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DAEC 2009 Initial Exam Administered Simulator Scenarios
	ML100351207
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Site:	Duane Arnold
Issue date:	09/21/2009
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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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 26 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 hours. 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 Recirc

Communicates with Real Time Desk.

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.

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.

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:

INSERT TRIGGER 1 SRO This inserts MF RP02A, which will trip the

Enters AOP 358 Loss of RPS AC Power A RPS MG Set.

Sends operator to investigate the trip.

Refers to TS 3.3.8.2. Condition A - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to remove in service power supply (condition met with EPA tripped)

Role Play: When contacted by control

Enters TS 3.6.1.3 - 4 hr LCO for Primary Cont. Isolation Valves room to investigate, wait 2 minutes and NOTE: The affected valves are already in their required (closed) position report that: due to the loss off RPS. The action has been met.

Enters TRM 3.3.4 Condition A - for Reactor Water conductivity

The A RPS MG set is running. monitoring

A2 EPA has tripped free - no

Directs transferring RPS to alternate power supply lights, smells bad, no fire or smoke

Contacts Duty Manager

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

BOP ROLE PLAY: As in plant operator report that alternate RPS is aligned to 1B32 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 POWER TRANSFER switch to A-MG [B-MG] OR ALT position as NOTE: When operator moves toward required and verify selected position white light remains on.

restoring RWCU, go to next event page 14 of 14

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Event #3 (cont) BOP (cont)

Evaluator Note: Continue to next event

Perform OI 358 RPS Appendix 4, RPS POWER SUPPLY TRANSFER once RWCU restoration step is reached. HALF SCRAM RECOVERY CHECKLIST as follows.

At Panel 1C36, reset the fuel pool exhaust radiation monitor RIS-4131A[B].

At Panel 1C36, reset the carbon bed vault radiation monitor RM-4138.

Reenergize the RWCU isolation valve(s) as necessary and/or restart the RWCU System as necessary per OI 261 (Group 5).

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.

Turn the REACTOR SCRAM RESET switch C71A-S5 first to Group 1 and 4 [Group 2 and 3] then to Group 2 and 3 [Group 1 and 4] to reset the scram signal.

Verify the following:

The eight white SCRAM GROUP indicating lights are ON.

"A" RPS MANUAL SCRAM (1C05A, A-3) annunciator is reset.

"B" RPS MANUAL SCRAM (1C05B, A-3) annunciator is reset.

Annunciator 1C05A, E-4 is reset.

Annunciator 1C05B, E-4 is reset.

Momentarily press the PCIS DIV 1 RESET and DIV 2 RESET pushbutton switches A71B-S32 and A71B-S33 and verify the following annunciators are reset:

PCIS GROUP 1 ISOLATION INITIATED (1C05B, A-8)

PCIS GROUP 2 ISOLATION INITIATED (1C05B, B-8)

RO (cont)

PCIS GROUP "4" ISOLATION INITIATED (1C05B, D-8)

PCIS GROUP "5" ISOLATION INITIATED (1C05B, E-8) page 15 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 OI 255 - CRD Hydraulic System, Section 6.1 and starts the check the B CRD pump, report it is standby pump as follows:

running hotter than normal.

Notifies field operator to verify adequate oil level in standby CRD Pump Role Play: As field operator directed to 1P-209A.

go to the CRD pump, report that the A CRD Pump oil level is good and that the

Verify standby CRD Pump 1P-209A Discharge Isolation V-17-8 full A CRD Pump 1P-209A Discharge open.

Isolation V-17-8 is full open.

At 1C05, starts A CRD PUMP 1P-209A by momentarily placing hand switch HS-1807A on 1C05 in the START position.

Role Play: As field operator, if requested, report that the standby pump has started and is operating normally. Stops the B pump as follows NOTE: If directed to reset the CRD high

Stops B CRD PUMP 1P-209B by momentarily placing hand switch vibration alarm then HS-1807B on 1C05 in the STOP position.

INSERT EVENT TRIGGER 26

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

This will reset the B CRD vibe alarm.

NOTE: Crew may notify personnel to BOP insure the switchgear room is clear before

Monitors BOP equipment cycling the CRD Pump Breaker.

May make PA announcement for start of pump EXAMINER NOTE: Continue to next event at examiners direction page 16 of 16

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

A SBDG starts 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 SRO alarm:

May direct placing the A SBDG in PTL IAW the Alarm Response actions INSERT EVENT TRIGGER 19

May enter TS 3.7.3.A - 7 day LCO for ESW inoperable This acknowledges the local 1C93 alarm. NOTE: This is a very recent TS interpretation, this may not have been reviewed with the applicants

Directs shutting down SBDG IAW OI 324 Role Play: Report to control room as

Notifies Duty Manager security that a lightning strike was seen in

Enters TS 3.8.1.B. - 7 day the east side of the yard by the startup

Directs performance of TS surveillance 3.8.1-1 within one hour transformer BOP Role Play: Report as A SBDG and

Directs field operator to check on the running SBDG local alarm indicates starting air pressure low

Places A DIESEL GENERATOR 1G-21 CONTROL hand switch HS-3231A on 1C08 in the PTL position Role Play: Report as Aux Operator that OR no problems exist in the switchyard

Shuts down the SBDG as follows IAW OI 324:

Role Play: IF asked, report as chemistry

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

If requested, SBDG Operating Checklist

IAW ARP - May dispatch an operator to check the A ESW pump OI 324A9 (Attachment 9). operation RO Continues to monitor reactor power, pressure and level EXAMINER NOTE: Continue to next event at examiners direction page 17 of 17

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 A well house. Report back after 5

Directs monitoring of Drywell pressure & temperature minutes that nothing abnormal was

Notifies Duty Manager observed at the well house.

