ML100351124

DAEC 2009 Initial Exam Proposed Simulator Scenarios

ML100351124
Person / Time
Site:	Duane Arnold
Issue date:	09/21/2009
From:	Division of Reactor Safety III
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Download: ML100351124 (83)

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Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 1 Facility: DAEC Scenario No.: 1 Op Test No.: 2009-01 Examiners: Operators:

Initial Conditions:

• The plant is operating at 70% power due to a downpower for maintenance.

Turnover:

• Perform Main Turbine Operational Tests IAW NS-930001 Sections 7.3, 7.4 and 7.5

• Return to full power using Recirc following completion of the test

• 3D Monicore Official Case has been printed and the P1 check per IPOI-3 is complete

• Per RE guidance raise power to 80% for pre-conditioning Critical Tasks: 1. ED due to low vessel level

2. Start the B SBDG to repower a vital bus for RPV reflood Event Malf. No. Event Event No. Type* Description N - BOP Perform Main Turbine Operational Tests (NS-930001)

1. N/A N - SRO Raise power with Reactor Recirc R - RO

2. N/A R - SRO A RPS MG set trip I - ALL TS 3.3.8.2. Condition A 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to remove in service power

3. RP02A TS - SRO supply I - RO B CRD pump requires removal from service due to high

4. RD26B I - SRO vibration

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9, Supplement 1

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 1 Event Malf. No. Event Event No. Type* Description A SBDG Start due to lightning strike in switchyard - SBDG C - BOP voltage regulator fails

5. DG07A C - SRO TS - SRO TS 3.8.1.B. - 7 day C - BOP A Well Water Pump trips.

6. SW21A C - SRO ED01A,F, Loss of offsite power and reactor scram. B DG fails to auto

7. M - ALL ED08C start. RCIC trips, Drywell leak C - BOP

8. HP02 HPCI Injection valve closes. ED required C - SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9, Supplement 1

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 1 DAEC 2009 NRC Scenario #1 The plant is operating at 70% power. Main Turbine Operational tests are scheduled to be performed. The crew will perform the Main Turbine Operational tests and once the tests are complete the RO will raise power with reactor recirc.

After power is raised, the A RPS MG set trip. The RO will respond to the half scram and reset when required. The BOP operator will take actions to transfer the RPS power supply. The SRO must address TS for one RPS channel inoperable.

Once TS are addressed for the RPS issue, the B CRD pump will experience high vibrations requiring removal from service. The standby pump will be started.

Then, a start of the A SBDG will occur due to a lightning strike in the switchyard. When the SBDG starts the voltage regulator will fail and the SBDG must be removed from service. The SRO must address TS for one SBDG inoperable. After TS are addressed,,

a trip of A Well Water Pump occurs. The BOP takes action IAW the AOP to start the standby pump to compensate for rising drywell pressure and temperature.

Once those actions are addressed, a Loss of Offsite Power and subsequent reactor scram occurs. Additionally, a leak will occur in the drywell. The B DG fails to auto start and must be manually started (CRITICAL TASK). Additionally, RCIC trips and the HPCI injection valve fails closed. EOPs will be entered on low reactor level and high drywell pressure.

An Emergency Depressurization will be required as vessel level continues to lower (CRITICAL TASK). B RHR and B Core Spray must be used to reflood the vessel.

The scenario may be terminated when RPV level has recovered to the normal band.

NUREG-1021, Revision 9, Supplement 1

QF-1030-19 Rev. 12 EXAMINATION SCENARIO GUIDE (ESG)

SITE: DAEC Main Turbine Operational Tests / Increase Power with Recirc / A RPS MG Set Trip / B CRD pump malfunction /

A SBDG Spurious start - voltage regulator failure / A Well ESG NRC 09-01 REV 0 Water Pump Trip / Loss of Offsite Power / Rx Scram /

B SBDG fails to auto start / RCIC Trip / HPCI injection valve closes PROGRAM: OPERATIONS #:

COURSE: INITIAL LICENSED OPERATOR #: 50007 TOTAL TIME: 90 MINUTES Developed by:

Instructor Date Validated by:

SME/Instructor Date Reviewed by:

Operations Manager Date Approved by:

Training Supervisor-Operations Date Page 1 of 1

2009 NRC ILT Scenario #1 GUIDE REQUIREMENTS Goal of The goal of this scenario is to evaluate ILT students during the NRC Training: Exam with 3 man crew.

Learning There are no formal learning objectives Objectives:

Prerequisites: None Simulator Simulator Booth Instructor Training Phone Talker Resources:

Simulator Floor Instructor

References:

None None Commitments:

Evaluation Dynamic Simulator Method:

Operating None Experience:

Initiating Event with Core Damage Frequency:

N/A due to exam security Important Components:

Related PRA N/A due to exam security Information:

Important Operator Actions with Task Number:

N/A due to exam security Page 2 of 2

2009 NRC ILT Scenario #1 SCENARIO

SUMMARY

The plant is operating at approximately 70% power. Main Turbine Operational tests are scheduled to be performed. The crew will perform the Main Turbine Operational tests and once the tests are complete the RO will raise power with reactor recirculation.

After power is raised, the A RPS MG set will trip. The BOP operator will take actions to transfer the RPS power supply. The RO will respond to the half scram and reset after the RPS has been transferred to the alternate power supply. The SRO must address Technical Specifications for one RPS channel inoperable.

Once Technical Specifications are addressed for the RPS issue, the B CRD pump will experience high vibrations which will require removing the pump from service. The B CRD pump will be started and the A CRD pump will be secured.

The A SBDG will spuriously start due to a lightning strike in the switchyard. When the A SBDG starts the voltage regulator shows signs of having failed, and the SBDG must be removed from service. The SRO must address Technical Specifications for one SBDG inoperable. After Technical Specifications are addressed, a trip of A Well Water Pump occurs. The BOP takes action IAW the AOP to start the standby pump to compensate for rising drywell pressure and temperature.

Once those actions are addressed, a Loss of Offsite Power and subsequent reactor scram occurs. After the scram, a leak will occur in the drywell. The B SBDG fails to auto start and must be manually started (CRITICAL TASK). Additionally, RCIC trips and the HPCI injection valve fails closed. EOPs will be entered on low reactor level and high drywell pressure.

An Emergency Depressurization will be required as vessel level continues to lower (CRITICAL TASK). B RHR and B Core Spray must be used to reflood the vessel.

The scenario may be terminated when RPV level has recovered to the normal band.

Page 3 of 3

2009 NRC ILT Scenario #1 SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

Start Sim View / Data Capture Program for EXAM ONLY 1.1 General Instructions

a. Restore the IC for ILT Scenario 1 (N-1) from the Thumb Drive that it is stored on.

This Thumb Drive also has the malfunction and override files on it.

a) Log onto one of the Computer Terminals using the logon from Lowell b) If the malfunction file is the exam file, go to c), otherwise:

(1) With a file manager, go to the \\greg\c$\opensim directory, and copy the Malfunc-New.dat file into that directory.

(2) Rename the Malfunc.dat file to Malfunc-OLD.dat (3) Rename the Malfunc-NEW.dat file to Malfunc.dat c) Make a copy of the exam scenario IC file and rename it as d_ic.000 d) Copy the IC file from the thumb drive to the \\greg\ryandev\ops\ic directory. This makes the exam IC number 000.

e) Reset to IC 000.

(1) Verify Malfunctions (2) Verify Overrides (3) Verify Remote functions (4) Verify event trigger definitions and accept all triggers

b. If the thumb drive is not available, then reset to IC 23 and set the Malfunctions, Remotes, Overrides, and Triggers as per the tables below.

c. Verify Rod Line >85% then lower flow if necessary to 70% power

d. Verify Alternate RPS aligned to 1B32 using remote function

e. Verify strip chart recorders are ON. If not perform 4.4.4 of OI 831.4 (PPC)

f. Set APRM Gains using remote function NM02

g. Verify APRM recorders are set to the APRM scale and are set in SLOW speed.

h. Verify Pull Sheet setup matches current step and rod position

i. Provide marked up copy of IPOI 3 marked up through Step 4.0 (16)

j. Provide marked up copy of NS-930001 ready to perform Sections 7.3, 7.4 and 7.5

k. Markup AOP 903 for the Severe Thunderstorm Watch - all actions performed up to transitioning out of section.

l. Place SPMET1 on a computer terminal (IAW AOP 903).

Page 4 of 4

2009 NRC ILT Scenario #1 1.2 EVENT TRIGGER DEFINITIONS:

Trigger Trigger Logic Statement Trigger Word Description No.

4 Logic: ZAODGFDG1 .GE. 0.2 When SBDG Freq comes on scale, delete start signal so SBDG will continue to run Command: DMF DG07A 11 ZLORCHS2404(2) .GE. 1 RCIC MO2404 open 13 RRLTAF .GT. 170 .AND. YCAB161 .GT. 1000 RPVWL >170 and HPCI injecting >1000gpm

1.3 MALFUNCTIONS

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup DG05A 1G21A Diesel Generator V/R 100 100 Oscillates In AUTO Setup STDG02 Trip Override - B SBDG 1G21 True TRUE Fails To Auto Start As Dir RP02A RPS EPA Breaker Trip - RPS A 1 False TRUE EPA BKR As Dir RD26B CRD Pump B High Vibration 7 False TRUE As Dir DG07A 1G21 A Diesel Generator 3 False TRUE Spurious Actuation As Dir SW21A Well Water Pump Trip - Pump A 5 False TRUE 1P58A As Dir ED01A Loss of Off Site Power Sources - 9 False TRUE Bkr M As Dir ED01F Loss of Startup Transformer 1X3 9 False TRUE Lockout Relay 386S As Dir ED08C 4kv/480v Bus Fault Bus 1A3 9 False TRUE As Dir RC01 RCIC Overspeed Trip 11 False TRUE As Dir RC02 RCIC Turbine Trip 11 False TRUE As Dir HP02 HPCI Turbine Trip 13 False TRUE As Dir RR15A Recirc LOOP Rupt - Design Bases 00:15:00 30 0 20 LOCA at 100%

OVERRIDES:

Time Override No. Override Title Delay Ramp ET Initial Final Value Value 1.5 REMOTE FUNCTIONS:

Time Remote Remote Title Delay Ramp ET Initial Final No. Value Value AS DIR AN06 Remote Func Feedback AN06- 19 Norm Ack Ack Switch 1C93 AS DIR RD15 Local Reset of CRD Pump Vib 21 Norm Ack Alarm Page 5 of 5

2009 NRC ILT Scenario #1 FLOOR INSTRUCTOR ACTIONS Simulator Pre-brief:

2.1 Individual position assignments 2.2 Simulator training changes since last module (N/A) 2.3 Simulator hardware and software modifications/problems that may impact training Page 6 of 6

2009 NRC ILT Scenario #1 TURNOVER INFORMATION Day of week and shift Today Day Shift Weather conditions Hot, Humid A Severe Thunderstorm Watch is in effect for the next 31/2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />. All AOP 903 actions are complete.

(Plant power levels) 70%

MWT 1347 MWE 426 CORE FLOW 34.5 Thermal Limit Problems/Power Evolutions Plant Risk Status CDF Baseline Color Green Existing LCOs, date of next surveillance None STPs in progress or major maintenance Perform Main Turbine Operational tests NS-930001, Section 7.3, 7.4 and 7.5 Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment None Comments, evolutions, problems, core damage frequency, etc.

Perform Main Turbine Operational tests NS-930001, Section 7.3, 7.4 and 7.5 Following test completion and Per RE guidance raise power to 80% with Recirc flow for pre-conditioning then hold for RE review.

Page 7 of 7

2009 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover COMPLETE TURNOVER: Get familiar with plant conditions.

