ML033140118

Final Section C Operating

ML033140118
Person / Time
Site:	Millstone
Issue date:	09/25/2003
From:	Wilson M Dominion Nuclear Connecticut
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-336/03-302
Download: ML033140118 (54)

Text

MILLSTONE POWER STATION SIMULATOR EXAM GUIDE APPROV SHEET !

Lesson

Title:

LOUT 2003 S i m u l a t d & ? & # ' l 1

Revision:

ID Number:

ES03LU1 ( \\

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This document is th its distribution.

strictly prohibited with r Station which controls tion of this document is illstone Power Station.

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Date Dehtepef Submitted by:

Reviewed I R\\L. Cimminp,,.&)

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r Teckyi6al Reviewer /

I Manager, Operations (Optional)

I Date Approved by:

Supervisor, Training Date

SIMULATOR EXAM GUIDE

SUMMARY

OF CHANGES

1.

Modified per NRC review comments. Removed the initial "Normal" action and replaced it with a "Component" malfunction.

Page 2 of 26

SIMULATOR EXAM GUIDE v

TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1.

Exam Overview

2.

Scenario Initial Conditions Sheet

3.

Exam Guide

4.

Exam Guide Summary

5.

STA Follow-up Questions Attach men ts 4

1.

Validation Checklists

2.

Shift Turnover Sheet

3.

Scenario Attribute Checklist Page 3 of 26

EXAM OVERVIEW

Title:

LOUT 2003 Simulator Exam #I ID Number: ESO3LU1 Revision: 1 J'

1.

Purpose:

This examination is used to evaluate crew/individual performance in the simulator to satisfy the requirements of NUREG 1021 for SRO-U applicants. To meet these requirements, this exam is designed to:

Evaluate the licensees' ability, as a team and individually, to respond to an emergency event.

Evaluate licensees in the following areas:

1)

2)

3)

a.

b.

Ability of the crew to perform crew-dependent critical tasks.

Ability of individuals to perform critical tasks.

Ability of each applicant to:

a) b)

Correctly diagnose events c) d)

e) 9 Demonstrate a responsible attitude g)

Respond and correctly interpret annunciators Properly interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly communicate information and interact with the rest of the crew J

Page 4 of 26

EXAM OVERVIEW

.d

Title:

LOUT 2003 Simulator Exam # I ID Number:

ES03LU1 Revision: 1

2.

Exam brief:

The simulator and room will be prepared for the exam.

1. The Simulator will be initialized at IC-98, 28% power, MOL, or an equivalent IC.

2. Power is being held constant for turnover. The unit was shut down three days ago to repair a small unisolable steam leak in the Turbine Building.

3. Bus 24E is aligned to bus 24D.

4. The Terry Turbine is tagged out for packing replacement.

5. TSAS 3.7.l.2by Action a, and TRM Table 7.15-1, Items A, B, and C, Action a, have been logged into for about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Shortly after the Crew takes the watch, per the Examiners direction, initiate a slow failure of the Letdown Backpressure Controller. This will result in a slow oscillation of letdown pressure, which will become more divergent as time continues. Manual control of the Letdown Backpressure Controller will be required to stop the oscillation.

Approximately 3 minutes after the failure of the Backpressure Controller has been resolved, the Containment Sump level transmitter will fail low. The crew will respond to the failure and log into Tech Spec action statement 3.4.6.1 b for Reactor Coolant Leakage Detection Systems, and 3.3.3.8, action 7, for Accident Monitoring.

Shortly after the Containment Sump level transmitter failure is resolved, an RCS leak on the RX Vessel Head Vent will develop. After the crew has identified that RCS leakage exists, and AOP 2568, Reactor Coolant System Leak, is used to respond to the leakage, the crew should continue the downpower using AOP 2575, Rapid Downpower. After the downpower is initiated, the A RCP will trip due to a loss of oil in the upper reservoir; however the automatic reactor trip will NOT be initiated. The US should direct a manual reactor trip. When the PPO attempts to trip the reactor, the trip pushbuttons do NOT operate. The PPO will open the CEDM MG set breakers, which will result in a reactor trip. When the reactor is tripped, the RCS leak will degrade to a small break LOCA. Additionally, a fault in the RSST will result in a Loss of Normal Power. Both D/Gs will automatically start and energize their respective buses. The A ARN pump should be manually started but will be in a severely degraded condition. The SPO should attempt to start the B ARN pump, but its breaker will NOT close. During the performance of EOP 2525, the C HPSl Pump will trip. The A HPSl Pump is degraded to the point that adequate SI flow CANNOT be achieved. The US will direct the PPO to start the B HPSl Pump.