RO Role Play: When directed to check the breaker for the A Well, report back after

Monitors reactor power pressure and level 5 minutes that the breaker is tripped, but

Monitors Drywell pressure & temperature you have no indications why.

BOP Role Play: When contacted, acknowledge as Duty Manager the requests by the SRO Per AOP 408 immediate actions:

to check out the SBDG and Well Pump

Ensures ESW is running to provide cooling to the Control Building issues Chillers and to reduce demand on the Well Water System. (The ESW pump must correspond to the running Control Building Chiller(s))

Examiner Note: May use QRC to start ESW pumps

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

EXAMINER NOTE: Continue to next event at examiners direction page 18 of 18

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

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:

Verify TRIGGER 11 goes TRUE to trip

Verifies and reports all rods in RCIC when RCIC is started

Provides RPV level and pressure status

Reports RPV level dropped below 170 (EOP 1 entry)

Role Play:

When directed to reset the RCIC BOP mechanical overspeed device, wait 5 minutes and report that the overspeed

May report MSIV closure (Group I Isolation) device will NOT reset.

Diagnoses Startup Transformer lockout

Diagnoses that the B SBDG failed to start page 19 of 19

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Events

STARTS B SBDG and verifies it loads BUS 1A4

7 & #8 (Continued) * (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).

RO/BOP

Attempts to maintain RPV level in the band initially directed by SRO (170 to 211)

Attempts to place RCIC in service IAW the QRC but diagnoses that RCIC trips

Places HPCI in service to restore RPV level to the directed band NOTE: Next Page begins actions for Drywell leak and loss of high pressure feed page 20 of 19

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

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 21 of 21

2009 NRC ILT Scenario #1 SCENARIO TIMELINE Events BOP

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

When level is above TAF, throttles injection to control RPV level.

Scenario Termination Criteria The scenario may be terminated after the ED is performed and level is being controlled.

- - END OF SCENARIO ***

page 22 of 21

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.doc Page 23 of 23

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.doc Page 24 of 24

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

EXAMINATION SCENARIO GUIDE (ESG)

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

POWER REDUCTION / VENT THE DRYWELL / 125 VDC ESG NRC 09-02 REV. 0 PANEL 1D11 TRIP /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 20

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 20

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 20

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

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

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

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

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

Page 4 of 20

2009 NRC Scenario #2 ESG 1.2 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 27 Logic: PCPDWG .GE. 1.4 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 RH10A RHR A Pump fail to auto-actuate TRUE TRUE Setup RH10B RHR B Pump fail to auto-actuate TRUE TRUE Setup RH10C RHR C Pump fail to auto-actuate TRUE TRUE Setup RH10D RHR D 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 15:00 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 20

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 20

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 hours. 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 20

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 20

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 20

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 (occurs after pump trip)

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 ROLE PLAY: If asked about filter demin

Complies with Technical Specification 3.4.1 Condition D. requirements alarm - tell the operator that a low flow for Recirculation Loops Operating. (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to complete single loop exists on E demin, its in HOLD and I will operation surveillances) acknowledge the 1C80 alarm. Use remote

Directs preparations for STP 3.4.1-02, Single Loop Operation functions to comply crew directions on condensate demins and alarm status.

Contacts Duty Manager 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 on the

If unable to reduce vibration to < 19 mils, reduce the A Recirc speed IN-LINE monitor and the reading is 20 to minimum.

mils.

Trip the A RECIRC MG SET MOTOR BREAKER 1A104 (HS at 1C04) page 10 of 20

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

For the Recirc Pump that tripped, perform the following:

ROLE PLAY: If asked following the pump

Verify open A[B] RECIRC PUMP DISCH BYP valve MO-4629 trip, Fan 1V-SF-12 is RUNNING with the hand switch HS-6534B in AUTO

Close MO-4627

After 5 minutes, reopens A RECIRC PUMP DISCHARGE valve ROLE PLAY: If the crew allows the pump MO-4627 to trip, when asked about relays state that

Controls reactor level and maintains in the Green Band (186 to 195) the drive motor overload has picked up.

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 20

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 Role Play: required by assuring that by 2 independent indications adequate core cooling is assured (OI 152, Section 7.3)

When contacted about the HPCI injection, report as the RE that you will investigate

Enters AOP 255.2 Power/Reactivity Abnormal Change the issue.

