95.56 Perform /P to Control RPV Pressure During an ATWS 95.57 Perform /Q to Reduced Reactor Power or SCRAM the Reactor Senior Reactor Operator 1.02 Determine Operability for Technical Specification Required Components 6.21 Direct Crew Response to Perform EOP Defeat 11 6.42 Direct Crew Response to Inject into the RPV with SBLC from the Boron Tank 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.50 Direct Crew Response to Perform /L to Control Level During an ATWS 6.51 Direct Crew Response to Perform Power/Level Control 6.55 Direct Crew Response to Perform Initial ATWS Actions 6.56 Direct Crew Response to perform /Q to reduce power/scram the reactor during ATWS 6.57 Direct Crew Response to perform /P to control RPV pressure during an ATWS UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Initial development for See Cover Initial development for 2017 Rev. 0 2017 NRC LOIT N/A NRC LOIT Examination See Cover Examination Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description The crew will assume the shift at approximately at 10% Reactor power with applicable portions of IPOI 2 completed. A CRD pump is OOS due to gearbox inspection.

1. The crew will be briefed as to the need to withdraw rods through step 17 (approximately 11% reactor power).

2. The crew will transfer from the Startup FRV to the A FRV, and then continue with the power ascension.

3. The crew will attempt to continue the power rise when a loss of notch indication for rod 26-19 and an entry into AOP 255.1. The crew will confer with RE and will substitute the rod position IAW OI 878.8 Section 8.2

4. Following the AOP entry, Annunciator RE-4116B OFFGAS VENT PIPE B DNSC/INOP due to an Electrical Fault. The crew will determine LCO 3.3.6.1 for Function 2c - Offgas Vent Stack - High Radiation - Channel B does not need be entered since not in the mode of applicability.

5. A grid voltage transient causes A SBDG to spuriously start, and the Voltage Regulator fails to maintain voltage. The crew will place the A SBDG handswitch to PTL, declare the A SBDG inoperable, and enter LCO 3.8.1, Condition B and LCO 3.7.3 Condition A.

6. A steam leak in the Steam Tunnel causing an entry into EOP 3.

7. The crew will attempt to insert a manual scram and discover an Electrical ATWS. The B CRD pump will trip shortly after due to high vibrations. Temperatures will continue to rise during the ATWS and cause Group 1 isolation.

The crew will lock out ADS (CRITICAL), perform the Electrical ATWS RIPs, and attempt to inject with SBLC only to discover that the inject valve is stuck and SBLC injection is not available.

The crew will transition to power level control and Terminate and Prevent injection.

(CRITICAL) and establish a level band until all rods are inserted. (CRITICAL)

Performance of Electrical RIPs (RPS Fuses) will insert rods to shutdown the Reactor.

(CRITICAL)

8. The crew will notice that RCIC failed to start and start RCIC manually.

After all rods are verified to be fully inserted, the crew will transition from EOP ATWS back to EOP 1 and establish an RPV level band of 170 -211 the scenario will be over.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Facility: Duane Arnold Energy Center Scenario No.: _____2___ Op-Test No.: 17-1 Examiners: Chuck Zoia Operators: SRO-U (2), SRO-I (7), RO (3)

Mike Bielby _____________________________

Randy Baker _____________________________

Initial Conditions/Turnover:

The crew will assume the shift at approximately at 10% Reactor power with applicable portions of IPOI 2 completed. A CRD pump is OOS due to gearbox inspection. The crew will be briefed as to the need to withdraw rods through step 17 (approximately 11% reactor power), transfer from the Startup FRV to the A FRV, and then continue with the power ascension.

Event Malf. Event Event No. No. Type* Description R ATC 1 Pull Control Rods to achieve 10-12% Reactor power R SRO N ATC Transfer Reactor Feed from the Startup Feed Regulating Valve to 2

the A Feed Regulating Valve N SRO I ATC RD04A1 3 Control Rod Position lost entry to AOP 255.1 827 I SRO RM03R RE-4116B Inoperable due to electrical power supply fault 4 TS SRO E4116B Tech Spec Inoperable (3.3.6.1 Function 2C)

C BOP A SBDG Start with erratic Voltage Control DG07A, 5

DG05A TS SRO Tech Spec Entry (3.8.1 Condition B / 3.7.3 Condition A)

Steam Leak in the Steam Tunnel (SCRAM prior to Automatic 6 MS04A M ALL Group 1 isolation) a)M ALL Electrical ATWS (Pulling RPS Fuses is successful)

RP05A,B 7a,b,c b)I BOP RPS Trip Test Switches Failure

,C,D c)I BOP Individual Scram Test Switches Failure C ATC 8 STRC01 RCIC Failure to Auto Start C SRO Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS

1. Set NRC Exam Security for the Simulator per QF-1071-08

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist.

3. Load the saved IC (in folder with this ESG) to a SNAPSHOT ______ reset to that SNAPSHOT and place the Simulator in RUN, OR

4. Reset to IC 184, place the simulator in RUN and perform the following:

a. Insert Event Triggers, Malfunctions, Overrides, and Remotes per the tables below

b. Using MOL pull sheets insert control rods to achieve approximately 8% reactor power

c. Using InSight bring up ypfastxen and set to -1.0000 three times to burn out Xenon

d. Pull rods as necessary to achieve approximately 8% reactor power after the Xenon burn.

e. Place Mode Selector switch to the RUN position.

5. RUN Schedule File Actions.sch and LEAVE IT RUNNING.

6. Verify Malfunctions.

7. Verify Remotes (Note that environmental remotes will already be timing)

8. Verify Overrides.

9. Ensure MOL pull sheet is in the 1C05B hanging file.

10. Establish EOOS conditions for OOS components and plant conditions

11. Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

a. Place Guarded system tags on B CRD pump

b. Place MIP tag on A CRD pump

12. Plant procedures being worked at time of scenario initiation including what steps are completed.

a. Remove CRAM group sheets from 1C05

b. OI 856.1 Section 4.1.5 (1) Place keep the following steps as complete:

a) All Notes and Steps 1-7 (2) Place keep the following steps as in progress:

a) Steps 8-9

c. Place OI 856.2 on desk open to Section 4.1

d. IPOI 2 section 4.3 (1) Place keep the following steps as complete:

a) All Notes, CRSs, and Cautions up to step 20 b) Steps 1-11a, 12-17, 19-20 (2) Place keep the following steps as in progress:

a) Steps 11b & c

e. Rod sequence sheets (1) Place keep rods as out up to and including Step 16.

f. Mark Power/Flow Map as necessary

g. Place ROD OUT placard on 1C05

h. Have DR up on one turret Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 1,3,5,17 MANUALLY ACTIVATED MANUALLY ACTIVATED 9 ZDIHVHS6514 == 1 HS-6514 RX BLDG SUPPLY FAN 1V-SF-10C to START 11 RPDIS1RUN(1) != 1 Reactor Mode Switch out of RUN MALFUNCTIONS:

Initial Final Time Malf. No. Malfunction Title ET Delay Ramp Value Value Setup MS18A VALVE CV1158A/B FAILURE - CV1158A 100 100 Setup MS18B VALVE CV1158A/B FAILURE - CV1158B 100 100 RPS SCRAM CIRCUIT FAILURE (ATWS)- AUTO Setup RP05A ACTIVE ACTIVE SCRAM FAILURE RPS SCRAM CIRCUIT FAILURE (ATWS)- MANUAL Setup RP05B ACTIVE ACTIVE SCRAM FAILURE Setup RP05C RPS SCRAM CIRCUIT FAILURE (ATWS)- ARI FAILURE ACTIVE ACTIVE Setup STRC01 TRIP OVRD- RCIC FAILS TO AUTO START ACTIVE ACTIVE Setup RM03RE4116B RE-4116B OFFGAS VENT PIPE B 1 3 SEC INACTIVE ACTIVE 1C03A (B-04) OFFGAS VENT PIPE RM-4116 A/B HI Setup AN1C03A(13) 1 3 SEC CRYWOLF CRYWOLF RAD 1G31 'A' DIESEL GENERATOR SPURIOUS START- DG Setup DG07A 3 INACTIVE ACTIVE A