• Provide Shift Turnovers to the SRO

• SRO will provide beginning of shift brief to coordinate the tasks that and ROs.

were identified on the shift turnover.

a. Review applicable current Plant Status

b. Review relevant At-Power Risk status

c. Review current LCOs not met and Action Requirements

d. Verify crew performs walk down of control boards and reviews turnover checklists EXAMINER NOTE: Continue to next event at examiners direction page 8 of 8

2009 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Booth Instructor respond as plant SRO personnel and respond as necessary:

Perform Main Directs BOP to perform NS-930001, Main Turbine Operational Tests, Turbine Sections 7.3, 7.4 and 7.5 operational tests IAW NS -

930001 RO Monitors Reactor power , pressure and level BOP Performs Sections 7.3, 7.4 and 7.5 of NS-930001 as follows:

7.3 OVERSPEED TRIP DEVICE AND MECHANICAL TRIP VALVE TEST (TEST A)

NOTE: The purpose of this test is to demonstrate the operability of the Overspeed Trip Device and Mechanical Trip Valve.

7.3.1 - Verify PRIMARY SPEED SIGNAL LOST light on first hit panel in 1C49 is OFF.

NOTE: The following procedural steps are performed at 1C07.

7.3.2 - In the MECHANICAL TRIP TEST area, momentarily depress the LOCKED OUT push-button.

7.3.3 - Confirm the following:

a. LOCKED OUT light ON

b. Annunciator MECHANICAL TRIP LOCKOUT (1C07A, A-8) is activated.

page 9 of 9

2009 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 (BOP Actions Continued)

Continued NOTE: If this test is suspended before actual testing of the Mechanical Trip Valve takes place, the Mechanical Trip Lockout can be removed by depressing the NORMAL push-button.

7.3.4 Depress and hold the OIL TRIP push-button until the TRIPPED light in the MECHANICAL TRIP area turns ON (several seconds).

7.3.5 Depress and hold (through Step 7.3.6.b) the PUSH TO RESET pushbutton and confirm the following in the MECHANICAL TRIP area:

a. RESETTING light ON

b. TRIPPED light OFF

c. RESET light ON 7.3.6 After an approximately 10 second time delay, confirm the following in the MECHANICAL TRIP TEST area:

a. LOCKED OUT light OFF

b. NORMAL light ON

c. RESETTING light OFF 7.3.7 Confirm annunciator MECHANICAL TRIP LOCKOUT (1C07A, A-8) is reset.

7.3.8 Verify acceptance of test results by initialing this step. (Any of the following indications, a through d, would indicate unsatisfactory results.)

a. Depressing the OIL TRIP push-button with no resultant TRIPPED indicator for the Mechanical Trip Valve.

b. RESETTING light does not come ON when PUSH TO RESET push-button is depressed.

c. RESETTING light remains ON after test.

d. LOCKED OUT light remains ON after test.

7.3.9 Should the results of this test be unsatisfactory, notify Maintenance immediately.

page 10 of 9

2009 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 (BOP Actions Continued)

Continued 7.4 POWER/LOAD UNBALANCE AND RELAY CIRCUITS TEST NOTE: The purpose of this test is to demonstrate operability of the Power/Load Unbalance Circuit that protects the Main Turbine against rapid acceleration due to loss of load when operating above 40% turbine load.

All procedural steps are performed at 1C49, Bay 1 TEST AND ADJUST.

7.4.1 Verify Prerequisite 6.5 has been satisfied.

7.4.2 Depress the POWER LOAD UNBALANCE-PUSH TO TEST push-button.

7.4.3 Confirm that yellow back-lighting for the POWER LOAD UNBALANCE-PUSH TO TEST push-button turns ON.

7.4.4 Release the POWER LOAD UNBALANCE-PUSH TO TEST pushbutton and confirm that the yellow back-lighting turns off.

7.5 MASTER TRIP 24 VDC SOLENOID VALVES TEST NOTE: The purpose of this test is to demonstrate operability of the two Master Trip Solenoid Valves that must function properly when a trip occurs.

All steps in Section 7.5 are performed at 1C07, in the MASTER TRIP SOLENOID TEST area of the panel, unless stated otherwise.

7.5.1 Verify that all 6.6 prerequisites have been satisfied.

7.5.2 Depress and hold (until Step 7.5.5) TEST TRIP A push-button.

7.5.3 Confirm TEST TRIP A white back-light turns OFF.

7.5.4 Confirm TEST TRIP SOLENOID AMPS for VALVE A indicates approximately zero amps.

page 11 of 9

2009 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 (BOP Actions Continued)

Continued 7.5.5 Release TEST TRIP A push-button.

7.5.6 Confirm TEST TRIP A white back-light is ON.

7.5.7 Confirm TEST TRIP SOLENOID AMPS for VALVE A indicates between 1 and 2 amps.

CAUTION: If a malfunction is observed during the test of one Master Trip Solenoid Valve, the other valve should NOT be tested until repairs are made.

7.5.8 Depress and hold (until Step 7.5.11) TEST TRIP B push-button.

7.5.9 Confirm TEST TRIP B white back-light turns OFF.

7.5.10 Confirm TEST TRIP SOLENOID AMPS for VALVE B indicates approximately zero amps.

7.5.11 Release TEST TRIP B push-button.

7.5.12 Confirm TEST TRIP B white back-light is ON.

7.5.13 Confirm TEST TRIP SOLENOID AMPS for VALVE B indicates between 1 and 2 amps.

REPORTS to CRS That the tests are completed SAT EXAMINER NOTE: Continue to next event at examiners direction page 12 of 9

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event #2 SRO Booth Instructor respond as plant Increase Power personnel and respond as necessary: Provides a reactivity brief (may be performed before scenario begins).

with Reactor Communicates with Real Time Desk.

Recirc Role Play: If necessary, call in as Real Provide direct oversight of power increase.

Time Desk to prompt crew to increase power RO Raises power with Recirc Pump Flow Controllers IAW IPOI-3, Section 4.

1. To raise recirc flow, verify the digital display to the S PERCENT SPEED DEMAND variable by pressing the display switch, then rotate the A[B] MG SET SPEED CONTROL SIC 9245A[B] knobs on 1C04 clockwise in small equal increments.

2. Keep loop flows balanced by comparing the Recirc Pump discharge flow on FI 4634A vs. FI 4634B or A pump (red channel) vs B pump (black channel) on FR-4635 Monitors critical plant parameters - power, pressure, level BOP Monitors balance of plant equipment.

Provides peer check for RO during power increase.

EXAMINER NOTE: Continue to next event at examiners direction page 13 of 13

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event #3 Booth Instructor: respond as plant CREW personnel and respond as necessary: Recognizes 1/2 scram on A side - Multiple Annunciators including, A RPS MG Set Trip Annunciator 1C05A A2 - A RPS Auto Scram Diagnoses Loss of RPS When directed:

SRO INSERT TRIGGER 1

• Enters AOP 358 Loss of RPS AC Power This inserts MF RP02A, which will trip the

• Sends operator to investigate the trip.

A RPS MG Set.

• Refers to TS 3.3.8.2. Condition A - 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to remove in service power supply (condition met with EPA tripped)

• Enters TRM 3.3.4 Condition A - for Reactor Water conductivity Role Play: When contacted by control monitoring room to investigate, wait 2 minutes and

• Directs transferring RPS to alternate power supply report that:

• Contacts Duty Manager

• The A RPS MG set is running.

• Directs OI 358 RPS Appendix 4, RPS POWER SUPPLY TRANSFER HALF SCRAM RECOVERY CHECKLIST.

• A2 EPA has tripped free - no lights, smells bad, no fire or smoke BOP Transfers A RPS to alternate power supply per AOP 358 as follows:

IF: an alternate RPS power supply is available as indicated by observing A-MG [B-MG] or ALT XFMR white light ON at 1C15 or 1C17 THEN: place handswitch C71B-S1A [C71B-S1B] RPS ALTERNATE ROLE PLAY: As in plant operator report POWER TRANSFER switch to A-MG [B-MG] OR ALT position as required that alternate RPS is aligned to 1B32 and verify selected position white light remains on.

Perform OI 358 RPS Appendix 4, RPS POWER SUPPLY TRANSFER HALF SCRAM RECOVERY CHECKLIST.

As directed, at Panel 1C36 - resets the Fuel Pool EXH Rad Monitor RIS-4131A NOTE: When operator moves toward restoring RWCU, go to next event RO Resets the 1/2 scram per ARP 1C-05A A2 - Step 4.1.b - Resets the half scram when the failure has been repaired and/or the trip signal has cleared.

EXAMINER NOTE: Continue to next event when operator moves toward restoring RWCU, page 14 of 14

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event #4 Booth Instructor: respond as plant CREW B CRD pump personnel and respond as necessary:

Responds to Annunciator 1C05A (C-7) B CRD 1P209B High Vibration requires When directed by Lead Evaluator:

removal from service due to INSERT EVENT TRIGGER 7 SRO high vibration This starts the B CRD pump vibrations.

Directs RO/BOP to carry out the ARP actions Booth Instructor respond as plant Notifies Duty Manager personnel and respond as necessary: RO Role Play: As field operator directed to Refers to ARP and starts the standby pump as follows check the B CRD pump, report it is

• Notifies field operator to verify adequate oil level in standby CRD Pump running hotter than normal.

1P-209A.

Role Play: As field operator directed to

• Verify standby CRD Pump 1P-209A Discharge Isolation V-17-8 full go to the CRD pump, report that the A open.

CRD Pump oil level is good and that the A CRD Pump 1P-209A Discharge

• At 1C05, starts A CRD PUMP 1P-209A by momentarily placing hand Isolation V-17-8 is full open. switch HS-1807A on 1C05 in the START position.

Role Play: As field operator, if requested, report that the standby pump has started Stops the B pump as follows and is operating normally.

• Stops B CRD PUMP 1P-209B by momentarily placing hand switch NOTE: If directed to reset the CRD high HS-1807B on 1C05 in the STOP position.

vibration alarm then

• Notifies CRS/Crew that the CRD Pumps have been swapped.

INSERT EVENT TRIGGER 21 This will reset the B CRD vibe alarm. BOP NOTE: Crew may notify personnel to Monitors BOP equipment insure the switchgear room is clear before May make PA announcement for start of pump cycling the CRD Pump Breaker.

EXAMINER NOTE: Continue to next event at examiners direction page 15 of 15

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event #5 Booth Instructor: respond as plant CREW personnel and respond as necessary:

A SBDG starts Responds to Annunciators:

When directed:

• 1C08A (A-10) A SBDG 1G-21 Running &

INSERT TRIGGER 3

• 1C08A (C-11) - A Diesel Gen Panel 1C-93 Trouble This starts the A SBDG

• 1C08A (C-12) - A SBDG 1G-21 Engine Cranking Verify Trigger 4 goes TRUE when SBDG

• 1C07A (A-11) - HVAC 1C23 trouble comes on scale to DMF DG07A so SBDG Recognizes start of A SBDG will keep running Observes that SBDG voltage is swinging When directed to acknowledge 1C93 alarm: SRO INSERT EVENT TRIGGER 19 May direct placing the A SBDG in PTL IAW the Alarm Response actions This acknowledges the local 1C93 alarm. Directs shutting down SBDG IAW OI 324 Notifies Duty Manager Role Play: Report to control room as Enters TS 3.8.1.B. - 7 day security that a lightning strike was seen in Directs performance of TS surveillance 3.8.1-1 within one hour the east side of the yard by the startup transformer BOP Role Play: Report as A SBDG and Directs field operator to check on the running SBDG local alarm indicates starting air pressure Places A DIESEL GENERATOR 1G-21 CONTROL hand switch HS-3231A low on 1C08 in the PTL position Role Play: Report as Aux Operator that OR no problems exist in the switchyard Shuts down the SBGT as follows IAW OI 324:

Role Play: IF asked, report as chemistry that you have not bromated in the past 12 1. Place A DIESEL GENERATOR 1G-21 CONTROL hand switch HS-3231A hours on 1C08 in the STOP position, hold for 5 to 10 seconds, and then return to AUTO.

