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2015 Duane Arnold Energy Center Initial License Examination Administered Scenarios and In-Plant JPMs
	ML15232A162
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Site:	Duane Arnold
Issue date:	08/20/2015
From:	; Division of Reactor Safety III
To:	; NextEra Energy Duane Arnold
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SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: 0 LMS ID: LMS Rev. Date:

SEG TITLE: NRC Initial License Exam, Scenario #1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~ 90 minutes Developed by: Raymond Keith Walton 1/28/2015 Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 43

NRC Initial License Exam - Scenario #1 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures:

Enabling There are no formal learning objectives for this evaluation.

Objectives:

Prerequisites: None Training Simulator Resources: Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team

References:

AOP 255.1, Rev. 44 OI 152, QRC 2, Rev. 1 AOP 255.2, Rev. 42 OI 255, Rev. 87 ARP 1C05A, Rev. 78 OI 255 QRC 1, Rev. 3 ARP 1C94, Rev. 48 OI 324, Rev. 113 IPOI 3, Rev. 143 OI 454, Rev. 65 OI 856.1, Rev. 45 Protected Content: Identify here and in training material as {C001}; See Comment for details.

None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 43

NRC Initial License Exam - Scenario #1 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See Cover Initial development for Initial development for 2015 NRC 0 2015 NRC LOIT N/A LOIT examination. See Cover examination.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 43

Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________

Initial Conditions: The plant is operating at 80% power due to a downpour for maintenance.

Thunderstorms are forecast for the area. B SBDG was recently returned from maintenance.

Turnover:

Complete B SBDG Testing per OI 324, SBDG, Section 6.4, synchronize and load.

Raise Reactor power using control rods to a load line of 94-95%.

Event Event # Malf # Eventy Description Type*

1 None N BOP Synchronize and load the B SBDG IAW OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.

2 None C BOP Report from field that B SBDG has a jacket cooling water leak TS SRO B SBDG declared inoperable per TS 3.8.1 3 None R ATC Raise reactor power with control rods 4 rd02 C ATC Stuck Control Rod 3023 5 rd11b C RO CRD Pump trip 6 hp01 C BOP HPCI spurious start requiring manual shutdown/isolation TS SRO HPCI declared inoperable per TS 3.6.

7 ed01( M ALL Loss of Offsite Power with Small break LOCA.

a-e) rr15b Failure of A SBDG to start in AUTO, will start in Manual.

stdg01 8 hp02 C BOP HPCI starts in Manual but trips shortly after.

Emergency Depressurization required.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 43

Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS General Instructions

a. Reset to IC 23 or the Snap (1) Raise power to ~80% with Recirc and Rods.

(2) Load Events (3) Load Malfunctions (4) Load Remote Functions

b. Verify Events validate FALSE

c. Ensure the following procedure is marked up prior to turnover and being provided to the candidates:

(1) OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM a) Place a checkmark in the placekeeping area for the NOTE at the beginning of the section b) Place a checkmark in the first two steps of the section regarding bromination not occurring and the SBDG readiness checklist being completed.

d. Build a schedule file to remove RD022223 on ET 20.

(1) Verify the schedule file is RUNNING.

e. Verify MOL Pull Sheets are out.

EVENT TRIGGERS Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7, Manual Trigger Manual Trigger 10, 11, 12, 13, 14, 15, 17, 30 20 ZAORDPDI1825 >= .60 Drive Water DP > 295 psig 23 ZLOHPHS2312(2) == 1 & HPCI Inject Valve Opening after mode switch ZDIRPC71AS1(1) == 1 in SHUTDOWN Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 43

Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 me Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup AN1C08B(26) 1C08B (C-02) B DIESEL GEN 1 Crywolf ON PANEL 1C 94 TROUBLE Setup rd022223 CONTROL ROD BLADE 3 Inactive Active STUCK- ROD 22-23 Setup stdg01 TRIP OVERRIDE - 'A' SBDG Inactive Active 1G31 FAILS TO AUTO START Setup stdg02 TRIP OVERRIDE - 'B' SBDG Inactive Active 1G21 FAILS TO AUTO START Setup rd070615 CONTROL ROD ACCUMULATOR TROUBLE- 45 sec 5 Inactive Active ROD 06-15 Setup Rd073435 CONTROL ROD ACCUMULATOR TROUBLE- 1 min 5 Inactive Active ROD 34-35 Setup rd11b CRD HYDRAULIC PUMP TRIP-5 Inactive Active PUMP B Setup hp01 HPCI INADVERTANT 7 Inactive Active INITIATION Setup rc01 RCIC PUMP TRIP 9 Inactive Active Setup ed01a LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR M Setup ed01b LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR J Setup ed01c LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR K Setup ed01d LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR X5960 Setup ed01e LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR X5940 Setup rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP 8 min 21 0 0.7 B

rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP 3 min 23 As Is 1 B

Setup hp02 HPCI TURBINE TRIP 15 sec 23 Inactive Active Setup rd11a CRD HYDRAULIC PUMP TRIP-24 Inactive Active PUMP A Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 43

Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Schedule File for SEG.

At On Action Description Time Event Delete malfunction None 20 CONTROL ROD BLADE STUCK- ROD 22-23 rd022223 Insert malfunction dg03b None 22 1G21 'B' DIESEL GENERATOR TRIP- DG B after 45 HS-3281B B DG 1G21 IDLE-RATED SWITCH None 10 Insert remote dg19 to IDLE (RATED,IDLE)

Insert remote dg11 to 'B' DIESEL GEN 1G21 DROOP SWITCH None 11 PARALLEL (UNIT,PARALLEL)

Insert remote dg19 to HS-3281B B DG 1G21 IDLE-RATED SWITCH None 13 RATED (RATED,IDLE)

'B' DIESEL GEN 1G21 DROOP SWITCH None 12 Insert remote dg11 to UNIT (UNIT,PARALLEL)

Insert remote rd03 to CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 None 28 5.00000 ISOLATION Insert remote rd03 to CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 None 27 100.00000 in 60 ISOLATION Delete malfunction CONTROL ROD ACCUMULATOR TROUBLE-None 14 rd070615 ROD 06-15 Delete malfunction CONTROL ROD ACCUMULATOR TROUBLE-None 15 rd073435 ROD 34-35 REMOTE FUNC FEEDBACK AN05- ACK SWITCH None 17 Insert remote an05 to ACK 1C94 (NORM,ACK)

Insert remote an05 to REMOTE FUNC FEEDBACK AN05- ACK SWITCH None 17 NORM after 5 1C94 (NORM,ACK)

Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 43

Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 SHIFT TURNOVER INFORMATION

Day of week and shift o Today o Day Shift

Weather conditions o Mild summer morning

(Plant power levels) o Reactor Power Level 80%

o Core Flow 40 Mlbm/hr

Protected train o Protected Train is A

Technical Specification Action statements in effect o None

Locked in / failed annunciators and alarms o None

Evolutions in progress or planned for upcoming shift o Start and load B SBDG from the Control Room in accordance with OI 324, Section 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM for industry OE investigation. 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months load run is required to be performed for maintenance. Offsite Sources STP was completed just prior to turnover (< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago).

o Power assention in progress following a sequence exchange.

Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline with one year to YELLOW o LERF Baseline with one year to YELLOW

Existing LCOs, date of next surveillance o None.

Procedures or major maintenance in progress o None

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment o Raise Power with rod withdrawal to 85% Power per RE Direction

Comments, problems, operator workarounds, etc.

o None Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 43

NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW Start B ESW

Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG IAW OI 454 to SYSTEM.

support starting B SBDG: CRS Simulator Operator:

Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, When directed FAST MANUAL STARTUP OF THE B SBDG SYSTEM.

to perform B Inform the control room that time ESW pump compression is being used and the B BOP prestart checks: ESW Pump is ready for start.

Start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.

Start Emergency Service Water Pump 1P-99B per OI 454.

Manually start either or both ESW pumps by performing either of the following:

o Start B ESW PUMP 1P-99B by placing HS-4928B on 1C06 in the START position

Verify B ESW PUMP 1P-99B running by observing the following on 1C06:

o B ESW PUMP 1P-99B red indicating light is ON.

o B ESW PUMP 1P-99B indicates normal running current of approximately 95-115 amps Simulator Operator

Verify adequate cooling for ESW Pump 1P-99B by observing that FI-4938B One (1) minute B ESW FLOW indicates greater than 300 gpm.

after the B Inform the control room that the BESW Pump is running satisfactory. The strainer

As soon as possible after ESW pump start, perform the following:

ESW Pump is started: is rotating, auto vents are closed and that o Inspect the auto vent/vac breaker for evidence of excessive leakage.

there is air flow in the room. The fan o Verify air flow from 1V-SF-56B, RHRSW/ESW Supply Fan.

switch has been returned to auto. o After air flow is verified, operate 1V-SF-56B as directed by CRS.

Control ESW/RHRSW pit level in accordance with OI 410.

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NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CREW

Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.

CRS

Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.

BOP

Start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.

If starting the Standby Diesel Generator from the Control Room on 1C08 perform the following:

After the B Simulator Operator

Set Prelube Timer KS-3238B to 2.0 minutes.

SBDG Prelube Inform the control room that the B

Start the B DIESEL GENERATOR 1G-21 PRELUBE pump by depressing pump is SBDG Prelube Pump is running the prelube pushbutton.

operating: satisfactory.

After the Prelube Pump has been running for 1 minute, place B DIESEL GENERATOR 1G-21 CONTROL handswitch HS-3231B momentarily in the START position, and then return it to the AUTO position.

Verify 1V-SF-21 Diesel Generator Supply Fan is running (verify red running light ON at 1C23).

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 43

NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Paralleling the CREW B SBDG to

Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG 1A4: SYSTEM.

CRS

Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE B SBDG SYSTEM TO ESSENTIAL BUS 1A4.

When directed BOP Simulator Operator to place HS-

Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE B 3281, IDLE- Acknowledge the request. SBDG SYSTEM TO ESSENTIAL BUS 1A4.

RATED Switch

Verify SBDG 1G-21 started.

in IDLE:

At 1C94, verify HS-3281B, IDLE-RATED SWITCH, in IDLE.

Perform the following on 1C08:

One (1) minute Simulator Operator o Adjusts B DIESEL GENERATOR 1G-21 VOLTAGE ADJUST after the Activate [ET 10]. control to maintain B DIESEL GENERATOR 1G-21 VOLTS meter request to place at approximately 4160 volts.

HS-3281B in Inform the control room that HS-3281B, IDLE-RATED SWITCH is in IDLE. o Adjusts B DIESEL GENERATOR 1G-21 SPEED ADJUST control IDLE: to maintain B DIESEL GENERATOR 1G-21 FREQUENCY meter at approximately 60 hertz.

When Simulator Operator

Place the GOVERNOR MODE SWITCH (DROOP) HS-3234B on 1C94 in the requested to Acknowledge the request. PARALLEL position.

place HS-

3234B, GOVERNOR MODE SWITCH in PARALLEL:

One (1) minute Simulator Operator after the Activate [ET 11].

request to place Inform the control room that HS3234B, HS-3234B in GOVERNOR MODE SELECT SWITCH is PARALLEL: in PARALLEL Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 43

NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW Starting the B

Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SBDG IAW OI SYSTEM.

324 (cont): CRS

Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE B SBDG SYSTEM TO ESSENTIAL BUS 1A4.

Simulator Operator

Enters AC Sources and SBDG LCOs.

Activate [ET 17].

TS LCO 3.8.1 Condition A- One Offsite Circuit INOPERABLE.

This will acknowledge the 1C94

TS LCO 3.8.1. Condition B- One DG INOPERABLE Annunciator Alarms and clear the Control Room Annunciator on 1C08. This must BOP occur prior to the next event.

Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE B SBDG SYSTEM TO ESSENTIAL BUS 1A4.

Verifies AC Sources and SBDG LCOs have been entered.

At 1C08, place BUS 1A4 Transfer handswitch to MANUAL.

Simulator Operator:

Place the SYNCHRONIZE switch for 4KV BREAKER 1A411 B DIESEL At the direction Activate [ET 1]. GENERATOR 1G-21, to ON.

of the Lead This will cause 1C08B (C-02), B Diesel

Using the B DIESEL GENERATOR 1G-21 VOLTAGE ADJUST, raise Examiner: Gen Panel 1C-94 Trouble to annunciate. INCOMING VOLTS SYNCHRONIZE to slightly more than RUNNING VOLTS SYNCHRONIZE.

Using the B DIESEL GENERATOR 1G-21 SPEED ADJUST, adjust diesel generator speed to a slow, clockwise synchroscope rotation.

Communications

When the synchroscope is at the 12 o'clock position, momentarily place the for the leak are control switch for 4KV BREAKER 1A411 B DIESEL GENERATOR 1G-21 in on page 14 the CLOSE position.

Confirms the red (breaker closed) and white (closing spring charged) indicating lights are ON.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 43

NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW Starting the B

Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SBDG IAW OI SYSTEM.

324 (cont): CRS

Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE B SBDG SYSTEM TO ESSENTIAL BUS 1A4.

When

Exits LCOs 3.8.1.A and 3.8.1.B when the 1A4 Transfer handswitch is taken Simulator Operator to AUTO.

Contacted to verify 1A4 inform the control room that 1A4 BOP Switchgear Switchgear Room is clear of personnel.

Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE B Room Clear of SBDG SYSTEM TO ESSENTIAL BUS 1A4.

Personnel, wait

Loads the Diesel Generator to 250-300 KW using 1G21 speed adjust 1 minute and

Place the SYNCHRONIZE switch for 4KV BREAKER 1A411 B DIESEL GENERATOR 1G-21 to OFF.

Place BUS 1A4 TRANSFER handswitch in AUTO.

Use B DIESEL GENERATOR 1G-21 SPEED ADJUST to load B DIESEL GENERATOR 1G-21 to 1,500 KW, observing B DIESEL GENERATOR 1G-21 KILOWATTS meter at 1C08 Simulator Operator

Adjust B SBDG speed and voltage, as necessary to attain desired loading Acknowledge the request. and power factor (0.9 power factor per Appendix 1).

Complete the SBDG Operating Checklist OI 324A9 (Attachment 9).

When directed to perform SBDG Operating Checklist OI 324A9 (Attachment 9):

EXAMINER NOTE: After initially loading the B SBDG, wait ~5 minutes then insert the next event.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 43

NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Crew

Responds to 1C08B (C-2), B Diesel Gen Panel 1C-94 Trouble Alarm When directed Simulator Operator

Responds to 1C94 (A-3), Jacket Coolant Level Low to investigate

Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Acknowledge the request.

the 1C94 Trouble Alarm:

Three (3) BOP minutes after Simulator Operator:

Send an Operator to 1C94 to determine the cause of the TROUBLE being directed Alarm and take corrective action per ARP 1C-94.

to investigate Inform the control room of the following:

At 1C92 monitor TI-3258B to determine if Jacket Coolant temperature is 1C94 Trouble high or low Alarm:

Coolant is on the floor around the

IF SBDG 1G-21 is running and NO LOOP or LOOP/LOCA emergency SBDG, the expansion tank is empty.

exists AND IF Jacket coolant temperature is above 195°F on TI-3258B

Annunciators in ALARM: THEN Unload and trip SBDG and notify CRS.

1C94 (A-3), Jacket Coolant Level

Unloads the B SBDG (CRITICAL)

Low

Trips the B SBDG (CRITICAL) 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Actions per the OI are on the next page.

Jacket coolant temp is 195°F, rising slowly.

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NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Floor Instructor Crew Jacket Coolant The crew may elect to unload and remove

Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Leak on the B the SBDG from service using OI 324. The CRS SBDG. steps documented to the right are the

Directs the operator to unload the B SBDG in accordance with OI 324, Sect expected student response using OI 324. 8.3, UNLOAD THE B SBDG.

(contd)

Enters LCOs 3.8.1.A and 3.8.1.B when the 1A4 Transfer handswitch is taken to MANUAL and exits 3.8.1.A when taken back to AUTO.