The crew should diagnose a LOCA with a concurrent Loss of Feedwater and enter EOP 2540, Functional Recovery.

J 4

Page 5 of 26

Using the Resource Assessment Trees, the US will complete the Safety Function Status Page. If the B HPSl Pump was NOT started prior to this, the US will determine that RCS Inventory Control is the first priority and direct the PPO to start the B HPSl Pump. Otherwise, the US will determine that RCS Heat Removal is the first priority, which will require the initiation of Once-Through-Cooling.

The scenario will be terminated when RCS Heat Removal (Once-Through-Cooling) and RCS Inventory Safety functions are satisfied. When the session is terminated, the examiners shall ask any questions of the licensees that require clarification of their actions.

u

3.

PlantKimulator differences that may affect the scenario are:

None

4.

Duration of Exam:

1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Page 6 of 26

SIMULATOR EXAM GUIDE SCENARIO INITIAL CONDITIONS

Title:

ID Number:

ES03LU1 LOUT 2003 Simulator Exam #I Revision: 1 Out of Service Equipment B Charging Pump Turbine Driven Auxiliary Feed Pump Crew Instructions After assuming the shift, hold power while placing B RBCCW Pump in operation and stopping C RBCCW Pump in preparation for performing maintenance on the C RBCCW Pump. Place a yellow caution tag on the C RBCCW Pump hand switch.

Page 7 of 26

SIMULATOR EXAM GUIDE

Title:

ID Number:

ES03LUI Revision: 3 LOUT 2003 Simulator Exam #I All Control Room Conduct, Operations and Communications shall be in accordance applicable Unit Procedures.

"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

J Page 8 of 26

Simulator Rxam Guide i

i

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LUl Revision:

1.

Task Assign Time IDNMalf Instructor Information I Activity Expected Actions Standard EDR14 (RO)

EDR15 (RI)

SWR22 (22F)

RNR22 MSRl3 (RI)

MSR12 (RO)

MSR13 (RO)

ED02 (BTI)

W30A (1 00%)

W20B RC03A (0.2%) (BTI)

S105A (75%)

(LOCL)

Initial Conditions Initialize the simulator to IC-98 (or equivalent), 28% power, MOL, Load Limit set to 1.39. RPS pot settings:

AT Nuclear A

4.00 4.35 B

4.42 4.52 C

4.00 4.08 D

4.42 4.08 Bus 24E is powered from bus 24D.

Ensure all loads powered from bus 24E are properly aligned to Facility 2.

Insert remote functions to remove the terry turbine from service.

Close MS-201 and 202.

Place yellow tags on MS-201,202 and steam supply valve.

Insert malfunction to cause a loss of RSST when the reactor is tripped.

Insert malfunction to cause the A AFW pump degraded performance.

B ARN pump trip.

Insert a malfunction to cause a small break LOCA in the Loop 1A cold leg when the reactor is tripped.

A HPSl Pump degraded performance.

MA TM EM MA MA TM EM Page 9 of 26

Simulator Wxam Guide i

(

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Standard Time IDNMalf Instructor Information / Activity Expected Actions TO RP04A RPO4B RP04C RP04D RP27B TO Manual reactor trip failure Automatic reactor trip failure.

Brief the "oncoming" SM. In addition to using the Turnover Sheet, provide the following information:

The plant is at 28% power and is holding for turnover. The unit was shut down to repair a small unisolable steam leak in the Turbine Building and is returning to 100%

RCS Boron concentration is 1175 ppm. The blend ratio is 351. Adding 20 gals of PMW every 15 minutes.

