ML17214A214

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Dua 2017 Ile - Administered Exam Scenarios
ML17214A214
Person / Time
Site: Duane Arnold 
Issue date: 06/14/2017
From: Bielby M
Operations Branch III
To:
NextEra Energy Duane Arnold
Bielby M
Shared Package
ML16308A454 List:
References
Download: ML17214A214 (96)
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Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 2 of 25 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 Experience:

None Risk Significant Operator Actions:

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 25 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.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE REVIEWER DATE Rev. 0 Initial development for 2017 NRC LOIT Examination Initial development for 2017 NRC LOIT Examination N/A See Cover See Cover

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 25 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.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 25 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 No.

Malf.

No.

Event Type*

Event Description 1

N ATC N SRO Reset B FRV 2

R ATC R SRO Raise power with rods 3

FW12B I ATC I SRO B FRV fails downscale 4

RD0602 19 C ATC TS SRO Control Rod drift out Tech Spec (3.1.3) 5 AN1C08 A(7)

C BOP TS SRO Remove S/U Transformer from service 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 1,

STRH0 2

C BOP C SRO MO-1905 fails to open

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 25 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 Setup AN1C08A(7) 1C08A (A-07) STARTUP XFMR 1X3 TROUBLE 1

CRYWOLF ON Setup RR15A RECIRC LOOP RUPT - DESIGN BASES LOCA AT 100% - LOOP A 9

15:00 0

0.05 Setup ED08C 4.16 KV/480V BUS FAULT - BUS 1A3 11 2 SEC INACTIVE ACTIVE Setup STRH01 LPCI A INJECT VALVE FAILS TO AUTO OPEN - MO-2003 ACTIVE ACTIVE Setup STRH02 LPCI B INJECT VALVE FAILS TO AUTO OPEN - MO-1905 ACTIVE ACTIVE Setup HP12 HPCI Aux Oil Pump 1P218 Trip 5

INACTIVE ACTIVE Setup FW12B FW REG VALVE CONTROLLER FAILURE (AUTO)- FWRV B 7

7:00 AS IS 0

Setup RD011415 CONTROL ROD DRIVES OUT-ROD 14-15 13 INACTIVE ACTIVE REMOTES:

Time Malf. No.

Malfunction Title ET Delay Ramp Initial Value Final Value Setup DO-HP-032 HS-2256(1) AUX OIL PUMP 1P-218 LITES (GREEN) 5 INACTIVE ACTIVE Setup DO-HP-033 HS-2256(2) AUX OIL PUMP 1P-218 LITES (RED) 5 INACTIVE ACTIVE 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 10 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 After the crew has assumed the shift:

If/when contacted as inplant operator for B FRV lockup reset:

After B FRV is reset and when contacted:

Booth Communicator Respond as plant personnel and respond as necessary Booth Communicator Inform the control room that you are standing by at the B FRV Booth Communicator Inform the control room that nothing abnormal to report at the B FRV CREW Reset the B FRV lockup CRS Direct crew to reset the B FRV IAW the ARP 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 the following:

Verify that the controller LED displays for the locked Feed Reg Valve are lit.

Verify the Feedwater Lockout Relay amber light above the associated Lockout Relay is dim.

o Reset a locked Feed Reg Valve as follows:

At HC-1621 B FEED REG VALVE MANUAL/AUTO 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.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 11 of 25 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.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 12 of 25 EVENT 2 Raise power If contacted as organization for assistance:

Prior to the next event, if the BOP is in the vicinity of the 1C05 panel and at the direction of the floor instructor:

Simulator Operator (NOTE: Insert Override NM02 at approximately 1 minute intervals during the power change)

This will ensure that APRM GAFs will maintain constant through the power change.

Booth Communicator Respond as plant personnel and respond as necessary Booth Communicator Contact the control room as the Aux Operator informing them that you are doing outside-outs.

CREW Raise reactor power by 5%

CRS Direct and observe reactivity manipulations to achieve a 5% raise in reactor power 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:

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.

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

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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 13 of 25 EVENT 3 FRV Failure After the crew has raised power, reset the B FRV, and at the direction of the Floor Instructor:

If contacted as organization for assistance:

If contacted as operators to inspect the B FRV locally:

Two minutes after being sent to investigate B FRV:

Simulator Operator Activate ET 7.

This will activate FW12B for failure of B FRV Booth Communicator Respond as plant personnel and respond as necessary Booth Communicator Acknowledge communication Booth Communicator Inform control room that nothing abnormal is seen at the FRV CREW Respond to B FRV failure downscale CRS Establish critical parameter monitoring of RPV Water Level Direct entering AOP 644 May direct entering AOP 255.2 ATC (1C05)

Assuming manual control of a malfunctioning system 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 May perform the following actions: (if entered AOP 255.2) o Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal.

o Verify proper operation/indication of other systems and/or indications o Verify control rod positions are correct for the established sequence, by using Rod Position Log.

o Verify thermal limits on the Official 3D Case.

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

Flow Map.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 14 of 25 EVENT 4 Rod Drift If contacted as organization for assistance:

Two minutes after contacted as RE:

Two minutes after sent to HCU:

One minute after contacted to isolate rod 14-15:

Simulator Operator Activate ET 13.

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

Booth Communicator Respond as plant personnel and respond as necessary Booth Communicator Inform control room that further analysis is required and will contact control room when have more information Booth Communicator Inform control room that nothing abnormal is seen at the HCU Simulator Operator DELETE MALF. RD011415 AND Booth Communicator Inform the control room that time compression has been used and that the Insert and Withdrawal Isolations for rod 14-15 are closed.