BOP

Implements OI 324, Sect 8.3, UNLOAD THE B SBDG Simulator Operator:

If the SBDG is in PARALLEL OPERATION, then reduce the load on the When contacted Acknowledge the request for support. Diesel Generator to 1500-1600 KW by using the DIESEL GENERATOR as the DSM 1G-21 SPEED ADJUST CONTROL.

Adjust A[B] DIESEL GENERATOR 1G-1G-21 VOLTAGE ADJUST to maintain 0.9 power factor per Appendix 1.

Operate at 1500-1600 KW for 10 minutes to allow for cooldown. (Based Simulator Operator: on the current conditions, the 10 minute cooldown may be waived).

When contacted Acknowledge the request for support.

Verify AC Sources LCO has been entered if applicable.

as Chemistry to investigate the

Place the BUS 1A4 TRANSFER breaker mode selector switch is in leak, MANUAL. (Critical for this evolution)

Reduce the load on the Diesel Generator to 50 KW by using the DIESEL GENERATOR 1G-21 SPEED ADJUST CONTROL.

Place the control switch for 4KV BREAKER 411 B DIESEL GENERATOR 1G-21 in the TRIP position. (Critical for this evolution) o Observe that the green (breaker tripped) and the white (closing spring charged) indicating lights are ON.

Place the BUS 1A4 TRANSFER breaker mode selector switch in the AUTO position. (Critical for this evolution)

At 1C08, confirm annunciator 4KV BUS AUTO TRANSFER INOP (1C08A, D-7) is reset. Actions continued on next page.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 43

NRC Initial License Exam, Scenario #1 SEG IF directed to Simulator Operator Crew place HS3234B

Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Acknowledge the request.

in UNIT:

Activate [ET 12] CRS

Directs the operator to unload the B SBDG in accordance with OI 324, Sect This will insert RF dg11 to UNIT 8.3, UNLOAD THE B SBDG.

Inform the control room that HS3234B,

Place the B GOVERNOR MODE SWITCH (DROOP) HS-3234B at B Governor Mode Switch is in UNIT. 1C94 in UNIT.

If directed to

Directs placing the B DIESEL GENERATOR 1G-21 CONTROL place HS3281B Simulator Operator handswitch HS-3231B on 1C08 in the PULL TO LOCK position.

in RATED:

Declares the B SBDG INOPERABLE (already INOP potentially due to Acknowledge the request. not exiting when 1A4 transfer switch was in MANUAL)

Activate [ET13]

TS LCO 3.8.1 Condition B- One DG INOPERABLE This will insert RF dg19 to RATED. o Perform SR 3.8.1.1 for operable offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

Inform the control room that HS3281B, IDLE-RATED SWITCH is in RATED. o Determine that the fault is not a common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

o Perform SR 3.8.1.2 for the operable EDG once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months o Restore the inoperable EDG to operable within 7 days BOP

Implements OI 324, Sect 8.3, UNLOAD THE B SBDG

At 1C94, place HS-3281B, IDLE-RATED SWITCH, in RATED.

EXAMINER NOTE: After the applicants shutdown the B SBDG and after declaring the B SBDG inoperable, the crew should proceed to withdrawing control rods.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 43

NRC Initial License Exam, Scenario #1 SEG Event 3 CRS Increase Directs Operators to increase power IAW IPOI and RE guidance Reactor Power with control RO rods Continues control rod withdrawal IAW OI 856.1 following the sequence.

Monitor neutron monitoring instrumentation during control rod movements.

If the crew does not transition to Simulator Operator:

Verifies the following indications:

raising reactor Contact the control room as the o White backlight on the Rod Select pushbutton turns ON power after the Reactor Engineer and inform them that o On the Full Core Display, the white XX-XX select light corresponding SBDG event: raising reactor power is a priority. to the rod selected turns ON o On the Four Rod Group Display, the white SELECT light turns ON If called as Simulator Operator denoting the position display for the selected rod.

organizational Acknowledge the requests and provide

Momentarily places the ROD MOVEMENT CONTROL in the OUT-personnel to needed support. NOTCH position and verifies:

support the power rise: o The green ROD IN light turns ON momentarily and then turns OFF o The red ROD OUT light turns ON after the green ROD IN light turns OFF.

o The red ROD OUT light turns OFF o The amber ROD SETTLE light turns ON and then turns OFF o The rod has been with drawn as indicated on the Four Rod Group Display BOP

Provides Peer checks to RO during rod withdrawals.

Monitors balance of plant equipment /plant status.

Examiner Note: The 3rd control rod will stick. Go to Event 4.

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NRC Initial License Exam, Scenario #1 SEG Event 4: CREW Stuck Control Diagnoses control rod 22-23 is stuck Rod Simulator Operator CRS At the direction Activate [ET 3]

of the Lead

Directs entry to AOP 255.1, Control Rod Movement/Indication Abnormal, This will stick Rod 22-23 at its current when informed of stuck control rod.

Examiner, position.

Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, When CRD requirements are met.

Simulator Operator

Contacts RE and/or Duty Manager.

drive water pressure is Verify [ET 20] actuates. RO greater than This will remove MF RD023023. This will 295 psig: allow rod 22-23 to move.

While pulling control rods, recognizes 22-23 stuck and informs the SRO.

Implements AOP 255.1, takes actions to address the stuck rod as follows:

Verify power is available to RMCS.

If contacted as

Verify the rod is actually selected.

organizational Simulator Operator

Demand a Rod Position Log and verify control rod positions.

personnel: Acknowledge the information.

Verify the following parameters indicate approximately their normal values at 1C05 o CRD Pump flow at FC-1814 CRD System Flow Control (40 gpm)

Evaluator Note:

o CRD Charging Water header pressure at PI-1816A (CRD It is satisfactory to adjust pressure greater Pressure) Charging Water Press (1450 psi) than normal but less than 350# to limit stress on the CRD o CRD Drive Water pressure at PDI-1825A (CRD Pressure)

Drive Water P (260 psid)

Evaluator Note:

Raises drive water pressure to 310-350 psid by adjusting MO1830 There is the potential to double notch a until drive water pressure PI-1825A is 310-350 psid.

control rod with elevated drive water

Attempts to move the rod pressure. There is a large note in the AOP to direct the crew to recover from the

Recognizes rod movement and reports success to SRO double notch IAW OI 255

Returns drive water pressure to its normal band Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 43

NRC Initial License Exam, Scenario #1 SEG Event 4: BOP When directed Simulator Operator

Monitors balance of plant equipment/plant status.

to the HCU to Acknowledge the request.

perform local

Contacts SANSOE to inspect control rod 22-23 HCU for abnormalities.

actions:

Two (2) minutes after initial Simulator Operator direction to Inform the control room that the HCU verify condition lineup is normal and HCU pressure is at the HCU: normal.

If contacted to monitor HCU Simulator Operator during control Inform the control room that the HCU rod movement looked and sounded normal during the after RD022223 move.

is removed:

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 43

NRC Initial License Exam, Scenario #1 SEG Crew If the crew

Recognize the Double Notch of the Control Rod.

double notches the control rod, CRS actions to

Direct actions IAW OI 255, Section 10.1, Restoration from a Withdraw recover are Double Notch.

included.

Notify Reactor Engineering.

Simulator Instructor If contacted as Acknowledge the Double Notch and inform RO the Reactor the crew that inserting the rod and

Verify thermal limits on an official or a predicted 3D case.

Engineer, continuing with the power change is

Use the CONTROL ROD MOVEMENT SWITCH C11A-S2 at 1C05 to permissible. INSERT the rod one notch to its intended position. NA if the double notch is anticipated as part of a planned reactivity manipulation and thermal limits are not adversely affected.

The crew should recommence the withdrawal of control rods IAW IPOI 3 once the double notched rod is restored.

EXAMINER NOTE: Continue to next event at examiners direction.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 43

NRC Initial License Exam, Scenario #1 SEG Event 5: Simulator Operator CREW After the crew ACTIVATE [ET 5].

Responds to annunciator 1C05A (A-7) B CRD PUMP TRIP OR MOTOR has performed OVERLOAD This will cause a trip of the B CRD pump AOP 255.1, and accumulator alarms for 06-15 and 34-raised power CRS 35.

and at the

Directs starting A CRD pump in accordance with OI 255.

direction of the

If HPCI is required to be operable, verify HPCI suction is aligned to the examiner: CSTs When directed Simulator Operator

Contacts organization for support.

to investigate RO the cause of the Acknowledge the request.

Implement actions of ARP 1C05A (A-7) B CRD PUMP TRIP OR B CRD pump MOTOR OVERLOAD trip.

Determine the cause of CRD 1P-209B trip as follows o Monitor alarm "B" CRD PUMP 1P-209B LO SUCT PRESSURE (1C05A, B-7).

Two (2) minutes after being Simulator Operator o If necessary send an Operator to Bus 1A4 to check targets on directed to Breaker 1A410 Inform the control room that 1A410, B investigate B o As soon as practical, monitor computer points W092 and CRD pump breaker tripped on inverse CRD Pump time delay overcurrent. W093 for any bearing temperature > 180°F breaker:

If due to CAUSES 1.1 through 1.5, start CRD Pump 1P-209A per OI 255 (CRD Hydraulic System).

Three (3)

If 1P-209B tripped due to any electrical fault, initiate a Work Request minutes after Simulator Operator to have the pump checked, meggered, and repaired as necessary.

being directed Inform the control room that B CRD to investigate pump motor is abnormally hot.

B CRD pump locally:

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 43

NRC Initial License Exam, Scenario #1 SEG Event 5: Simulator Operator If the crew elects to start the A CRD pump in accordance with OI 255 here are the expected student responses.

When directed Activate [ET 28].

to verify The crew may address 1C05A (E-6) CRD MECHANISM HIGH TEMP, but This will position V-17-8 1/2 turn open.

adequate oil the condition is expected for the loss of the CRD Pump.

level and close Inform the control room that there is CREW V-17-8 to 1/2 turn adequate oil level in the A CRD pump open: motor and speed changer and the V

Implements OI 255, Section regarding Startup of a CRD Pump 8, A CRD Pump Discharge Valve is 1/2 CRS turn open.

Directs starting A CRD pump in accordance with OI 255, Section regarding Startup of a CRD Pump.

When contacted RO Simulator Operator as the Reactor

Prepare to start CRD Pump 1P-209A as follows:

Engineer and Acknowledge the request for support.

Verify adequate oil level in CRD Pump 1P-209A motor and speed informed of the changer High CRD Temperatures,

Close 1P-209A Pump Discharge Isolation V-17-8 to approximately 1/2 turn open.

Simulator Operator

Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in When directed Acknowledge the request. MANUAL.

to slow open V- AND

At 1C05, verify MO-1833, INLET TO CRD RETURN LINE, is fully open 17-8, A CRD Pump Activate [ET 27]

Start CRD PUMP 1P-209A by momentarily placing handswitch Discharge HS-1807A on 1C05 in the START position This will position V-17-8 full open in 60 Valve: seconds.

Slowly open Discharge Isolation V-17-8 to pressurize downstream piping and to prevent CRD pump from tripping on low suction pressure.

After the ramp Simulator Operator is complete and V-17-8 is full Inform the control room that V-17-8 is open: full open.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 43

NRC Initial License Exam, Scenario #1 SEG CREW

Implements OI 255, Section regarding Startup of a CRD Pump CRS

Directs starting A CRD pump in accordance with OI 255, Section regarding Startup of a CRD Pump.

When directed Simulator Operator RO to vent both Acknowledge the request.

Vent both CRD Discharge Filters 1F-201A and B CRD Discharge Filters: Inform the control room that time

At 1C05, verify charging header pressurized > 1200 psig on PI-1816A compression is being used and that CHARGING WATER PRESSURE both CRD Discharge Filters have been

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

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

Slowly adjust DRIVE WATER P CONTROL MO-1830 to obtain approximately 260 psid on PDI-1825A DRIVE WATER P Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 43

NRC Initial License Exam, Scenario #1 SEG If the crew elects to start the CRD pump in accordance with OI 255 QRC 1 here are the expected student responses.

CREW

Implements OI 255, QRC 1, CRD Rapid Start CRS

Directs starting A CRD pump in accordance with OI 255, QRC 1, CRD Rapid Start.

RO

If one CRD Pump is running, proceed to step (2), otherwise start CRD Pump as follows:

Close MO-1830, Drive Water P Control

Verify FC-1814, CRD System Flow Control in Manual and Closed

Start 1P-209A[B], CRD Pump

Throttle MO-1830, Drive Water P Control partially open.

Adjust FC-1814, CRD System Flow Control and throttle MO-1830, Drive Water P Control to achieve desired pressure and flow.

Verify operating CRD Pump motors above 9 amps

Restore FC-1814, CRD System Flow Control to Auto Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 43

NRC Initial License Exam, Scenario #1 SEG Accumulator CREW Trouble

Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO annunciator PRESSURE OR HI LEVEL response CRS If contacted to Simulator Operator

Comply with Technical Specification requirements for Control Rod Scram determine if Accumulators.

Inform the control room that there are there are any

May enter TS LCO 3.1.5.Condition A (twice)- One control rod scram NO slow control rods.

slow control accumulator inoperable with reactor steam dome pressure >900 psig.

rods based on o Declare the associated control rod scram time slow within 8 last scram time hours OR testing: o Declare the associated control rod inoperable within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Will Enter TS LCO 3.1.5 Condition B- Two or more control rod scram accumulators inoperable with reactor steam dome pressure >900 psig.

o Restore charging water header pressure to > 940 psig within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of discovery of Condition B concurrent with charging header pressure < 940 psig. AND o Declare the associated control rod scram time slow within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR o Declare the associated control rod inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Must verify less than 6 control rods have been declared slow

Must verify separation criteria for both slow control rods declaration and/or inoperable control rod declaration.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 43

NRC Initial License Exam, Scenario #1 SEG When directed Simulator Operator CREW to investigate

Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO Acknowledge the request.

accumulator PRESSURE OR HI LEVEL trouble alarms:

CRS Simulator Operator

Directs recharging the accumulators in accordance with OI 255.

Three (3) Inform the control room that the alarms RO minutes after are due to low pressure. Control rod

Implement actions of ARP 1C05A (F-7), CRD ACCUMULATOR LO being directed accumulator 06-15 is indicating 935 PRESSURE OR HI LEVEL to investigate psig and 34-35 is indicating 930 psig.

Check the Full Core Display on 1C05 to determine which accumulator I will recharge the two accumulators in accumulators are in the trouble condition.

trouble alarms: accordance with OI 255. o Determines that 06-15 and 34-35 are in trouble condition.

Send an Operator to the accumulators to determine the cause of the alarm.

Simulator Operator

Recharge accumulator per OI 255 (CRD HYDRAULIC SYSTEM).

Ten (10) Activate [ET 14]

minutes after being directed This will remove MF RD070615.

to recharge the Inform the control room that accumulators: accumulator 06-15 has been recharged.

Final accumulator pressure is 1200 psig.

Simulator Operator Ten (10) minutes after Activate [ET 15]

recharging 06- This will remove MF RD073435.

15:

Inform the control room that accumulator 34-35 has been recharged.

Final accumulator pressure is 1170 psig.

Continue to next event at examiners direction.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 43

NRC Initial License Exam, Scenario #1 SEG Event 6: Simulator Operator: Crew When directed Activate [ET 7].

Respond to auto initiation of HPCI.

by the This causes an auto initiation of HPCI.

examiner:

Implement OI 152, QRC 2, Tripping HPCI.

CRS Simulator Operator

Directs tripping HPCI after verifying that HPCI operation is not required When contacted by assuring that by 2 independent indications adequate core cooling is as Acknowledge the information.

assured.

organizational personnel to

Enters AOP 255.2, Power/Reactivity Abnormal Change support HPCI

Comply with Technical Specification requirements for HPCI.

auto initiation:

TS LCO 3.5.1.Condition F- HPCI System INOPERABLE o F.1.- Verify by administrative means RCIC System is OPERABLE If the operator immediately checks status of Floor Instructor o F.2.- Restore HPCI System to OPERABLE status within 14 days.

relay E41A-K6: Inform the operator that the relay appears the same as C71A-K3D. BOP

Implements actions of OI 152 QRC 2 to trip HPCI.