If requested, SBDG Operating Checklist OI 324A9 (Attachment 9). IAW ARP - May dispatch an operator to check the A ESW pump operation RO Continues to monitor reactor power, pressure and level EXAMINER NOTE: Continue to next event at examiners direction page 16 of 16

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event #6 Booth Instructor: respond as plant CREW personnel and respond as necessary:

A Well Water Responds to Annunciator 1C23C F-1 A Well Water Pump High/Low Flow Pump trip When directed:

INSERT EVENT TRIGGER 5 SRO This inserts the A Well Water trip.

Enters AOP 408 WELL WATER SYSTEM ABNORMAL OPERATION Directs starting of additional Well Water pump and restores system Role Play: When contacted by control parameters room, acknowledge request to check out Directs monitoring of Drywell pressure & temperature A well house. Report back after 5 minutes that nothing abnormal was Notifies Duty Manager observed at the well house.

RO Role Play: When directed to check the Monitors reactor power pressure and level breaker for the A Well, report back after 5 minutes that the breaker is tripped, but Monitors Drywell pressure & temperature you have no indications why.

BOP Role Play: When contacted, acknowledge Per AOP 408 immediate actions:

as Duty Manager the requests by the SRO to check out the SBDG and Well Pump May start one OR both ESW pumps to provide cooling to the Control issues Building Chillers and to reduce demand on the Well Water System.

Starts a standby Well Water Pump, and adjusts flow at the back panel.

Examiner Note: May use QRC to start ESW pumps EXAMINER NOTE: Continue to next event at examiners direction page 17 of 17

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event Booth Instructor: Insert the next Crew

1. 7 & #8 malfunction at the direction of the Lead Responds to Loss of Offsite Power Indications Loss of Offsite examiner

Power, When Directed:

B SBDG fails to SRO auto start, INSERT TRIGGER 9 RCIC trips, Enters EOP 1 on RPV level <170 inches This starts the LOOP event.

Drywell leak, Directs initial RPV level band 170 to 211 using available systems HPCI injection valve closes EXAMINER NOTE: The following steps Directs starting the B SBDG and verifying it loads the Bus are related to the Loss of Offsite Power (CRITICAL TASK #1) and initial level and power restoration Directs Reactor pressure control using SRVs Enters AOP 304.1 LOSS OF 4160V NON-ESSENTIAL ELECTRICAL EXAMINER NOTE: The BOP may start POWER the B SBDG prior to the SRO directing the Enters AOP 301 LOSS OF ESSENTIAL ELECTRICAL POWER action.

Directs Defeat 11 RO Places Mode switch to Shutdown BOOTH NOTE:

Verifies and reports all rods in Verify TRIGGER 11 goes TRUE to trip Provides RPV level and pressure status RCIC when RCIC is started Reports RPV level dropped below 170 (EOP 1 entry)

Attempts to maintain RPV level in the band initially directed by SRO (170 to Role Play:

211)

When directed to reset the RCIC Attempts to place RCIC in service IAW the QRC but diagnoses that RCIC mechanical overspeed device, wait 5 trips minutes and report that the overspeed device will NOT reset. Places HPCI in service to restore RPV level to the directed band Events page 18 of 18

2009 NRC ILT Scenario #1 SCENARIO TIMELINE

1. 7 & #8 BOP (Continued)

May report MSIV closure (Group I Isolation)

Diagnoses Startup Transformer lockout Diagnoses that the B SBDG failed to start STARTS B SBDG and verifies it loads BUS 1A4 (CRITICAL TASK #1)

Installs Defeat 11

• At Panel 1C35, place CV-4371A GROUP 3 OVERRIDE keylock switch S583B in OVERRIDE OPEN position and confirm amber light is ON.

• Confirm CV-4371A opens by observing valve position indicating lights on 1C35 (red light is ON and the green light is OFF).

NOTE: Next Page begins actions for Drywell leak and loss of high pressure feed page 19 of 18

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Events EXAMINER NOTE: The following steps CREW

1. 7 & #8 are related to the drywell leak and loss of Recognizes rising Drywell Pressure (Continued) high pressure feed Recognizes HPCI System trips on 211 and will not reset Booth Instructor:

When level is >170 and HPCI is injecting, VERIFY TRIGGER 13 GOES TRUE to trip SRO HPCI. Enters Alternate Level Control leg of EOP 1 Directs injection of Standby Liquid May direct starting B CRD pump The LOCA is Booth Instructor: Enters EOP 2 on rising DW pressure intended to be When directed:

inserted after Directs Torus Spray when Containment Pressure is >2.0 psig the initial post INSERT EVENT TRIGGER 30 Directs lockout of ADS scram activities This starts the LOCA event start to calm May direct Defeat 4 down. May Enter EOP 3 if Steam Tunnel temperature rises above Max Normal Directs Drywell Spray when Containment Pressure is >11.0 psig OR before Drywell temperature reaches 280 degrees Directs Emergency Depressurization per EOP-ED after RPV level drops to +15 inches but before RPV level reaches -25 inches Directs opening 4 ADS SRVs (CRITICAL TASK #2)

Directs RPV level restoration with B Core Spray and B RHR pumps RO Monitors and reports RPV level trend As directed, injects to the RPV with B Standby Liquid As directed, starts the B CRD pump page 20 of 20

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Events BOP

1. 7 & #8 Installs Defeat 4 as time permits (Continued)

Sprays the torus when directed

• Places Containment Spray Enable Switch HS-2001C[1903C] in the MAN position

• Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve Handswitch in OPEN and verify MO-2005[MO-1932] opening.

• Throttles open MO-2006[MO-1933], Torus spray Valve.

Locks out ADS as directed Sprays the Drywell when directed

• Opens MO-2000[MO-1902], Inboard Drywell Spray Valve.

• Throttles open MO-2001[MO-1903], Outboard Drywell Spray

• Verifies MO-2005[MO-1932] Outboard Torus Cooling/ Spray Valve open.

• Throttle MO-2001[MO-1903] Outboard Drywell spray valve as necessary to maintain 4800 gpm per operating RHR pump and desired spray flow.

Opens 4 ADS SRVs (CRITICAL TASK #2)

Injects to the RPV with B Core Spray and B RHR once RPV pressure lowers below pump shutoff head Scenario Termination Criteria The scenario may be terminated after the ED is performed and level is being restored with available low pressure ECCS Event Classification FS1- SAE (RPV Level <-25 and RPV level <15

• • • END OF SCENARIO ***

page 21 of 20

SEG Validation Checklist 2009 NRC Exam Scenario #1 THIS SECTION IS ONLY REQUIRED FOR EVALUATED SCENARIOS.

Correct IC or plant status identified.

Shift turnover forms filled out (both CRS/OSM and NSOE) if required.

Additional documents are prepared (STPs, Work Orders, LCO Paperwork).

Tasks and Objectives have been verified to be correct.

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

SOMS tags identified and included in setup instructions.

Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.

Setup files correctly called out.

Malfunction list is accurate.

Override list is accurate.

Remote function list is accurate.

Event triggers are accurate.

Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.

Instructor Activity section is accurate and complete:

Actions are clearly defined for Booth or Floor instructor.

Role-playing is clearly noted.

The sequence of events is completely and concisely narrated even if it takes no instructor action.

Automatic actions that require verification are noted.

Reasonable alternate paths are considered and included.

Event trigger activation is distinguished from narrative text (Bold font)

Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.

Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.

Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.

2009 DAEC NRC Scenario 1 Script Rev 7-17-09cah.docPage 22 of 22

SEG Validation Checklist 2009 NRC Exam Scenario #1 Expected Student Response Section is accurate and complete:

Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)

Tasks are clearly noted and properly numbered as appropriate.

Knowledge objectives are clearly noted and properly numbered as appropriate.

Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)

Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)

Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.

Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.

Actions are listed using a logical order; by position and chronology. (N/A as appropriate)

Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.

Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)

For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.

Turnover information (as required) is correct:

Day and shift are appropriate.

Weather conditions do not conflict with malfunctions.

Power levels are correct.

Thermal limit problems and power evolutions are realistic and include a reason for any downpower.

Existing LCOs include start date, remaining time and actions.

Plant Risk Assessment (CDF and Color).

STPs are appropriate for day and shift.

Core Damage Frequency has been properly calculated and listed to 3 decimal places.

Maintenance is realistic for plant conditions.

Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.

SME/Instructor Date SME/Instructor Date 2009 DAEC NRC Scenario 1 Script Rev 7-17-09cah.docPage 23 of 23

SEG Validation Checklist 2009 NRC Exam Scenario #1 Crew: Instructors:

OSM ____________________________ Booth ________________________________

CRS ____________________________ Floor __________________________

STA __________________________________ Extra ________________________________

1C05 ____________________________

1C03 ____________________________

BOP ____________________________

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

SEG Validation Checklist 2009 NRC Exam Scenario #1 Crew Comment:

Resolution:

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 2 Facility: DAEC Scenario No.: 2 Op Test No.: 2009-01 Examiners: Operators:

Initial Conditions:

• The plant is at 70% power for a rod sequence exchange

• The sequence exchange will commence when informed by the RE

• All systems are operable Turnover:

• Perform STP 3.6.1.7 DW to Suppression Chamber Vacuum Breaker operability test Critical Tasks: 1. Terminate and Prevent injection under ATWS conditions

2. Insert all control rods to shutdown the reactor under all conditions

3. Spray the drywell to control drywell parameters while in the safe region of the DWSIL curve Event Malf. No. Event Event No. Type* Description Perform STP 3.6.1.7 DW to Suppression Chamber N - BOP

1. NA Vacuum Breaker Operability Test N - SRO A Recirc Pump High Vibration - removal from service C - RO

2. RR35A C - SRO TS 3.4.1. condition D (Single Loop)

TS - SRO HPCI spurious start.

C - BOP

3. HP01 C - SRO TS 3.5.1.F.1 and 2.

TS - SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9, Supplement 1

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 2 Event Malf. No. Event Event No. Type* Description Power reduction required by RE due to previous events to R - RO ensure margin to thermal limits - control rods using reverse

4. NA R - SRO pull sheet Steam leak in primary containment will require the BOP to C - BOP

5. MS02 vent the drywell C - SRO 125VDC Div1 Panel 1D11 trips causing an RPV level event.

Manual action will be required to control level C - ALL

6. ED13A TS - SRO TS 3.8.7 condition B (Distribution Systems - Operating)

B Recirc high vibration & pump trip, Reactor Scram, Hydraulic ATWS, several rods must be manually inserted.

RR35B

7. M - All RP05F Drywell pressure degrades due to small break, requiring entry to EOP-2 C - BOP RH10A/

8. C - SRO RHR pumps fail to auto start on high drywell pressure B/C/D

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9, Supplement 1

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 2 DAEC 2009 NRC Scenario #2 The plant is at 70% power. The RO will perform STP 3.6.1.7 DW to Suppression Chamber Vacuum Breaker Operability Test.

Then, the A Recirc Pump will experience high vibrations requiring action to trip the pump. The crew takes actions IAW the ARP and maintains RPV level following the transient The SRO makes preparations to perform STP 3.4.1-02, Single Loop Operability, and addresses Technical Specifications (TS 3.4.1 Condition D)

A spurious start of HPCI will occur and require the BOP to trip the pump. The SRO will address Technical Specifications (TS 3.5.1 Condition F). Once the HPCI issue is addressed, the crew will be informed by reactor engineering that a power reduction is required due to previous two events. The RO will insert control rods per the pull sheet.

Then, a small Steam Leak inside Primary Containment will occur, requiring the crew to vent the drywell per OI-573. A loss of the 125 VDC panel 1D11 then occurs. This leads to an RPV level transient. The crew responds to the FWLC failure and places control circuitry to Level A. The SRO declares the Div 1 125 VDC distribution subsystem inoperable and addresses Technical Specifications (TS 3.8.7 Condition B).