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

CRS Direct entering AOP 255.1 May direct (re-)entering AOP 255.2 Notify the Reactor Engineer of the abnormal rod pattern.

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

Place the C11A-S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position momentarily to abort the rod sequence timer.

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.

Run an OFFICIAL 3D CASE for abnormal reactor power/control rod distributions.

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

When power is stabilized, plot location on the Stability Power / Flow Map.

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

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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 15 of 25 EVENT 5 Loss of 1X3 When contacted to investigate 1X3 alarm:

2 min. after told to investigate 1X3 alarm:

When contacted as ITC Midwest:

If contacted as the organization for assistance:

Simulator Operator Insert ET1 This inserts AN1C08A(7), S/U Xfmr trouble alarm.

Booth Communicator Acknowledge request.

Booth Communicator Inform Control Room there is a Sudden Internal Pressure Trip Alarm in and you are leaving the area.

Booth Communicator Acknowledge notification.

Booth Communicator Acknowledge request.

CREW

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

CRS

  • Direct taking out 1X3 out of service per OI 304.2 (or OI 304.2 QRC)
  • Using OI 304.2 section TRANSFERRING ESSENTIAL BUS 1A3[4]

FROM STARTUP TO STANDBY TRANSFORMER:

  • If in Mode 1,2, or 3, verify the following Tech Spec conditions are entered and exited:
  • T.S. 3.8.1 Condition B for associated SBDG
  • If the Startup XFMR Offsite Circuit is currently inoperable, then enter and exit the following additional Tech Spec conditions:
  • T.S. 3.0.3 (per 3.8.1F)
  • Determine that the final Tech Spec determination:
  • T.S. 3.8.1 Condition A
  • Notify ITC Midwest that the Startup Transformer (1X3) has been removed from service.
  • 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)

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 16 of 25 EVENT 5 One minute after contacted to verify switchgear rooms clear:

If/When contacted as organization:

Booth Communicator Inform the control room that the switchgear rooms are clear.

Booth Communicator Acknowledge information/requests BOP (1C08)

  • Using OI 304.2 QRC1:
  • Transfer 1A3 to the Standby Transformer by performing the following:
  • Place BUS 1A3 TRANSFER switch in MANUAL.
  • Insert the handle in the SYNCHRONIZE switch for 4KV BREAKER 1A301 STANDBY TRANSFORMER TO BUS 1A3, 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 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.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 17 of 25 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.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 18 of 25 EVENT 6 After the crew takes HS-4310 to Auto Open:

Simulator Operator Insert ET 9 This will start a drywell leak.

Simulator Operator Verify ET 15 goes ACTIVE This will increase the size of the leak leading the crew to scram.

CREW Respond to a coolant leak in containment.

CRS Directs enter AOP 573 BOP (1C03/1C24)

Monitor outside barometric pressure utilizing Computer Point M000 to determine if weather conditions are causing a change in indicated 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 19 of 25 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

  • 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

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 25 EVENT 6 After Drywell Pressure exceeds 2 psig:

If contacted to investigate 1P-218 breaker (1D41-13):

Two minutes after sent to investigate 1D41-13:

If contacted to investigate 1A3 Lockout:

Two minutes after sent to 1A3:

Simulator Operator Verify ET 5 AND 11 goes active This will insert HP12 to trip the HPCI Aux Oil Pump and ED08C to Lockout Bus 1A3 Booth Communicator Acknowledge request.

Booth Communicator Inform control room that 1D41-13 HPCI Aux. Oil Pump 1P218 is tripped and has an acrid odor, no smoke or fire.

Booth Communicator Acknowledge request.

Booth Communicator Inform control room that 1A3 has a ground fault indication.

CREW

  • Performs a crew update of entry into EOP 2 due to Drywell Pressure.
  • Obtains containment parameters.
  • May direct installation of Defeat 4 - Drywell Cooler Isolation Defeat
  • Directs spraying the torus after confirmation that torus pressure is greater than 2 psig.
  • Directs spraying the drywell before drywell temperature reaches 280F.

(CRITICAL)

  • Verifies torus water level less than 13.5 ft.
  • Verifies plot of drywell temperature and drywell pressure on the DWSIL curve allows drywell sprays.
  • Verifies recirculation pumps are secured.
  • Directs maximizing torus cooling.
  • Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in T/L (T/L-3 and T/L 10), T/T (T/T-6), DW/T (DW/T-6) and PC/P (PC/P-7) legs
  • Directs entering AOP 301 for Loss of 1A3 BOP (1C03/1C08/1C23)
  • Installs Defeat 4 - Drywell Cooler Isolation Defeat
  • Utilizes OI 149 QRC to spray the torus.
  • Utilizes OI 149 QRC to spray the drywell.
  • Utilizes OI 149 QRC to establish torus cooling.
  • Place A SBDG in Pull-to-Lock

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 21 of 25 EVENT 7 ALC CREW

  • 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)

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.

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 22 of 25 EVENT 8/9 Emergency Depress.:

CREW

  • After RPV level reaches +15 enters and implements the mitigation 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 torus water level above 4.5 feet
  • Direct Crew Response to Perform an Emergency Depressurization Using SRVs
  • Perform an Emergency Depressurization Using SRVs.
  • Recognizes MO-1905 does not automatically open at 450 psig and takes action at 1C03 to open MO-1905. (CRITICAL)

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 23 of 25 EVENT 8 EOP 1 Implementation after EOP ED:

CREW

  • Implements mitigation strategies of EOP 1 after EOP ED to restore adequate core cooling 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 level is being restored and at the direction of the Floor Instructor:

Simulator Operator Place the simulator in FREEZE.