This relay is energized to demonstrate the

Depresses and hold HS-2259, Remote Turbine Trip PB understanding of what it should look like.

Verify HV-2201, HPCI Turbine Stop Valve Closes

When HPCI speed is zero rpm, places 1P-218, Aux Oil Pump, in PTL.

Verify HV-2200, HPCI Turbine Control Valve, closes

Verify annunciator 1C03-3C (A6) is activated.

Release HS-2259, HPCI Remote Turbine trip PB RO

Continues to monitor reactor power, pressure and level

May need to control level adjusting level setpoint.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 43

NRC Initial License Exam, Scenario #1 SEG AOP 255.2 due Crew to HPCI auto

Respond to auto initiation of HPCI.

start

Implement AOP 255.2, Power/ Reactivity Abnormal Change.

When contacted Simulator Operator CRS as

Directs AOP 255.2, Power/ Reactivity Abnormal Change.

organizational Acknowledge the information.

Establish critical parameter monitoring of Reactor Power, Reactor personnel to Pressure, and RPV Water Level, as priorities allow.

support HPCI auto initiation:

Notify the Reactor Engineer and Operations Manager.

After the cause has been determined and corrected, return to normal operation.

BOP

Take any necessary steps to bring the reactor power/reactivity transient under control, including, but not limited to:

Assuming manual control of a malfunctioning system (completed when HPCI was tripped)

Verify proper operation/indication of systems and/or indications.

Monitor the Off-Gas System radiation levels on Panel 1C02 for any change in Off-Gas activity.

RO

Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal

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

Verify thermal limits on the Official 3D Case

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

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 43

NRC Initial License Exam, Scenario #1 SEG Event 7: Simulator Operator: LOSS OF POWER EVENT LOOP, A DG Activate [ET 21] Crew Fails To Auto This will result in a Small Break LOCA Responds to Loss of Offsite Power Start. (Will start immediately on a ramp and a LOOP after in manual.) CRS 60 seconds The crew may initially enter Station Black Out until the SBDG is restored to 1A3 Small Recirc Simulator Operator:

Directs Reactor pressure control using SRVs Leak

Enters AOP 304.1 LOSS OF 4160V NON-ESSENTIAL ELECTRICAL POWER

Enters AOP 301 LOSS OF ESSENTIAL ELECTRICAL POWER Directs starting the A DG and verifying it loads the Bus Critical Task #2 IF the reactor is (CRITICAL TASK #2) shutdown under all conditions, THEN

Directs RPV level band 170 to 211 using available systems crew actions must be taken to restore and maintain RPV level for adequate RO core cooling. (> -25" or -39")

Provides RPV level and pressure status BOP

May report MSIV closure (Group I Isolation)

Diagnoses that the A DG did not start

Acknowledges that the B DG failed will not start and should be in Pull To Lock.

BOP will start the A SBDG with HS-3231A at 1C08 and verifies the output breaker closes.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 43

NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) CREW LOOP, A DG Responds to annunciator 1C05B-B1 - Primary Containment Pressure Hi/Lo Fails To Start Diagnoses rising containment pressure and lowering RPV water level.

but CAN be manually CRS started.

Directs a reactor scram due to lowering RPV water level from SBLOCA.

Small Recirc Leak

Direct the operator to Insert a manual reactor scram, and carry out IPOI 5 (Reactor Scram procedure)

Confirms that the reactor is shutdown

Direct the operator performance of the IPOI 5 immediate actions RO

Perform the immediate operator responses to a reactor scram.

Actions of IPOI 5 QRC-1:

o Initiate a backup manual scram o Place the Mode Switch in SHUTDOWN o Verify all control rods fully inserted (single rod permissive) o Verify condenser backpressure is stable o If all control rods are not fully inserted, use the RIPs per CRS o Restore and maintain RPV level +170 to +211 (setback) o Verify recirc runback to 20%

o Monitor RPV pressure o Verify Turbine/Generator trip o Verify neutron flux lowering o Insert SRM/IRM detectors o Announce scram via plant page o Proceeds to IPOI 5 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 43

NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) CRS Enters AOP 573 - Primary Containment Control LOOP, A DG

Directs operators to monitor containment parameters Fails To Start

Enters EOP RPV Control due to RPV low level (was entered when the but CAN be scram occurred).

manually

IF EOP-1 Alternate Level Control Leg is entered may direct:

started.

o Lockout of ADS Small Recirc o Start of CRD pump.

Leak o Start of SBLC pump Directs Reactor Water level band of 170 to 211 using available systems - (HPCI unavailable, will lead to ED)

Directs Defeat 4 - This results DW Cooling Fans in FAST

Enters EOP Primary Containment Control when containment pressure reaches 2 psig.

Directs initiation of Torus Spray prior to Torus Pressure exceeding 11 psig

IF Torus Pressure exceeds 11 psig, directs initiation of Drywell Spray.

Directs Defeat 4 - This results DW Cooling Fans in FAST

Enters EOP Primary Containment Control when containment pressure reaches 2 psig.

Directs initiation of Torus Spray prior to Torus Pressure exceeding 11 psig

IF Torus Pressure exceeds 11 psig, directs initiation of Drywell Spray.

Event 8: Simulator Operator: BOP HPCI starts but Verify [ET 23] is active Starts HPCI to maintain RPV level band. (HPCI will start but will trip) trips Reports to crew that HPCI has tripped.

Verify hp02 is on delay when the HPCI Turbine is started. Attempts to restart (unsuccessful).

After HPCI runs for 15 seconds the HPCI Turbine Trips.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 43

NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) RO LOOP, A DG

Assists BOP in controlling RPV level and monitoring other critical primary Output BKR containment plant parameters FAILS and will not close. B DG BOP Fails To Start

If directed, performs Defeat 4 to maximize drywell cooling but CAN be

Places Torus Spray in service as follows:

manually started. 1. Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve Small Recirc handswitch in OPEN and verify valve opening Leak 2. Throttle open MO-2006[MO-1933], Torus Spray Valve

As directed starts CRD pump

1. Ensures Recirc Pumps are tripped

2. Repositions HS-1903C - Enable Containment Spray Valves to Manual

3. Depending on RPV level may take HS-1903B to 2/3 Core Coverage/LPCI INIT Interlock Override to MANUAL OVERRD

4. Open MO-2000[1902] , Inboard Drywell Spray Valve

5. Throttle open MO-2001[1903], Outboard Drywell Spray Valve.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 32 of 43

NRC Initial License Exam, Scenario #1 SEG Crew

Implements the mitigation strategies of EOP 1, RPV Control RO

Inserts a manual reactor scram.

Completes a scram report that includes all rods in, reactor pressure and trend and reactor water level and trend.

Restores and maintains RC/L 170-211 using RCIC and other alternate injection systems.

Maintains RC/P 800-1055 psig. using directed pressure control systems.

Lowers reactor pressure to the directed control band using the directed control system.

CRS

Performs a crew update of entry into EOP 1 due to RPV level or Drywell Pressure.

Directs an RPV level band of 170-211 using RCIC and other alternate injection systems.

Directs installation of Defeat 11

Directs an RPV pressure band of 800-1055 psig using directed pressure control systems.

Directs lowering reactor pressure to lessen the driving head on the leak in the drywell.

Shows concern for maintaining plant cooldown within the limits.

Placekeeps in EOP 1 to the applicable WAIT UNTIL step in RC/P (RC/P-6) leg Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 33 of 43

NRC Initial License Exam, Scenario #1 SEG Crew

Respond to and implement the actions of AOP 304.1, Loss of 4160V Non-Essential Power BOP

Announces suspending all evolutions in progress associated with electrical switchgear and switching operations

Verify two Well Water Pumps in service. Starts either A or C Well Water Pump and adjusts well water flow.

Verify Well Water Pump 1P-58D secured. In AUTO, verifies FC-4414D, demand is zero.

Verify GSW Pumps 1P-889A and B in service

Place Bus 1A1 Transfer switch in MANUAL.

Place Bus 1A2 Transfer switch in MANUAL.

CRS

Enters AOP 304.1, Loss of Both Non-Essential Buses

Directs the BOP to take actions IAW AOP 304.1 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 34 of 43

NRC Initial License Exam, Scenario #1 SEG Crew

Implements the mitigation strategies of EOP 2, Primary Containment Control At the direction Simulator Operator: BOP of the Lead Activate [ET 24]

Examiner This will trip the A CRD Pump

Informs the CRS of containment parameters including parameter name, value and trend.

Installs Defeat 4.

Critical Task #22 BEFORE drywell

Utilizes OI 149 QRC to spray the torus.

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

Utilizes OI 149 QRC to spray the drywell.(Critical Task #22)

Trips the running recirculation pump.

CRS once the crew completes the Simulator Operator:

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

ED Brief and at Activate [ET 9]

Obtains containment parameters.

the direction of This will trip the RCIC Pump

Directs installation of Defeat 4.

the Lead

Directs spraying the torus after confirmation that torus pressure is greater Examiner than 2 psig.

Directs spraying the drywell before drywell temperature reaches 280F.

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.

Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in T/L (T/L-3 and T/L 10), T/T (T/T-2), DW/T (DW/T-6) and PC/P (PC/P-7) legs Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 35 of 43

NRC Initial License Exam, Scenario #1 SEG Crew

Implements that mitigation strategies of the ALC contingency of EOP 1 BOP

Lockouts ADS.

RO

Attempts to restore and maintain RPV level above +15

Maximizes injection with CRD in accordance with AIP 407.

Injects with SBLC in accordance with AIP 406.

Verifies injection subsystems can be lined up for injection

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

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.

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:

Informs SRO when 4 SRVs are open

Monitors and controls RPV level as he depressurization occurs Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 36 of 43

NRC Initial License Exam, Scenario #1 SEG Critical Task #1 IF the reactor is CRS Directs the performance of ED once RPV Water Level cannot be shutdown under all conditions and RPV maintained > +15 (Critical #1) level drops to +15, THEN perform ED-1 Override open CV-4371A (Defeat 11) - Completed Earlier In The Emergency RPV Depressurization Scenario before RPV level reaches -25".

ED-2 Are all control rods inserted to at least position 00? (YES)

ED-5 Does a drywell high pressure ECCS signal exist? (YES)

ED-6 Prevent injection from Core Spray and RHR pumps not required to assure adequate core cooling.

ED-7 Is torus water level above 4.5 ft? (YES)

ED-8 Open the 4 ADS SRVs.

OK to exceed Cooldown rate limit.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 37 of 43

NRC Initial License Exam, Scenario #1 SEG Crew

Implements mitigation strategies of EOP 1 after EOP ED to restore adequate core cooling RO

Verifies low pressure ECCS systems start and align to inject into the RPV

Reports when 1 Core Spray pump is injecting above 3000 gpm. and 1 other ECCS pump is injecting.

Trips Core Spray pumps when RPV level indicates on the GEMACs

Throttles RHR injection to restore and maintain RPV 170-211 CRS

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

Direct injection with one or more 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

Directs tripping Core Spray pumps when RPV level indicates on the GEMACs Directs throttling RHR injection to maintain RPV level 170-211 CRS and Crew:

Diagnoses HPCI failure to run Directs Emergency Depressurization.

Directs Opening 4 SRVs (CRITICAL TASK #2)

When Directed opens 4 ADS SRVs to emergency (CRITICAL TASK #2)

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 38 of 43

NRC Initial License Exam, Scenario #1 SEG

- - END OF SCENARIO ***

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 39 of 43

NRC Initial License Exam, Scenario #1 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Jacket Water Leak on B SBDG

2. Stuck Control Rod

3. B CRD Pump Trip

4. Low HCU Pressure

5. HPCI Spurious Start After EOP Entry:

1. Failure of A SBDG To Start

2. LOOP

3. A CRD Pump Trips

4. RCIC Trips

5. HPCI Trips Abnormal Events:

1. AOP 255.1, CONTROL ROD MOVEMENT/INDICATION ABNORMAL

2. AOP 255.2, POWER/REACTIVITY ABNORMAL CHANGE

3. AOP 301, LOSS OF ESSENTIAL ELECTRICAL POWER Major Transients:

1. LOOP

2. LOCA

3. ED Critical Tasks:

1. Critical Task #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. (> -25" or -39")

2. Critical Task #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".

3. Critical Task #22 BEFORE drywell temperature reaches 280°F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays.

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 40 of 43

NRC Initial License Exam, Scenario #1 SEG

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.

(> -25" or -39")

Safety Adequate core cooling is defined by EOPs as either:

Significance:

Core submergence (+15")

Steam cooling with injection of makeup water to the RPV (-25")

Required ECCS injection with RPV level above 2/3 core height (-39")

Cue: RPV level will drop to <+15" and automatic system response will not restore RPV level for adequate core cooling.

Performance If the crew performs actions that restore and maintain RPV level above +15, Standard: this critical task should be considered satisfactory because the crew has anticipated the potential loss of core cooling.

If one CS is operating at 3000 gpm and another ECCS pump is injecting, RPV water level must be restored and maintained above -39". This would normally be expected after an Emergency RPV Depressurization.

If ECCS is not injecting (less than 1 CS at 3000 gpm and another ECCS pump injecting), RPV water level must be restored and maintained above -25". This may be expected after an emergency RPV depressurization with ECCS problems Progression is to be made by the crew to use all available systems to restore RPV level above the directed level (-25" or -39"). Satisfactory performance of this CT does not require completion of starting all available systems if RPV level is restored above the directed level (-25" or

-39").

If RPV injection is secured and RPV level is below +15" but above -25",

the critical task is met, although remediation may be required.

Feedback: Lowest valid RPV water level indicator is being maintained above directed value.

EOP step(s): RC/L-10, L-11, L-12 BWROG: RPV-1.2 (1.2 is only after RPV pressure is lowered)

Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 41 of 43

NRC Initial License Exam, Scenario #1 SEG

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".

Safety If the lowering RPV water level trend had not been reversed before RPV level Significance: drops to +15", emergency RPV depressurization should be performed prior to RPV level reaching -25". The consequence of not depressurizing the RPV when level is below -25" is a loss of adequate core cooling. Depressurizing prematurely may unnecessarily cause unneeded stress on the RPV and piping.

Cue: RPV level lowered to +15".

Performance The crew must Initiate emergency RPV depressurization after the lowest valid Standard: level indication shows <+15" and prior to the lowest valid level indicates -25".

The critical task is not satisfactory if the actions for Emergency RPV Depressurization are not complete. (See definitions)

Feedback: RPV pressure is rapidly lowering.

EOP step(s): RC/L-4, L-7, L-8 BWROG: RPV 1.1 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 42 of 43

NRC Initial License Exam, Scenario #1 SEG

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

Safety If DW sprays were initiated when in the shaded area of the DWSIL, this could Significance: lead to an evaporative cooling pressure drop which could result in:

Deinerting the containment or containment negative pressures below design.

OR

Drywell-below-torus differential pressure beyond design.

Operation of DW sprays if DW temperature cannot be maintained below 280°F, will ensure that the design temperatures of the components within the DW are not exceeded.

If DW sprays are not utilized when available, the next EOP actions will be to Emergency RPV Depressurize, which will lower the amount of ambient heat to the DW, but will cause additional pressure/temperature stress on the RPV.

Cue: DW temperature is rising and is below 280°F.

Average DW temperature and DW pressure conditions allow DW spray per the DWSIL curve Performance DW sprays are initiated on at least one side of RHR prior to 280°F DW Standard: temperature.

If DW sprays are initiated while in the shaded area of the Drywell Spray Initiation Limit (DWSIL), this would be a critical task failure.

If the crew does not secure Recirculation pumps prior to initiating DW sprays, the critical task is considered satisfactory although remediation may be required.

Feedback: DW spray flow initiated and DW temperature is lowering.

EOP step(s): DW/T-4, -5 BWROG: N/A Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 43 of 43

SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #:

LMS ID: LMS Rev. Date:

SEG TITLE: NRC Initial License Exam, Scenario #2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~ 90 minutes Developed by: Raymond Keith Walton 1/28/2015 Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 40

NRC Initial License Exam - Scenario #2 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures:

Enabling There are no formal learning objectives for this evaluation.