Setup MS08A STEAM LEAKAGE IN STEAM TUNNEL LINE A 5 6:00 0 0.35 Setup RP05E ALL INDIVIDUAL ROD SCRAM SWITCHES FAIL ACTIVE ACTIVE Setup RD11A CRD HYDRAULIC PUMP TRIP - PUMP A ACTIVE ACTIVE Setup RD26B CRD PUMP B HIGH VIBRATION 11 1:00 INACTIVE ACTIVE Setup RD11B CRD HYDRAULIC PUMP TRIP - PUMP B 11 1:30 INACTIVE ACTIVE Setup SL04 SBLC INJECT VALVE V-26-9 STUCK 0 0 Setup RD04A2619 CR RPIS REED SW FAILURE OPEN- ROD 26-19 8 8 1G31 'A' DIESEL GENERATOR V/R OSCILLATES IN 30 Setup DG05A 3 5 SEC 0 100 AUTO- DG A SEC POWER GRID FREQUENCY DISTURBANCE Setup ED02 3 0 45 (DELETE in 1 SEC)

POWER GRID VOLTAGE TRANSIENT Setup ED03 3 50 45 (DELETE in 1 SEC)

REMOTES:

Initial Final Time Remote No. Remote Title ET Delay Ramp Value Value Setup MC01 MN COND 1E-7A VACUUM BREAKER V-03-73 17 02:00 CLOSED OPEN Setup MC02 MN COND 1E-7B VACUUM BREAKER V-03-67 17 02:30 CLOSED OPEN Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG OVERRIDES:

Initial Final Time Remote No. Remote Title ET Delay Ramp Value Value HS-1807A(1) CRD PUMP 1807 BREAKER Setup DO-RD-615 OFF OFF TRIPPED (GREEN)

HS-1807A(2) CRD PUMP 1807 BREAKER Setup DO-RD-616 OFF OFF TRIPPED (WHITE)

HS-1807A(3) CRD PUMP 1807 BREAKER Setup DO-RD-617 OFF OFF TRIPPED (RED)

Setup DI-RD-187 HS-1807A CRD PUMP 1P-209A OFF OFF SCHEDULE FILES:

Actions.sch

@ Time Event Action Description 9 Modify malfunction ms08a to 0.6 in 300 Conduct simulator crew pre-scenario brief using TR-AA--230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SHIFT TURNOVER INFORMATION

Today, Day Shift

Warm summer afternoon temperatures in the mid 70s

Plant power - ~10% with the corresponding MWth and core flow.

Protected Train - A

Procedures or major maintenance in progress:

o IPOI 2 startup in progress o A CRD Pump OOS, gearbox open for inspection Approximate time for restoration is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

Technical Specification Action statements in effect:

o DAEC is in compliance with all LCOs

Plant PRA Status o CDF: 1.29 x 10-6, GREEN, 1 year to Yellow ICDP o LERF 3.05 x 10-7, GREEN, 1 year to Yellow ILERP

Evolutions in progress or planned for upcoming shift:

o Continue to raise power IAW with IPOI 2 to complete step 17 this will achieve a reactor power approximately 11%;

o The ATC operator shall transfer feed control from the Startup FRV to the A FRV IAW OI 644 Section 3.6 o Continue to raise power IAW IPOI 2

Comments, problems, operator workarounds, etc.

o NSPEOs available for the shift include:

Aux Operator and Second Assistant One extra NSPEO available in Work Control Radwaste Operator Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 Simulator Operator CREW (NOTE: Insert Override NM02 at

Withdraw control rods IAW IPOI 2 and OI 856.1 to complete step 17 IPOI 2 approximately 1 minute intervals during the power change) CRS This will ensure that APRM GAFs will

Direct and observe reactivity manipulations to achieve step 17 maintain constant through the power complete change. ATC (1C05)

When reactor power reaches approximately 10% power on APRMs or as desired by the CRS/OSM o Monitor neutron monitoring instrumentation during control rod movements.

o Verifies the following indications:

White backlight on the Rod Select pushbutton turns ON

On the Full Core Display, the white XX-XX select light corresponding to the rod selected turns ON

On the Four Rod Group Display, the white SELECT light turns ON denoting the position display for the selected rod.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 ATC (1C05) Cont.

o Momentarily places the ROD MOVEMENT CONTROL in the Raise Power OUT-NOTCH position and verifies:

Cont.

The green ROD IN light turns ON momentarily and then turns OFF

The red ROD OUT light turns ON after the green ROD IN light turns OFF.

The red ROD OUT light turns OFF

The amber ROD SETTLE light turns ON and then turns OFF

The rod has been withdrawn as indicated on the Four Rod Group Display

Continue to raise power with control rod withdrawal until one bypass valve is open and the second bypass valve is approximately 25%

open.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2 CREW

Shift FRV from the S/U FRV to the A FRV Shift FRV from Booth Communicator CRS S/U to A Acknowledge coordination

Coordinate shifting feed flow control from the STARTUP FEED REG OI 644 VALVE to A FEED REG VALVE.

ATC (1C05)

IF called as any Booth Communicator

Shift feed flow control from the STARTUP FEED REG VALVE to A DAEC support Acknowledge communication FEED REG VALVE as follows:

personnel: o Verify the MASTER FEED REG VALVE CONTROLLER, LC-4577, is in AUTO and select V with the D pushbutton on the display.

o Verify the STARTUP FEED REG VALVE CONTROLLER, If/when Booth Communicator HC-1622, is in AUTO.

contacted for Instruct operator to continue the power o Verify the A FEED REG VALVE CONTROLLER HC-1579 is guidance after ascension. in MANUAL.

FRV transfer: o Select V on the display for the A FEED REG VALVE CONTROLLER, HC-1579.

o Slowly open A FEED REG VALVE CV-1579 using the potentiometer on HC-1579.

o Monitor reactor water level closely and confirm auto operation of FEEDWATER STARTUP FEED REG VALVE CV-1622.

o When the display on CV-1579 is matching the display on LC-4577, select AUTO on HC-1579.

o Select MANUAL on STARTUP FEED REG VALVE CONTROLLER HC-1622.

o Slowly close STARTUP FEED REG VALVE CV-1622 using the potentiometer on HC-1622.

o Monitor reactor water level closely and verify auto operation of A FEED REG VALVE CV-1579.

o Close MO-1631, Startup Feedline Block.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3 CREW Control Rod

Perform the Follow Up Actions of AOP 255.1 for Abnormal Rod Position Lost EVALUATOR NOTE: Control and Position Indications AOP 255.1 AOP 255.1 and OI 878.8 are to be given to CRS the ATC operator. In the event that the

Direct the performance of AOP 255.1 for Abnormal Rod Control and CRS proceeds to give these to the BOP, Position Indications prompt the CRS to give these to the ATC

Consult with Reactor Engineer to enter Substitute Rod Position into 3D Monicore per REDP7 Section 3.7, Substituting Rod Positions In 3D Monicore.

ATC (1C05)

For rod position indication lost at one notch:

IF called as any Booth Communicator o Attempt to move the affected rod out, as allowed by rod DAEC support Acknowledge communication sequence, to an adjacent notch to check for reed switch personnel: failure o Consult with CRS/OSM and Reactor Engineer to modify rod pattern if necessary to avoid leaving the control rod at the If contacted as Booth Communicator notch with no position indication RE for Acknowledge communication substituting position for rod 26-19:

Two minutes Booth Communicator after contacted Report to the control room that you as RE: concur with substituting rod position for rod 26-19 and to continue with startup.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3 CREW Position

Substitute notch position IAW OI 878.8 Section 8.2 Substitution CRS 878.8

Direct substituting notch position for rod 26-19

Direct rod 26-19 insertion to position 08 ATC (1C05)

At 1C05, verify the Rod Worth Minimizer (RWM-OD) keylock mode switch is in the OPERATE position.