Bus 24E is being supplied by bus 24D in preparation for swapping RBCCW Pumps for scheduled maintenance.

Vital Switchgear Room temperature is being logged once per shift. All switchgear room conditions are normal.

The Terry turbine is tagged out for packing replacement.

After you assume the shift, start the "B" RBCCW Pump on facility 2 and stop the "C" RBCCW Pump. Place a yellow caution tag on the hand switch and inform Work Control.

When you are ready to take the shift, please inform me.

TM TM AE Page 10 of 26

Simulator,mxam Guide

\\

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LUl Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard To + var.

CVOGC (100%) Shortly after the Crew has taken the Inst.

300 Sec.

watch, insert malfunction to cause increasingly divergent oscillations of the Letdown Backpressure Controller PPO/US us us us TI + 15 WD03 (0%)

After the crew has resolved the SPO min.

Ramp = 150 backpressure control problem, insert a malfunction to fail the Containment Sump level transmitter to zero.

sec.

us us us TI + 30 RC04 (5%)

Shortly after the crew resolves the PPO min.

Ramp = 200 level instrument failure, insert a malfunction to cause a 35 gpm leak TM Note oscillations in letdown backpressure or letdown flow.

Direct the PPO to take MANUAL control of the Backpressure Controller and stabilize letdown backpressure.

The US may have a board operator, or himself, reference the ARP (C02/3-C8) for Hi/Low Letdown Backpressure. This may be done before or after the backpressure controller is placed in manual.

Notifyldirect I&C to investigate the malfunction.

Observe the CTMT Norm Sump Level; Hi/Lo annunciator and report that the CTMT Sump level is trending to or reading zero.

Direct the SPO to obtain the appropriate ARP Determine that the level instrument has failed and report failed CTMT Sump level indication to the 1&C Department.

Obtain Tech Specs and log into TSAS 3.4.6.1 b and 3.3.3.8, Table 3.3-1 I, Action 7.

Observe and report indications of RCS leak:

Rising CTMT press, rising CTMT temp, rising gas MP-14-OPS-GDL02 TM AE MP-14-OPS-GDL02 MP-14-OPS-GDL02 Tech Specs MP-14-OPS-GDLO2 Page 11 of 26

Simulator,pxam Guide t

i

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision:

Task Assign Time IDNMalf instructor information / Activity Expected Actions Standard sec.

on the Rx Vessel Head Vent.

us us SM Event classification may be asked as a follow-up question after the exam is complete.

us us us Because the crew will be able to determine the location of the leak from available indications and due to the limited resources, the remaining and particulate RM readings.

Also report letdown lowering and backup charging pumps starting.

Determines leak rate of greater than 10 gpm, but less than 50 gpm.

Enter AOP 2568, Reactor Coolant System Leak:

I. Ensure adequate SHUTDOWN MARGIN.

2. Verify Pressurizer level 35 -70%.

3. Maintain Pressurizer pressure 2225 to 2300 psia.

4. Maintain SG level 55 - 75%

5. Ensure RBCCW and Service Water are operating properly.

6. Ensure at least 2 CARS operating with RBCCW flow to them.

Direct PPO to obtain a leak rate from PPC or other indications.

When it is determined that the RCS leakage exceeds I O gpm, then classify the event as a When leak rate is determined to be greater than Tech Spec allowed value, log into TSAS 3.4.6.2b Action b.

Determine that the plant shutdown must continue.

Reference AOP 2575, Rapid Downpower, and coordinate a plant shutdown.

UEID-1 (BU2).

TM AE AOP2568 AOP 2568 MP-26-EPI-FAPO6-002 Tech Specs AOP 2568 AOP 2575 Page 12 of 26

Simulator %am Guide t

i

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Stand a rd actions for determining the leak location per AOP 2568 may be performed after commencing the down power.

us us us us us us us us The required notifications may be us completed with one phone call.

Direct SPO to determine whether leakage in into a Steam Generator per step 5. I.

Direct PPO to determine whether leakage in into Containment per step 5.2.

Direct PPO to determine whether leakage is pasta PORVs of Pressurizer safeties per step 5.3.