Objectives:

Prerequisites: None Training Simulator Resources: Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team

References:

STP 3.3.1.1-17 Rev 08 OI 358 Rev 66 AOP 358 Rev 31 OI 149 Rev 146 ARP 1C05A Rev 78 OI 150 Rev 78 AOP 255.1 Rev 44 EOP 1 Rev 18 AOP 255.2 Rev 42 EOP 2 Rev 16 AOP 302.1 Rev 54 EOP ATWS Rev 21 AOP 691 Rev 8 TRM Tech Specs Protected Content: Identify here and in training material as {C001}; See Comment for details.

None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 40

NRC Initial License Exam - Scenario #2 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See Cover Initial development for Initial development for 2015 NRC 0 2015 NRC LOIT N/A LOIT examination. See Cover examination.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 40

Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________

Initial Conditions: The plant is operating at 80% power due to a downpower for maintenance. Thunderstorms are forecast for the area. B CRD pump was recently taken OOS for maintenance.

Turnover:

Start B SBDG for ST after maintenance.

Raise Reactor power recirculation flow.

Event Event # Malf # Eventy Description Type*

1 None N BOP Perform MSIV test per STP 3.3.1.1-17 for D MSIVs 2 None R RO Raise Power with Recirculation Flow to 85% RTP R SRO 3 rp02a C BOP Trip of RPS MG Set TS SRO Tech Spec 3.3.8; 3.4.5, A & B & C; TRM 3.3.4 entry 4 rd01 C ATC Control Rod Drift (30-23) with AOP 255.1& 255.2 entry 3023 TS SRO Tech Spec entry 3.1.3 5

ed13a C BOP 125 VDC Div 1 panel 1D11 trip results in AOP entries TS SRO Tech Spec entry 3.8.7, Condition B 6 rc08 BOP Spurious start of RCIC, requires manually stopping RCIC TS SRO Tech Spec Entry 3.5.3, Condition A 7 mc04b R RO Condenser Vacuum Leak (recoverable)

C BOP Fast Power Reduction 8 mc04b M ALL Rising backpressure from Event 5 progression necessitates reactor scram.

ATWS occurs 9 hp03 I BOP Failure of HPCI controller (complicates RPV level restoration).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 40

Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.

General Instructions

1. Reset to IC23 and raise power to ~80% RTP

a. Load Events

b. Load Malfunctions

c. Load Overrides

2. OR Reset to the IC provided by the LOIT Exam Development Team

3. Verify Events validate FALSE

4. Reset APRM Gains and clear recorders

5. Complete the Exam Setup Checklist

6. Ensure no BIAS is inserted on the FRV Controllers by verifying Y at 0.0

7. Fill in STP 3.3.1.1-17 Cover Matter through prerequisites, and have for turnover.

8. Verify MOL Pull Sheets are out.

Trigger No. Trigger Logic Statement Trigger Word Description 3, 5, 7, 9, Manual Trigger 11, 13, 15, 17 20 ZLOHPHS2202(2) == 1 HPCI MO 2404 Starts to open Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 40

Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup rp02a RPS EPA BREAKER TRIP-3 Inactive Active RPS A EPA BKR Setup rd013023 CONTROL ROD DRIFTS OUT-5 Inactive Active ROD 30-23 Setup ed13a 125 VDC DISTRIBUTION 7 Inactive Active PANEL FAULT- PNL 1D11 Setup mc04b MAIN CONDENSER AIR 6 min 9 0 .9 INLEAKAGE- HP CONDENSER Setup rc08 INADVERTENT RCIC 11 Inactive Active INITIATION Setup mc04b MAIN CONDENSER AIR 3 min 13 .9 1.2 INLEAKAGE- HP CONDENSER Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE VOLUME 0 75 (VARIABLE)

Setup hp03 HPCI FLOW CONTROLLER 1 min 20 As Is 30 FAILS Setup fw02a CONDENSATE PUMP TRIP-15 Inactive Active PUMP A Setup fw02b CONDENSATE PUMP TRIP-15 Inactive Active PUMP B Setup rc01 RCIC OVERSPEED TRIP 17 Inactive Active Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 40

Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Remote No. Remote Title Delay Ramp ET Initial Final Value Value Setup mc01 MN COND 1E-7A VACUUM BREAKER V-03-73 28 CLOSED OPEN (CLOSED,OPEN)

Setup mc02 MN COND 1E-7B VACUUM BREAKER V-03-67 28 CLOSED OPEN (CLOSED,OPEN)

Setup rp02 ATWS TEST SWITCH (AKA 2:30 DEFEAT 12) HS-1863A 12 RUN TEST min (RUN,TEST)

Setup rp03 ATWS TEST SWITCH (AKA DEFEAT 12) HS-1864A 3 min 12 RUN TEST (RUN,TEST)

Time Override No. Override Title Delay Ramp ET Initial Final Value Value Setup DI-PC-037 HS-4321A GRP 7 CHAN A DW NORMAL NORMAL CLG AND FAN OVR DI-PC-038 HS-4321B GRP 7 CHAN B DW NORMAL NORMAL CLG AND FAN OVR Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 40

Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 SHIFT TURNOVER INFORMATION

Day of week and shift o Today o Day Shift

Weather conditions o Mild summer morning

(Plant power levels) o Reactor Power Level 80%

o Core Flow 40 Mlbm/hr

Protected train o Protected Train is B

Technical Specification Action statements in effect o None

Locked in / failed annunciators and alarms o None

Evolutions in progress or planned for upcoming shift o Perform STP 3.3.1.1-17, Main Steam Isolation Valve Functional Test for D Main Steam Line ONLY.

Retesting a relay.

o Raise power with recirculation flow to achieve 85% RTP following a sequence exchange per RE direction.

Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline GREEN with one year to YELLOW o LERF Baseline GREEN with one year to YELLOW

Existing LCOs, date of next surveillance o None.

Procedures or major maintenance in progress o None

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment

Comments, problems, operator workarounds, etc.

o One Extra NLO Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW:

Perform Main Verifies Prerequisites for STP 3.3.1.1-17:

Steam Isolation

No other testing on the RPS System Valve Testing

All MSIVs are OPEN CRS:

Authorizes performance of STP 3.3.1.1-17 for D MSIVs.

BOP:

Verify energized at 1C15, RPS Trip Channel A1 B Line MSIV 90%

OPEN relayC71A-K3E.

Verify energized at 1C15, RPS Trip Channel B1 C Line MSIV 90%

OPEN relayC71A-K3F.

If the MODE SWITCH is in RUN, then visually confirm (at 1C15) the following CHAN A1 MSIV CLOSURE SCRAM BYP MODE SWITCH NOT IN RUN relay C71A-K11A contacts open (if MODE SWITCH is not in RUN, mark step 7.1.2.a and 7.1.2.b N/A)

Station personnel at 1C15 and 1C17 in preparation for observing test response of relays to the C71A-K3H and C71A-K3G, concurrent with cycling CV-4420 and CV-4421

At 1C03, take A INBD MSIV TEST CV-4420 handswitch HS-4412B to TEST and release.

At 1C03, verify that CV-4420 goes partially closed and reopens fully.

RO:

Perform Peer Checks EXAMINER NOTE: After completion of STP, crew will move to raise reactor power Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: CREW:

Raise Power The crew will brief the reactivity change prior to taking the shift.

with Recirculation CRS:

flow.

Directs power to be raised from 80 to 85% using recirculation pump flow.

Simulator Operator:

RO:

If Contacted as the Reactor Inform the crew to raise power with Recirc

Performs Recirculation Pump flow adjustments to raise power from Engineer to Flow to achieve approximately 85% power 80% to 85%.

provide and hold power constant until a rod

Monitors plant parameters for expected response during reactivity guidance, sequence is approved for further power manipulation.

ascension.

BOP:

Evaluator Note:

Monitor the plant.

Proceed to the next event when core flow

Perform Reactivity Peer Checks to the ATC while adjusting reaches ~44 mlbm/hr (~83% RTP) or at Recirculation flow.

the discretion of the Lead Examiner.

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NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 CRS:

Trip of RPS MG Directs Operators to IAW AOP 358 Set

Technical Specifications for this condition are listed on the next page.

Tech Spec RO:

3.3.8 entry

Report Power Pressure Level Report Simulator Operator:

Report the Loss of A RPS At the direction Activate [ET 3] BOP:

of the Lead Examiner Respond as plant personnel as necessary.

Complete actions IAW AOP 358 o Direct an Operator to 1A3 Essential Switchgear Room to Simulator Operator: assist in troubleshooting the RPS Electrical Distribution When called as Reports the A RPS MG Set is tripped and system.

the 2nd Asst. to faint acrid smell and abnormally hot to o Suspend all evolutions in progress associated with electrical investigate the touch, Both EPAs are tripped. 1Y30 looks switchgear and switching operations.

loss of RPS, ok.

wait 2 minutes, o Verify applicable automatic actions have occurred. Manually initiate those automatic actions that should have occurred but failed to occur.

o Declare CIT-2738 inoperable, due to loss of RWCU flow to monitor. Refer to TRM 3.3.4 Simulator Operator:

When called as o Verify the fault is not suspected to be on the RPS bus prior to the 2nd Asst. to Report that 1Y16 is aligned to the alternate reenergizing the bus on the RPS Power Supply.

verify Alt power RPS power. [verify RF rp04 is in 1Y16] o IF an alternate RPS power supply is available as indicted by aligned to 1Y16, observing A MG or ALT XFMR white light ON at 1C15 Place handswitch C71B S1A RPS ALTERNATE POWER TRANSFER to A MG OR ALT position as required and verify Simulator Operator: selected position white light remains on.

When contacted to verify the Report cleanup beds in hold. o WHEN A RPS bus is energized then as directed by the CRS, Cleanup Beds perform OI 358 RPS Appendix 4, RPS POWER SUPPLY in hold, wait 3 TRANSFER HALF SCRAM RECOVERY CHECKLIST, and minutes restore RWCU System.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed Simulator Operator: CRS:

to verify sat inform the control room that everything TS Entries possible operation of the appears normal.

Enters TSs C EPAs, Wait 2 minutes and o TRM LCO 3.3.4 A RCS Conductivity monitor 4 hr to restore monitoring.

o TS LCO 3.3.1.1 A One or more required channels inoperable.

All Required actions met Simulator Operator: o 3.3.1.1 B One or more Functions with one or more required When contacted Acknowledge the request for support. channels inoperable in both trip systems. All Required as Chemistry, actions met o TS LCO 3.4.5 A, Required Drywell Sump System inoperable.

Restore required Drywell Sump System to OPERABLE status. 24 hrs.

o TS LCO 3.4.5 B, Required Primary Containment Air Sampling System inoperable.

Initiate action to restore required Primary Containment Air Sampling System to OPERABLE status.

Immediately o TS LCO 3.4.5 C, Required Drywell sump System and containment air sampling inoperable, Restore Drywell Sump System to Operable OR restore Air Sampling to Operable 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months o TS LCO 3.3.3.1 One or more Functions with one required channel inoperable. 30 day LCO o TS LCO 3.6.1.3 A (12 times) (If Overriden) - Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unless MSIV Applicable to all the Group 3 Isolation vales repositioned in the Group 3 Isolation ARP actions Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE OI 358 Appendix 4 Actions DSM Simulator Operator: BOP:

Acknowledge to support.

At 1C05, position REACTOR SCRAM RESET hand switch C71A-S5 to Group 1 and 4 [Group 2 and 3] and then to Group 2 and 3 [Group 1 and 4] to reset Half Scram.

Electricians Simulator Operator:

Verify "A"["B"] RPS AUTO SCRAM annunciator (1C05A[B], A-2[A-2]) reset.

Acknowledge to support.

At 1C36, reset Main Steam Line radiation monitors RIS-4448A/C[B/D].

At 1C36, reset Fuel Pool Exhaust radiation monitor RIS-4131A[B].

At 1C36, reset Carbon Bed Vault radiation monitor RM-4138.

At 1C05, momentarily press and release:

PCIS DIV 1 RESET pushbutton A71B-S32 and PCIS DIV 2 RESET pushbutton A71B-S33 verifying the following annunciators reset:

o PCIS GROUP 1 ISOLATION INITIATED (1C05B, A-8) o PCIS GROUP 2 ISOLATION INITIATED (1C05B, B-8) o PCIS GROUP "4" ISOLATION INITIATED (1C05B, D-8) o PCIS GROUP "5" ISOLATION INITIATED (1C05B, E-8)

Verify reactor water sample valves are restored to their desired lineup per IPOI 7 Attachment 5, Group 1 Isolations.

Notify Shift Chemistry Technician to restore Hydrogen Chemistry System CAVs analyzers to service if required.

Allow the crew

Reenergize the following RWCU isolation valve(s) as necessary to get to the 1/2 [NA any non-applicable step(s)]:

Scram o MO-2700 (at 1B3219)

Recovery

Restart RWCU System as directed per OI 261 (Group 5).

Checklist prior

Exit Tech Spec as necessary for applicable PCIVs returned to operable to proceeding. status due to re-energizing the valve in the previous step.

Actions Continued on the next page Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP:

At 1C04, open A [B] PUMP MINI PURGE ISOL CV-1804A[CV-1804B] by taking HS-1804A[HS-1804B] to CLOSE, then to OPEN, allowing it to spring-return to AUTO.

Verify the following GROUP 3 Isolations RESET per IPOI 7, unless CRS directs otherwise [NA any non-applicable step(s)]:

o Standby Gas Treatment System per OI 170.

o Drywell (Containment Atmosphere Control System) per OI 573.

o Reactor Building HVAC System per OI 734.

Verify PCIS GROUP 3 ISOLATION INITIATED annunciator (1C05B, C-8) reset.

At 1C35, place CV-4371A GROUP 3 OVERRIDE switch S583B in NORM

Verify the following GROUP 2 Isolations RESET per IPOI 7, unless CRS directs otherwise Examiner Note: When the crew is about to restore Cleanup to service and at the lead examiners direction, move on to the next event.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: CREW:

Control Rod Diagnoses control rod 30-23 is drifting Drift with AOP CRS:

entry

Directs entry to AOP 255.1, Control Rod Movement/Indication Tech Spec Abnormal, Mispositioned control rod section.

entry 3.1.3

Directs entry into AOP 255.2 Power Reactivity Abnormal Change.

Simulator Operator:

Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, At the direction requirements are met.

of the lead Activate [ET 5]

examiner, This will actuate RD013023, causing Rod

Evaluate the entry into TS LCO 3.1.3 C Control Rod Inoperable once 30-23 to drift out of the core. the control rod is isolated.

Direct the Organization to write a clearance to remove the Amphenoils to electrically disable the HCU after it is Isolated.

If contacted as Simulator Operator:

Contacts RE and/or Duty Manager.

the second report that the HCU lineup is normal and RO:

assistant HCU pressure is normal.

Recognizes Rod 30-23 is drifting and informs the SRO.

1C05A (D-6) Rod Drift Actions o At 1C05, select affected Control Rod, monitor 4 rod display to determine if a control rod is drifting, and if so in what direction.

o Actions Continue on the next page.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE o IF any control rod is drifting OUT, perform the following:

If more than one rod is drifting OUT, manually scram the reactor per IPOI 5 (Reactor Scram).

Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN Simulator Operator: position momentarily (less than 1/2 second) to abort the rod sequence timer.

Acknowledge the request When directed If any control rod indicates withdrawal movement, to Mechanically attempt to drive the affected rods in to their required Isolate HCU 30- delete malfunction RD013023 and call positions per the rod sequence by placing the C11A 23, wait 4 back and inform the control room the hcu has been isolated with V-18-1008 (30-23), S3 EMERG IN/NOTCH OVERRIDE SELECT switch on minutes and 1C05 in the EMERG ROD IN position.

Insert Isolation, and V-18-1275 (30-23)

Withdraw Isolation. If any control rod inserted per Step 3.2.c begins to drift out again, fully insert the affected rods by:

If necessary, place the RWM Operators Display (RWM-OD) keylock mode switch to the BYPASS position.

Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position.