The B Recirc pump experiences vibration issues and will trip (if not tripped by the operators) and the reactor will be scrammed. The control rods will not insert due to hydraulic ATWS. EOP 1 will be entered due to scram required with power above 5% or unknown. The operators take actions to maintain RPV level and stabilize RPV pressure during an ATWS and ATWS Power/Level control will be entered. The crew will be required to terminate and prevent injection (CRITICAL TASK). Repeated manual scram will insert all control rods (CRITICAL TASK). Additionally, a small leak in the drywell will develop and the RHR pumps will fail to auto start. The crew will enter EOP 2 and control the containment parameters by spraying the Torus and DW (CRITICAL TASK - to spray DW).

The scenario may be terminated when the reactor is shutdown, containment parameters are improving and RPV level is restored to the normal band.

NUREG-1021, Revision 9, Supplement 1

p EXAMINATION SCENARIO GUIDE (ESG)

SITE: DAEC TORUS TO DW VACUUM BRKR TEST / A RECIRC PUMP HI VIBRATION / HPCI SPURIOUS START /

POWER REDUCTION / 125 VDC PANEL 1D11 TRIP /

ESG NRC 09-02 REV. 0 VENT THE DRYWELL / B RECIRC PUMP TRIP /

HYDRAULIC ATWS / SMALL LOCA / RHR PUMPS FAIL TO AUTO START PROGRAM: OPERATIONS #:

COURSE: INITIAL LICENSED OPERATOR #: 50007 TOTAL TIME: 90 MINUTES Developed by:

Instructor Date Validated by:

SME/Instructor Date Reviewed by:

Operations Manager Date Approved by:

Training Supervisor-Operations Date Page 1 of 21

2009 NRC Scenario #2 ESG GUIDE REQUIREMENTS The goal of this scenario is to evaluate ILT students during the NRC Goal of Exam with 3 man crew.

Training:

There are no formal learning objectives Learning Objectives:

None Prerequisites:

Simulator Training Simulator Booth Instructor Resources: Phone Talker Simulator Floor Instructor None

References:

None Commitments:

Dynamic Simulator Evaluation Method:

None Operating Experience:

Initiating Event with Core Damage Frequency:

Related PRA N/A due to exam security Information:

Important Components:

N/A due to exam security Important Operator Actions with Task Number:

N/A due to exam security Page 2 of 21

2009 NRC Scenario #2 ESG SCENARIO

SUMMARY

The plant is at 70% power. The BOP will perform STP 3.6.1.7 DW to Suppression Chamber Vacuum Breaker Operability Test.

Then, the A Recirc Pump will experience high vibrations requiring action to trip the pump.

The crew takes actions IAW the ARP and maintains RPV level following the transient. The SRO makes preparations to perform STP 3.4.1-02, Single Loop Operability, and addresses Technical Specifications (TS 3.4.1 Condition D)

A spurious start of HPCI will occur and require the BOP to trip the pump. The SRO will address Technical Specifications (TS 3.5.1 Condition F). Once the HPCI issue is addressed, the crew will be informed by reactor engineering that a power reduction is required due to previous two events. The RO will insert control rods per the pull sheet.

Then, a small Steam Leak inside Primary Containment will occur, requiring the crew to vent the drywell per OI-573. A loss of the 125 VDC panel 1D11 then occurs. This leads to an RPV level transient. The crew responds to the FWLC failure and places control circuitry to Level A. The SRO declares the Div 1 125 VDC distribution subsystem inoperable and addresses Technical Specifications (TS 3.8.7 Condition B).

The B recirc pump experiences vibration issues and will trip (if not tripped by the operators) and the reactor will be scrammed. The control rods will not insert due to hydraulic ATWS.

EOP 1 will be entered due to scram required with power above 5% or unknown. The operators take actions to maintain RPV level and stabilize RPV pressure during an ATWS and ATWS Power/Level control will be entered. The crew will be required to terminate and prevent injection (CRITICAL TASK). Repeated manual scram will insert all control rods (CRITICAL TASK). Additionally, a small leak in the drywell will develop and the RHR pumps will fail to auto start. The crew will enter EOP 2 and control the containment parameters by spraying the Torus and DW (CRITICAL TASK - to spray DW).

The scenario may be terminated when the reactor is shutdown, containment parameters are improving and RPV level is restored to the normal band.

Page 3 of 21

2009 NRC Scenario #2 ESG SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

Start Sim View / Data Capture Program.

1.1 General Instructions

a. Restore the IC for ILT Scenario 2 (N-2) from the Thumb Drive that it is stored on.

This Thumb Drive also has the malfunction and override files on it.

a) Log onto one of the Computer Terminals using the logon from Lowell b) If the malfunction file is the exam file, go to c), otherwise:

(1) With a file manager, go to the \\greg\c$\opensim directory, and copy the Malfunc-New.dat file into that directory.

(2) Rename the Malfunc.dat file to Malfunc-OLD.dat (3) Rename the Malfunc-NEW.dat file to Malfunc.dat c) Make a copy of the exam scenario IC file and rename it as d_ic.000 d) Copy the IC file from the thumb drive to the \\greg\ryandev\ops\ic directory. This makes the exam IC number 000.

e) Reset to IC 000.

(1) Verify Malfunctions (2) Verify Overrides (3) Verify Remote functions (4) Verify event trigger definitions and accept all triggers

b. If the thumbdrive is not available, then reset to IC 23 and set the Malfunctions, Remotes, Overrides, and Triggers as per the tables below.

c. Verify load is less than 450 MWe, and MO-9147 and MO-9148 2nd Stage Reheat High Load valves are closed

d. Verify strip chart recorders are ON. If not perform 4.4.4 of OI 831.4 (PPC)

e. Set APRM Gains using remote function NM02

f. Verify Pull Sheet setup matches current step and rod position

g. Mark up control rod withdrawal sheets to Step 22 - RODS OUT

h. Provide signed on copy of STP 3.6.1.7 DW to Suppression Chamber Vacuum Breaker Operability Test

i. Have copies of STP 3.4.1-02 and STP 3.4.2-03 ready for RR trip event

j. Control panel setups, including valves/equipment to tag out: None

k. Markup AOP 903 for the Severe Thunderstorm Watch - all actions performed up to transitioning out of section.

l. Place SPMET1 on a computer terminal (IAW AOP 903).

Page 4 of 21

2009 NRC Scenario #2 ESG 1.2 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 27 Logic: PCPDWG .GE. 1.5 Deletes leak in DW to PREVENT press going Command: DMF MS02 up to >1.8. Sim booth can then control ms02 to control pressure for venting.

1.3 MALFUNCTIONS

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup RH01A RHR A Pump fail to auto-actuate TRUE TRUE Setup RH01B RHR B Pump fail to auto-actuate TRUE TRUE Setup RH01C RHR C Pump fail to auto-actuate TRUE TRUE Setup RH01D RHR DA Pump fail to auto-actuate TRUE TRUE Setup RP05F Hydraulic lock scram discharge TRUE TRUE volume As Dir RR35A Recirc Pump Vibes High - Pump A 10:00 5 50 100 As Dir RR05A Recirc pump shaft seizure - pump 10:00 5 FALSE TRUE A

As Dir HP01 Inadvertent HPCI initiation 1 FALSE TRUE As Dir ED13A 125 VDC distribution panel fault - 7 FALSE TRUE PNL 1D11 As Dir RR35B Recirc Pump Vibes High - Pump B 5:00 9 50 100 As Dir RR05B Recirc pump shaft seizure - pump 5:00 9 FALSE TRUE B

As Dir MS02 Steam leak inside the primary 5:00 3 0 0.4 containment (VI)

As Dir MS03A MSL rupture inside primary 10:00 11 0 10 containment - Stm line A As Dir EG05 Generator field breaker fails open 17 FALSE TRUE OVERRIDES:

Time Override No. Override Title Delay Ramp ET Initial Final Value Value SETUP RD HS-1830 DRV WTR Pressure CTRL VLV NORM NORM SETUP SL HS-2613 SBLC OFF OFF 1.5 REMOTE FUNCTIONS:

Time Remote Remote Title Delay Ramp ET Initial Final No. Value Value AS DIR RP02 ATWS TEST SWITCH HS-1863A 60 13 RUN TEST (RUN, TEST)

AS DIR RP03 ATWS TEST SWITCH HS-1864A 70 13 RUN TEST (RUN, TEST)

AS DIR FW10 CONDENSATE FILTER DEMIN E 15 100 0 EFF VLV CV-1719E AS DIR AN01 REMOTE FUNC FEEDBACK 30 15 NORM ACK AN01-ACK SWITCH 1C80 Page 5 of 21

2009 NRC Scenario #2 ESG FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments 2.2 Simulator Training changes since last module (N/A) 2.3 Simulator hardware and software modifications/problems that may impact training Page 6 of 21

2009 NRC Scenario #2 ESG TURNOVER INFORMATION Day of week and shift Today Day Shift Weather conditions Hot, Humid A Severe Thunderstorm Watch is in effect for the next 31/2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />. AOP 903 Actions are completed.

(Plant power levels) Approx. 70%

MWT ~1390 MWE ~450 CORE FLOW ~45 Mlbm/hr Thermal Limit Problems/Power Evolutions Plant Risk Status CDF Baseline Color Green Existing LCOs, date of next surveillance STPs in progress or major maintenance None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment None Comments, evolutions, problems, core damage frequency, etc.

The plant is at about 70% power for a rod sequence exchange, which will be performed per RE guidance.

First perform STP 3.6.1.7 DW to Suppression Chamber Vacuum Breaker operability test Page 7 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover COMPLETE TURNOVER: Get familiar with plant conditions.

• Provide Shift Turnovers to the SRO

• SRO will provide beginning of shift brief to coordinate the tasks that and ROs.

were identified on the shift turnover.

a. Review applicable current Plant Status

b. Review relevant At-Power Risk status

c. Review current LCOs not met and Action Requirements

d. Verify crew performs walk down of control boards and reviews turnover checklists EXAMINER NOTE: Continue to next event at examiners direction page 8 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Booth Instructor respond as plant SRO Perform STP personnel and respond as necessary: Directs BOP to perform 3.6.1.7 DW to Suppression Chamber Vacuum 3.6.1.7 Breaker operability test DW to RO Suppression Chamber Monitors Reactor power, pressure and level vacuum BOP Breaker operability test Performs STP 3.6.1.7-01 as follows (for each vacuum breaker):

Examiner Note: The steps are the same for each vacuum breaker CV-4327A thru

• Cycle CV-4327A open and closed by depressing and releasing TEST G (no E vacuum breaker) pushbutton INTERNAL VACUUM BREAKER CV-4327A, and perform confirmations as required below:

• Confirm the upper CLOSED light deenergizes as the valve opens and energizes when the valve closes.

Role Play: When asked, state that another operator will perform the post surveillance test checklist

• Confirm the lower CLOSED light deenergizes as the valve opens and energizes when the valve closes.

• Confirm the OPEN light energizes as the valve opens and Role Play: When asked to check Drywell deenergizes as the valve closes N2 Makeup system accumulator pressure, acknowledge request and report back after 5 minutes that pressure is 100 psig.

• Verifies all valves indicate closed

• Contacts field operator to check PI-4372 and record Drywell N2 Makeup system accumulator pressure.

Notifies SRO that the test is completed EXAMINER NOTE: Continue to next event at examiners direction page 9 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Booth Instructor: respond as plant CREW personnel and respond as necessary A Recirc Hi Responds to indications of A Recirc Pump trouble Vibes - Pump Ann: 1C04A (B-4) - A Recirc Pump Motor High Vibration trips INSERT TRIGGER 5 - IMF RR35A Ann: 1C80 (C-1) - Filter demin 1T-13E Low Flow This starts the A Recirc Pump High SRO Vibration & Shaft Seizure event Directs response IAW the ARP Enters AOP 264 Loss of Recirc Pumps Enters AOP 255.2 Power/Reactivity Abnormal change Complies with Technical Specification 3.4.1 Condition D. requirements for ROLE PLAY: If asked about filter demin Recirculation Loops Operating. (24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> to complete single loop operation alarm - tell the operator that a low flow surveillances) exists on E demin, its in HOLD and I will acknowledge the 1C80 alarm. Use remote Directs preparations for STP 3.4.1-02, Single Loop Operation functions to comply crew directions on Contacts Duty Manager condensate demins and alarm status.