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

      • END OF SCENARIO ***

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 24 of 25 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}

NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 1.docx TR-AA-230-1003-F06 Revision 0 Page 25 of 25 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.

Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 2 of 25 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. 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 Experience:

None Risk Significant Operator Actions:

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 25 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.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE REVIEWER DATE Rev. 0 Initial development for 2017 NRC LOIT Examination Initial development for 2017 NRC LOIT Examination N/A See Cover See Cover

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 25 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.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 25 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 No.

Malf.

No.

Event Type*

Event Description 1

R ATC R SRO Pull Control Rods to achieve 10-12% Reactor power 2

N ATC N SRO Transfer Reactor Feed from the Startup Feed Regulating Valve to the A Feed Regulating Valve 3

RD04A1 827 I ATC I SRO Control Rod Position lost entry to AOP 255.1 4

RM03R E4116B TS SRO RE-4116B Inoperable due to electrical power supply fault Tech Spec Inoperable (3.3.6.1 Function 2C) 5

DG07A, DG05A C BOP TS SRO A SBDG Start with erratic Voltage Control Tech Spec Entry (3.8.1 Condition B / 3.7.3 Condition A) 6 MS04A M ALL Steam Leak in the Steam Tunnel (SCRAM prior to Automatic Group 1 isolation) 7a,b,c RP05A,B

,C,D a)M ALL b)I BOP c)I BOP Electrical ATWS (Pulling RPS Fuses is successful)

RPS Trip Test Switches Failure Individual Scram Test Switches Failure 8

STRC01 C ATC C SRO RCIC Failure to Auto Start

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 25 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:

Time Malf. No.

Malfunction Title ET Delay Ramp Initial Value Final Value Setup MS18A VALVE CV1158A/B FAILURE - CV1158A 100 100 Setup MS18B VALVE CV1158A/B FAILURE - CV1158B 100 100 Setup RP05A RPS SCRAM CIRCUIT FAILURE (ATWS)- AUTO SCRAM FAILURE ACTIVE ACTIVE Setup RP05B RPS SCRAM CIRCUIT FAILURE (ATWS)- MANUAL SCRAM FAILURE ACTIVE ACTIVE 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 Setup AN1C03A(13) 1C03A (B-04) OFFGAS VENT PIPE RM-4116 A/B HI RAD 1

3 SEC CRYWOLF CRYWOLF Setup DG07A 1G31 'A' DIESEL GENERATOR SPURIOUS START-DG A

3 INACTIVE ACTIVE 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 Setup DG05A 1G31 'A' DIESEL GENERATOR V/R OSCILLATES IN AUTO-DG A 3

5 SEC 30 SEC 0

100 Setup ED02 POWER GRID FREQUENCY DISTURBANCE (DELETE in 1 SEC) 3 0

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

Time Remote No.

Remote Title ET Delay Ramp Initial Value Final 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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 25 OVERRIDES:

Time Remote No.

Remote Title ET Delay Ramp Initial Value Final Value Setup DO-RD-615 HS-1807A(1) CRD PUMP 1807 BREAKER TRIPPED (GREEN)

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

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

OFF OFF 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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 25 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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 10 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 IPOI 2 Simulator Operator (NOTE: Insert Override NM02 at approximately 1 minute intervals during the power change)

This will ensure that APRM GAFs will maintain constant through the power change.

CREW Withdraw control rods IAW IPOI 2 and OI 856.1 to complete step 17 CRS Direct and observe reactivity manipulations to achieve step 17 complete 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.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 11 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 Raise Power Cont.

ATC (1C05) Cont.

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

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.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 12 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2 Shift FRV from S/U to A OI 644 IF called as any DAEC support personnel:

If/when contacted for guidance after FRV transfer:

Booth Communicator Acknowledge coordination Booth Communicator Acknowledge communication Booth Communicator Instruct operator to continue the power ascension.

CREW Shift FRV from the S/U FRV to the A FRV CRS Coordinate shifting feed flow control from the STARTUP FEED REG VALVE to A FEED REG VALVE.

ATC (1C05)

Shift feed flow control from the STARTUP FEED REG VALVE to A FEED REG VALVE as follows:

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, HC-1622, is in AUTO.

o Verify the A FEED REG VALVE CONTROLLER HC-1579 is in MANUAL.

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.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 13 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3 Control Rod Position Lost AOP 255.1 IF called as any DAEC support personnel:

If contacted as RE for substituting position for rod 26-19:

Two minutes after contacted as RE:

EVALUATOR NOTE:

AOP 255.1 and OI 878.8 are to be given to the ATC operator. In the event that the CRS proceeds to give these to the BOP, prompt the CRS to give these to the ATC Booth Communicator Acknowledge communication Booth Communicator Acknowledge communication Booth Communicator Report to the control room that you concur with substituting rod position for rod 26-19 and to continue with startup.

CREW Perform the Follow Up Actions of AOP 255.1 for Abnormal Rod Control and Position Indications CRS Direct the performance of AOP 255.1 for Abnormal Rod Control and Position Indications 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:

o Attempt to move the affected rod out, as allowed by rod sequence, to an adjacent notch to check for reed switch failure o Consult with CRS/OSM and Reactor Engineer to modify rod pattern if necessary to avoid leaving the control rod at the notch with no position indication

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 14 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3 Position Substitution 878.8 CREW Substitute notch position IAW OI 878.8 Section 8.2 CRS 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.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 15 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4 Offgas Vent Pipe RM Downscale After crew has substituted the rod postion and/or when directed by the Floor Instructor:

If contacted to investigate 1D60:

IF called as any DAEC support personnel:

Simulator Operator:

ACTIVATE ET 1 This causes RE-4116B OFFGAS VENT PIPE B to fail.