Contacts Reactor Engineering, Duty Manager

Enters TS 3.5.1.F.1 and 2. - verify RCIC is operable and enter 14 day NOTE: Because HPCI is secured with an LCO to return HPCI to operability initiation signal sealed in 1C03C, D-11

Conducts Crew Brief once conditions are stable may alarm on HPCI Vacuum Tank Hi Lvl.

BOP

Refers to OI 152 QRC 2 to trip HPCI:

Role Play: When called as field operator, inform the crew that you will check out the

Depresses and hold HS-2259, Remote Turbine trip PB Level 2 switches suspected of causing the

Verify HV 2201, HPCI Turbine Stop Valve, closes HPCI spurious start. After two minutes,

When HPCI speed is zero rpm, place 1P-218, Aux Oil Pump, in Pull-report that the level switches all indicate To-Lock normally.

Verify HV-2200, HPCI Turbine Control Valve , closes NOTE: The E41A-K6 and K7 (initiation relays) have actuated (back panels).

Verify annunciator 1C03C (A6) is activated.

Release HS-2259, HPCI Remote Turbine trip PB RO Role Play: When called as Duty Manager, inform the crew that you will get

Continues to monitor reactor power, pressure and level 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 20

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 power reduction is required due to the Reduction with control rods previous two events.

Communicates with Real Time Desk.

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 inserting rods RO 2 steps using a reverse sequence in the pull sheet. DO NOT change recirc flow.

Lowers power as directed by SRO using RE guidance - reverse pull sheet sequence We will monitor the thermal limits and let you know if a further reduction is

Monitors critical plant parameters - power, pressure, level necessary BOP NOTE: The request may need to be

Monitors balance of plant equipment.

emphasized if the crew has an extended reactivity brief

Provides peer check for RO during power increase.

EXAMINER NOTE: Continue to next event at examiners direction page 13 of 20

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) 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 o If using the test pushbuttons, depress PB-5831A[B], SBGT Train control room to check areas for leaks due A[B] Test Pushbutton.

o 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.

BOOTH INSRUCTOR:

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

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 0.1 increments if necessary.

Position switches at 1C03 as follows:

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 20

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: Responds to Numerous Annunciators including 1C08A D-9 A DG Control 125VDC Div1 Panel 1D11 Power Failure trips SRO When directed by examiner:

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 RO Event Trigger 9 to TRUE and move to next event.

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

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

Monitors BOP Equipment

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

ROLE PLAY: If asked as field operator to

Place the BUS 1A2 TRANSFER breaker mode selector switch in the investigate issue, report after 2 minutes MANUAL position.

that 1D10 CKT 6 has tripped free and there is no sign of smoke or fire at the

Select Phase 1 with the BUS 1A2 STARTUP XFMR AMPERES breaker. 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 20

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #7 & #8 Booth Instructor: CREW Responds to B Recirc Pump Hi vibrations B Recirc HI When directed by examiner:

ANN: 1C04B (B-1) B Recirc Pump Motor High Vibration Vibration, Pump INSERT EVENT TRIGGER 9 Trip, Reactor SRO Scram, This inserts a high vibrations on B Recirc

Directs ARP actions to address B Recirc Pump Hi Vibration pump Hydraulic

Directs Reactor Scram prior to manually tripping B Recirc Pump due to ATWS, Small increasing B Recirc Pump Hi Vibration LOCA, All RHR Role Play: When asked as field operator

If B Recirc Pump has automatically tripped, recognizes operating in pumps fail to to check out problem with A recirc pump. natural circulation and directs Reactor Scram start on LO-LO-LO level signal Report back after 2 minutes that a

Enters EOP 1 then transitions to EOP ATWS when informed not all rods DANGER vibration alarm is lit on the are FULL In IN-LINE monitor and the reading is 20

Directs Lockout of ADS mils.

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

Directs Initiation of ARI NOTE: If the plant scrams on level, from

Directs Condensate and Feed injection be terminated and previous event, the actions listed for the prevented & Verifies that HPCI is Locked Out (from previous recirc pump vibrations do not apply event) (CRITICAL TASK #1)

Directs Defeat 12 - allows scram/reset/scram actions to insert control Role Play: After request to install Defeat rods by resetting the ARI solenoids 12, wait approximately 2 minutes and

Directs Start of Standby Liquid Control inform control room that it is installed. NOTE: SBLC will fail to inject Use Trigger 13

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 20

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.

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 NOTE: SBLC will fail to inject

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 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) page 17 of 20

2009 NRC ILT Scenario #2 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Examiner Note: The drywell leak will CREW increase creating containment issues. Recognizes rising drywell pressure/temperature These steps address the crew response Recognizes failure of RHR pumps to auto start on RPV Lo-Lo-Lo Level actions 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 Performs scram-reset-scram to insert control rods scram attempt (for the scram-reset-scram Informs SRO when all rods are in (CRITICAL TASK #2)

RIP), THEN DMF RP05F. This will allow Restores RPV level to a band of 170 to 211 the rods to insert when the third scram is put in.

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

- - END OF SCENARIO ***

page 18 of 20

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.doc Page 19 of 20

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