RO IAW the ARP

• Checks computer points B079 (temperature) and B551

• Dispatches a field operator to local panel 1C466C to check vibration indication IAW ARP direction When a vibration level of >19 mils is confirmed Role Play: When asked as field operator to check out problem with A recirc pump.

• Reduce the speed of both Recirc M-G sets to maintain vibration <19 mils.

Report back after 2 minutes that a DANGER vibration alarm is lit and the

• If unable to reduce vibration to < 19 mils, reduce the A Recirc speed reading is 20 mils. to minimum.

• Trip the A RECIRC MG SET MOTOR BREAKER 1A104 (HS at 1C04) page 10 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 (cont) RO (cont)

ROLE PLAY: If asked following the pump For the Recirc Pump that tripped, perform the following:

trip, Fan 1V-SF-12 is RUNNING with the hand switch in AUTO

• Verify open A[B] RECIRC PUMP DISCH BYP valve MO-4629

• Close MO-4627 ROLE PLAY: If the crew allows the pump

• After 5 minutes, reopens A RECIRC PUMP DISCHARGE valve to trip, when asked about relays state that MO-4627 the drive motor overload has picked up.

Controls reactor level and maintains in the Green Band (186 to 195)

IAW AOP 255.2, Places one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal.

BOP IAW the ARP

• Checks computer points B079 (temperature) and B551

• Dispatches a field operator to local panel 1C466C to check vibration and temperature indication IAW ARP direction Monitors BOP equipment EXAMINER NOTE: Continue to next event at examiners direction page 11 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 Booth Instructor: CREW HPCI spurious When directed by examiner: Recognizes spurious start of HPCI start.

INSERT EVENT TRIGGER 1 SRO This starts HPCI inadvertent start. Directs tripping HPCI after verifying that HPCI operation is no longer required by assuring that by 2 independent indications adequate core cooling is assured (OI 152, Section 7.3)

Role Play:

Enters AOP 255.2 Power/Reactivity Abnormal Change When contacted about the HPCI injection, Contacts Reactor Engineering, Duty Manager report as the RE that you will investigate the issue. Enters TS 3.5.1.F.1 and 2. - verify RCIC is operable and enter 14 day LCO to return HPCI to operability Conducts Crew Brief once conditions are stable NOTE: Because HPCI is secured with an initiation signal sealed in 1C03C, D-11 BOP may alarm on HPCI Vacuum Tank Hi Lvl.

Refers to OI 152 QRC 2 to trip HPCI:

• Depresses and hold HS-2259, Remote Turbine trip PB Role Play: When called as field operator,

• Verify HV 2201, HPCI Turbine Stop Valve, closes inform the crew that you will check out the Level 2 switches suspected of causing the

• When HPCI speed is zero rpm, place 1P-218, Aux Oil Pump, in Pull-HPCI spurious start. After two minutes, To-Lock report that the level switches all indicate

• Verify HV-2200, HPCI Turbine Control Valve , closes normally but the E41A-K6 and K7

• Verify annunciator 1C03C (A6) is activated.

(initiation relays) have actuated.

• Release HS-2259, HPCI Remote Turbine trip PB RO Role Play: When called as Duty Continues to monitor reactor power, pressure and level Manager, inform the crew that you will get a team to investigate the issue. May need to control level adjusting level setpoint EXAMINER NOTE: Continue to next event at examiners direction page 12 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 ROLE PLAY: Call in to the control room SRO as the reactor engineer and state that a Power Provides a reactivity brief 10% power change is required due to the Reduction with previous two events. Communicates with Real Time Desk.

control rods Youve been monitoring the core and the Provide direct oversight of power decrease.

margin to thermal limits is now very slim.

In order to avoid TS actions, it is now required to reduce power by 10% using a RO reverse sequence in the pull sheet. DO Lowers power as directed by SRO using RE guidance - reverse pull sheet NOT change recirc flow sequence Monitors critical plant parameters - power, pressure, level NOTE: The request may need to be emphasized if the crew has an extended reactivity brief BOP Monitors balance of plant equipment.

Provides peer check for RO during power increase.

EXAMINER NOTE: Continue to next event at examiners direction page 13 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 Booth Instructor: respond as plant Crew Steam leak in personnel and respond as necessary: Recognizes Drywell pressure is increasing.

primary containment When directed by examiner: SRO requires venting the drywell INSERT EVENT TRIGGER 3

• Enters AOP-573 and direct crew actions to vent the primary containment This inserts a small steam leak into the to maintain 1 to 1.5 psig.

DW.

• Contacts the Duty Manager.

Verify that Event Trigger 27 (DMF MS02)

NOTE: goes true when DW/P reaches 1.5 psig. BOP

• Starts SBGT per the QRC (OR OI 170)

IMMEDIATE ACTIONS Start SBGT Train A[B] using one of the following methods:

Role Play: Acknowledge request by If using the test pushbuttons, depress PB-5831A[B], SBGT Train A[B]

control room to check areas for leaks due Test Pushbutton.

If initiating a secondary containment isolation, proceed as follows:

to control room annunciator 1C-35A C4 Momentarily depress PB-7606A[B] A[B] Group 3 Initiation pushbutton.

DW/TORUS 1C-219A GAS/PART/IODINE Verify Lockout Relay L/R-5830A[B] is TRIPPED.

HI RAD OR DNSCL Verify AV-5801A[B], Cooldown/ Outside Air Valve, is CLOSED.

After 5 minutes, report back that you have Verify AV-5825A[B], Intake Valve, is OPEN.

observed no apparent reason for the alarm Confirm EC-5805A[B], Constant Heater, is ON when >2400 scfm.

Confirm TDIC-5805A[B], Variable Heater T Controller, is controlling at approximately 16°T.

Verify AV-5815A[B], Fan Inlet Valve, is OPEN.

BOOTH INSRUCTOR: Verify 1V-EF-15A[B], Exhaust Fan, is RUNNING.

Re-Insert MS02 @ 0.1 if pressure is Verify AV-5817A[B], Discharge Valve, is OPEN.

lowering before venting. May change in Position switches at 1C03 as follows:

0.1 increments if necessary.

Switch Description Position When venting starts, HS-4303 Outbd Drywell Vent Isol CV-4303 Auto Open Re-insert MS02 @ 0.1 HS-4310 Inbd DW Vent Bypass Isol CV-4310 Auto Open NOTE: May open CV-4302 to augment the venting EXAMINER NOTE: Continue to next event at examiners direction page 14 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Booth Instructor: respond as plant CREW personnel and respond as necessary:

125VDC Div1 Responds to Numerous Annunciators including 1C08A D-9 A DG Control Panel 1D11 Power Failure trips When directed by examiner: SRO INSERT EVENT TRIGGER 7 Enters AOP 302.1-Loss of 125 VDC Power, Tab 1-Loss of 125vdc Div 1.

This inserts a fault to trip 1D11 May direct, as time permits, the RO to transfer to A level control to control reactor level and try to maintain normal band.

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

BOOTH INSTRUCTOR:

Directs transferring non-essential power to the startup transformer.

If level increases to a scram, then set Event Trigger 9 to TRUE and move to next RO event.

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

NOTE: If the RO does not place the level Place the A level controller in service with handswitch controller to A a scram will occur.

BOP Monitors BOP Equipment Transfers non-essential power to the startup transformer per OI 304.1, ROLE PLAY: If asked as field operator to section 4.2. as follows.

investigate issue, report after 2 minutes

• Place the BUS 1A2 TRANSFER breaker mode selector switch in the that 1D10 CKT 6 has tripped free and MANUAL position.

there is no sign of smoke or fire at the breaker.

• 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 meter switch.

• Place the control switch 4KV BREAKER 1A202 STARTUP XFMR TO BUS 1A2 momentarily in the CLOSE position. Observe that the red (breaker closed) and the white (closing spring charged) indicating lights are ON EXAMINER NOTE: Continue to next event at examiners direction page 15 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #7 & #8 Booth Instructor: CREW B Recirc HI When directed by examiner: Responds to B Recirc Pump Hi vibrations Vibration, Pump INSERT EVENT TRIGGER 9 ANN: 1C04B (B-1) B Recirc Pump Motor High Vibration Trip, Reactor This inserts a high vibrations on B Recirc SRO

Scram, pump Hydraulic

• Directs ARP actions to address B Recirc Pump Hi Vibration ATWS, Small LOCA, All RHR

• When B Recirc Pump has tripped, recognizes operating in natural NOTE: If the plant scrams on level, from circulation and directs Reactor Scram pumps fail to previous event, the actions listed for the start on LO-LO-recirc pump vibrations do not apply

• Enters EOP 1 then transitions to EOP ATWS when informed not all rods LO level signal in

• Directs Lockout of ADS

• Directs Defeat 15 - allows MSIVs to remain open on lo-lo-lo level

• Directs Initiation of ARI Role Play: After request to install Defeat 12, wait approximately 2 minutes and

• Directs Condensate and Feed injection be terminated and inform control room that it is installed. prevented & Verifies that HPCI is Locked Out (from previous Use Trigger 13 event) (CRITICAL TASK #1)

• Directs Defeat 12 - allows scram/reset/scram actions to insert control rods by resetting the ARI solenoids

• Directs Start of Standby Liquid Control

• Direct installation of Defeat 11

• Directs a level band per ATWS EOP NOTE: SBLC will fail to start and inject

• Directs performance of Hydraulic ATWS RIPs (CRITICAL TASK #2 - this must be directed to enable the RO to insert rods)

• When turbine trips, directs sending field operator to open field breaker (will not trip due to 125 VDC issue) page 16 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RO IAW the ARP for Recirc Pump High Vibration

• Checks computer points B079 (temperature) and B551

• Dispatches a field operator to local panel 1C466C to check vibration indication IAW ARP direction When a vibration level of >19 mils is confirmed

• Reduce the speed of both Recirc M-G sets to maintain vibration <19 mils.

• If unable to reduce vibration to < 19 mils, reduce the A Recirc speed to minimum.

• Trips the A RECIRC MG SET MOTOR BREAKER 1A104.

• Recognizes that a reactor scram is required due to no recirc pumps running

• As directed, inserts manual scram with PBs

• Places mode switch in shutdown

• Recognizes not all rods are in and informs SRO of Hydraulic ATWS

• Initiates ARI

• Takes actions to insert control rods

• Starts Standby Liquid Control

• Terminates and prevents Feedwater and Condensate injection by placing FRV controllers to manual and dialed down.

(CRITICAL TASK #1)

• Takes actions to insert control rods page 17 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP BOOTH INSTRUCTOR:

• Locks out ADS After the first scram for hydraulic RIPs:

• If asked, verifies HPCI is locked out INSERT EVENT TRIGGER 11

• Install Defeat 15 This inserts a small steam leak in the

• Installs Defeat 12 containment.

• Installs Defeat 11

• Performs Hydraulic ATWS RIPs (CRITICAL TASK #2 - Must be performed to enable RO to insert control rods)

Examiner Note: The drywell leak will CREW increase creating containment issues.

Recognizes rising drywell pressure/temperature These steps address the crew response actions Recognizes failure of RHR pumps to auto start on RPV Lo-Lo-Lo Level SRO Enters EOP 2 on high drywell pressure OR High Torus Level When informed that all rods are full in, Exits EOP ATWS Re-enters EOP-1, then directs RPV level band of 170 to 211 Directs Torus Spray when Containment Pressure is >2.0 psig Directs Drywell Spray when Torus Pressure is > 11.0 psig OR before Drywell temperature reaches 280 degrees (CRITICAL TASK #3)

Booth Instructor:

RO When the crew resets RPS for the third scram attempt (for the scram-reset-scram Performs scram-reset-scram to insert control rods RIP), THEN DMF RP05F. This will allow the rods to insert when the third scram is Informs SRO when all rods are in (CRITICAL TASK #2) put in.

page 18 of 21

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP

• Starts all RHR pump which had failed to auto start on Lo-Lo-Lo RPV level

• Sprays the torus when directed

• Places Containment Spray Enable Switch HS-2001C[1903C] in the MAN position

• Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve Handswitch in OPEN and verify MO-2005[MO-1932] opening.