Booth Communicator:

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

Booth Communicator:

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

CRS Determine affected Tech Spec TS LCO 3.3.6.1 Condition A o Function 2c Offgas Vent Stack - High Radiation - Channel B o Determine NOT in mode of applicability BOP (1C03/1C10)

At 1C10, monitor OFFGAS STACK VENT PIPE B RAD MONITOR RM-4116B to determine if DOWNSCALE or INOPERATIVE.\\

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

o RM4116B - 1D60 Breaker 03

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 16 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5 If contacted to investigate A SBDG:

Three minutes after requested to investigate A SBDG:

If contacted to verify operation of A ESW:

Two minutes after requested to verify operation A ESW:

Simulator Operator:

ACTIVATE ET 3 This causes a momentary grid disturbance. A SBDG will spuriously start and its voltage regulator fail.

Booth Communicator:

Acknowledge Request Booth Communicator:

Inform control room that A SBDG appears to be normal and all alarms at 1C93 are as expected.

Booth Communicator:

Acknowledge Request Booth Communicator:

Inform control room that A ESW is operating SAT.

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

CRS Determine affected Tech Spec LCO 3.8.1 Condition B and 3.7.3 Condition A Request STP 3.8.1-01 and/or STP 3.8.1-02 BOP (1C08)

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

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

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

o Place A SBDG handswitch HS-3231A in PTL

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 17 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6 EOP 3 Steam Leak in Steam Tunnel After SBDG TS has been declared and/or at the direction of the Floor Instructor:

After 1V-SF-10C is taken to start:

Simulator Operator:

ACTIVATE ET 5 This will insert MS08A to start the Steam Tunnel steam leak.

(NOTE: Bring up EOPSLD and monitor Steam Tunnel Temperature)

Simulator Operator:

VERIFY ET 9 ACTIVATES This will modify ms08a to 0.6 to worsen the steam tunnel leak.

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

CRS Direct Crew Response for performance of EOP 3 for high area temperatures level including EOP 1 o Direct Main Plant Supply and Exhaust Fans in a 3-2-3 lineup o Determines RPV pressure reduction will lessen the leakage rate.

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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 18 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6 EOP 3 Cont.:

BOP (1C21/1C23)

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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 19 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A EOP 1 Transition to ATWS When the MODE switch is taken out of run:

Simulator Operator:

VERIFY ET 11 ACTIVATES This will cause B CRD pump HI Vibes followed by B CRD pump trip CREW Implements the mitigation strategies of EOP 1 and EOP ATWS CRS 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.

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.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A ATWS If directed to vent the scram air header:

Two (2) minutes after being directed to vent the scram air header:

Booth Communicator:

Acknowledge the request.

Booth Communicator:

Inform the control room that you cannot vent the scram air header due to the valve being bound.

CREW 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.

Directs performance of the ATWS QRC Directs installation of Defeat 11-Containment N2 Supply Isolation Defeat Directs initiation of SBLC.

Directs electrical ATWS rod insertion procedures Exits the ATWS Q leg flowpath and enters L leg actions ATC (1C05)

Performs the ATWS QRC.

Reports completion of the ATWS QRC. Determines that ARI was 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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 21 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A/8 ATWS EVALUATOR NOTE:

Ensure that while level is lowering that the RO acknowledges RCIC failure to auto start and recommends starting RCIC.

CREW 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 Recognizes that RCIC did not start automatically and start manually.

Reports reactor power when RPV level reaches 87 and lowering.

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

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

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 22 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7A/B/C ATWS CREW 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 break Main Condenser Vacuum:

Simulator Operator:

Acknowledge the direction, then ACTIVATE ET 17 This inserts remote functions mc01 and mc02.

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 23 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew has inserted all control rods, is restoring RPV Water Level and at the direction of the Floor Instructor:

Simulator Operator Place the simulator in FREEZE.

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

      • END OF SCENARIO ***

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 24 of 25 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}

NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG Filename: 2017 DUA ILE Administered Exam Scenario 2.docx TR-AA-230-1003-F06 Revision 0 Page 25 of 25 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.

Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 2 of 23 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:

Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator-Certification Training 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. 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 Experience:

None Risk Significant Operator Actions:

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 23 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.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE REVIEWER DATE Rev. 0 Initial development for 2017 NRC LOIT Examination Initial development for 2017 NRC LOIT Examination N/A See Cover See Cover

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 23 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 No.

Malf.

No.

Event Type*

Event Description 1

None N BOP N SRO Swap running EHC pumps 2

RR36B C ATC C SRO B Recirc pump runback (20%)

3 RR05B RR06B C BOP TS SRO B Recirc pump trip Tech Spec Entry (3.4.1) 4 None R ATC R SRO Reduce power below MELLLA with rods 5

RD11A, RD0706 15, RD0734 35, RD0738 19 C ATC TS SRO B CRD pump trip with accumulator lights Tech Spec Entry (3.1.5) 6 RR15B M ALL Coolant leak from steam line in containment 7

RP05G M ALL Hydraulic ATWS 8

DI-RH-014 I BOP I SRO Containment enable switch for B side inoperable 9

DI-RH-076 C BOP C SRO MO-2000 Inboard Drywell Spray valve fails to open (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 23 EVENT TRIGGER DEFINITIONS:

Trigger No.

Trigger Logic Statement Trigger Word Description 1,3,5,13, 21,23,27 Manually Activated Manually Activated 11 ZDIRDHS1807A(4)== 1 A CRD PUMP HS TO START MALFUNCTIONS:

Time Malf. No.