At 1C05 (RWM-OD), press the ETC soft-key until the SUBSTITUTE OPTIONS menu choice becomes available.

Press the appropriate soft-key.

Press the INCREMENT POSITION soft-key to select the desired position.

Independently verify desired position on RWM Display

Press the ENTER SUBSTITUTE soft-key.

Verify screen display.

Press the EXIT soft-key

Insert rod 26-19 to position 08 BOP (1C28)

At 1C28, verify the Rod Worth Minimizer (RWM-CC) keylock MODE switch in the OPER position.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4 CREW Offgas Vent

Respond to annunciators per ARP 1C03A (C-4)

Pipe RM CRS Downscale

Determine affected Tech Spec TS LCO 3.3.6.1 Condition A o Function 2c Offgas Vent Stack - High Radiation - Channel B After crew has Simulator Operator: o Determine NOT in mode of applicability substituted the BOP (1C03/1C10)

ACTIVATE ET 1 rod postion

At 1C10, monitor OFFGAS STACK VENT PIPE B RAD MONITOR and/or when This causes RE-4116B OFFGAS VENT RM-4116B to determine if DOWNSCALE or INOPERATIVE.\

directed by the PIPE B to fail.

Send an Operator to the following panels to verify the breakers Floor Instructor: closed/reset:

o RM4116B - 1D60 Breaker 03 If contacted to Booth Communicator:

investigate 1D60: After 2 minutes, inform control room that Breaker 03 for 1D60 is closed in with no noticeable problems.

IF called as any Booth Communicator:

DAEC support personnel: Acknowledge Communication Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 15 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5 Simulator Operator: CREW ACTIVATE ET 3

Respond to annunciators per ARP 1C08A (A-10)

CRS This causes a momentary grid

Determine affected Tech Spec LCO 3.8.1 Condition B and 3.7.3 disturbance. A SBDG will spuriously start Condition A and its voltage regulator fail.

Request STP 3.8.1-01 and/or STP 3.8.1-02 BOP (1C08)

Booth Communicator:

If contacted to

Verify that EMERG SERV WATER PUMP 1P-99A is running.

investigate A

Verify 1V-SF-20 Diesel Generator Supply Fan is running.

SBDG: Acknowledge Request

If A SBDG 1G-31 was not started for testing and is no longer Booth Communicator: required for operation, shut down A SBDG 1G-31 per OI 324 Three minutes (Standby Diesel Generator System).

after requested Inform control room that A SBDG o Place A SBDG handswitch HS-3231A in PTL to investigate appears to be normal and all alarms at A SBDG: 1C93 are as expected.

If contacted to Booth Communicator:

verify operation of A ESW: Acknowledge Request Two minutes Booth Communicator:

after requested to verify Inform control room that A ESW is operation A operating SAT.

ESW:

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6 CREW EOP 3

Respond to annunciators per ARP 1C04B (B-4), STEAM LEAK DET Steam Leak in AMBIENT HI TEMP/EOP 3.

Steam Tunnel CRS After SBDG TS Simulator Operator:

Direct Crew Response for performance of EOP 3 for high area has been temperatures level including EOP 1 ACTIVATE ET 5 declared and/or o Direct Main Plant Supply and Exhaust Fans in a 3-2-3 lineup at the direction This will insert MS08A to start the Steam of the Floor Tunnel steam leak. o Determines RPV pressure reduction will lessen the leakage Instructor: rate.

(NOTE: Bring up EOPSLD and monitor

Before steam tunnel temperature reaches the Group 1 setpoint enter Steam Tunnel Temperature) EOP 1 and direct inserting manual reactor scram.

After 1V-SF- Simulator Operator:

10C is taken to VERIFY ET 9 ACTIVATES start:

This will modify ms08a to 0.6 to worsen the steam tunnel leak.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6 BOP (1C21/1C23)

EOP 3 Cont.:

Go to 1C21 to determine which area has the high temperature condition.

Start 1V-EF-1, 1V-EF-2, and 1V-EF-3 MAIN PLANT EXHAUST FANS by positioning the following handswitches to START and verify their respective dampers indicate OPEN:

o Fan Handswitch Panel Damper o 1V-EF-1 HS-7613 1C23A 1V-AD-16U o 1V-EF-2 HS-7614 1C23B 1V-AD-16V o 1V-EF-3 HS-7615 1C23C 1V-AD-16W o Start the Reactor Building Exhaust Fans by positioning the following handswitches to START:

o Fan Handswitch Panel o 1V-EF-11A HS-7611A 1C23A o 1V-EF-11B HS-7611B 1C23B o Start the Reactor Building Supply Fans by positioning the following handswitches to START:

o Fan Handswitch Panel o 1V-SF-10A HS-6512 1C23A o 1V-SF-10B HS-6513 1C23B o 1V-SF-10C HS-6514 1C23C Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 18 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A CREW EOP 1

Implements the mitigation strategies of EOP 1 and EOP ATWS Transition to CRS ATWS

Enters EOP 1, RPV Control based on reactor power is above 5% or unknown after a scram signal is received.

Determines that a reactor scram has been initiated When the Simulator Operator:

Validates isolations, initiations and SBDG initiations that should have MODE switch is VERIFY ET 11 ACTIVATES occurred but did not.

taken out of run: This will cause B CRD pump HI Vibes

Recognizes and implements the CRS IF any rod is withdrawn past followed by B CRD pump trip position AND it has NOT been determined that the reactor will remain shutdown under all conditions without boron THEN exit this procedure and enter ATWS.

ATC (1C05)

Inserts a manual reactor scram.

Reports the B CRD pump high vibes and trip

Recognizes an electrical ATWS has occurred and reports the type of ATWS and reactor power.

Places the master Feedwater level controller to 158.5 in AUTO.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A CREW ATWS

Implements the mitigation strategies of EOP 1 and EOP ATWS CRS

Directs locking out ADS.

Verifies at least one set of inboard and outboard MSIVs are not open.

If directed to

Directs performance of the ATWS QRC Booth Communicator:

vent the scram

Directs installation of Defeat 11- Containment N2 Supply Isolation air header: Acknowledge the request.

Defeat

Directs initiation of SBLC.

Directs electrical ATWS rod insertion procedures Two (2) minutes

Exits the ATWS Q leg flowpath and enters L leg actions after being Booth Communicator: ATC (1C05) directed to vent Inform the control room that you

Performs the ATWS QRC.

the scram air cannot vent the scram air header due to

Reports completion of the ATWS QRC. Determines that ARI was header: the valve being bound. unsuccessful. Reports RPV level and reactor power.

Announces failure to scram.

Reports SBLC inject pressure high and no flow.

Reports Group 1 isolation.

BOP (1C03/1C35)

Locks out ADS (CRITICAL)

Installs Defeat 11 - Containment N2 Supply Isolation Defeat Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A/8 CREW ATWS

Implements AOP ATWS power level control actions.

CRS

Directs terminating and preventing injection from CS, RHR and Condensate and Feedwater.

Directs starting RCIC manually

Directs reporting reactor power at 87 and lowering.

Directs continuing to lower RPV level until conditions allow for reinjection.

ATC (1C05/1C04)

Terminates injection: (CRITICAL) o Condensate and Feed:

Close Feedwater Regulating Valves CV-1579, CV-1621, CV-1622 as follows:

o Take MANUAL control of Master Fed Reg Valve Auto/Man Control LC-4577 and dial the controller down until all Feedwater Regulating Valves indicate closed as indicated on:

HC-1579, A Feed Reg Valve Manual/Auto Transfer HC-1621, B Feed Reg Valve Manual/Auto Transfer HC-1622, Startup Feed Reg Valve Manual/Auto Transfer EVALUATOR NOTE:

Recognizes that RCIC did not start automatically and start manually.