• Throttles open MO-2006[MO-1933], Torus spray Valve.

• Sprays the Drywell when directed (CRITICAL TASK #3)

• Opens MO-2000[MO-1902], Inboard Drywell Spray Valve.

• Throttles open MO-2001[MO-1903], Outboard Drywell Spray Scenario Termination Criteria All Control Rods inserted, DW spray in service, RPV level restored to 170 - 211 Event Classification SS2.1 - SAE - auto scram failure

• • • END OF SCENARIO ***

page 19 of 21

SEG Validation Checklist 2009 NRC Exam Scenario #2 THIS SECTION IS ONLY REQUIRED FOR EVALUATED SCENARIOS.

Correct IC or plant status identified.

Shift turnover forms filled out (both CRS/OSM and NSOE) if required.

Additional documents are prepared (STPs, Work Orders, LCO Paperwork).

Tasks and Objectives have been verified to be correct.

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

SOMS tags identified and included in setup instructions.

Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.

Setup files correctly called out.

Malfunction list is accurate.

Override list is accurate.

Remote function list is accurate.

Event triggers are accurate.

Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.

Instructor Activity section is accurate and complete:

Actions are clearly defined for Booth or Floor instructor.

Role-playing is clearly noted.

The sequence of events is completely and concisely narrated even if it takes no instructor action.

Automatic actions that require verification are noted.

Reasonable alternate paths are considered and included.

Event trigger activation is distinguished from narrative text (Bold font)

Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.

Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.

Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.

2009 DAEC NRC Scenario 2 Script Rev 7-17-09cah.docPage 20 of 21

SEG Validation Checklist 2009 NRC Exam Scenario #2 Expected Student Response Section is accurate and complete:

Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)

Tasks are clearly noted and properly numbered as appropriate.

Knowledge objectives are clearly noted and properly numbered as appropriate.

Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)

Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)

Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.

Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.

Actions are listed using a logical order; by position and chronology. (N/A as appropriate)

Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.

Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)

For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.

Turnover information (as required) is correct:

Day and shift are appropriate.

Weather conditions do not conflict with malfunctions.

Power levels are correct.

Thermal limit problems and power evolutions are realistic and include a reason for any downpower.

Existing LCOs include start date, remaining time and actions.

Plant Risk Assessment (CDF and Color).

STPs are appropriate for day and shift.

Core Damage Frequency has been properly calculated and listed to 3 decimal places.

Maintenance is realistic for plant conditions.

Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.

SME/Instructor Date SME/Instructor Date 2009 DAEC NRC Scenario 2 Script Rev 7-17-09cah.docPage 21 of 21

SEG Validation Checklist 2009 NRC Exam Scenario #2 Crew: Instructors:

OSM ____________________________ Booth ________________________________

CRS ____________________________ Floor __________________________

STA __________________________________ Extra ________________________________

1C05 ____________________________

1C03 ____________________________

BOP ____________________________

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

SEG Validation Checklist 2009 NRC Exam Scenario #2 Crew Comment:

Resolution:

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 3 Facility: DAEC Scenario No.: 3 Op Test No.: 2009-01 Examiners: Operators:

Initial Conditions:

• Startup in progress, reactor power is about 4%

• D IRM is bypassed

• RWM is bypassed Turnover:

• Continue the startup IAW IPOI 2 until one bypass valve is at least 40%

open

• Perform RCIC System STP 3.5.3 Post Startup Operability Test

• The test is complete through Step 7.1.5

• The walkdown inspection criteria of NS500002 has been completed for the current cycle.

• D IRM is bypassed due to welding in the vicinity of the D IRM preamp

• RWM is inoperable, TS 3.3.2.1 Condition C was entered and Required Actions C.2.1.1 and C.2.2 are met. STP 3.3.2.1-04 is being performed by a qualified STA.

Critical Tasks: 1. Manually scram the reactor due to lowering Torus level IAW EOP 2

2. ED due to low Torus level and ensure 4 SRVs are open Event Malf. No. Event Event No. Type* Description R - RO 1 NA R - SRO Continue startup

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9, Supplement 1

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 3 Event Malf. No. Event Event No. Type* Description C - RO 2 RD03 C - SRO A Control Rod in step 23 will uncouple and over-travel out.

TS - SRO The RO successfully recouples the rod The SRO will address TS 3.1.3 Condition C - until recoupled N - BOP 3 NA N - SRO Perform RCIC System STP 3.5.3 Post Startup Operability Test C - BOP 4 MS29B C - SRO RCIC isolation signal. Fails to auto isolate.

TS - SRO The SRO will address TS 3.6.1.3 Condition A - PCIS and TS 3.5.3 Condition A - RCIC I - RO 5 NM04B I - SRO B IRM fails upscale. The RO will be required to contact TS - SRO I & C, unbypass D IRM, bypass B IRM and reset the half scram.

The SRO will address TS 3.3.1.1 Condition A for 2 IRMs Inop until only 1 is bypassed C - ALL 6 ED08A TS - SRO Bus 1A1 lockout trip TS 3.4.1 Condition D M - ALL 7 PC14 An unisolable Torus Leak develops Field operators to check areas for the leak, and may fill torus with Core Spray and/or HPCI C - BOP 8 AD HS- C - SRO One SRV fails to open during the ED. The BOP must open 4405 a LLS SRV to meet ED criteria

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9, Supplement 1

Scenario Outline ES-D-1 DAEC 2009 NRC Scenario 3 DAEC 2009 NRC Scenario #3 A reactor startup is in progress with power at about 4%. The crew will continue the startup. Then, a control rod overtravel will occur when it is withdrawn to 48. The RO successfully recouples the rod IAW the AOP. The startup continues and when one bypass valve is open >40% the crew perform RCIC System STP 3.5.3 Post Startup Operability Test.

Following the completion of the test indications of a RCIC Steam Line break will occur and RCIC will fail to auto isolate as required. The BOP must isolate RCIC. The SRO will address TS. The startup will then continue.

While moving control rods B IRM fails upscale resulting in a half scram. The SRO will contact maintenance to determine status of work in the area of the D IRM and when informed of work completion will unbypass the D IRM. Once that occurs, the RO will bypass B IRM and reset the half scram. The SRO will address TS 3.8.1.1 Condition A for 2 IRMs Inop until only 1 IRM remains bypassed.

After the IRM TS are addressed, a lockout trip will occur on the 1A1 4KV Bus. The crew will take remedial actions IAW the AOP.

The Torus will then develop an unisolable leak. As torus level lowers the crew will attempt to make up torus level but will be unsuccessful and a manual scram will be required (CRITICAL TASK). An Emergency Depressurization will then be required and one ADS SRV will fail to open requiring an LLS SRV to be opened (CRITICAL TASK).

The scenario may be terminated after the ED is performed and RPV level is returning to the normal band.

NUREG-1021, Revision 9, Supplement 1

EXAMINATION SCENARIO GUIDE (ESG)

SITE: DAEC CONTINUE STARUP FROM 4% POWER, CONTROL ROD OVERTRAVEL, RCIC SYSTEM STP, RCIC ISOLATION FAILURE, IRM UPSCALE TRIP, BUS 1A1 ESG ILT 09-03 REV 0 LOCKOUT TRIP, TORUS LEAK, MANUAL SCRAM, ED, ONE ADS SRV FAILS PROGRAM: OPERATIONS #:

COURSE: INITIAL LICENSED OPERATOR #: 50007 TOTAL TIME: 90 MINUTES Developed by:

Instructor Date Validated by:

SME/Instructor Date Reviewed by:

Operations Manager Date Approved by:

Training Supervisor-Operations Date Page 1 of 24

2009 NRC Scenario #3 ESG GUIDE REQUIREMENTS Goal of The goal of this scenario is to evaluate ILT students during the NRC Training: Exam with 3 man crew.

Learning There are no formal learning objectives Objectives:

Prerequisites: None Simulator Training Simulator Booth Instructor Resources: Phone Talker Simulator Floor Instructor

References:

IPOI 2, Startup, Rev 111 Commitments: None Evaluation Dynamic Simulator Method:

Operating None Experience:

Initiating Event with Core Damage Frequency:

Related PRA N/A due to exam security Information:

Important Components:

N/A due to exam security Important Operator Actions with Task Number:

N/A due to exam security Page 2 of 24

2009 NRC Scenario #3 ESG SCENARIO

SUMMARY

A reactor startup is in progress with power at about 4%. The crew will continue the startup.

Then, a control rod overtravel will occur when it is withdrawn to 48. The RO successfully recouples the rod IAW the AOP. The startup continues and when one bypass valve is open

>40% the crew perform RCIC System STP 3.5.3 Post Startup Operability Test.

Following the completion of the test, indications of a RCIC Steam Line break will occur and RCIC will fail to auto isolate as required. The BOP must isolate RCIC. The SRO will address Technical Specifications. The startup will then continue.

While moving control rods B IRM fails upscale resulting in a half scram. The SRO will contact maintenance to determine status of work in the area of the D IRM and when informed of work completion will un-bypass the D IRM. Once that occurs, the RO will bypass B IRM and reset the half scram. The SRO will address TS 3.8.1.1 Condition A for 2 IRMs INOP until only 1 IRM remains bypassed.

After the IRM Technical Specifications are addressed, a lockout trip will occur on the 1A1 4KV Bus. The crew will take remedial actions IAW the AOP.

The Torus will then develop an unisolable leak. As torus level lowers the crew will attempt to make up torus level but will be unsuccessful and a manual scram will be required (CRITICAL TASK). An Emergency Depressurization will then be required and one ADS SRV will fail to open requiring an LLS SRV to be opened (CRITICAL TASK).

The scenario may be terminated after the ED is performed and RPV level is returning to the normal band.

Page 3 of 24

2009 NRC Scenario #3 ESG SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

Start Sim View / Data Capture Program.

1.1 General Instructions

a. Restore the IC for ILT Scenario 3 (N-3) from the Thumb Drive that it is stored on.

This Thumb Drive also has the malfunction and override files on it.

a) Log onto one of the Computer Terminals using the logon from Lowell b) If the malfunction file is the exam file, go to c), otherwise:

(1) With a file manager, go to the \\greg\c$\opensim directory, and copy the Malfunc-New.dat file into that directory.

(2) Rename the Malfunc.dat file to Malfunc-OLD.dat (3) Rename the Malfunc-NEW.dat file to Malfunc.dat c) Make a copy of the exam scenario IC file and rename it as d_ic.000 d) Copy the IC file from the thumb drive to the \\greg\ryandev\ops\ic directory. This makes the exam IC number 000.

e) Reset to IC 000.

(1) Verify Malfunctions (2) Verify Overrides (3) Verify Remote functions (4) Verify event trigger definitions and accept all triggers

b. If the thumbdrive is not available, then reset to IC 11 and set the Malfunctions and overrides as per the tables below.

c. Verify strip chart recorders are ON. If not perform 4.4.4 of OI 831.4 (PPC)

d. Ensure pressure set is set at greater than or equal to 940 (needed for STP)

e. Provide marked up copy of STP 3.5.3-06 ready to perform marked through step 7.1.5.

Also complete Section 7.1.26.

f. Verify Pull Sheet setup shows current step and rod position (Step 23 @ 46)

g. Provide marked up copy of IPOI 2 marked up TO Step 4.3(11)(b)

h. Place maintenance border for D IRM Bypass switch and place D IRM in bypass

i. Place RWM in bypass

j. Verify that the APRM recorders are on IRM range, and in slow speed.

k. Markup AOP 903 to have all actions done, waiting for the severe weather to either be upgraded or downgraded by the NWS.

l. Have SPMET1 on the far PPC terminal.