Malfunction Title ET Delay Ramp Initial Value Final Value Setup RD070615 Control Rod Accumulator Trouble - Rod 06-15 5

1 min Inactive Active Setup RD073435 Control Rod Accumulator Trouble - Rod 34-35 5

1 min 10 sec Inactive Active Setup RD073819 Control Rod Accumulator Trouble - Rod 38-19 5

1 min 30 sec Inactive Active Setup rr15b RECIRC LOOP RUPT - DESIGN BASES LOCA AT 100% - LOOP B 13 15 min.

0 1.5 Setup AN1C03B(8) 1C03B (A-08) 'B' RHR Pump 1P-229B Trip Or Motor Overload ON ON Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE VOLUME (VARIABLE) 75 75 Setup rd11b CRD HYDRAULIC PUMP TRIP-PUMP B 5

Inactive Active Setup RR06B RECIRC M-G DRIVE MOTOR BREAKER TRIP - M-G B 3

2:00 INACTIVE ACTIVE 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-2000 CLOSE CLOSE Setup DO-RH-063 HS-1915(2) RHR PUMP 1P-229B LITES -

(WHITE)

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

(RED)

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

(AMBER)

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

(GREEN)

On Off Setup DO-RH-132 HS-2000(1) CONTAINMENT SPRAY MOV-2000 (GREEN) 21 1:00 ON OFF Setup DO-RH-133 HS-2000(2) CONTAINMENT SPRAY MOV-2000 (RED) 21 1:00 ON OFF Setup DI-RH-076 (NEW)

HS-2000 CONTAINMENT SPRAY MOV-2000 27 CLOSE OPEN Setup DI-RH-033 HS-1915 RHR PUMP 1P-229B STOP STOP

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 23 REMOTES:

Time Malf. No.

Malfunction Title ET Delay Ramp Initial Value Final Value Setup RH10 MAN OPER OF 'B' RHR PUMP (1P229B BREAKER)

Norm Open Setup rp02 ATWS TEST SWITCH (AKA DEFEAT 12)

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

HS-1864A (RUN,TEST) 23 2:00 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 10 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 11 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 After the crew has taken the shift:

When contacted as organization personnel:

One minute after contacted to perform EHC pump checks:

Booth Communicator Acknowledge Request Booth Communicator Inform control room that EHC pump checks are SAT.

Crew

  • Direct switching running EHC pumps BOP (1C07)

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

Verify annunciator EHC PUMPS 1P97A/B BOTH RUNNING (1C07A, C-4) is activated Verify both EHC pump 1P-97A/B amps have stabilized Stop EHC Pump 1P-97A by momentarily placing handswitch HS-3665A 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 12 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2 Recirc Runback After EHC pumps are swapped and at the direction of the floor instructor:

When contacted as organization personnel:

When contacted as plant personnel to investigate B Recirc Pump:

Simulator Operator Insert ET 1 This will cause B Recirc Pump 20%

runback Booth Communicator Acknowledge Request Booth Communicator Wait 2 minutes and inform Control Room that there is nothing abnormal about the B Recirc Pump, but will continue to investigate.

Crew Respond to a B Recirc Pump 20% Runback CRS Enter and direct actions of AOP 255.2 Comply with Tech Specs and OI 264, Appendix 1 May enter Tech Spec LCO 3.4.1 Condition C (depending scoop tube 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.

Stabilize Reactor water level.

Place one APRM recorder in each trip system to fast speed Verify thermal limits on the 3D Monicore Report.

When power is stabilized, plot location on the Stability Power / Flow Map Determine Recirc Pump Speed mismatch is outside of acceptable limits Reduce core power by inserting control rods to bellow MELLLA limits.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 13 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3/4 AOP 264 After power has been reduced below MELLLA and at the floor instructors direction:

When sent to either 1C149 or 1C113B:

Two minutes after sent to 1C113B:

Two minutes after sent to 1C149:

When contacted as support personnel:

Simulator Operator Insert ET 3 This will insert B Recirc Pump shaft seizure and, after a 2:00 delay, trip the drive motor breaker for the B Recirc pump.

Booth Communicator Acknowledge Request Booth Communicator Inform Control Room that the B Recirc MG Drive Motor breaker is tripped with indication of a ground fault Relay B31-K3B active. No smoke, smell, or fire.

Booth Communicator Inform Control Room that 1V-SF-12 handswitch is in AUTO Booth Communicator Acknowledge Request Crew Respond to B Recirc Pump trip CRS Directs entering AOP 264 and reentering AOP 255.2.

Directs and supervises reactivity manipulation to lower power below 60%.

Comply with the Technical Specification LCO 3.4.1 Condition D ATC (1C05/1C04)

Verify the AUTOMATIC ACTIONS have occurred:

o B RECIRC MG SET MOTOR BREAKER 1A204 is OPEN.

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.

Stabilize reactor water level between 186 and 195.

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

Close B RECIRC PUMP DISCHARGE valve MO-4628.

Re-perform appropriate steps in AOP 255.2 concurrently.

After 5 minutes, reopen B RECIRC PUMP DISCHARGE valve MO-4628.

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

BOP Send operator to 1C149 and verify that Recirculation Pump MG Set 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.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 14 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5 CRD pump trip/accumulator TS When contacted to investigate CRD pump and breaker:

Two minutes after request for CRD pump and breaker status:

When contacted to investigate the accumulators:

Two minutes after request for accumulator pressures:

Simulator Operator ACTIVATE ET 5 This will cause the B CRD pump to trip and accumulator lights to illuminate after a time delay Booth Communicator Acknowledge Request Booth Communicator Inform Control Room that CRD pump is warm to the touch/ CRD breaker 1A410 has tripped on time delay overcurrent Booth Communicator Acknowledge Request Booth Communicator Inform the control room 06-15, 34-35, 38-19 accumulator pressures:

06 915 psig, 34 890 psig, 38 935 psig Crew Respond to B CRD pump trip and corresponding accumulator lights CRS Directs starting the A CRD Pump Comply with the Technical Specification requirements for Control Rod Scram Accumulators (3.1.5 Condition A(3 times) and Condition B)

ATC (1C05)

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

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

o Verify adequate oil level in CRD Pump 1P-209A motor and speed changer.

o Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in MANUAL.

o Verify MO-1833, INLET TO CRD RETURN LINE, is fully open.