Ensure that while level is lowering that the

Reports reactor power when RPV level reaches 87 and lowering.

RO acknowledges RCIC failure to auto

Uses available injection sources to re-inject to desired band.

start and recommends starting RCIC.

BOP (1C03)

Verifies or trip/lockout HPCI. (CRITICAL)

RHR: (CRITICAL) o Place MO-2004 and/or MO-1904 LPCI OPEN INTLK OVERRIDE HS-2004C and/or HS-1904C to OVERRIDE o When 1C03B (B-5) RHR RX LO PRESSURE PERMISSIVE AT 450 PSIG is activated, close MO-2004[MO-1904] by taking HS-2004[HS-1904] to CLOSE Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 21 of 25

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A/B/C CREW ATWS

When all rods are in, transition from ATWS to EOP 1 CRS

Directs securing SBLC injection

Directs transition back to EOP 1

Directs RPV level restoration using Condensate and Feedwater.

Directs Pressure Control using SRVs ATC (1C05)

Reports all rods in

Secures SBLC injection

Restores RPV water level using Condensate and Feedwater (CRITICAL)

BOP (Backpanel Area/1C05)

Reports all RIPs failed to insert rods with exception of RPS Fuses removal. (CRITICAL)

IF directed to Simulator Operator:

break Main Condenser Acknowledge the direction, then Vacuum:

ACTIVATE ET 17 This inserts remote functions mc01 and mc02.

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew Simulator Operator has inserted all Place the simulator in FREEZE.

control rods, is restoring RPV Water Level Floor Instructor and at the Announce the scenario is complete; direction of the please stand by your stations and do Floor Instructor: not discuss the scenario with your crew.

- - END OF SCENARIO ***

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Loss of notch indication

2. RE-4116B Offgas Vent Pipe B Failed Downscale

3. A SBDG 1G-21 Spurious Start After EOP Entry:

1. RCIC Fails to Auto Start

2. B CRD Pump Trip

3. SBLC fails to inject Abnormal Events:

1. AOP 255.1

2. ARP 1C08A Major Transients:

1. EOP 3 Steam Tunnel Leak

2. Electrical ATWS Critical Task

1. #4: IF a scram is required and reactor power is above 5%, THEN reduce power below 5%

using one or more of the following methods: {BWROG RPV 4.1, 5.1, 6.1}

Inserting control rods using RIPs

2. #6: IF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation. {BWROG RPV 4.2, 5.2, 6.2}

3. #10: IF a reactor scram is required, and reactor power is >5%, and Power/Level Control is required, THEN terminate and prevent injection until conditions allow reinjection.

{BWROG RPV 6.3}

4. #7: IF performing ATWS Power/Level Control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. {BWROG RPV 5.5}

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NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG CREW GRADING ATTACHMENT ESG ___2_____ Rev. ___0___ Date ________________

Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P.

Management Representative/Lead Evaluator ______________/________________

Crew Critical Tasks Task Statement SAT UNSAT

1. IF a scram is required and reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods:

Inserting control rods using RIPs

2. IF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation.

3. IF a reactor scram is required, and reactor power is >5%, and Power/Level Control is required, THEN terminate and prevent injection until conditions allow reinjection.

4. IF performing ATWS Power/Level Control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems.

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SIMULATOR EXERCISE GUIDE SEG SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG 206 LMS Rev. Date: N/A SEG TITLE: NRC INITIAL LICENSE EXAM, SCENARIO #ALT SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~90 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal This Evaluation Scenario Guide evaluates the Operators ability to:

Objective: Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Evaluation Guide, no tasks are trained. Evaluated tasks are listed on page 3.

Objectives:

Prerequisites: Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator- Certification Training Training A. Simulator Resources: B. Evaluation team C. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G. Simulator Video recording equipment

References:

A. OI 693.2, Rev. 51 B. AOP 646 Rev. 23 C. AOP 255.2 Rev. 43 D. AOP 264 Rev. 14 E. AOP 573 Rev. 6 F. EOP 2 Rev. 18 G. EOP 1 Rev. 20 H. ATWS Rev. 23 I. ED Rev. 11 J. ATWS Rev. 23 K. IPOI 4 Rev. 133 L. IPOI 3 Rev. 152 M. ARP 1C04B Rev. 81 N. ARP 1C04A Rev. 62 O. ARP 1C05A Rev. 82 P. OP-AA-102-1003 Rev. 11 Q. OI 644 QRC 2, Rev. 0 R. OI 149 QRC 4, Rev. 0 S. OI 153 QRC 1, Rev. 4 Protected Content: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 1.04 Respond to Annunciators 10.03 Alternate CRD Pumps 72.02 Insert Control Rods using Single Notch 93.22 Perform the Immediate Operator Responses to a Reactor Scram 94.03 Respond to Power/Reactivity Abnormal Change Condition.

94.19 Respond to Loss of Feedwater Heating Condition.

94.53 Respond to Primary Containment Control Abnormal Situation 94.58 Respond to Loss of Reactor Recirculation Pump(s) 95.00 Respond to Emergency Situations 95.21 Perform EOP Defeat 11.

95.25 Perform Defeat 15 95.44 Perform actions of RC/L of EOP 1 95.45 Perform initial EOP 1 actions (RC) 95.46 Perform actions of RC/P of EOP 1 95.50 Perform /L to Control RPV Level during an ATWS.

95.52 Control RPV Injections prior to, during, and subsequent to ED during ATWS.

95.55 Perform initial ATWS actions (/).

95.56 Perform /P to Control RPV Pressure During an ATWS.

95.57 Perform /Q to Reduce Reactor Power or Scram the Reactor.

95.63 Perform DW/T leg of EOP 2 95.64 Perform PC/P leg of EOP 2 Senior Reactor Operator 1.02 Determine operability for TS required components 4.21 Direct Crew Actions to Perform the Immediate Operator Responses to a Reactor Scram 5.03 Direct Crew Responses to Power/Reactivity Abnormal Change Condition 5.19 Direct Crew Response to Loss of Feedwater Heating Condition 5.53 Direct Crew response to a Primary Containment Control Abnormal Situation 5.58 Direct Crew response to Loss of Reactor Recirculation Pump(s) 6.21 Direct Crew Response to Perform EOP Defeat 11 6.25 Direct Crew Response for performance of Defeat 15 6.44 Direct Crew Response for performance of the RC/L leg of EOP 1 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.46 Direct Crew Response for performance of RC/P leg of EOP 1 6.50 Direct Crew Response to Perform /L to Control Level During an ATWS 6.52 Direct Crew Response to Control RPV Injection prior to, during and subsequent to Emergency Depressurization during ATWS 6.55 Direct Crew Response to Perform Initial ATWS Actions (/)

6.56 Direct Crew Response to perform /Q to reduce power/scram the reactor during ATWS 6.57 Direct Crew Response to perform /P to control RPV pressure during an ATWS 6.63 Direct Crew Response for performance of the DW/T leg of EOP 2 6.64 Direct Crew Response for performance of the PC/P leg of EOP 2 Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev. 0 Initial development for 2017 Initial development for N/A See Cover NRC LOIT Examination 2017 NRC LOIT See Cover Examination Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description When the crew assumes the shift reactor power is approximately 100%. The B RHR Pump is inoperable due to breaker refurbishment; return time is approximately three days. After crew turnover, maintenance has requested immediately swapping running EHC pumps.

1. The crew will swap running EHC pumps IAW OI 693.2 Section 6.2.

2. Once the EHC pump swap is completed, the B Recirc Pump will experience a 20%

runback. The crew will check Recirc pump limits of OI 264; the crew may enter Tech Spec LCO 3.4.1 Condition C.

3. The B Recirc Pump will experience erratic parameters and will trip and the crew will enter Tech Spec LCO 3.4.1 Condition D.