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.

Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the OFF position.

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

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: BOP:

Control Rod

Monitors balance of plant equipment/plant status.

Drift

Contacts SANSOE to inspect control rod 30-23 HCU for abnormalities.

(Contd)

Simulator Operator:

When contacted as the Reactor Acknowledge and inform the control Enginer, room that you will evaluate the current rod configuration.

When contacted Simulator Operator:

as the Acknowledge the request for support.

DSM/Operation s Direstor EXAMINER NOTE: Continue to next event at examiners direction.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: CREW 125 VDC Div 1 The crew will recognize the loss of 1D11 panel 1D11 trip CRS:

results in AOP

Possibly enters AOP 644 entries

Enters AOP 302.1-Loss of 125 VDC Power, Tab 1-Loss of 125vdc Tech Spec Div 1 entry (3.8.7.B)

May direct, as time permits, the RO to transfer to A level control to control reactor level and try to maintain normal band.

Simulator Operator:

Enters TS LCO 3.8.7.B - 8 Hr LCO (1D11)

At the direction

Directs transferring non-essential power to the startup transformer.

of the Lead Activate [ET 7]

Examiner This inserts ed13a causing a loss of 1D11 RO:

Takes manual control of FW and attempts to restore reactor water level to the normal band.

OR Simulator Operator:

Place the A level controller in service with handswitch If reactor water Activate [ET 9]

Place 3 Element to Single Element level increases move to next event.

Monitor Power Pressure and Level at 1C05 to a scram, then NOTE: If the RO does not place the level controller to A a scram will occur.

When contacted Simulator Operator:

as the second assistant to go report after 2 minutes that 1D10 CKT 6 to the 1A3 has tripped free and there is no sign of smoke or fire at the breaker. BOP Actions Continued on the next page.

switchgear room to in Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Simulator Operator: Actions continued from the previous page.

When directed inform the control room that there are no BOP:

to investigate abnormal indications and all breakers are

Recognize the Loss of 1D11 1D11, wait 1 Closed.

Monitors BOP Equipment minute

Transfers non-essential power to the startup transformer per OI 304.1, section 4.2. as follows.

o Place the BUS 1A2 TRANSFER breaker mode selector switch in the MANUAL position.

o Select Phase 1 with the BUS 1A2 STARTUP XFMR AMPERES meter switch and observe the ammeter reading.

Select Phase 1 with the BUS 1A2 AUX XFMR AMPERES Simulator Operator: meter switch.

When contacted Acknowledge the request for support.

o Place the control switch 4KV BREAKER 1A202 STARTUP to provide XFMR TO BUS 1A2 momentarily in the CLOSE position.

organizational Observe that the red (breaker closed) and the white (closing

support, spring charged) indicating lights are ON o Observe that the bus has parallel supplies by observing current on the supply ammeters.

o Trip the supply breaker from the auxiliary transformer by placing the control switch 4KV BREAKER 1A101[201] AUX XFMR TO BUS 1A1[1A2] momentarily in the TRIP position.

Observe that the white (closing spring charged) and the green (breaker open) indicating lights are ON.

Actions Continued on the Next Page.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions Continued from Previous Page.

Transfers non-essential power to the startup transformer per OI 304.1, section 4.2. as follows.

o Select individual phases with the BUS 1A1[1A2] STARTUP XFMR AMPERES meter switch to observe the current load and to verify approximately equal phase currents.

o On the BUS 1A1[2] VOLTS meter, verify that all three phases indicate approximately 4160V by selecting each phase selector switch position. Observe that all three white (phase energized) indicating lights are ON.

o Place the BUS 1A1[2] TRANSFER breaker mode switch in the AUTO position.

o If both 1A1 and 1A2 non-essential buses are now powered from the Startup Transformer, notify ITC Midwest System Control Operator that the Auxiliary Transformer has been unloaded and to adjust the DAEC 161 KV bus low limit in EMS accordingly. - NA o Record the time ITC Midwest was notified the Auxiliary Transformer was unloaded in the Operating Log.

Continue to next event at examiners direction.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6: Crew:

Acknowledges annunciator 1C04c Spurious start of RCIC, Announces alarm to the SRO requires manually CRS:

stopping RCIC Will direct the follow actions:

Tech Spec

Trip RCIC Entry 3.

Reenter AOP 255.2 for Power Reactivity Abnormal

Enter TS 3.5.3 Conditon A for RCIC Inoperable.

May look at TS 3.3.5.3 for RCIC instrumentation.

At the Simulator Operator:

discression the Activate [ET 11]

Establish critical parameter monitoring of Reactor Power, Lead Examiner This will spuriously start RCIC Reactor Pressure, and RPV Water Level, as priorities allow.

RO:

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

Verify thermal limits on the Official 3D Case.

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

Flow Map.

When sent to

Notify the Reactor Engineer and Operations Manager.

investigate the Simulator Operator: BOP:

Spurious start Inform the control room that the Level

Depress HS-2460, RCIC Manual Turbine Trip pushbutton.

of RCIC, wait 3 Switch for the RCIC Turbine has minutes,

Verify MO-2405, RCIC Turbine Stop Valve, closes.

actuated.

Verify MO-2512, RCIC Inject Valve, closes.

Verify MO 2510, RCIC Min Flow Bypass Valve, closes.

Continue to next event at examiners direction.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Crew:

Recognizes the rising backpressure Condenser Simulator Operator:

Vacuum Leak Activate [ET9] CRS:

(recoverable) Will direct the follow actions:

This will insert mc04b, result in degrading Emergent backpressure.

Enter AOP 691 Power

Perform a fast power reduction to maintain condenser Reduction backpressure.

Direct IPOI 4 Fast Power Reduction HP Tech high Simulator Operator: RO:

rad brief Acknowledge the order

Perform Fast Power Reduction (complete step sequence on the next page.

If contacted as o Lower Recirculation flow to 39 Mlbm/hr.

Aux Operator to Simulator Operator: o Insert control rods IAW the fast power reduction sequence perform a High Acknowledge the order sheet.

Rad Entry to investigate.

Insert a manual reactor scram if condenser backpressure reaches 6 of Hg absolute.

BOP:

if the crew Simulator Operator:

inserts a Activate [ET 13]

Establish critical parameter monitoring of condenser backpressure.

manual scram If contacted as the Aux Simulator Operator:

Operator to go Acknowledge the order in to the condenser bay and investigate Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Fast Power Reduction Steps IAW IPOI 4 RO:

o IF core flow is greater than or equal to () 39 Mlb/hr AND power is greater than or equal to () than 70 percent of rated, THEN at 1C04, reduce A and B MG SET SPEED CONTROL to lower core flow to 39 Mlb/hr while maintaining level between +186" and +211".

o Perform the following as required to reduce core flow and to insert rods per the Fast Power Reduction Sequence Sheet(s)

Bypass the Rod Worth Minimizer.

Station a second licensed operator in place as a peer checker for control rod movement.

If necessary to achieve desired conditions, insert control rods using the Fast Power Reduction Sequence Sheet(s) until power is less than or equal to

() 70% with core flow greater than or equal to () 39 Mlb/hr (equivalent to load line of less than 80%).

At 1C04, reduce A and B MG SET SPEED CONTROL to lower core flow to 27 Mlb/hr while maintaining level between +186" and +211".

Insert control rods using the Fast Power Reduction Sequence Sheet(s) until power is less than or equal to

() 36% with core flow greater than or equal to () 27 Mlb/hr (equivalent to load line of less than 52%).

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Back pressure Crew gets worse.

The crew will determine that continued degradation in condenser backpressure will reach a turbine trip setpoint and take the unit offline.

Enters and implements the actions of IPOI 5, Reactor Scram.

Simulator Operator:

Enters and implements the actions of EOP 1, RPV Control.

At the direction of the Lead Activate [ET 13] RO:

Examiner, This will worsen the condenser air

Scrams the reactor and performs the scram choreography.

inleakage driving the crew to insert a

Reports a hydraulic ATWS and reactor power.

manual scram.

Dials master feed water regulating valve controller to 158.5 in AUTO CRS:

With the *Simulator Operator:*

concurrence Modify MC04B to 1.8 with a 30 Sec

Directs scramming the reactor and performing IPOI 5, Reactor Scram.

from the Lead Ramp to drive the crew to scram if the

Enters EOP 1 due to a scram required with power above 5% or unknown.

Examiner fast power reduction is effective at

Verifies automatic isolations, ECCS initiations, and SBDG initiation.

maintaining back pressure.

Transitions to EOP ATWS.

When all rods are inserted, Simulator Operator:

Activate [ET 15]

this will trip both condensate pumps At the direction of the Lead

Examiner, Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Simulator Operator: Crew If directed to Acknowledge the request, wait 10 minutes

Implements the mitigation strategies of ATWS.

locally trip the and use [RF rr11] and open the drive RO:

A Recirc MG motor breaker. Call the control room and Set Drive Motor inform them that the drive motor breaker is

Reports a hydraulic ATWS and reactor power.

Breaker open.

Dials master feed water regulating valve controller to 158.5 in AUTO Floor Instructor

Performs the ATWS QRC.

Manually driving control rods, drifting

Reports completion of the ATWS QRC. Determines that ARI was NOT rods, and repeated manual scram will effective. Reports RPV level and reactor power.

insert all control rods. To perform

Coordinates with the BOP operator the performance of the Hydraulic Rod repeated manual scram the crew will Insertion Procedures.

need to direct the 2nd Assistant to BOP:

install EOP DEFEAT 12

Installs Defeat 15.

Critical Task # 4 IF a scram is required

Announces failure to scram and direct the 2nd Asst. to install EOP Defeat and Reactor power is above 5%, THEN 12 for Repeated Manual Scram RIP 103.

reduce power below 5% using one or

Installs Defeat 11.

more of the following methods:

Locks out ADS Inserting control rods using RIPs.

Perform Hydraulic ATWS RIPs (CRITICAL)

When directed o RIP 103.2, Drifting Rods to install Defeat Simulator Operator o Start a second CRD pump, if available.

12: Acknowledge the request. o Place CRD Flow Controller FC-1814 in MANUAL and run the Activate [ET 12]. output to maximum.

o Observe increased cooling water flow on FI-1838 and cooling This will install Defeat 12 after time water dp increase on PDI-1832A.

delays.

Three (3) o Throttle open MO-1830, DRIVE WATER sP CO N Simulator Operator necessary to maximize cooling water flow and pressure.

minutes after being directed Contact the control room and inform o Monitor for inward rod motion. Rods will drift in.

to install Defeat them that Defeat 12 is installed.

12: CRS Actions continued on the next page.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS:

Directs locking out ADS.

Verifies at least one set of inboard and outboard MSIVs are open.

Directs installation of Defeat 15.

Directs performance of the ATWS QRC.

Floor Instructor

Directs the injection of SBLC If the crew does not efficiently inject

Recognizes the applicability of Continuous Recheck Statement in Level SBLC, enter power level control, restore Leg of EOP ATWS and enters Power Level Control.

power to at least one RPS bus, and/or reinitiate torus cooling (after the loss of offsite power) the crew may be required to emergency depressurize due to not Directs coordination of the Hydraulic ATWS Rod Insertion Procedures being able to maintain torus water temperature and RPV pressure below the Heat Capacity Limit.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Crew

Implements AOP ATWS power level control actions.

RO:

Critical Task # 10 IF a reactor scram is required, and Reactor power is >5%,

Verifies HPCI is locked out.

and Power/level control is required,

Terminates and prevents injection from condensate and feed. (CRITICAL)

THEN terminate and prevent injection

Reports reactor power when RPV level reaches 87 and lowering.

until conditions allow reinjection.

Controls RPV level -25 to +87 using condensate Critical Task #11 IF performing ATWS and feedwater. (CRITICAL)

Power/level control and Conditions are

As Time Permits, assist in RIPs met to allow reinjection, THEN crew BOP:

actions are taken to maintain RPV level above -25" by injecting using Table 1B

Terminates and prevents injection from HPCI, CS, RHR when systems. required.

Continues to perform Hydraulic Rod Insertion Procedures CRS:

Simulator Operator

Directs installation of Defeat 4.

If directed to break main Activate [ET 28].

Directs terminating and preventing injection from HPCI, CS, RHR and condenser Acknowledge the request. Condensate and Feedwater.

vacuum:

Directs reporting reactor power at 87 and lowering.

Directs an RPV level band of -25 to +87 with condensate and feedwater.

This band will be dependent on the level that is reported when power drops below 5%

Simulator Operator Directs an RPV pressure band of 800-1055 psig. using desired system (EHC).

Three (3) Inform the control room the main minutes after condenser vacuum breakers are open.

the request:

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When all control CRS:

rods are

Recognize that all rods have inserted inserted:

Evaluate Transitioning to EOP 1 from ATWS

Direct the RO to secure Boron Injection

Upon the report of SBLC Pumps secured, transition to EOP 1 RO:

When directed by the CRS, Secure SBLC Pumps

Inform the CRS that SBLC Pumps are secured Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the Contingency Actions Crew parameters of

Enters and implements the actions of an Emergency Depressurization the Heat with an ATWS condition present.

Capacity Limit RO:

are exceeded and an

Terminates and prevents injection from Condensate and Feedwater.

Emergency

Slowly re-injects into the RPV to restore and maintain RPV level -25 to Depress. Is +15 using condensate and feedwater.

required with ATWS conditions BOP:

present:

Terminates and prevents injection from HPCI, Core Spray, RHR.

Reports torus water level.

Opens 4 ADS SRVs.

Reports RPV level at 160 psig. and lowering CRS:

Enters Emergency Depressurization.

Directs terminating and preventing injection from HPCI, Core Spray, RHR, Condensate and Feedwater.

Directs opening 4 ADS SRVs.

Directs reporting of RPV level at 160 psig. and lowering Directs slowly re-injecting into the RPV to restore and maintain RPV level -

25 to +15 using condensate and feedwater.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the Contingency Actions Crew parameters of

Crew will enter and implement the actions of Emergency the Heat Depressurization.

Capacity Limit RO:

are exceeded and an

Restores and maintains RPV 170-211 using condensate and feedwater.

Emergency BOP:

Depress. Is

Reports torus water level.

required:

Opens 4 ADS SRVs.

Restores and maintains RPV 170-211 using condensate and feedwater.

CRS:

Enters Emergency Depressurization.

Directs opening 4 ADS SRVs.

Directs restoring and maintaining RPV level 170-211 using condensate and feedwater.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew Crew transitions to

Implements the mitigation strategies of EOP 1, RPV Control EOP 1 from RO:

EOP ATWS

Restores and maintains RC/L 170-211 using RCIC and other alternate injection systems.

Maintains RC/P 800-1055 psig. using directed pressure control systems.

Lowers reactor pressure to the directed control band using the directed control system.

CRS:

Performs a crew update of entry into EOP 1 due to Exiting EOP ATWS

Directs an RPV level band of 170-211 using RCIC and other alternate injection systems.

Directs installation of Defeat 11 if not completed prior.

Directs an RPV pressure band of 800-1055 psig using directed pressure control systems.

May Enter Alternate Level Control Leg of EOP 1

Lock Out ADS

Restore and maintain RPV level above +15 in. with one or more Preferred Injection Systems (Table 1A)

Wait Until RPV level drops to +15 in.

Placekeeps in EOP 1 to the applicable WAIT UNTIL step in RC/P (RC/P-6) leg Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions to start CRS:

RCIC from a

Recognize Condensate and Feed no longer available.

tripped conditions.

Direct the RO to inject with RCIC to restore Reactor Water Level RO:

At the direction Simulator Operator:

Verify MO-2511, RCIC Pump Discharge Valve, is open.

of the Lead Activate [ET 17]

Open MO 2426, RCIC Lube Oil Cooler Supply Valve.

Examiner, this will trip the RCIC Turbine on

Start 1P 227, RCIC Vacuum Pump.

overspeed.

Open MO-2404, RCIC Turbine Steam Supply Valve.

For RPV injection, immediately open MO-2512, RCIC Inject Valve.

Verify MO-2510, RCIC Min Flow Bypass Valve, closes as RCIC flow raises above 80 gpm.