Page 4 of 24

2009 NRC Scenario #3 ESG 1.2 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 11 ZAOFWPI4564 .LE. 0.45 Indicated RPV pressure less than ~500 psig

1.3 MALFUNCTIONS

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup RD031803 Control Rod Uncoupled-Rod 18-03 TRUE TRUE Group 6 Isolation Valve(s) Fail(s)

Setup MS31A TRUE TRUE To Close - MO2400 Group 6 Isolation Valve(s) Fail(s)

Setup MS31B TRUE TRUE To Close - MO2401 RCIC Steam Supply Line Break As Dir RC06 1 0 100 (RCIC Room)

As Dir NM04B IRM Channel Fails-CHNL B 3 AS IS 100 As Dir ED08A 4.16kv/480V Bus Fault-Bus1A1 7 FALSE TRUE Primary Containment Torus As Dir PC14 600 9 0 100 Leakage As Dir TC02B B EHC Pump Trip 11 FALSE TRUE OVERRIDES:

Time Override No. Override Title Delay Ramp ET Initial Final Value Value SETUP AD HS-4405 ADS PSV4405,C MSL,1140 PSI AUTO AUTO (Auto, Open) 1.5 REMOTE FUNCTIONS:

Time Remote Remote Title Delay Ramp ET Initial Final No. Value Value CS01 A Core Spray CST Suction 180 20 0 20 Valve V-21-01 CS02 B Core Spray CST Suction 180 22 0 20 Valve V-21-02 Page 5 of 24

2009 NRC Scenario #3 ESG FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments 2.2 Simulator training changes since last module (N/A) 2.3 Simulator hardware and software modifications/problems that may impact training Page 6 of 24

2009 NRC Scenario #3 ESG TURNOVER INFORMATION Day of week and shift Today Day Shift Weather conditions Hot, Humid A Severe Thunderstorm Watch is in effect for the next 3 1/2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />. AOP actions are complete.

(Plant power levels) 4%

MWT 90.5 MWE 0 CORE FLOW 12.5 Thermal Limit Problems/Power Evolutions Plant Risk Status CDF Baseline Color Green Existing LCOs, date of next surveillance:

3.3.2.1 Condition C - Required Action C.2.1.1 is met AND Required Action C.2.2 is met by performing STP 3.3.2.1-04 3.5.1 Condition B - Required Action B.1, Day 1 of 7 STPs in progress or major maintenance RCIC System STP 3.5.3 Post Startup Operability Test - complete through step 7.1.5 RWM STP 3.3.2.1-04 Control Rod Movement Verification being performed by an additional STA.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment D IRM is bypassed due welding in the Reactor Building in the vicinity of the preamp.

WCC will inform you when the work is complete.

Comments, evolutions, problems, core damage frequency, etc.

The plant is operating at approximately 4% power An additional STA is performing STP 3.3.2.1-04 Control Rod Movement Verification Perform RCIC System STP 3.5.3 Post Startup Operability Test:

• The test is complete through step 7.1.5 and Step 7.1.26 is also complete and needs to be performed as soon as the bypass valve is opened greater than 40%

• The walkdown inspection criteria of NS 500002 has been completed for the current cycle

• An extra operator will perform the STP to monitor Torus temperature during the RCIC run and will notify the control room of any temperature issue.

Torus Cooling is in service to support the RCIC run; the risk evaluation for going to run with Torus Cooling in service is complete and approved.

IPOI 2 is in progress at step 4.3(11)(b)

Continue the startup Page 7 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover COMPLETE TURNOVER: Get familiar with plant conditions.

• Provide Shift Turnovers to the SRO

• SRO will provide beginning of shift brief to coordinate the tasks that and ROs.

were identified on the shift turnover.

a. Review applicable current Plant Status

b. Review relevant At-Power Risk status

c. Review current LCOs not met and Action Requirements

d. Verify crew performs walk down of control boards and reviews turnover checklists page 8 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Booth Instructor respond as plant SRO personnel and respond as necessary:

Continue the Directs Operators to increase power IAW IPOI and RE guidance startup RO Continues control rod withdrawal while monitoring critical plant parameters BOP Monitors balance of plant equipment/plant status EXAMINER NOTE: Continue to next event at examiners direction page 9 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Booth Instructor: respond as plant CREW personnel and respond as necessary: Responds to Annunciators 1C-05 D6- Rod Drift & D7 - Rod Overtravel Control Rod overtravel out SRO Directs response IAW the ARP Booth Instructor: When the operator Refers to TS 3.1.3.C - Technical Specifications for Control Rod Operability positions rod to 46, THEN DMF RD031803 require that an uncoupled Control Rod be fully inserted within 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> and disarmed within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />. If this cannot be accomplished, the Reactor shall be in Mode 3 in the following 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

Notifies RE & Duty Manager Role Play: As RE, request that the RO control room attempt to recouple rod Takes the following actions IAW the ARP:

If Rod is uncoupled, attempt to recouple the rod.

• Insert the associated CRD to Position 46 or as directed by the CRS and Reactor Engineer.

• Verify Rod Overtravel Out, 1C05A, D-7 alarm clears.

• Take the Rod Drift Alarm Reset/Test handswitch to Reset.

• Verify Rod Drift, 1C05A, D-6 alarm clears.

• Withdraw the associated CRD to Position 48.

• If the associated CRD remains coupled, give the associated CRD a withdraw signal and observe the CRD remains at position 48 and does not overtravel.

If the control rod recouples:

• Contact the Reactor Engineer.

• If in Mode 1 or 2, perform a coupling check and log the results.

Inform the CRS that the rod is re-coupled BOP Performs peer check of RO actions.

EXAMINER NOTE: Continue to next event at examiners direction page 10 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 Booth Instructor respond as plant SRO Perform RCIC personnel and respond as necessary: Directs continuation of RCIC System STP 3.5.3 Post Startup System STP Operability Test 3.5.3 Post Enters TS 3.5.3 Condition A @ STP step 5.1.18 Startup Operability Test RO NOTE: Provide copy of STP completed through step 7.1.5 Monitors critical parameters - reactor power, pressure, level Peer checker for BOP operator BOP Notifies HPs of RCIC run.

ROLE PLAY: As HP, inform control room you are standing by for RCIC run. Continues RCIC STP at procedure step 7.1.6 as follows:

7.1.6 Verify TEST MODE TURBINE SPEED ADJUST is fully counterclockwise.

7.1.7 Verify handswitch AC POWER TO TURBINE SPEED TEST CKT is in OFF.

7.1.8 Verify the AC POWER TO TURBINE SPEED TEST CKT light is off.

7.1.9 Verify handswitch TURBINE SPEED TEST SELECT is in NORMAL.

7.1.10 Verify FLOW CONTROL FIC-2509 is set at 415 gpm.

7.1.11 Verify MO-2512 RCIC INJECT valve is closed.

7.1.12 Verify MO-2511 PUMP DISCHARGE valve is open.

7.1.13 At 1C03, verify open REDUNDANT SHUTOFF MO-2316.

7.1.14 Open MO-2426 LUBE OIL COOLER SUPPLY valve.

7.1.15 Perform the following:

a. Place CV-2435 in the OPEN/AUTO-CL position and confirm valve indicates open.

page 11 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 - b. Start VACUUM PUMP 1P-227.

continued 7.1.16 Commence monitoring Torus water level and temperature by performing STP 3.6.2.1-01 (Suppression Pool Water Temperature Surveillance), Section 7.1.

EXAMINER NOTE: Operator may make page announcement to clear personnel from RCIC area and will inform CRS as required in next step that RCIC is now considered inoperable 7.1.17 Verify unnecessary/unauthorized personnel are clear of the RCIC Room (unless exempt per Step 2.1.9).

7.1.18 Performance of Step 7.1.19 makes the RCIC System inoperable.

Ensure Steps 7.1.19 through 7.1.32 are completed within the time allowed by Prerequisite6.2.1. Record the date and time below and inform the CRS of the start of the inoperability condition.

Date / Time: ___________ / ______________

CAUTION Operation of the RCIC turbine below 2000 rpm should be minimized to avoid cycling the turbine exhaust check valve and to assure adequate turbine lube oil pressure.

7.1.19 Open TEST BYPASS MO-2515 to 44-46% open as indicated on ZI-2515 RCIC TEST BYP MO-2515 POSITION.

a. Record RCIC Start Time: _______________________

7.1.20 Open MO-2404 using handswitch MO2404 TURBINE STEAM SUPPLY.

7.1.21 Adjust MO-2515 until the following parameters are established:

a. Pump flow is > 400 gpm as indicated on FI-2509 PUMP DISCHARGE FLOW page 12 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 - b. Pump discharge pressure is > 1105 psig continued 7.1.22 Confirm the following:

a. CV-2410, RCIC STEAM LINE DRAIN ISOL valve closes.

b. CV-2411, RCIC STEAM LINE DRAIN ISOL valve closes.

c. CV-2436, CLOSED RADWASTE DISCH ISOL valve closes.

BOOTH INSTRUCTOR: d. CV-2435, CLOSED RADWASTE DISCH ISOL valve closes.

When procedure step 7.1.23 is being e. TURBINE CONTROL VALVE HV-2406 is throttling.

performed and (BEFORE RCIC is 7.1.23 Record the following:

secured):

a. PUMP DISCHARGE PRESS PI-2506 ________ psig INSERT EVENT TRIGGER 1

b. PUMP DISCHARGE FLOW FI-2509 ______ gpm This starts the RCIC steam line leak.

c. RCIC TURBINE SPEED SI-2457 _________ rpm Goto the next event for details. d. RCIC TEST BYP MO-2515 POSITION ZI-2515 ______ %

e. TURBINE EXHAUST PRESS PI-2423 _______ psig

f. STEAM INLET PRESSURE PI-2403 ________ psig 7.1.24 Confirm RCIC flowrate from Step 7.1.23.b is 400 gpm.

7.1.25 Confirm reactor vessel pressure is greater than or equal to () 940 psig and less than or equal to () 1025 psig.

7.1.26 Refer to Performance Information steps of NS500002 for applicable walkdown inspection criteria. All steps of NS500002 are to be performed at this point unless NS500002 has been completed for the current cycle. If NS500002 has been completed for the current cycle, this step may be marked N/A. Components identified in NS500002 may be inspected in any sequence during the walkdown.

7.1.27 Close MO-2404 TURBINE STEAM SUPPLY valve.

7.1.28 Secure (monitoring Torus water level and temperature) from performing STP 3.6.2.1-01 (Suppression Pool Water Temperature Surveillance), Section 7.1.

page 13 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 -

continued 7.1.29 Immediately initiate performance of STP 3.6.2.1-01 (Section 7.2) IF Suppression pool average water temperature is greater than (>) 95°F but less than or equal to () 110°F when testing which adds heat to the suppression pool is completed. Otherwise, mark this step N/A.

7.1.30 Confirm that the following has occurred automatically:

a. CV-2410, RCIC STEAM LINE DRAIN ISOL valve opens.

b. CV-2411, CLOSED RADWASTE DISCH ISOL valve opens.

c. CV-2436, CLOSED RADWASTE DISCH ISOL valve opens.

7.1.31 Place CV-2435 in the AUTO position and verify the valve indicates closed.

7.1.32 Close TEST BYPASS MO-2515.

7.1.33 Perform the following:

a. Record the date and time below and inform the CRS of the return to service of the RCIC System.

Date / Time: ___________ / ______________

b. Determine the elapsed time since date and time was recorded in Step 7.1.18 and record elapsed time below:

Elapsed time: _________

c. Confirm that the elapsed time recorded in Step 7.1.33.b is less than or equal to the allowable time recorded in Prerequisite Error!

Reference source not found.. If the elapsed time is greater than the allowable time recorded in Prerequisite Error! Reference source not found., inform the CRS immediately.

d. Notify Health Physics that RCIC Turbine run is complete.