4. The crew will lower power IAW IPOI 3 and OI 255.2.

5. Then the B CRD pump will trip on overcurrent and three CRD accumulators alarm on low pressure. Permission is given to start standby pump IAW OI 255. After the A CRD Pump is returned to service the CRD Accumulators remain in alarm on low pressure. The crew will enter LCO 3.1.5 Condition A (3 times) and B.

6. A small leak in the drywell and rising drywell pressure. As temperature rises in the Drywell, the crew will insert a manual scram prior to Drywell temperature reaching 280F.

7. The crew will determine that there is a hydraulic ATWS and transition to EOP ATWS. The crew will lockout ADS (CRITICAL), perform the ATWS QRC, inject SBLC, Terminate and Prevent injection (CRITICAL) and establish a level band until all rods are inserted (CRITICAL), and insert the control rods with the RIPS. (CRITICAL)

8. As Primary Containment pressures and temperatures rise HS-1903C, B Enable Containment Spray Valves, will not function.

9. MO-2000, A INBD DRYWELL SPRAY, will not open causing Drywell temperature to rise past 280F. MO-2000, A INBD DRYWELL SPRAY, will be able to be opened through manual operations if an individual is sent to open the valve.

The scenario may be terminated after all rods are in and RPV level is being restored Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Facility: Duane Arnold Energy Center Scenario No.: _____ALT___ Op-Test No.: 17-1 Examiners: Chuck Zoia Operators: _____________________________

Mike Bielby _____________________________

Randy Baker _____________________________

Initial Conditions/Turnover:

When the crew assumes the shift reactor power is approximately 100%. The B RHR Pump is inoperable due to breaker refurbishment; return time is approximately three days. After crew turnover, maintenance has requested immediately securing the B CRD Pump for a GE Service Bulletin that directs replacing the oil in the gear box.

Event Malf. Event Event No. No. Type* Description 1 None N BOP Swap running EHC pumps N SRO 2 RR36B C ATC B Recirc pump runback (20%)

C SRO 3 RR05B C BOP B Recirc pump trip RR06B TS SRO Tech Spec Entry (3.4.1) 4 None R ATC Reduce power below MELLLA with rods R SRO 5 RD11A, C ATC B CRD pump trip with accumulator lights RD0706 15, TS SRO Tech Spec Entry (3.1.5)

RD0734 35, RD0738 19 6 RR15B M ALL Coolant leak from steam line in containment 7 RP05G M ALL Hydraulic ATWS 8 DI-RH- I BOP Containment enable switch for B side inoperable 014 I SRO 9 DI-RH- C BOP MO-2000 Inboard Drywell Spray valve fails to open 076 C SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR SET UP INSTRUCTIONS

1. Set NRC Exam Security for the Simulator per QF-1071-08 ____

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist. ____

3. Load the saved IC (in folder with this ESG) to a SNAPSHOT ______

a. Reset to that SNAPSHOT. ____

b. Place the Simulator in RUN ____

OR

4. Reset to IC 20, place the simulator in RUN and perform the following:

a. Insert event triggers, malfunctions, overrides and remotes per the tables below.

5. Have a second instructor verify that the auto triggers are setup as indicated below and evaluate to FALSE ____

6. Verify Malfunctions ____

7. Verify Remotes (Note that environmental remotes will already be timing) ____

8. Verify Overrides ____

9. Ensure MOL pull sheet is in the 1C05B hanging file. ____

10. Ensure EOOS has the same system status lineup as the start of the simulator scenario.

11. Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

a. Place a Testing and Maintenance border on 1C03B (A-8) B RHR Pump 1P-229B Trip or Motor Overload

b. Hang MIP tags on the following:

(1) HS-1915, B RHR PUMP 1P-228B

c. Hang Guarded System tags on the following:

(1) A ESW (2) A RHRSW (3) A DG (4) 1A3 (5) 1B3 (6) 1B34

11. Provide appropriate shift turnover documentation.

a. Have STP 3.4.2-01 Jet Pump Operability Test available upon request.

12. RUN Schedule File ESG_alt.sch and LEAVE IT RUNNING.

13. Mark up withdrawal/pull sheet up to completed step Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 1,3,5,13, Manually Activated Manually Activated 21,23,27 11 ZDIRDHS1807A(4) == 1 A CRD PUMP HS TO START MALFUNCTIONS:

Time Malf. No. Malfunction Title ET Delay Ramp Initial Value Final Value RD070615 Control Rod Accumulator Trouble - Rod 5 1 min Setup Inactive Active 06-15 RD073435 Control Rod Accumulator Trouble - Rod 5 1 min Setup Inactive Active 34-35 10 sec RD073819 Control Rod Accumulator Trouble - Rod 5 1 min Setup Inactive Active 38-19 30 sec rr15b RECIRC LOOP RUPT - DESIGN BASES 13 15 min.

Setup 0 1.5 LOCA AT 100% - LOOP B AN1C03B(8) 1C03B (A-08) 'B' RHR Pump 1P-229B Trip Setup ON ON Or Motor Overload Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE 75 75 VOLUME (VARIABLE)

Setup rd11b CRD HYDRAULIC PUMP TRIP- PUMP B 5 Inactive Active Setup RR06B RECIRC M-G DRIVE MOTOR BREAKER 3 2:00 INACTIVE ACTIVE TRIP - M-G B Setup rr05b RECIRC PUMP SHAFT SEIZURE- PMP B 3 5:00 0 100 Setup rr36b Spurious 20% Recirc Runback B Train 1 INACTIVE ACTIVE Setup rh01b RHR PUMP TRIP - PUMP B ACTIVE ACTIVE Setup rh10b RHR B PUMP FAIL TO AUTO-ACTUATE ACTIVE ACTIVE OVERRIDES:

Time Malf. No. Malfunction Title ET Delay Ramp Initial Value Final Value Setup DI-RH-014 HS-1903C CONT SPRAY VLV CTRL OFF OFF Setup DI-RH-076 HS-2000 CONTAINMENT SPRAY MOV- CLOSE CLOSE 2000 Setup DO-RH-063 HS-1915(2) RHR PUMP 1P-229B LITES - On Off (WHITE)

Setup DO-RH-064 HS-1915(3) RHR PUMP 1P-229B LITES - On Off (RED)

Setup DO-RH-065 HS-1915(4) RHR PUMP 1P-229B LITES - On Off (AMBER)

Setup DO-RH-062 HS-1915(1) RHR PUMP 1P-229B LITES - On Off (GREEN)

DO-RH-132 HS-2000(1) CONTAINMENT SPRAY 21 1:00 ON OFF Setup MOV-2000 (GREEN)

DO-RH-133 HS-2000(2) CONTAINMENT SPRAY 21 1:00 ON OFF Setup MOV-2000 (RED)

Setup DI-RH-076 HS-2000 CONTAINMENT SPRAY MOV- 27 CLOSE OPEN (NEW) 2000 Setup DI-RH-033 HS-1915 RHR PUMP 1P-229B STOP STOP Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG REMOTES:

Time Malf. No. Malfunction Title ET Delay Ramp Initial Value Final Value Setup RH10 MAN OPER OF 'B' RHR PUMP (1P229B Norm Open BREAKER)

ATWS TEST SWITCH (AKA DEFEAT 12)

Setup rp02 23 2:30 RUN TEST HS-1863A rp03 ATWS TEST SWITCH (AKA DEFEAT 12) 23 2:00 Setup RUN TEST HS-1864A (RUN,TEST)

SCHEDULE FILES:

ESG_alt

@Time Event Action Description Setup 11 Delete malfunction rd073819 CONTROL ROD ACCUMULATOR TROUBLE- ROD 38-19 Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SHIFT TURNOVER INFORMATION

Today, Dayshift

Warm, summer day, temperatures in the high 70s. No inclement weather expected.

Plant power - ~100% Rx Pwr with corresponding MWe, MWth and core flow.

Protected train - A

Procedures or major maintenance in progress:

o B RHR Pump is inoperable because of a fault in the motor winding. Maintenance expects repairs to be completed in 3 days.