Start 1P-99A and B, ESW Pumps.

Start 1V-AC-15A and B, RCIC Room Cooling Units.

Recognize the Trip of RCIC, and inform the CRS.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 32 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS:

Direct Crew Response for performance of the T/T leg of EOP 2.

Directs operating all available torus cooling using only RHR pumps NOT required for adequate core cooling.

Before torus water temperature reaches 110F enter EOP 1 and shutdown the reactor.

Maintain torus water temperature below the Heat Capacity Limit (Graph 4).

Wait until torus water temperature and RPV pressure cannot be maintained below the Heat Capacity Limit (Graph 4).

Direct the reseting of the LO-LO-LO LPCI Logic to allow for restoration of Torus Cooling BOP:

Place RHR in Torus Cooling IAW OI 149, QRC 2

Verify RHRSW in service per OI 416/OI 416 QRC 1.

Verify 1P-99A and B, ESW Pumps, running.

Place HS 2059 [HS 1959], A & C [B & D] RHRSW PUMPS LOCA TRIP OVERRIDE, in MANUAL OVERRD position.

Verify MO-2046[1947], RHR HX Service Water Outlet Valve, CLOSED.

Start RHRSW Pumps 1P-22 A[B] and/or 1P-22 C[D].

Throttle open MO-2046[1947], RHR HX Service Water Outlet Valve, to obtain 1200 - 2600 gpm per running pump.

AS TIME ALLOWS, Perform the follow up actions

Verify two or more River Water Supply Pumps running.

Place LIC-4231[4232] in MANUAL.

Adjust LIC-4231[4232] to achieve the desired River Water makeup flow. (Combined flow of ESW and RHRSW)

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 33 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP Actions continued from previous page.

Place RHR in Torus Cooling IAW OI 149, QRC 2

Verify 1P229A[B, C, and/or D], RHR Pumps, running.

If a LPCI HI Drywell pressure condition (2 # ) exists, place HS-2001C[1903C] Enable Containment Spray Valves in the MAN position.

Open MO-2005[1932], Outboard Torus Cooling/Spray Valve.

Throttle MO-2007[1934], Torus Cooling Test Valve, to maintain 4800 gpm per each operating RHR pump.

Close MO-2030[1940], A[B] Heat Exch Bypass Valve.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 34 of 40

NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS:

Direct the BOP or ATC to restore Reactor Water Level with HPCI following the loss of Feed and Condensate once all rods are in.

RO/ BOP:

Start HPCI when Directed IAW OI 152 QRC 1 o If HPCI previously tripped on RPV High Water Level, depress HS-2299, RX HI WATER LEVEL HPCI TURBINE TRIP reset switch.

o Open MO-2247, HPCI Lube Oil Cooler Supply Valve.

o Start 1P-233, HPCI Vacuum Pump .

o Open MO-2202, HPCI Turbine Steam Supply.

o Start 1P-218, HPCI Aux Oil Pump .

o Verify MO-2311, HPCI Pump Discharge Valve, open.

o For RPV injection, immediately open MO-2312, HPCI Inject Valve.

o Verify MO-2318, HPCI Min Flow Bypass Valve, closes as HPCI flow raises above 600 gpm.

Recognize the HPCI Turbine fails to reach required speed and discharge pressure.

Take manual control of the HPCI Turbine IAW ACP 1410.1 and place FIC 2309 in MANUAL and control the HPCI Turbine in MANUAL

Report to the CRS that HPCI is injecting to the RPV in MANUAL due to a failed controller.

- - END OF SCENARIO ***

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 35 of 40

NRC Initial License Exam, Scenario #2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS DISCUSSION ITEMS No discussion points.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 36 of 40

NRC Initial License Exam, Scenario #2 SEG QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Loss of A RPS

2. Drifting Control Rod

3. Loss of 1D11

4. RCIC Inadvertent Initiation

5. Condenser Air In leakage After EOP Entry:

1. ATWS

2. HPCI Controller Failure Abnormal Events:

1. AOP 255.1, Control Rod Drift

2. AOP 255.2, Power Reactivity Abnormal Change

3. AOP 358, Loss of RPS Power

4. AOP 691, Condenser High Back Pressure Major Transients:

1. ATWS

2. Power/Level Control

3. EOP 1 Alternate Level Control Leg Critical Tasks:

1. Critical Task # 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:

Manual scram signal

Inserting control rods using RIPs.

Manual ARI signal

Injection of Boron

2. Critical Task # 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.

3. Critical Task #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.

Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 37 of 40

NRC Initial License Exam, Scenario #2 SEG

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:

Manual scram signal

Inserting control rods using RIPs.

Manual ARI signal

Injection of Boron Safety The UFSAR and Safety Limits ensure that specified acceptable fuel design limits are not Significance: exceeded during steady state operation, normal operational transients and abnormal operational transients.

The fuel cladding integrity safety limit is set such that no significant fuel damage is calculated to occur if the limit is not violated. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environs. The MCPR fuel cladding safety limit ensures that during normal operations and abnormal transients the fuel rods will not experience transition boiling and possible cladding damage.

The MCPR analysis assumes that the control rods will insert in a specified time. If the control rods do not insert when a scram is required, the plant is beyond the fuel cladding MCPR analysis thus the fuel cladding safety limit is challenged and potential cladding damage may be occurring.

Cue: A manual or automatic scram signal has been inserted and failed to lower reactor power below 5%.

Performance The crew successfully initiates a manual scram signal after a automatic scram failed has Standard: occurred and/or, The crew initiates a manual ARI causing control rod insertion and/or, The crew successfully performs RIPs (the task of sending an operator to vent the scram air header should not be considered as control room operator actions and thus should not be considered as a method for this CT) and/or, The crew successfully performs RIPs as allowed by the scenario to insert control rods capable of being inserted and/or, The crew successfully injects boron into the RPV.

If the crew performed the actions for Power/level control and that caused power to lower below 5% before any of the above actions were performed, this CT should be considered as N/A. If this CT was N/A due to Power/level control lowering power and the actions related with this CT were not competently performed, the responsible individual(s) and possible crew may fail or require remediation due to competencies.

If the crew was performing the actions of Power/level control and was correctly performing actions for this CT, this CT should be considered satisfactory.

If the crew is not performing the correct procedures for the given conditions and this results in the reactor remaining at power, this should be considered an individual failure and possible crew failure.

Example: The crew is individually driving control rods during an electrical ATWS and ARI is available and has not been attempted.

If ARI automatically initiates and results in power lowering below 5%, this CT should be N/A.

Feedback: Control rod positions and/or boron injection.

EOP step(s): ATWS Q-1, Q-3, Q-6, Q-8 BWROG: RPV 4.1, RPV 5.1, RPV 6.1 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 38 of 40

NRC Initial License Exam, Scenario #2 SEG

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.

Safety RPV water level must be lowered during ATWS to either lower reactor power or to Significance: prevent challenging the containment.

If power is known to be below 5%, it is highly unlikely that the reactor is producing a significant power such that power/level control will effectively reduce power further, thus entering power/level control is not required or safety significant.

If power is above 5%, or cannot be determined and RPV level is above 87", power level control is required to reduce reactor power in order to prevent or mitigate the consequences of any large irregular neutron flux oscillations induced by neutronic/thermal-hydraulic instabilities.

If power is known to be above 5%, or cannot be determined and RPV water level is above +15", and torus water temperature is above 110°F, and either an SRV is open or will reopen or DW pressure is above 2 psig, then power level control is required to reduce power in order to preserve containment integrity.

Thus terminating and preventing injection will aid in lowering power and can preclude failure of containment or equipment necessary for the safe shutdown of the plant.

Cue: ATWS EOP entry required with reactor power above 5% or cannot be determined and either:

RPV water level is above +87" or

RPV water level is above +15" and torus water temperature is above 110°F, and either an SRV is open or will reopen or DW pressure is above 2 psig.

Performance Injection from all of the following is terminated until conditions allow reinjection:

Standard:

Condensate/Feedwater

HPCI

RHR

Core Spray

Alternate ATWS injection systems (Table 2B)

Reinjection should not occur until RPV water level is below 87" and one of the

Reactor power drops below 5%

Reactor power drops below 5%

All SRVs remain closed AND DW pressure remains below 2 psig.

CRD, SBLC, and RCIC injection are allowed.

If RCIC was not injecting but other systems were injecting outside the shroud at a flowrate below RCIC flowrate, the critical task is satisfactory although remediation may be necessary.

If RPV level is not lowering to the required conditions, and the crew is not controlling RCIC injection, the critical task is satisfactory, although remediation may be required.

Feedback: Injection flowrate for the listed systems remain at zero until reinjection is allowed.

EOP step(s): ATWS/L two CRS, and L-1, -2.

BWROG: RPV 6.3 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 39 of 40

NRC Initial License Exam, Scenario #2 SEG

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.

Safety Maintaining RPV water level above -25" will ensure that the covered portion of Significance: the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.

The use of table 1B systems is to ensure the flowpath of the injection water is outside the shroud and mixes with the warmer water in the lower plenum prior to it reaching the core.

Cue: Power level control has been entered in ATWS, RPV water level is below +87",

and one or more of the following conditions have been met for reinjection:

Reactor power drops below 5%

RPV level reaches +15"

All SRVs remain closed and DW pressure remains <2 psig.

Performance Table 1B Injection systems are injecting to maintain RPV level above -25".

Standard: Restarting of FW injection to maintain RPV level is satisfactory for this critical task.

If injection with Table 1B systems are not required to maintain RPV level above

-25", this critical task would be N/A. Example: RCIC has been operating and is maintaining RPV level.

If the crew injects with Core Spray in an attempt to maintain RPV level above

-25", this should be considered a critical task failure unless an ATWS ED has been performed.

If an uncontrolled injection (above 2.8 Mlb/hr) causes a power rise above 5%, it should be considered a critical task failure.

If an uncontrolled injection does not cause a power rise above 5%, but does cause RPV water level to go above the EOP ATWS maximum recorded RPV level, the critical task is satisfactory although remediation may be necessary.

If RPV water level goes above the EOP ATWS maximum recorded RPV level due to CRD, SBLC and/or level swell, this should not require remediation.

Feedback: RPV water level is being maintained above -25".

EOP step(s): ATWS /L-3 BWROG: RPV 6.4 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 40 of 40

SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: 0 LMS ID: LMS Rev. Date:

SEG TITLE: NRC Initial License Exam, Scenario #3 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: ~ 90 minutes Developed by: Jesse Seymour 2/18/15 Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 31

NRC Initial License Exam - Scenario #3 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures:

Enabling There are no formal learning objectives for this evaluation.

Objectives:

Prerequisites: None Training Simulator Resources: Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team

References:

AOP 255.2, Rev 42 EOP3 EOP 4, Rev 20 AOP 410, Rev 28 IPOI 3, Rev 144 ARP 1C04B, Rev 79 IPOI 5, Rev 58 ARP 1C04C, Rev 45 OI 149, Rev 146 ARP 1C05A, Rev 78 OI 150, Rev 78 ARP 1C05B, Rev 98 OI 152, Rev 111 ARP 1C06A, Rev 68 OI 264, Rev 134 ARP 1C07B, Rev 87 OI 878.4, Rev 40 ARP 1C23B, Rev 22 STP 3.6.2.1-01, Rev 8 ED, Rev 9 Technical Specifications EOP 2, Rev 16 EOP1, Rev 18 Protected Content: Identify here and in training material as {C001}; See Comment for details.

None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance.

Operating None Experience:

Risk Significant Operator Actions:

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 31

NRC Initial License Exam - Scenario #3 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See Cover Initial development for Initial development for 2015 NRC 0 2015 NRC LOIT N/A LOIT examination. See Cover examination.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 31

Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________

Initial Conditions:

Reactor power approximately 40%

Power ascension in progress.

Turnover:

Continue power ascension in accordance with IPOI 3, POWER OPERATIONS (35% - 100%

RATED POWER, Section 4.0. Steps are completed up to step 5.

Raise power to approximately 50%.

Stabilize power at approximately 50% and perform RCIC pump surveillance test Event Event # Malf # Eventy Description Type*

1 R ATC Raise power with recirculation flow.

C ATC 2 rr17a A Recirc Pump Speed Controller Failure.

C SRO I ATC APRM C fails (inoperable).

2 nm08c TS SRO Tech Spec review (3.3.1.1, 3.3.2.1) 3 N BOP RCIC Start IAW OI 150 rc06 A RCIC system isolation signal is received due to steam leak; isolation is C BOP 4 sw14a faulted.

sw14b TS SRO Tech Spec entry (3.5.3)

C BOP 5 sw19b River Water Supply Pump trip.

C SRO 6 M (ALL) Large break LOCA occurs (Recirc Pump suction break). Faulted LPCI initiation.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 31

Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS General Instructions

1. Reset to IC13 and lower power to ~40% RTP

a. Lower reactor power using recirculation flow and control rods

b. Load Events

c. Load Malfunctions

d. Load Overrides

e. Place Torus Cooling in service with 1 RHR Pump and 1 RHRSW Pump operating on each side.

2. OR Reset to the IC provided by the LOIT Exam Development Team

3. Verify B and C APRMs are BYPASSED.

4. Mark up OI 150, Section 5.2 to step 7, and verify all steps to that point have been completed.

5. Mark up IPOI 3 up to and including step 7. NA step 8.

6. Obtain keys from key locker for Placing Torus Cooling in service.

7. Verify Events validate FALSE

8. Reset APRM Gains and clear recorders

9. Complete the Exam Setup Checklist

10. Ensure no BIAS is inserted on the FRV Controllers by verifying Y at 0.0

11. Verify EOOS up-to-date.

12. Verify the SUFRV Lined up to the operating Feed Pump.

13. Have a copy of Daily Jets STP available to provide when requested.

Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7, 9 Manual Trigger Manual Trigger 20 YCAB002 >= 48 Power > 48%

21 1A1/1A2 Transfer 1A1/1A2 Transfer 22 HPCI Starts ZDIRPC71AS1(1) ==1 & ZLOHPHS2202(2)

== 1 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 31

Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value (sec)

Setup rh10c RHR C PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup rh10d RHR D PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup rh10a RHR A PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup rh10b RHR B PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup stdg01 TRIP OVERRIDE - 'A' SBDG Inactive Active 1G31 FAILS TO AUTO START Setup stdg02 TRIP OVERRIDE - 'B' SBDG Inactive Active 1G21 FAILS TO AUTO START Setup cs05a CORE SPRAY PUMP A -

Inactive Active FAILURE TO AUTO-INITIATE Setup cs05b CORE SPRAY PUMP B -

Inactive Active FAILURE TO AUTO-INITIATE Setup strh02 LPCI B INJECT VALVE FAILS Inactive Active TO AUTO OPEN - MO-1905 Setup ms31b GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- Inactive Active MO2401 Setup ms31a GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- Inactive Active MO2400 Setup strh01 LPCI A INJECT VALVE FAILS Inactive Active TO AUTO OPEN - MO-2003 Setup sthp01 HPCI SYSTEM AUTO Inactive Active INITIATION BLOCK Setup nm08c APRM CHANNEL FAILS- CHNL 1 As Is 100 C

Setup rc06 RCIC STEAM SUPPLY LINE 6 min 3 0 30 BREAK (RCIC ROOM)

Setup sw19b RIVER WATER SUPPLY PUMP 5 Inactive Active TRIP- PUMP B, 1P117B Setup rr15a RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP 6 min 7 0 2 A

Setup rr17a RECIRC M-G FLOW CTRLR FAILS, AUTO/MAN MODES- M- 1 min 20 As Is 80 GA Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 31

Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value (sec)

Setup sw14a RCIC ROOM COOLER ESW 3 min 3 As Is 85 FLOW BLOCKAGE- 1V-AC-15A Setup sw14b RCIC ROOM COOLER ESW 3 min 3 As Is 85 FLOW BLOCKAGE- 1V-AC-15B Setup strc01 TRIP OVRD- RCIC FAILS TO AUTO START 3 Inactive Active Write a sch file to block the initiation and valve light power Setup fw02a CONDENSATE PUMP TRIP-21 Inactive Active PUMP A Setup fw02b CONDENSATE PUMP TRIP-21 Inactive Active PUMP B Setup hp02 HPCI TURBINE TRIP 22 Inactive Active Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 31

Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 OVERRIDES Time Over. No. Override Title Delay Ramp ET Initial Final Value Value REMOTE FUNCTIONS Time Remote No. Remote Title Delay Ramp ET Initial Final Value Value Setup fp08 RCIC DELUGE MAN May need to ISOLATION VALVE V-33-84 Open Closed look up (OPEN,CLOSE)

Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 31

Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 SHIFT TURNOVER INFORMATION

Day of week and shift o Today o Day Shift

Weather conditions o Warm Spring Day

(Plant power levels) o Reactor Power Level 42%

o Core Flow 30 Mlbm/hr

Protected train o Protected Train is B

Technical Specification Action statements in effect o TS LCO 3.5.1 Condition B- Day 1 of 7 One low pressure ECCS subsystem inoperable for reasons other than Condition A.