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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 15 of 23 EVENT 5 CRD pump trip/accumulator TS Cont.:

When contacted to verify switchgear rooms cleared for CRD pump start:

When contacted to investigate the accumulators after CRD pump is started:

One minute after request for accumulator pressures:

If contacted as RE to verify slow rods:

Booth Communicator Wait one minute and report that the switchgear rooms are clear.

Booth Communicator Acknowledge Request Booth Communicator Inform the control room 06-15, 34-35, 38-19 accumulator pressures:

06 925 psig, 34 900 psig, 38 1100 psig Booth Communicator Inform control room that there are currently no slow rods.

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

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

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

o Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain approximately 40 gpm on FI-1814 CRD SYSTEM FLOW.

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

o Slowly adjust DRIVE WATER dP CONTROL MO-1830 to obtain approximately 260 psid on PDI-1825A DRIVE WATER P.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 16 of 23 EVENT 6/8/9 EOP 2 Coolant Rupture If contacted as plant personnel to deenergize MO-2000:

One minute after ET 21 is activated:

If contacted to open locally open MO-2000:

TWO minutes after contacted to locally open MO-2000:

Simulator Operator INSERT ET 13 This inserts a leak from the B Recirc Loop.

Booth Communicator Acknowledge Request Simulator Operator ACTIVATE ET 21 This will turn off the lights on 1C03 for MO-2000 after a one minute delay.

AND Booth Communicator Contact the Control Room and inform them that the breaker for MO-2000 (1B34-19) is open.

Booth Communicator Acknowledge Request Simulator Operator ACTIVATE ET 27 AND Booth Communicator Contact the Control Room and inform them that MO-2000 is open.

Crew

  • Enters into EOP 2 due to Drywell Pressure.
  • Obtains containment parameters.
  • May directs installation of Defeat 4 - Drywell Cooler Isolation Defeat.
  • Directs spraying the torus after confirmation that torus pressure is greater than 2 psig.
  • Directs spraying the drywell before drywell temperature reaches 280F.
  • Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in the PC/P (PC/P-7) leg BOP (1C03)
  • May install Defeat 4 - Drywell Cooler Isolation Defeat.
  • Utilizes OI 149 QRC to spray the torus using A side Torus Sprays.
  • Realizes that MO-2000 INBD DRYWELL SPRAY valve will not open and HS-1903C ENABLE CONTAINMENT SPRAY VALVES will not function.
  • Sends operator to open breaker for MO-2000 and open MO-2000.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 17 of 23 EVENT 7 EOP 1 Transition to ATWS Crew

  • Implements the mitigation strategies of EOP 1, RPV Control.

CRS

  • 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)

  • 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.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 18 of 23 EVENT 7 ATWS Cont.:

When directed to install Defeat 12 (Reset of ARI):

Simulator Operator ACTIVATE ET 23 This will place Remote Functions RP02 in TEST after a time delay; to install Defeat

12.

When RP02 is inserted, call the control room and inform them that Defeat 12 is complete.

Crew

  • Implements the actions of ATWS.

CRS

  • Directs locking out ADS.
  • Directs Defeat 15 - MSIV and MSL Drain RX LO-LO-LO Level Isolation Defeat
  • Directs the ATWS QRC be completed.
  • 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.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 19 of 23 EVENT 7 ATWS Crew

  • 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)

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 23 EVENT 7 ATWS BOP (1C03/1C35)

  • 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 ATWS Transition to EOP 1 After all rods have inserted:

Floor Instructor Monitor and ensure that crew monitors pressure during re-flood of the RPV.

Crew should limit injection to ensure cooldown limits are not violated Crew

  • When all rods are in, transition from ATWS to EOP 1 CRS
  • Directs securing SBLC injection
  • Directs re-entry into EOP 1

ATC (1C05)

  • Reports that all rods in after performing Hydraulic RIPs
  • Secures SBLC
  • Controls level 170-211 using Condensate and Feedwater

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 21 of 23 When RPV level is being restored and at the direction of the Floor Instructor:

Simulator Operator Place the simulator in FREEZE.

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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 22 of 23 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:
  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 Injection of Boron

  1. 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}
  1. 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}
  1. 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}

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt.docx TR-AA-230-1003-F06 Revision 0 Page 23 of 23 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.

Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 1 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT (1B) Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 2 of 23 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:

Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator-Certification Training 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. 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 Experience:

None Risk Significant Operator Actions:

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 4 of 23 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.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE REVIEWER DATE Rev. 0 Initial development for 2017 NRC LOIT Examination Initial development for 2017 NRC LOIT Examination N/A See Cover See Cover

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 5 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 6 of 23 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 No.

Malf.

No.

Event Type*

Event Description 1

None N BOP N SRO Swap running EHC pumps 2

RR36B C ATC C SRO B Recirc pump runback (20%)

3 None R ATC R SRO Reduce power below MELLLA with rods 4

RD11A, RD0706 15, RD0734 35, RD0738 19 C ATC TS SRO B CRD pump trip with accumulator lights Tech Spec Entry (3.1.5) 5 RR05B RR06B C BOP TS SRO B Recirc pump trip 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-014 I BOP I SRO Containment enable switch for B side inoperable 9

DI-RH-076 C BOP C SRO MO-2000 Inboard Drywell Spray valve fails to open (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 7 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 8 of 23 EVENT TRIGGER DEFINITIONS:

Trigger No.