Technical Specification Action statements in effect o TS 3.5.1 Condition A, Day 1 of 30 day LCO, due to B RHR Pump inoperative o TS 3.6.2.3, Condition A, Residual Heat Removal (RHR) Suppression Pool Cooling, Day 1 of 30 day LCO, due to B RHR Pump inoperative

Plant PRA/PSA Status including CDF/LERF & color o CDF : GREEN 1.35 E-6, 1 YR TO YELLOW ICDP o LERF: GREEN 3.32E-7, 1 YR TO YELLOW ILERP

Evolutions in progress or planned for upcoming shift o Maintenance has requested swapping running EHC pumps to allow for checks on the running pump.

Comments, problems, operator workarounds, etc.

o NSPEOs available for the shift include:

Aux Operator and Second Assistant One extra NSPEO available in Work Control Radwaste Operator Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 10 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 Crew After the crew

Switch running EHC pumps has taken the CRS shift:

Direct switching running EHC pumps BOP (1C07)

When contacted as organization Booth Communicator

At 1C07, start standby EHC pump 1P-97B by momentarily placing personnel: Acknowledge Request handswitch HS-3665B in the START position.

Verify annunciator EHC PUMPS 1P97A/B BOTH RUNNING Booth Communicator (1C07A, C-4) is activated One minute after contacted Inform control room that EHC pump

Verify both EHC pump 1P-97A/B amps have stabilized to perform EHC checks are SAT.

Stop EHC Pump 1P-97A by momentarily placing handswitch HS-3665A pump checks: in the STOP position

Verify annunciators EHC PUMPS 1P-97A/B BOTH RUNNING and EHC PUMP 1P-97A/B HS NOT IN AUTO are reset Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 11 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2 Crew Recirc Runback Simulator Operator

Respond to a B Recirc Pump 20% Runback After EHC Insert ET 1 CRS pumps are This will cause B Recirc Pump 20%

Enter and direct actions of AOP 255.2 swapped and at runback the direction of

Comply with Tech Specs and OI 264, Appendix 1 the floor

May enter Tech Spec LCO 3.4.1 Condition C (depending scoop tube instructor: position based on time of scoop tube lock)

Direct and supervise reducing power with rods ATC (1C04/1C05)

Attempt to lock B Recirc Pump Scoop Tube.

When contacted

Stabilize Reactor water level.

as organization Booth Communicator

Place one APRM recorder in each trip system to fast speed personnel: Acknowledge Request

Verify thermal limits on the 3D Monicore Report.

When power is stabilized, plot location on the Stability Power / Flow When contacted Booth Communicator Map as plant Wait 2 minutes and inform Control personnel to

Determine Recirc Pump Speed mismatch is outside of acceptable Room that there is nothing abnormal limits investigate B about the B Recirc Pump, but will Recirc Pump: continue to investigate.

Reduce core power by inserting control rods to bellow MELLLA limits.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3/4 Crew AOP 264

Respond to B Recirc Pump trip After power has Simulator Operator CRS been reduced Insert ET 3

Directs entering AOP 264 and reentering AOP 255.2.

below MELLLA and at the floor This will insert B Recirc Pump shaft

Directs and supervises reactivity manipulation to lower power below seizure and, after a 2:00 delay, trip the 60%.

instructors drive motor breaker for the B Recirc direction:

Comply with the Technical Specification LCO 3.4.1 Condition D pump.

ATC (1C05/1C04)

When sent to

Verify the AUTOMATIC ACTIONS have occurred:

Booth Communicator either 1C149 or o B RECIRC MG SET MOTOR BREAKER 1A204 is OPEN.

1C113B: Acknowledge Request o B GENERATOR FIELD BREAKER is OPEN.

Momentarily place B RECIRC MG SET MOTOR BREAKER 1A204 handswitch in the STOP position to achieve GREEN FLAG status.

Two minutes Booth Communicator Inform Control Room that the B Recirc

Stabilize reactor water level between 186 and 195.

after sent to 1C113B: MG Drive Motor breaker is tripped with

Verify open B RECIRC PUMP DISCH BYP valve MO-4630.

indication of a ground fault Relay B31-

Close B RECIRC PUMP DISCHARGE valve MO-4628.

K3B active. No smoke, smell, or fire.

Re-perform appropriate steps in AOP 255.2 concurrently.

Two minutes Booth Communicator

After 5 minutes, reopen B RECIRC PUMP DISCHARGE valve after sent to Inform Control Room that 1V-SF-12 MO-4628.

1C149: handswitch is in AUTO

Insert control rods per the Control Rod Withdrawal Sequence Sheets to maintain power less than or equal to () 60.0%.

When contacted Booth Communicator BOP as support Acknowledge Request

Send operator to 1C149 and verify that Recirculation Pump MG Set personnel: Room Supply fan 1V-SF-11 has its respective handswitch HS-6534A in AUTO or START.

Send an Operator to 1C113B in the MG Set Room to monitor relays.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5 Simulator Operator Crew CRD pump ACTIVATE ET 5

Respond to B CRD pump trip and corresponding accumulator lights trip/accumulator This will cause the B CRD pump to trip CRS TS and accumulator lights to illuminate after a

Directs starting the A CRD Pump time delay

Comply with the Technical Specification requirements for Control When contacted Rod Scram Accumulators to investigate Booth Communicator (3.1.5 Condition A(3 times) and Condition B)

CRD pump and Acknowledge Request ATC (1C05) breaker:

Send operator to check 1P-209B breaker and to the pump for fault indications.

Two minutes after request for Booth Communicator

Start CRD Pump 1P-209A per OI 255 or OI 255 QRC1.

CRD pump and Inform Control Room that CRD pump is o Verify adequate oil level in CRD Pump 1P-209A motor and breaker status: warm to the touch/ CRD breaker speed changer.

1A410 has tripped on time delay o Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm overcurrent in MANUAL.

When contacted o Verify MO-1833, INLET TO CRD RETURN LINE, is fully to investigate open.

the Booth Communicator o Start CRD PUMP 1P-209A accumulators: Acknowledge Request o Vent both CRD Discharge Filters 1F-201A and B, using the following Vent Valves:

Two minutes Booth Communicator after request for Inform the control room 06-15, 34-35, accumulator 38-19 accumulator pressures:

pressures:

06 915 psig, 34 890 psig, 38 935 psig Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 14 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT 5 Crew CRD pump

Respond to B CRD pump trip and corresponding accumulator lights trip/accumulator ATC (1C05)

TS Cont.:

Start CRD Pump 1P-209A per OI 255 or OI 255 QRC1. (Cont.)

o Verify charging header pressurized > 1200 psig on PI-1816A When contacted CHARGING WATER PRESSURE.

Booth Communicator to verify switchgear Wait one minute and report that the o Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to rooms cleared switchgear rooms are clear. obtain approximately 40 gpm on FI-1814 CRD SYSTEM for CRD pump FLOW.

start: o When FC-1814 is properly controlling flow, then shift to AUTO.

When contacted Booth Communicator o Slowly adjust DRIVE WATER dP CONTROL MO-1830 to to investigate obtain approximately 260 psid on PDI-1825A DRIVE WATER the Acknowledge Request P.

accumulators after CRD pump is started:

Booth Communicator One minute Inform the control room 06-15, 34-35, after request for 38-19 accumulator pressures:

accumulator 06 925 psig, 34 900 psig, pressures:

38 1100 psig Booth Communicator If contacted as RE to verify Inform control room that there are slow rods: currently no slow rods.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT 6/8/9 Simulator Operator Crew EOP 2 INSERT ET 13

Implements the mitigation strategies of EOP 2, Primary Containment Coolant Rupture This inserts a leak from the B Recirc Control Loop. CRS

Enters into EOP 2 due to Drywell Pressure.

If contacted as

Obtains containment parameters.

plant personnel Booth Communicator

May directs installation of Defeat 4 - Drywell Cooler Isolation Defeat.

to deenergize Acknowledge Request

Directs spraying the torus after confirmation that torus pressure is greater MO-2000:

than 2 psig.