Restore low pressure ECCS subsystem to operable status within 7 days.

Locked in / failed annunciators and alarms o None

Evolutions in progress or planned for upcoming shift o Raise Power with Recirc to approximately 50% RTP.

o Perform RCIC post maintenance confidence run for maintenance performed a week ago IAW OI 150, Section 5.2. in CST to CST mode of operation.

o RCIC Inop STP, 3.5.3-01 was completed just prior to turnover.

Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline with one year to YELLOW o LERF Baseline with one year to YELLOW

Existing LCOs, date of next surveillance o None.

Procedures or major maintenance in progress o None

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment

Comments, problems, operator workarounds, etc.

o One Extra NLO is in work control waiting for the RCIC Test Run and has been briefed.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW:

Raise power with Recirc flow. CRS:

Simulator Operator:

Directs power to be raised from 40 to 50% using recirculation pump flow.

If Contacted as Inform the crew to raise power with Recirc the Reactor Flow to achieve approximately 50% power RO:

Engineer to and hold power constant until a rod provide

Performs Recirculation Pump flow adjustments to raise power from sequence is approved for further power 40 to 50%.

guidance, ascension.

Monitors plant parameters for expected response during reactivity manipulation.

BOP:

Adjusts generator excitation manual regulator adjust to maintain the generator nulled.

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NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Simulator Operator: CREW:

When power Verify [ET 20] activates.

reaches ~48% This will cause A Recirc MG Set speed to CRS:

rise.

Will enter AOP 255.2 on the Power/Reactivity Abnormal.

Contact the Duty Station Manager/Operations Director and/or the Reactor When contacted Engineer.

Simulator Operator:

as the 2nd Asst.

Report that the power switch is on and the

May Enter TS 3.4.1 Condition C for the Mismatch in Recirc Pump Speeds.

to go to the MG Set Room to thermal overload button on the motor is o Recirc Pump Speed Mismatch graph on the following page.

investigate the reset.

If the B Scoop Tube was locked, the CRS may direct the crew to reset the Recirc Pump B Scoop Tube in accordance with OI 264 Speed Changer, Wait 2 RO:

minutes and

ARP 1C04A (C-5) Actions taken for the scoop lock.

Will Lock the A Recirc MG Set Scoop Tube from 1C04. The crew may lock the B Scoop tube if they do not diagnose the event properly When Simulator Operator:

Take actions IAW AOP 255.2 Contacted as Agree to support trouble shooting efforts.

the DSM/OD

If directed, reset the B Scoop Tube in accordance with OI 264 When BOP:

Contacted as Simulator Operator:

Acknowledge the situation and inform the

Direct inplant operators to investigate the scoop tube malfunction the RE CRS that you will develop a plan for

Take actions for AOP 255.2 recovery.

Run 3D Case

Plot Power to Flow Simulator Operator:

Resetting the scope tube lock on the next page.

When contacted Acknowledge the request and deliver the as procedures STP after 5 minutes.

to deliver a copy of STP 3.4.1-Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Resetting the scoop tube lock on B Recirc Pump BOP:

If directed, reset the B Scoop Tube in accordance with OI 264 o If A[B] Recirc MG Set is running, reset the Scoop Tube Lockout as follows o Verify Scoop Tube Position P-%

o Adjust setpoint S-% to approximately match Scoop Tube Position P-o Verify controller output V-% approximately matches Scoop Tube Position P-%.

o At 1C04, reset scoop tube lock by momentarily placing handswitch B31A-S3A[B] to RESET and then verify the following:

o Annunciator 1C04A, C-5[1C04B, C-2], "A[B] RECIRC MG SCOOP TUBE LOCK" resets.

o Amber SCOOP TUBE LOCKED Light located at 1C04 (above A[B]

Scoop Tube Control handswitch B31A-S3A[B]) is OFF.

o Verify that the Recirc pump speed is stable by observing the following parameters o SETPOINT (S), Percent Position (P), Percent Speed (X), Recirc pump discharge flow, Total core flow, Core pressure drop, APRM readings o Verify that SETPOINT (S) is selected for digital display.

EXAMINER NOTE: After power has been raised to approximately 50%, commence Event 2.

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NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3: Simulator Operator: Crew:

Identifies the following:

ACTIVATE [ET 1]

a half-scram has occurred.

This will cause C APRM to fail upscale.

a rod out-block has occurred.

BOP:

OI 878.4 actions to Unbypass A APRM and take C APRM Out of operate.

OI 878.4 actions to Bypass C APRM o If an APRM is currently bypassed, perform the following for If Contacted as Simulator Operator: the bypassed APRM, otherwise N/A this step:

a maintenance o Verify the APRM upscale, inoperative, and if greater than 5%

Acknowledge the issue, and/or to provide reactor power, downscale trips on Panel 1C37 are reset.

or support maintenance support for o Verify the IRM/APRM recorders on Panel 1C05 indicate organization, troubleshooting/repair. approximately the same average power for the bypassed APRM as they do for the other APRM channels in operation.

o Place the APRM BYPASS switch C51B-S3 or C51B-S6 on Panel 1C05 in the neutral (unbypassed) position.

Following the o Observe that the bypass light on Panel 1C05 and/or that the Simulator Operator:

reset of the half- bypass light on Panel 1C37 is/are OFF.

scram, crew Call the CRS as the Operations Director o Verify the two APRM channels in the RPS trip system which should proceed and direct the crew to proceed with the are to remain UNBYPASSED are OPERABLE, otherwise to the RCIC RCIC Trouble Shooting Run to test the comply with Technical Specifications and TRM for inoperable surveillance Flow Controller. RPS instrumentation.

test. If crew o Place the APRM BYPASS switch C51B-S3 (C51B-S6) on does not Panel 1C05 in the A, C, or E (B, D, or F) position for the proceed, channel to be bypassed.

o Observe that the bypass lights for the bypassed channel on Panel 1C37 and/or Panel 1C05 is/are ON.

Unbypass the D APRM

Bypass the B APRM

Actions are repeated for B and D APRMs RO and CRS Actions are on the following pages Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RO:

Responds to failure of APRM C

Acknowledges 1C05A (B-2), APRM A, C, OR E UPSCALE TRIP OR INOP.

o Check the SCRAM GROUP A and B lights on 1C05 to determine if a full Reactor scram has occurred.

o If a full Reactor scram occurs, perform IPOI 5 (Reactor Scram).

o Monitor APRM indications on Panels 1C05 and/or 1C37.

o If only A RPS half scram has occurred:

If any B RPS channel APRM is rapidly approaching or has exceeded its trip setpoint, manually scram the Reactor and perform IPOI 5 (Reactor Scram).

o Suspend testing in progress on other RPS instrumentation.

o If the trip is due to a loss of power, perform AOP 358 (Loss of RPS AC Power) and comply with Technical Specification requirements for Reactor Protection System (RPS) Instrumentation.

o If it is determined that an APRM has failed:

Comply with Technical Specification requirements for Reactor Protection System (RPS) Instrumentation and the Technical Requirements Manual requirements for Control Rod Block Instrumentation.

With permission from the CRS, bypass the affected APRM o Reset the half scram.

Acknowledges 1C05B (A-6), ROD OUT BLOCK. References ARP.

Identifies that APRM C has failed.

When directed by the CRS, bypasses the C APRM.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS:

Directs crew response for failed APRM C

Reviews TS 3.3.1.1, Condition A for applicability Instrumentation.

Reviews TS 3.3.2.1 for applicability.

Reviews TRM LCO 3.3.2, Condition A for applicability.

Directs C APRM to be bypassed.

Directs the half-scram to be reset.

Briefs the crew on the effects of the Scoop Tube and APRM Failure.

Direct the B APRM to be bypassed if not completed.

EXAMINER NOTE: After the half-scram is reset and B APRM is BYPASSED, crew should proceed to RCIC Confidence Run (Event 3).

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 CRS:

RCIC

Directs crew to conduct the RCIC Run IAW OI 150, Section 5.2 in Confidence Run Simulator Operator: CST to CST Mode.

Call the control room as Ray Wheaten and

Verify RCIC LCO has been entered, LCO 3.5.3, Condition A - RCIC At the Direction System inoperable. Per the turnover, the RCIC Inop STP was direct the crew to proceed with the RCIC of the Lead previously completed, and restore to OPERABLE in 14 days.

Run, and that this is the crews priority.

Examiner, RO:

Monitors plant parameters during RCIC Run.

BOP:

Simulator Operator: Starts RCIC in CST to CST mode in accordance with OI 150.

When Wait 4 minutes and inform the control

Start 1V AC 15A and B RCIC ROOM CLG UNITS at 1C23 Contacted as Room that

Open the REDUNDANT SHUTOFF valve MO 2316 on 1C03.

the Extra

Oil level has been verified Operator for the

Open the TEST BYPASS valve MO 2515 to 44-46% open as satisfactory indicated on RCIC TEST BYP MO 2515 POSITION ZI 2515.

RCIC Run,

And standing by outside the RCIC

Verify MO 2511 PUMP DISCHARGE valve is open.

Room.

Start 1P 227 VACUUM PUMP by placing handswitch HS 2415 on

Air Flow Verified through the 1C04 in the START position.

coolers.

Open MO 2426 LUBE OIL COOLER SUPPLY by placing HS 2426 in the OPEN position momentarily and observing proper valve position indication.

If time permits, ensure unnecessary/unauthorized personnel are clear of the RCIC Room.

Initiate Torus water temperature monitoring per STP 3.6.2.1-01. This is only required while heat is being added to the Torus.

BOP Actions Continued Next Page Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When Simulator Operator:

Open MO 2404 TURBINE STEAM SUPPLY by placing the Contacted as handswitch in the OPEN position momentarily and observing proper Acknowledge the running of RCIC and the Health Physics, valve position indication and that RCIC turbine speed, pump potential to change rad levels in the plant.

discharge pressure, and RCIC flow indicators indicate increases.

When contacted Simulator Operator:

Verify CV 2410, CV 2411, and CV 2436 Close as an operator Report that the pump is operating sat.

Verify that MO 2510 MIN FLOW BYPASS opens when RCIC Flow is to verify RCIC less than 80 gpm with pump discharge pressure greater than 125 Running Sat, psig.

Verify HV 2406 TURBINE CONTROL VALVE Governor Valve is When Simulator Operator: throttling to control turbine speed.

Contacted as a Report that you will begin trouble shooting

In the CST to CST mode, throttle MO 2515 TEST BYPASS to achieve member of the and to stand by for direction from the team. the desired discharge pressure.

maintenance

Verify that MO 2510 MIN FLOW BYPASS valve closes as RCIC flow staff for trouble rises above 80 gpm.

shooting

Adjust FIC 2509 FLOW CONTROL until desired flow is achieved; do not throttle RCIC turbine speed below the minimum of 2000 rpm.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 31

NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: Simulator Operator: CREW: identify that a RCIC isolation signal is present due to a steak leak in the RCIC room (e.g. high area temperature).

When RCIC ACTIVATE [ET 3]

flow to the CST This will cause a small leak in the RCIC RO:

has been Room. Temperatures in the room will not

Monitor 1C05 indications for Power/Pressure/Level.

established, exceed MAX SAFE limits.

and with

If Required, attempt to Isolate the RCIC Steam Lines while the BOP is in the back panels area.

direction from the lead

Identifies that a valid RCIC isolation signal should be present due to a steam examiner: leak in the RCIC Room.

Identifies that an automatic RCIC isolation has failed to occur.

Manually initiates RCIC isolation by performing the following in accordance Simulator Operator: with OI-150, Section 7.1 or the applicable ARPs:

As the extra Inform the crew that a steam leak occurred o Closes MO-2400 RCIC INBD STEAM LINE ISOL, and MO-2401 operator at the in the RCIC Room, the RCIC room was RCIC OUTBD STEAM LINE ISOL.

RCIC Room evacuated, all personnel are accounted Door, once the for, and that there are no injured High Amb Temp personnel. BOP: performs the following:

alarm sounds,

May recognize the 1C23 Trouble Annunciator on 1C07, and investigate the Back Panel Area for the cause of the alarm.

Upon investigation, the crew may take actions to Isolate RCIC.

Acknowledges 1C04B (B-04) STEAM LEAK DET AMBIENT HI TEMP, 1C04C (A-07) References ARP(s).

Goes to the back panel area to report temperatures.

Established Ventilation in a 3-2-3 line up.

RO/BOP/CRS

Make Plant Announcement to alert personnel to the steam leak from RCIC CRS Actions continued on the next page.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 31

NRC Initial License Exam, Scenario #3 SEG Examiner Note: Once the RCIC test flow to the CST has been established, commence Event #4.

CRS Actions continued from the previous page.

SIMUATOR OPERATOR CRS: performs the following:

When the crew

May enters EOP-3, Secondary Containment Control has isolated Delete ESW COOLER Blockage the RCIC [sw14a and sw14b] o Implements actions of EOP-3 SC/T leg for RCIC room Steam Leak, temperature being greater than the Max Normal Operating Limit, but less than the Max Safe Operating Simulator Operator Limit.

If directed to Insert OVER RIDES deenergize MO- DO-RC-013 to off o Directs manual isolation of the RCIC system if not 2401, DO-RC-014 to off already done.

DI-RC-008 to auto

References Technical Specifications to address RCIC system inoperability:

And inform the crew that 1D14 Ckt 1, MO-2401 Power Supply is open. o TS 3.5.3, Condition A May declare TS 3.6.1.3, Condition B for two valves that failed to shut on the Isolation Signal in a single flow path.

Simulator Operator Insert OVER RIDES If directed to DO-RC-010 to off deenergize MO- DO-RC-011 to off 2400, DI-RC-006 to auto And inform the crew that MO-2400 Power Supply is open.

EXAMINER NOTE: Once RCIC manual isolation has occurred and SRO has completed TS call, commence event #5.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 31

NRC Initial License Exam, Scenario #3 SEG Event 6: Simulator Operator: when directed by CREW: identifies a trip of the B River Water Supply Pump.

lead examiner River Water Supply Pump ACTIVATE [ET 5] RO:

spurious trip

Monitors plant parameters.

to cause the B RWS Pump to trip.

BOP: Performs the following:

Attempt to start standby pumps in both RWS Subsystems as When contacted necessary to restore needed makeup flow.

Simulator Operator:

Send an operator to the Intake Structure to verify alarms and check as the AUX Operator to and inform the control room that the B RWS pump breaker condition.

investigate the RWS Pump is hot to touch and that there

Verify the Auto Start is not selected to the inop pump.

loss of the B is no smoke and no fire. CRS:

RWS Pump, directs crew response as follows:

Wait 4 Minutes

May Enter AOP-410, LOSS OF RIVER WATER SUPPLY o Update the Online Risk Monitor for the status of River Water Supply Pumps.

May Direct actions IAW the ARP 1C06A (A-3) B RWS Pump Trip for DSM Call Simulator Operator: the tripped RWS Pump

LCO 3.7.2 met, Technical Specification Inoperable Log entry.

Acknowledge the request for support.