Trigger Logic Statement Trigger Word Description 1,3,5,13, 21,23,27 Manually Activated Manually Activated 11 ZDIRDHS1807A(4)== 1 A CRD PUMP HS TO START MALFUNCTIONS:

Time Malf. No.

Malfunction Title ET Delay Ramp Initial Value Final Value Setup RD070615 Control Rod Accumulator Trouble - Rod 06-15 5

1 min Inactive Active Setup RD073435 Control Rod Accumulator Trouble - Rod 34-35 5

1 min 10 sec Inactive Active Setup RD073819 Control Rod Accumulator Trouble - Rod 38-19 5

1 min 30 sec Inactive Active Setup rr15b RECIRC LOOP RUPT - DESIGN BASES LOCA AT 100% - LOOP B 13 15 min.

0 1.5 Setup AN1C03B(8) 1C03B (A-08) 'B' RHR Pump 1P-229B Trip Or Motor Overload ON ON Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE VOLUME (VARIABLE) 75 75 Setup rd11b CRD HYDRAULIC PUMP TRIP-PUMP B 5

Inactive Active Setup RR06B RECIRC M-G DRIVE MOTOR BREAKER TRIP - M-G B 3

2:00 INACTIVE ACTIVE 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-2000 CLOSE CLOSE Setup DO-RH-063 HS-1915(2) RHR PUMP 1P-229B LITES -

(WHITE)

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

(RED)

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

(AMBER)

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

(GREEN)

On Off Setup DO-RH-132 HS-2000(1) CONTAINMENT SPRAY MOV-2000 (GREEN) 21 1:00 ON OFF Setup DO-RH-133 HS-2000(2) CONTAINMENT SPRAY MOV-2000 (RED) 21 1:00 ON OFF Setup DI-RH-076 (NEW)

HS-2000 CONTAINMENT SPRAY MOV-2000 27 CLOSE OPEN Setup DI-RH-033 HS-1915 RHR PUMP 1P-229B STOP STOP

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 9 of 23 REMOTES:

Time Malf. No.

Malfunction Title ET Delay Ramp Initial Value Final Value Setup RH10 MAN OPER OF 'B' RHR PUMP (1P229B BREAKER)

Norm Open Setup rp02 ATWS TEST SWITCH (AKA DEFEAT 12)

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

HS-1864A (RUN,TEST) 23 2:00 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 10 of 23 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 11 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1 After the crew has taken the shift:

When contacted as organization personnel:

One minute after contacted to perform EHC pump checks:

Booth Communicator Acknowledge Request Booth Communicator Inform control room that EHC pump checks are SAT.

Crew

  • Direct switching running EHC pumps BOP (1C07)

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

Verify annunciator EHC PUMPS 1P97A/B BOTH RUNNING (1C07A, C-4) is activated Verify both EHC pump 1P-97A/B amps have stabilized Stop EHC Pump 1P-97A by momentarily placing handswitch HS-3665A 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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 12 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2/3 Recirc Runback After EHC pumps are swapped and at the direction of the floor instructor:

When contacted as organization personnel:

When contacted as plant personnel to investigate B Recirc Pump:

Simulator Operator Insert ET 1 This will cause B Recirc Pump 20%

runback Booth Communicator Acknowledge Request Booth Communicator Wait 2 minutes and inform Control Room that there is nothing abnormal about the B Recirc Pump, but will continue to investigate.

Crew Respond to a B Recirc Pump 20% Runback CRS Enter and direct actions of AOP 255.2 Comply with Tech Specs and OI 264, Appendix 1 May enter Tech Spec LCO 3.4.1 Condition C (depending scoop tube 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.

Stabilize Reactor water level.

Place one APRM recorder in each trip system to fast speed Verify thermal limits on the 3D Monicore Report.

When power is stabilized, plot location on the Stability Power / Flow Map Determine Recirc Pump Speed mismatch is outside of acceptable limits Reduce core power by inserting control rods to bellow MELLLA limits.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 13 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4 CRD pump trip/accumulator TS When contacted to investigate CRD pump and breaker:

Two minutes after request for CRD pump and breaker status:

When contacted to investigate the accumulators:

Two minutes after request for accumulator pressures:

Simulator Operator ACTIVATE ET 5 This will cause the B CRD pump to trip and accumulator lights to illuminate after a time delay Booth Communicator Acknowledge Request Booth Communicator Inform Control Room that CRD pump is warm to the touch/ CRD breaker 1A410 has tripped on time delay overcurrent Booth Communicator Acknowledge Request Booth Communicator Inform the control room 06-15, 34-35, 38-19 accumulator pressures:

06 915 psig, 34 890 psig, 38 935 psig Crew Respond to B CRD pump trip and corresponding accumulator lights CRS Directs starting the A CRD Pump Comply with the Technical Specification requirements for Control Rod Scram Accumulators (3.1.5 Condition A(3 times) and Condition B)

ATC (1C05)

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

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

o Verify adequate oil level in CRD Pump 1P-209A motor and speed changer.

o Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in MANUAL.

o Verify MO-1833, INLET TO CRD RETURN LINE, is fully open.

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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 14 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4 CRD pump trip/accumulator TS Cont.:

When contacted to verify switchgear rooms cleared for CRD pump start:

When contacted to investigate the accumulators after CRD pump is started:

One minute after request for accumulator pressures:

If contacted as RE to verify slow rods:

Booth Communicator Wait one minute and report that the switchgear rooms are clear.