Directs spraying the drywell before drywell temperature reaches 280F.

Simulator Operator

Directs inserting a manual reactor scram ACTIVATE ET 21

Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in the PC/P This will turn off the lights on 1C03 for MO- (PC/P-7) leg One minute 2000 after a one minute delay. BOP (1C03) after ET 21 is AND

May install Defeat 4 - Drywell Cooler Isolation Defeat.

activated:

Booth Communicator

Utilizes OI 149 QRC to spray the torus using A side Torus Sprays.

Contact the Control Room and inform

Realizes that MO-2000 INBD DRYWELL SPRAY valve will not open and them that the breaker for MO-2000 HS-1903C ENABLE CONTAINMENT SPRAY VALVES will not function.

(1B34-19) is open.

Sends operator to open breaker for MO-2000 and open MO-2000.

If contacted to Booth Communicator open locally Acknowledge Request open MO-2000:

Simulator Operator TWO minutes after contacted ACTIVATE ET 27 to locally open AND MO-2000: Booth Communicator Contact the Control Room and inform them that MO-2000 is open.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT 7 Crew EOP 1

Implements the mitigation strategies of EOP 1, RPV Control.

Transition to CRS ATWS

Enters EOP 1, RPV Control based on reactor power is above 5% or unknown after a scram signal is received.

Determines that a reactor scram has been initiated

Validates isolations, initiations and SBDG initiations that should have occurred but did not.

Recognizes and implements the CRS IF any rod is withdrawn past position AND it has NOT been determined that the reactor will remain shutdown under all conditions without boron THEN exit this procedure and enter ATWS.

ATC (1C05)

Inserts a manual reactor scram

Recognizes a hydraulic ATWS has occurred and reports the type of ATWS and reactor power.

Places the master feedwater level controller to 158.5 in AUTO.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT 7 Simulator Operator Crew ATWS Cont.: ACTIVATE ET 23

Implements the actions of ATWS.

CRS When directed This will place Remote Functions RP02 in to install Defeat TEST after a time delay; to install Defeat

Directs locking out ADS.

12 (Reset of 12.

Directs Defeat 15 - MSIV and MSL Drain RX LO-LO-LO Level Isolation ARI): When RP02 is inserted, call the control Defeat room and inform them that Defeat 12 is

Directs the ATWS QRC be completed.

complete.

Directs Defeat 11 - Containment N2 Supply Isolation Defeat installation.

Directs injection of SBLC.

Directs performance of Hydraulic RIPS including installation of Defeat 12 - Reset of ARI.

Directs power level control mitigation strategies.

May direct inserting Defeat 4 - Drywell Cooler Isolation Defeat.

Directs Terminate/prevent injection from HPCI, Condensate/Feedwater, Core Spray and RHR. (CRITICAL)

Directs reporting reactor power at 87 and lowering.

Directs RPV level continues to be lowered until reactor power is less than 5% or RPV level reaches 15.

Directs RPV level control band of -25 to either 15 or the RPV level when reactor power was 5% with condensate and feedwater.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT 7 Crew ATWS

Implements the actions of ATWS.

ATC (1C05)

Terminates injection: (CRITICAL)

Condensate and Feed:

Close Feedwater Regulating Valves CV-1579, CV-1621, CV-1622 as follows:

Take MANUAL control of Master Fed Reg Valve Auto/Man Control LC-4577 and dial the controller down until all Feedwater Regulating Valves indicate closed as indicated on:

HC-1579, A Feed Reg Valve Manual/Auto Transfer

HC-1621, B Feed Reg Valve Manual/Auto Transfer

HC-1622, Startup Feed Reg Valve Manual/Auto Transfer

Completes the ATWS QRC. Reports completion and includes SBLC availability, ARI failure, reactor power and RPV level.

Injects SBLC. (CRITICAL)

Reports reactor power at 87 and lowering.

Reports RPV level when reactor power is less than 5% or when 15 is reached.

Secures RCIC when RPV level is under control.

Directs RPV level control band of -25 to either 15 or the RPV level when reactor power was 5% with condensate and feedwater.

(CRITICAL)

Performs the front panel RIPs after RPV level is under control.

(CRITICAL)

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT 7 BOP (1C03/1C35)

ATWS

Locks out ADS. (CRITICAL)

Installs Defeat 15 - MSIV and MSL Drain RX LO-LO-LO Level Isolation Defeat

Installs Defeat 11 - Containment N2 Supply Isolation Defeat installation.

Coordinates performance of the Hydraulic ATWS RIPs

Installs Defeat 4 - Drywell Cooler Isolation Defeat.

Terminates injection: (CRITICAL)

Verifies or trip/lockout HPCI.

RHR:

Place MO-2004 and/or MO-1904 LPCI OPEN INTLK OVERRIDE HS-2004C and/or HS-1904C to OVERRIDE

When 1C03B (B-5) RHR RX LO PRESSURE PERMISSIVE AT 450 PSIG is activated, close MO-2004[MO-1904] by taking HS-2004[HS-1904] to CLOSE.

EVENT 7 Crew ATWS

When all rods are in, transition from ATWS to EOP 1 Transition to CRS EOP 1 Floor Instructor

Directs securing SBLC injection Monitor and ensure that crew monitors

Directs re-entry into EOP 1 After all rods pressure during re-flood of the RPV.

Directs RPV level 170-211 using Condensate and Feedwater.

have inserted: Crew should limit injection to ensure ATC (1C05) cooldown limits are not violated

Reports that all rods in after performing Hydraulic RIPs

Secures SBLC

Controls level 170-211 using Condensate and Feedwater Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG When RPV level Simulator Operator is being restored Place the simulator in FREEZE.

and at the Floor Instructor direction of the Floor Instructor: Announce the scenario is complete; please stand by your stations and do not discuss the scenario with your crew.

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. B Recirc Pump 20% runback

2. Recirculation pump trip

3. CRD pump trip

4. Accumulator fails to recharge After EOP Entry:

1. B side containment enable switch fails to operate

2. A side Inboard Drywell Spray valve (MO-2000) fails to open Abnormal Events:

1. AOP 255.2

2. AOP 264 Major Transients:

1. LOCA

2. ATWS Critical Tasks:

4: IF a scram is required and Reactor power is above 5%, THEN reduce power below 5%

using one or more of the following methods: {BWROG RPV 4.1, 5.1, 6.1}

Inserting control rods using RIPs Injection of Boron

6: IF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation. {BWROG RPV 4.2, 5.2, 6.2}

10: IF a reactor scram is required, and reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. {BWROG RPV 6.3}

11 IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. {BWROG RPV 6.4}

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG CREW GRADING ATTACHMENT ESG ___ALT_____ Rev. ___0___ Date ________________

Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P.

Management Representative/Lead Evaluator ______________/________________

Crew Critical Tasks Task Statement SAT UNSAT

1. IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods:

Injection of Boron Inserting control rods using RIPs

2. IF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation.

3. IF a reactor scram is required, and reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection.

4. IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems.

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SIMULATOR EXERCISE GUIDE SEG SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG 206 LMS Rev. Date: N/A SEG TITLE: NRC INITIAL LICENSE EXAM, SCENARIO #ALT (1B)

SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~90 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT (1B) Rev.0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal This Evaluation Scenario Guide evaluates the Operators ability to:

Objective: Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Evaluation Guide, no tasks are trained. Evaluated tasks are listed on page 3.