EXAMINER NOTE: Commence event # 7 at the direction of the Lead Examiner.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 31

NRC Initial License Exam, Scenario #3 SEG Event 7: Simulator Operator: perform the following CREW: Will recognize the automatic reactor scram, lowering RPV level, at the direction of the Lead Examiner: lowering RPV pressure, and rising drywell pressure and Enter EOP 1 Large Break and 2 LOCA (Recirc Activate [ET 7]

Suction break) and verify rr15a activates on ramp RO: performs the following:

with faulted

Performs IPOI 5 QRC 1, Reactor Scram Immediate Operator Actions:

LPCI auto o Initiates a backup manual reactor scram.

initiation (manual o Places THE MODE SWITCH in SHUTDOWN.

alignment o Verifies all control rods fully inserted.

required).

o Verifies main turbine trip Simulator Operator: o Verifies main generator lockout.

If Contacted as Agree to support required actions an operator in o Verifies neutron flux is lowering.

the plant, o Inserts all functional SRM and IRM detectors.

Event 7: Simulator Operator: CREW:

Large Break When Contacted to provide support

Upon receipt of a 2# Drywell Pressure signal, LOCA (Recirc

The crew will recognize the failure of all ECCS Systems to automatically Acknowledge the request Suction break) start and with faulted o Start A and B SBDGs LPCI auto initiation o Start A, B, C, D RHR Pumps (manual o Start A and B Core Spray Pumps alignment o Start HPCI required).

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 31

NRC Initial License Exam, Scenario #3 SEG CREW:

Implements the mitigation strategies of EOP 1, RPV Control RO:

Inserts a manual reactor scram.

Simulator Operator:

Completes a scram report that includes all rods in, reactor pressure and trend and reactor water level and trend.

Activate [ET 9]

When directed

Restores and maintains RC/L 170-211 using RCIC and other alternate This will trip HPCI and prevent it from by the Lead injection systems.

restarting.

Examiner,

Maintains RC/P 800-1055 psig. using directed pressure control systems.

Lowers reactor pressure to the directed control band using the directed control system.

CRS:

Performs a crew update of entry into EOP 1 due to RPV level or Drywell Pressure.

Directs an RPV level band of 170-211 using RCIC and other alternate injection systems.

Directs installation of Defeat 11

Directs an RPV pressure band of 800-1055 psig using directed pressure control systems.

Directs lowering reactor pressure to lessen the driving head on the leak in the drywell.

Shows concern for maintaining plant cooldown within the limits.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 31

NRC Initial License Exam, Scenario #3 SEG CREW:

Implements the mitigation strategies of EOP 2, Primary Containment Control CRITICAL TASK #33 Maintain RPV level

Recognizes the failed ECCS initiation (LPCI) and directs action to establish above TAF with operator actions LPCI injection (CRITICAL TASK #33).

BOP:

Informs the CRS of containment parameters including parameter name, value and trend.

Installs Defeat 4.

Utilizes OI 149 QRC to spray the torus.

Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve handswitch in OPEN and verify valve opening

Throttle open MO-2006[MO-1933], Torus Spray Valve

Utilizes OI 149 QRC to spray the drywell.(CRITICAL Task #22)

CRITICAL TASK #22 DW spray on high

Ensures Recirc Pumps are tripped DW temperature

Repositions HS-1903C - Enable Containment Spray Valves to Manual

Depending on RPV level may take HS-1903B to 2/3 Core

Coverage/LPCI INIT Interlock Override to MANUAL OVERRD

Open MO-2000[1902] , Inboard Drywell Spray Valve

Throttle open MO-2001[1903], Outboard Drywell Spray Valve.

Trips the running recirculation pump.

CRS:

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

Obtains containment parameters.

Directs installation of Defeat 4.

Directs spraying the torus after confirmation that torus pressure is greater than 2 psig.

Directs spraying the drywell before drywell temperature reaches 280F.

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.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 31

NRC Initial License Exam, Scenario #3 SEG CREW:

Implements that mitigation strategies of the ALC contingency of EOP 1 BOP:

Lockouts ADS.

RO:

Attempts to restore and maintain RPV level above +15

Maximizes injection with CRD in accordance with AIP 407.

Injects with SBLC in accordance with AIP 406.

Verifies injection subsystems can be lined up for injection

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

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.

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.

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 31

NRC Initial License Exam, Scenario #3 SEG CREW:

ED when Reactor Water Level is < +15 and before Reactor Water Level reaches -25(CRITICAL)

Critical Task #1 IF the reactor is CRS:

shutdown under all conditions and RPV

Diagnoses HPCI failure to run level drops to +15, THEN perform Emergency RPV Depressurization

Directs Emergency Depressurization.

before RPV level reaches (-25").

Directs Opening 4 SRVs

When Directed opens 4 ADS SRVs to emergency BOP:

Informs SRO when 4 SRVs are open

Monitors and controls RPV level as he depressurization occurs Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 31

NRC Initial License Exam, Scenario #3 SEG Event 7: Simulator Operator: BOP: performs plant EOP operations as directed by the SRO. Aligns systems (RHRSW, RHR, etc.) and reports trends as required.

Large Break ROLE PLAY: if contacted as Equipment LOCA (Recirc Operator, perform required component Suction break) manipulations and make appropriate

Identifies failure of automatic LPCI alignment and injection and with faulted reports to the Control Room. manually aligns LPCI injection by starting RHR pumps and LPCI auto opening valves as necessary (CRITICAL TASK).

initiation (manual alignment required).

EXAMINER NOTE: when sufficient crew execution of the EOPs has been observed, then the scenario may be terminated.

- - END OF SCENARIO ***

Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 31

NRC Initial License Exam, Scenario #3 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)

Malfunctions:

Before EOP Entry:

1. Runaway Recirc Pump

2. A APRM Fails Upscale

3. RCIC Steam Leak with Failure to Automatically Isolate

4. RWS Pump Trips After EOP Entry:

1. LPCI Pumps Fail to Auto Start

2. Condensate Pump Trip

3. Failure of SBDG to Start

4. Trip of HPCI Abnormal Events:

1. Power Reactivity Abnormal Change

2. High Ambient Temperature

3. Loss of RWS, AOP or ARP Actions 4.

Major Transients:

1. LOCA

2. Emergency Depressurization Critical Tasks:

1. Critical Task #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".

2. Critical Task #22 DW spray on high DW temperature

3. Critical Task #33 Maintain RPV level above TAF with operator actions Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 31

NRC Initial License Exam, Scenario #3 SEG

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".

Safety If the lowering RPV water level trend had not been reversed before RPV level Significance: drops to +15", emergency RPV depressurization should be performed prior to RPV level reaching -25". The consequence of not depressurizing the RPV when level is below -25" is a loss of adequate core cooling. Depressurizing prematurely may unnecessarily cause unneeded stress on the RPV and piping.

Cue: RPV level lowered to +15".

Performance The crew must Initiate emergency RPV depressurization after the lowest valid Standard: level indication shows <+15" and prior to the lowest valid level indicates -25".

The critical task is not satisfactory if the actions for Emergency RPV Depressurization are not complete. (See definitions)

Feedback: RPV pressure is rapidly lowering.

EOP step(s): RC/L-4, L-7, L-8 BWROG: RPV 1.1 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 31

NRC Initial License Exam, Scenario #3 SEG

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

Safety If DW sprays were initiated when in the shaded area of the DWSIL, this could Significance: lead to an evaporative cooling pressure drop which could result in:

Deinerting the containment or containment negative pressures below design.

OR

Drywell-below-torus differential pressure beyond design.

Operation of DW sprays if DW temperature cannot be maintained below 280°F, will ensure that the design temperatures of the components within the DW are not exceeded.

If DW sprays are not utilized when available, the next EOP actions will be to Emergency RPV Depressurize, which will lower the amount of ambient heat to the DW, but will cause additional pressure/temperature stress on the RPV.

Cue: DW temperature is rising and is below 280°F.

Average DW temperature and DW pressure conditions allow DW spray per the DWSIL curve Performance DW sprays are initiated on at least one side of RHR prior to 280°F DW Standard: temperature.

If DW sprays are initiated while in the shaded area of the Drywell Spray Initiation Limit (DWSIL), this would be a critical task failure.

If the crew does not secure Recirculation pumps prior to initiating DW sprays, the critical task is considered satisfactory although remediation may be required.

Feedback: DW spray flow initiated and DW temperature is lowering.

EOP step(s): DW/T-4, -5 BWROG: N/A Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 31

NRC Initial License Exam, Scenario #3 SEG

33. The Reactor is shutdown and RPV water level can be maintained above +15 inches with preferred and alternate injection systems, THEN inject to restore and maintain RPV level above +15 inches.

Safety The preferred method of core cooling is core submergence. If this method is Significance: available, the crew is directed to inject with preferred and alternate systems to maintain the preferred method of core cooling. Although other methods will provide core cooling, such as Emergency Depressurization, the core temperatures will be higher.

Cue: RPV level is lowering and preferred and/or alternate methods of injection are available to maintain RPV level above +15 inches, but will not maintain +15 inches without operator action.

If automatic actions will maintain RPV level above +15 inches, this task should be N/A.

Adequate time needs to be given to allow the crew to restart injection.

The crew has indications that the system(s) is(are) available for injection.

Performance The crew should start or align systems or power supplies to maintain RPV level Standard: above +15 inches.

This could be taking manual control of a failed automatic controller, restoring power to a bus that has an available injection system, opening a valve that failed to auto open, or resetting a trip signal for an injection system.

If starting of injection with operator actions will not maintain RPV level above

+15 inches, this critical task should be N/A. If this is the situation, and the crew does not attempt any of these systems, resulting in RPV level reaching +15 inches sooner than if the injection systems were started, remediation may be necessary, although the CT is N/A.

Feedback: Injection systems are maintaining RPV level above +15 inches.

EOP step(s): RC/L-3 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 31

JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 1 TITLE: VENT THE SCRAM AIR HEADER TR-AA-230-1003-F10, Revision 2

JOB PERFORMANCE MEASURE JPM Page 2 of 13 JPM TITLE: VENT THE SCRAM AIR HEADER JPM NUMBER: 201001 REV. 0 TASK NUMBER(S) /

TASK TITLE(S):

K/A NUMBERS: 201001 K1.09 K/A VALUE: 3.1/3.2 Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER:

APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room:

Simulator: Other:

Lab:

Time for Completion: 10 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed)

Instructor/Developer Date Reviewed by: Signature On File (NRC Developed)

Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed)

SME (Technical Review) Date Approved by: Signature On File (NRC Developed)

Training Supervision Date Approved by: Signature On File (NRC Developed)

Training Program Owner Date TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical /

Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)

{C001}

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 4 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

SUPERVISOR DATE See Cover Initial development for Initial development for 2015 NRC 0 2015 NRC LOIT N/A LOIT examination. See Cover examination.

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 5 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs)

SIMULATOR SETUP INSTRUCTIONS: NONE SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE Required Materials: 1. RIP 101.3, Rev 1

2. Crescent Wrench General

References:

1. RIP 101.3, Rev. 1 Task Standards: 1. The operator simulates closing V-17-61.

2. The operator simulates removing pipe plug d/s of V-17-174.

3. Simulates opening V-17-174.

4. The operator simulates closing V-17-174.

5. Operator simulates installing pipe plug d/s of V-17-174.

6. Operator simulates opening V-17-61.

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 6 of 13 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

The plant is operating at 70% power.

An ATWS has occurred.

The Shift Manager has directed the RO to perform IPOI 5 QRC 2, ATWS.

The RO has directed you to vent the scram air header.

INITIATING CUES (IF APPLICABLE):

Vent the scram air header in accordance with RIP 101.3 and inform the control room.

This JPM is not Time Critical.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 7 of 13 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:1 Close V-17-61 (Scram Pilot Air Header Isolation Vlv).

Critical Y RIP 101.3 Step 1 Standard: The operator simulates closing V-17-61.

Evaluator Cue: When the operator has simulated turning the handwheel in the clockwise direction, tell the operator The valve stem is in and handwheel stops moving.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 8 of 13 Performance Step: 2 Remove the pipe plug located downstream of V-17-174, (PI-Critical Y 184/PS1842 Test Connection Isolation valve).

RIP 101.3 Step 2 Standard: The operator simulates removing pipe plug d/s of V-17-174.

Evaluator Cue: When the operator has simulated turning the cap in the clockwise direction, tell the operator, The pipe plug has been removed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 Open V-17-174, (PI-184/PS1842 Test Connection Isolation valve).

Critical Y RIP 101.3 Step 3 Standard: Simulates opening V-17-174.

Evaluator Cue: When the operator has simulated turning the handwheel in the counter clockwise direction, tell the operator, The valve stem is up and handwheel stops moving. You hear a loud rush of air coming from the open pipe. The air flow diminishes over time.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 9 of 13 Performance Step: 4 Communicates actions to control room.

Critical N RIP 101.3 Per Cue Standard: The operator simulates calling the control room and informs RO that scram air header is depressurized.

Evaluator Cue: When the operator simulates informing the control room that the Scram Air Header has been vented IAW RIP 101.3, tell the operator That all control rods indicated inserted. Restore the Scram Air Header.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Question and Answer:

Critical N What do you expect the position of the scram pilot valves to be before and Q&A after venting?

Standard: The operator should respond that the scram pilot valves will be closed before venting and open after venting.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 10 of 13 Performance Step: 6 Restoration: Close V-17-174, (PI-184/PS1842 Test Connection Isolation Critical Y valve).

RIP 101.3, Restoration, Step 1 Standard: The operator simulates closing V-17-174.

Evaluator Cue: When the operator has simulated turning the handwheel in the clockwise direction, tell the operator The valve stem is in and handwheel stops moving.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 Restoration: Reinstall the pipe plug downstream of V-17-174.

Critical Y RIP 101.3, Restoration, Step 2 Standard: Operator simulates installing pipe plug d/s of V-17-174.

Evaluator Cue: When the operator simulates putting the pipe plug back on, tell the operator The pipe plug is installed Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 11 of 13 Performance Step: 8 Restoration: Open V-17-61, Scram Pilot air header isolation valve.

Critical Y RIP 101.3, Restoration, Step 1 Standard: Operator simulates opening V-17-61.

Evaluator Cue: When the operator has simulated turning the handwheel in the counter clockwise direction, tell the operator, The valve stem is up and handwheel stops moving.

Performance: SATISFACTORY UNSATISFACTORY Comments:

When the scram air header has been vented and restored, the JPM is complete.

Terminating Cues:

Direct the Operator to show the location of 1C208 to complete the RCIC Start JPM.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 1 JPM VENT THE SCRAM AIR HEADER Page 12 of 13 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date:

LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

TR-AA-230-1003-F10, Revision 2

JPM Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS:

The plant is operating at 70% power.

An ATWS has occurred.

The Shift Manager has directed the RO to perform IPOI 5 QRC 2, ATWS.

The RO has directed you to vent the scram air header.

INITIATING CUES (IF APPLICABLE):

Vent the scram air header in accordance with RIP 101.3 and inform the control room.

This JPM is not Time Critical.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2

JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 2 TITLE: OPERATE RCIC FROM 1C208 TR-AA-230-1003-F10, Revision 2

JOB PERFORMANCE MEASURE JPM Page 2 of 13 JPM TITLE: OPERATE RCIC FROM 1C208 JPM NUMBER: 295016-01 REV. 0 TASK NUMBER(S) / 94.28/

TASK TITLE(S): Transfer Control to the Remote Shutdown Panel K/A NUMBERS: 295016 AK2.02 K/A VALUE: 4.0/4.1 Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER:

APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room:

Simulator: Other: X To be performed in the Training Building prior to the In Plant portion of the JPM, In Plant Lab:

portion is required after the Task.

Time for Completion: 40 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed)

Instructor/Developer Date Reviewed by: Signature On File (NRC Developed)

Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed)

SME (Technical Review) Date Approved by: Signature On File (NRC Developed)

Training Supervision Date Approved by: Signature On File (NRC Developed)

Training Program Owner Date TR-AA-230-1003-F10, Revision 2

2015 NRC In Plant 2 JPM OPERATE RCIC FROM 1C208 Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.