Booth Communicator Acknowledge Request Booth Communicator Inform the control room 06-15, 34-35, 38-19 accumulator pressures:

06 925 psig, 34 900 psig, 38 1100 psig Booth Communicator Inform control room that there are currently no slow rods.

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

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

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

o Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain approximately 40 gpm on FI-1814 CRD SYSTEM FLOW.

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

o Slowly adjust DRIVE WATER dP CONTROL MO-1830 to obtain approximately 260 psid on PDI-1825A DRIVE WATER P.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 15 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5 AOP 264 After power has been reduced below MELLLA and at the floor instructors direction:

When sent to either 1C149 or 1C113B:

Two minutes after sent to 1C113B:

Two minutes after sent to 1C149:

When contacted as support personnel:

Simulator Operator Insert ET 3 This will insert B Recirc Pump shaft seizure and, after a 2:00 delay, trip the drive motor breaker for the B Recirc pump.

Booth Communicator Acknowledge Request Booth Communicator Inform Control Room that the B Recirc MG Drive Motor breaker is tripped with indication of a ground fault Relay B31-K3B active. No smoke, smell, or fire.

Booth Communicator Inform Control Room that 1V-SF-12 handswitch is in AUTO Booth Communicator Acknowledge Request Crew Respond to B Recirc Pump trip CRS Directs entering AOP 264 and reentering AOP 255.2.

Directs and supervises reactivity manipulation to lower power below 60%.

Comply with the Technical Specification LCO 3.4.1 Condition D ATC (1C05/1C04)

Verify the AUTOMATIC ACTIONS have occurred:

o B RECIRC MG SET MOTOR BREAKER 1A204 is OPEN.

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.

Stabilize reactor water level between 186 and 195.

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

Close B RECIRC PUMP DISCHARGE valve MO-4628.

Re-perform appropriate steps in AOP 255.2 concurrently.

After 5 minutes, reopen B RECIRC PUMP DISCHARGE valve MO-4628.

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

BOP Send operator to 1C149 and verify that Recirculation Pump MG Set 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.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 16 of 23 EVENT 6/8/9 EOP 2 Coolant Rupture If contacted as plant personnel to deenergize MO-2000:

One minute after ET 21 is activated:

If contacted to open locally open MO-2000:

TWO minutes after contacted to locally open MO-2000:

Simulator Operator INSERT ET 13 This inserts a leak from the B Recirc Loop.

Booth Communicator Acknowledge Request Simulator Operator ACTIVATE ET 21 This will turn off the lights on 1C03 for MO-2000 after a one minute delay.

AND Booth Communicator Contact the Control Room and inform them that the breaker for MO-2000 (1B34-19) is open.

Booth Communicator Acknowledge Request Simulator Operator ACTIVATE ET 27 AND Booth Communicator Contact the Control Room and inform them that MO-2000 is open.

Crew

  • Enters into EOP 2 due to Drywell Pressure.
  • Obtains containment parameters.
  • May directs installation of Defeat 4 - Drywell Cooler Isolation Defeat.
  • Directs spraying the torus after confirmation that torus pressure is greater than 2 psig.
  • Directs spraying the drywell before drywell temperature reaches 280F.
  • Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in the PC/P (PC/P-7) leg BOP (1C03)
  • May install Defeat 4 - Drywell Cooler Isolation Defeat.
  • Utilizes OI 149 QRC to spray the torus using A side Torus Sprays.
  • Realizes that MO-2000 INBD DRYWELL SPRAY valve will not open and HS-1903C ENABLE CONTAINMENT SPRAY VALVES will not function.
  • Sends operator to open breaker for MO-2000 and open MO-2000.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 17 of 23 EVENT 7 EOP 1 Transition to ATWS Crew

  • Implements the mitigation strategies of EOP 1, RPV Control.

CRS

  • 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)

  • 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.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 18 of 23 EVENT 7 ATWS Cont.:

When directed to install Defeat 12 (Reset of ARI):

Simulator Operator ACTIVATE ET 23 This will place Remote Functions RP02 in TEST after a time delay; to install Defeat

12.

When RP02 is inserted, call the control room and inform them that Defeat 12 is complete.

Crew

  • Implements the actions of ATWS.

CRS

  • Directs locking out ADS.
  • Directs Defeat 15 - MSIV and MSL Drain RX LO-LO-LO Level Isolation Defeat
  • Directs the ATWS QRC be completed.
  • 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.

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 19 of 23 EVENT 7 ATWS Crew

  • 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)

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 20 of 23 EVENT 7 ATWS BOP (1C03/1C35)

  • 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 ATWS Transition to EOP 1 After all rods have inserted:

Floor Instructor Monitor and ensure that crew monitors pressure during re-flood of the RPV.

Crew should limit injection to ensure cooldown limits are not violated Crew

  • When all rods are in, transition from ATWS to EOP 1 CRS
  • Directs securing SBLC injection
  • Directs re-entry into EOP 1

ATC (1C05)

  • Reports that all rods in after performing Hydraulic RIPs
  • Secures SBLC
  • Controls level 170-211 using Condensate and Feedwater

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 21 of 23 When RPV level is being restored and at the direction of the Floor Instructor:

Simulator Operator Place the simulator in FREEZE.

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

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 22 of 23 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:
  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 Injection of Boron

  1. 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}
  1. 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}
  1. 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}

NRC INITIAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG Filename: 2017 DUA ILE Administered Exam Scenario Alt 1B.docx TR-AA-230-1003-F06 Revision 0 Page 23 of 23 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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