Objectives:

Prerequisites: Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator- Certification Training Training A. Simulator Resources: B. Evaluation team C. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G. Simulator Video recording equipment

References:

A. OI 693.2, Rev. 51 B. AOP 646 Rev. 23 C. AOP 255.2 Rev. 43 D. AOP 264 Rev. 14 E. AOP 573 Rev. 6 F. EOP 2 Rev. 18 G. EOP 1 Rev. 20 H. ATWS Rev. 23 I. ED Rev. 11 J. ATWS Rev. 23 K. IPOI 4 Rev. 133 L. IPOI 3 Rev. 152 M. ARP 1C04B Rev. 81 N. ARP 1C04A Rev. 62 O. ARP 1C05A Rev. 82 P. OP-AA-102-1003 Rev. 11 Q. OI 644 QRC 2, Rev. 0 R. OI 149 QRC 4, Rev. 0 S. OI 153 QRC 1, Rev. 4 Protected Content: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

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NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 1.04 Respond to Annunciators 10.03 Alternate CRD Pumps 72.02 Insert Control Rods using Single Notch 93.22 Perform the Immediate Operator Responses to a Reactor Scram 94.03 Respond to Power/Reactivity Abnormal Change Condition.

94.19 Respond to Loss of Feedwater Heating Condition.

94.53 Respond to Primary Containment Control Abnormal Situation 94.58 Respond to Loss of Reactor Recirculation Pump(s) 95.00 Respond to Emergency Situations 95.21 Perform EOP Defeat 11.

95.25 Perform Defeat 15 95.44 Perform actions of RC/L of EOP 1 95.45 Perform initial EOP 1 actions (RC) 95.46 Perform actions of RC/P of EOP 1 95.50 Perform /L to Control RPV Level during an ATWS.

95.52 Control RPV Injections prior to, during, and subsequent to ED during ATWS.

95.55 Perform initial ATWS actions (/).

95.56 Perform /P to Control RPV Pressure During an ATWS.

95.57 Perform /Q to Reduce Reactor Power or Scram the Reactor.

95.63 Perform DW/T leg of EOP 2 95.64 Perform PC/P leg of EOP 2 Senior Reactor Operator 1.02 Determine operability for TS required components 4.21 Direct Crew Actions to Perform the Immediate Operator Responses to a Reactor Scram 5.03 Direct Crew Responses to Power/Reactivity Abnormal Change Condition 5.19 Direct Crew Response to Loss of Feedwater Heating Condition 5.53 Direct Crew response to a Primary Containment Control Abnormal Situation 5.58 Direct Crew response to Loss of Reactor Recirculation Pump(s) 6.21 Direct Crew Response to Perform EOP Defeat 11 6.25 Direct Crew Response for performance of Defeat 15 6.44 Direct Crew Response for performance of the RC/L leg of EOP 1 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.46 Direct Crew Response for performance of RC/P leg of EOP 1 6.50 Direct Crew Response to Perform /L to Control Level During an ATWS 6.52 Direct Crew Response to Control RPV Injection prior to, during and subsequent to Emergency Depressurization during ATWS 6.55 Direct Crew Response to Perform Initial ATWS Actions (/)

6.56 Direct Crew Response to perform /Q to reduce power/scram the reactor during ATWS 6.57 Direct Crew Response to perform /P to control RPV pressure during an ATWS 6.63 Direct Crew Response for performance of the DW/T leg of EOP 2 6.64 Direct Crew Response for performance of the PC/P leg of EOP 2 Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev. 0 Initial development for 2017 Initial development for N/A See Cover NRC LOIT Examination 2017 NRC LOIT See Cover Examination Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description When the crew assumes the shift reactor power is approximately 100%. The B RHR Pump is inoperable due to breaker refurbishment; return time is approximately three days. After crew turnover, maintenance has requested immediately swapping running EHC pumps.

1. The crew will swap running EHC pumps IAW OI 693.2 Section 6.2.

2. Once the EHC pump swap is completed, the B Recirc Pump will experience a 20%

runback. The crew will check Recirc pump limits of OI 264; the crew may enter Tech Spec LCO 3.4.1 Condition C.

3. The crew will lower power IAW IPOI 3 and OI 255.2.

4. Then the B CRD pump will trip on overcurrent and three CRD accumulators alarm on low pressure. Permission is given to start standby pump IAW OI 255. After the A CRD Pump is returned to service the CRD Accumulators remain in alarm on low pressure. The crew will enter LCO 3.1.5 Condition A (3 times) and B.

5. The B Recirc Pump will experience erratic parameters and will trip and the crew will enter Tech Spec LCO 3.4.1 Condition D.

6. A small leak in the drywell and rising drywell pressure. As temperature rises in the Drywell, the crew will insert a manual scram prior to Drywell temperature reaching 280F.

7. The crew will determine that there is a hydraulic ATWS and transition to EOP ATWS. The crew will lockout ADS (CRITICAL), perform the ATWS QRC, inject SBLC, Terminate and Prevent injection (CRITICAL) and establish a level band until all rods are inserted (CRITICAL), and insert the control rods with the RIPS. (CRITICAL)

8. As Primary Containment pressures and temperatures rise HS-1903C, B Enable Containment Spray Valves, will not function.

9. MO-2000, A INBD DRYWELL SPRAY, will not open causing Drywell temperature to rise past 280F. MO-2000, A INBD DRYWELL SPRAY, will be able to be opened through manual operations if an individual is sent to open the valve.

The scenario may be terminated after all rods are in and RPV level is being restored Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Facility: Duane Arnold Energy Center Scenario No.: _____ALT___ Op-Test No.: 17-1 Examiners: Chuck Zoia Operators: _____________________________

Mike Bielby _____________________________

Randy Baker _____________________________

Initial Conditions/Turnover:

When the crew assumes the shift reactor power is approximately 100%. The B RHR Pump is inoperable due to breaker refurbishment; return time is approximately three days. After crew turnover, maintenance has requested immediately securing the B CRD Pump for a GE Service Bulletin that directs replacing the oil in the gear box.

Event Malf. Event Event No. No. Type* Description 1 None N BOP Swap running EHC pumps N SRO 2 RR36B C ATC B Recirc pump runback (20%)

C SRO 3 None R ATC Reduce power below MELLLA with rods R SRO 4 RD11A, C ATC B CRD pump trip with accumulator lights RD0706 15, TS SRO Tech Spec Entry (3.1.5)

RD0734 35, RD0738 19 5 RR05B C BOP B Recirc pump trip RR06B TS SRO Tech Spec Entry (3.4.1) 6 RR15B M ALL Coolant leak from steam line in containment 7 RP05G M ALL Hydraulic ATWS 8 DI-RH- I BOP Containment enable switch for B side inoperable 014 I SRO 9 DI-RH- C BOP MO-2000 Inboard Drywell Spray valve fails to open 076 C SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 23

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR SET UP INSTRUCTIONS

1. Set NRC Exam Security for the Simulator per QF-1071-08 ____

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist. ____

3. Load the saved IC (in folder with this ESG) to a SNAPSHOT ______

a. Reset to that SNAPSHOT. ____

b. Place the Simulator in RUN ____

OR

4. Reset to IC 20, place the simulator in RUN and perform the following:

a. Insert event triggers, malfunctions, overrides and remotes per the tables below.

5. Have a second instructor verify that the auto triggers are setup as indicated below and evaluate to FALSE ____

6. Verify Malfunctions ____

7. Verify Remotes (Note that environmental remotes will already be timing) ____

8. Verify Overrides ____

9. Ensure MOL pull sheet is in the 1C05B hanging file. ____

10. Ensure EOOS has the same system status lineup as the start of the simulator scenario.

11. Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

a. Place a Testing and Maintenance border on 1C03B (A-8) B RHR Pump 1P-229B Trip or Motor Overload

b. Hang MIP tags on the following:

(1) HS-1915, B RHR PUMP 1P-228B

c. Hang Guarded System tags on the following:

(1) A ESW (2) A RHRSW (3) A DG (4) 1A3 (5) 1B3 (6) 1B34

11. Provide appropriate shift turnover documentation.

a. Have STP 3.4.2-01 Jet Pump Operability Test available upon request.

12. RUN Schedule File ESG_alt.sch and LEAVE IT RUNNING.

13. Mark up withdrawal/pull sheet up to completed step Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 23