Role Play: Acknowledge as Health 7.1.34 At 1C03, close REDUNDANT SHUTOFF MO-2316.

Physics that the RCIC run is complete page 14 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 - 7.1.35 When RCIC turbine speed has decreased to zero, as indicated by continued SI-2457, perform the following:

a. Close MO-2426 LUBE OIL COOLER SUPPLY valve. (Verify handswitch in AUTO.)

b. Confirm MIN FLOW BYPASS MO-2510 indicates closed.

c. Record RCIC Stop Time: _____________

7.1.36 At 1C23, verify the following control switches are in AUTO:

a. RCIC ROOM CLG UNIT 1V-AC-15A

b. RCIC ROOM CLG UNIT 1V-AC-15B 7.1.37 Place the RHR and ESW Systems in the desired conditions as directed by the Control Room Supervisor.

7.1.38 At 1C04, align the RCIC System, with the exception of the Vacuum Pump, in the Standby Readiness Lineup per OI 150 or in a lineup as directed by the Control Room Supervisor.

7.1.39 Approximately 30 minutes after the RCIC turbine stop time recorded in Step 0.c, stop VACUUM PUMP 1P-227.

EXAMINER NOTE: 30 minute wait at RCIC STP step 7.1.39 is NOT required before continuing to next event.

page 15 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 Booth Instructor: respond as plant CREW personnel and respond as necessary:

RCIC isolation Responds to Annunciators:

signal. Fails to 1C04C A5 - RCIC MO-2405 TURBINE TRIP auto isolate. When Directed:

1C04C A7 - RCIC A LOGIC MAN/AUTO ISOL INITIATED INSERT TRIGGER 1 1C04C A8 - RCIC B LOGIC MAN/AUTO ISOL INITIATED This inserts a RCIC steam line break with a failure to isolate.

SRO Direct response IAW ARP Directs verification of isolation TS 3.6.1.3 Condition A - Isolate & Deactivate affected line within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Role Play:

TS 3.5.3 Condition A - RCIC Inop - restore in 14 days and verify HPCI When contacted as the Duty Manager, operable immediately ensure the crew will continue the startup while the organization evaluates the extent Contacts Duty Manager of the damage to RCIC.

RO Monitors critical plant parameters BOP Recognizes RCIC Trip Diagnoses failure of MO-2400 and MO-2401 to isolate and manually closes at least one valve EXAMINER NOTE: Continue to next event at examiners direction page 16 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 Booth Instructor: respond as plant CREW personnel and respond as necessary:

B IRM fails Responds to Annunciators:

upscale. When directed by the lead evaluator:

1C-05B B3 - IRM B, D, OR F UPSCALE TRIP OR INOP INSERT EVENT TRIGGER 3 1C-05B A2 - "B" RPS AUTO SCRAM This inserts the IRM B failure.

SRO Directs actions IAW the ARP Enters TS 3.3.1.1 Condition A for 2 IRMs Inop Role Play: When contacted regarding Contacts I&C to check status on IRM D welding status. Inform the control room that they just completed the work. Direct bypassing IRM B Direct reset of 1/2 scram Role Play: As necessary for other Exits TS once only 1 IRM is bypassed notifications. Contacts Duty Manager/Maintenance to determine welding status Directs un-bypassing IRM D RO Reviews ARP actions Unbypasses IRM D Bypasses IRM B Resets 1/2 Scram BOP Monitors BOP equipment Checks IRM back panel indication EXAMINER NOTE: Continue to next event at examiners direction page 17 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Booth Instructor: respond as plant CREW LOSS OF personnel and respond as necessary:

4160V BUS Responds to Annunciator 1A1 When directed by the lead evaluator:

1C08A A2 - BUS 1A1 LOCKOUT TRIP OR LOSS OF VOLTAGE INSERT EVENT TRIGGER 7 SRO This inserts the Bus 1A1 Lockout.

Directs actions IAW ARP Enters AOP 304.1 - Loss of Non essential Bus Role Play: When contacted by MCR to May Enter AOP 264 - Loss of Recirc Pump investigate 1A1 loss, Report back in 5 minutes that the bus has a lockout and Contacts Duty Manager BKR 1A102 has an overcurrent flag Refers to TS 3.4.1 Condition D - single loop surveillance within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> RO Monitors critical plant parameters Responds to the recirc Pump trip IAW AOP 264 For the Recirc Pump that tripped, performs the following:

• Verify open A[B] RECIRC PUMP DISCH BYP valve MO-4629[4630].

• Close A[B] RECIRC PUMP DISCHARGE valve MO-4627[4628].

• After 5 minutes, reopen A[B] RECIRC PUMP DISCHARGE valve MO-4627[4628] (unless the A[B] Pump has to be isolated).

BOP For LOSS of 1A1 ONLY, perform the following:

Crosstie 1B1 and 1B2 by performing the following:

• Momentarily place control switch FEEDER BREAKER 1B101 XFMR 1X11 to LC 1B1 to the TRIP position.

• Momentarily place control switch TIE BREAKER 1B107 LC 1B1/1B2 in the CLOSE position.

page 18 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP Crosstie 1B5 and 1B6 by performing the following:

• Momentarily place control switch FEEDER BREAKER 1B501 XFMR Booth Instructor: 1X51 to LC 1B5 to the TRIP position.

When the operator goes to the back panel

• Momentarily place control switch TIE BREAKER 1B505 LC 1B5/1B6 in to Start the Offgas Glycol Pump: the CLOSE position.

INSERT EVENT TRIGGER 9 Place BUS 1A1 TRANSFER switch in MANUAL.

This will initiate the Torus Leak. Verify Offgas Closed Cooling Water Pump 1P-105A[B] in service.

Details are in the next event. Start Offgas Glycol Pump 1P-243A[B].

EXAMINER NOTE: Continue to next event at examiners direction page 19 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 & 8 Booth Instructor: respond as plant CREW Unisolable personnel and respond as necessary:

Torus leak, Respond to annunciator 1C-03 D9 - Torus Hi/Lo water level SRV fails to Diagnoses Torus Low level open Role Play: When called by MCR to find SRO out were the leak is, respond in 5 minutes that from the catwalk youve seen water on Directs actions IAW the ARP (ARP refers to EOP) the floor of the west side of the Torus Enters EOP 2 - Primary Containment Control due to LOW Torus Level <10.1 room but cannot determine where its feet coming from. Youll continue to check May direct raising Torus level with Core Spray and/or HPCI Directs contacting field operator to check areas for leaks NW corner room is B -CS (V-21-2)

When it is determined that Torus level cannot be maintained >7.1 SE corner room is A - CS (V-21-1) feet, directs a manual scram and an EOP 1 entry (CRITICAL TASK #1)

Role Play: When contacted by CR to perform OI 151 - Fill Torus with Core Directs maintaining RPV level between 170 and 211 Spray, acknowledge request and report Directs a RPV pressure band to maintain back in 5 minutes that Core Spray is aligned to fill the Torus. Enters EOP 3 - Secondary Containment - due to Torus Area level > Max Normal Use triggers to insert REMOTES:

Determines that Torus level is continuing to lower and BEFORE

1. 20 = cs01 for A Core Spray Torus level drops to 7.1 feet, Directs Emergency

1. 22 = cs02 for B Core Spray Depressurization. Open 4 SRVs Booth Instructor: (CRITICAL TASK #2)

If Anticipate ED is directed, and RPV pressure drops to ~500 psig, Verify Event Trigger 11 goes active to trip B EHC pump page 20 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 & 8 RO (cont.) Monitors critical plant parameters As directed, Inserts manual scram (CRITICAL TASK #1)

Takes IPOI 5 Reactor Scram Actions

• Initiates a backup manual reactor scram.

• Place THE MODE SWITCH in the SHUTDOWN position.

• Verify all control rods fully inserted by one or both of the following means:

• Verifies the Refuel One Rod Select Permissive:

o Position THE MODE SWITCH to REFUEL.

o Turn Rod Select Power off and then on.

o Verify the white Refuel Select Permissive light is lit.

o Return THE MODE SWITCH to SHUTDOWN.

• On the FULL CORE DISPLAY, verify the green FULL IN light for each rod is on.

Maintains RPV level as directed BOP

• Contacts field operators to check for leaks

• Monitors reactor pressure and maintains in the band directed by the SRO

• If directed, attempts to makeup Torus level with HPCI IAW OI 152 Section 12.1 as follows:

• Verify the CST has at least 75,000 gallons of water available for use by the HPCI and RCIC Systems on demand. This corresponds to approximately 9.5 ft. with one CST or 5.2 ft. with two CSTs.

page 21 of 24

2009 NRC ILT Scenario #3 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 & 8 BOP (Cont)

(cont.)

• With HS-2318A in the OVERRIDE position, HPCI shall be considered inoperable and the requirements of Technical Specifications complied with.

• Position HS-2318A EMERGENCY TORUS FILL PERMISSIVE on 1C03 to OVERRIDE.

• Open MO-2318 MIN FLOW BYPASS valve with HS-2318 on 1C03.

• Observe Torus level, UR-4325 at 1C03.

• Observe CST Levels LI-5216A and LI-5217A on 1C06 while draining CSTs.

When Directed attempts to open 4 ADS SRVs to emergency depressurize and recognizes that only 3 opened. Then takes action to open an additional LLS SRV (CRITICAL TASK #2)

Informs SRO when 4 SRVs are open Scenario Termination Criteria The scenario may be terminated after the ED is performed and RPV level is returning to the normal band Event Classification HA1.6 or 1.8 ALERT

• • • END OF SCENARIO ***

page 22 of 24

SEG Validation Checklist SEG ________2009 NRC Exam Scenario #3________ Rev. _____0________

Correct IC or plant status identified.

Shift turnover forms filled out (both CRS/OSM and NSOE) if required.

Additional documents are prepared (STPs, Work Orders, LCO Paperwork).

Tasks and Objectives have been verified to be correct.

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

SOMS tags identified and included in setup instructions.

Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.

Setup files correctly called out.

Malfunction list is accurate.

Override list is accurate.

Remote function list is accurate.

Event triggers are accurate.

Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.

Instructor Activity section is accurate and complete:

Actions are clearly defined for Booth or Floor instructor.

Role-playing is clearly noted.

The sequence of events is completely and concisely narrated even if it takes no instructor action.

Automatic actions that require verification are noted.

Reasonable alternate paths are considered and included.

Event trigger activation is distinguished from narrative text (Bold font)

Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.

Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.

Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.

2009 DAEC NRC Scenario 3 Script Rev 7-17-09cah.docPage 23 of 24

SEG Validation Checklist SEG ________2009 NRC Exam Scenario #3________ Rev. _____0________

Expected Student Response Section is accurate and complete:

Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)

Tasks are clearly noted and properly numbered as appropriate.

Knowledge objectives are clearly noted and properly numbered as appropriate.

Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)

Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)

Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.

Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.

Actions are listed using a logical order; by position and chronology. (N/A as appropriate)

Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.

Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)

For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.

Turnover information (as required) is correct:

Day and shift are appropriate.

Weather conditions do not conflict with malfunctions.

Power levels are correct.

Thermal limit problems and power evolutions are realistic and include a reason for any downpower.

Existing LCOs include start date, remaining time and actions.

Plant Risk Assessment (CDF and Color).

STPs are appropriate for day and shift.

Core Damage Frequency has been properly calculated and listed to 3 decimal places.

Maintenance is realistic for plant conditions.

Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.

SME/Instructor Date SME/Instructor Date 2009 DAEC NRC Scenario 3 Script Rev 7-17-09cah.docPage 24 of 24

SEG Validation Checklist SEG ________2009 NRC Exam Scenario #3________ Rev. _____0________

Crew: Instructors:

OSM ____________________________ Booth ________________________________

CRS ____________________________ Floor __________________________

STA __________________________________ Extra ________________________________

1C05 ____________________________

1C03 ____________________________

BOP ____________________________

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

SEG Validation Checklist SEG ________2009 NRC Exam Scenario #3________ Rev. _____0________

Crew Comment:

Resolution:

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.