Direct SPO to determine whether leakage is into RBCC W per step 5.4.

Direct SPO fo determine whether leakage is into the Auxiliary Building per step 5,5.

Direct PPO to determine whether leakage is into the Safety Injection system.

Ensure board operators maintain parameters specified in Attachments 1, 5, and 6.

Direct board operator to inform HP of the power change and rise in Letdown flow.

Direct or perform:

I. Inform CONVEX and IS0 New England or rapid down power.

2. Refer to MP-01-SM-GDLOI.01 and perform notifications as required.

3. Notify Unit 3 of rapid down power.

AOP 2568 AOP 2568 AOP 2568 AOP 2568 AOP 2568 AOP 2568 AOP 2575 AOP 2575 AOP 2575 Page 13 of 26

Simulator, vxam Guide

(

i

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Stand a rd The US may opt to borate directly from the RWST. Applicable steps are contained in AOP 2575.

However, with an RCS leak, boration to the charging pump suction would allow a blended make up to the VCT while maintaining a constant down power rate.

This action was performed earlier to commence the down power; however, they may be verified by the PPO.

US Inform board operators of manual reactor trip AOP 2575 US AOP 2575 US Determine the appropriate down power rate and AOP 2575 requirements.

Direct the SPO to maintain SG levels 55 to 70%

and FRV D/P greater than 20 psid.

direct the PPO to confirm the corresponding Boric Acid addition rate.

Direct the PPO to continue boration to the charging pump suction.

Direct SPO to maintain temperature control with the main turbine until the PPO is able to do so.

MP-14-OPS-GDL02 PPO Perform the following:

AOP 2575

1. Ensure the Makeup Mode Selector switch is in DILUTE and the Primary Makeup Water Flow controller is set to zero.

2. Ensure CH 51 2 and CH-196 are closed.

3. Ensure Boric Acid Flow controller is in AUTO.

4. Adjust Boric Acid Flow controller to the previously determined Boric Acid flow rate.

5. Open CH-504.

6. Place Makeup Mode Selector switch in MANUAL.

7. Start a Boric Acid Pump and ensure discharge pressure is greater than 90 psig.

8. When ready, open CH-196 PPO When (If) required, raise Boration and dilution flow AOP 2575, Page 14 of 26

Simulator v,xam Guide

(

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Stand a rd TI + 45 min.

Ramp = 180 down power, insert a malfunction for RCl2A (100%) Shortly after the crew initiates a sec.

an oil leak on A RCP TI -I-47 RC11A This action must be performed min.

prior to the US directing a manual Reactor trip. Approximately 1-2 minutes after the low oil level alarm, insert a malfunction to seize the A RCP. (This will result in an RPS trip signal, but the reactor will NOT automatically trip.)

SPTA-5: MANUALLY SHUT DOWN THE REACTOR.

The PPO may open the CEDM MG output breakers without direction from the US.

us PPO us Crew us PPO I SPO us and perform a blended make up to the VCT while maintaining the appropriate boration (down power) rate.

Direct PPO to insert CEAs as required to maintain AS1 within 0.01 of ESI.

Observe annunciators associated with loss of oil in A RCP.

Obtain ARP 25908 Direct PPO to check A RCP upper oil reservoir level indication and determine the rate of level decrease.

Observe the trip of the A RCP, but the reactor does NOT automatically trip.

Direct a manual reactor trip and carry out EOP 2525, Standard Post Trip Actions.

Push the 4 reactor trip push buttons and observe a failure to trip.

Direct a manual reactor trip by opening the CEDM MG output breakers.

AOP 2575 MP-14-OPS-GDL02 TM ARP 2590B MP-14-OPS-GDL02 AE MP-14-OPS-GDL02 CT EOP 2525 EC EOP 2525 Pace 15 of 26

Simulato wxam Guide L;

(

(

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Expected Actions Standard Time IDNMalf Instructor Information / Activity PPO may report degradation of A HPSl Pump.

US PPO Place Master Alarm Silence in SILENCE.

Announce Unit 2 trip on the plant paging system.

Complete and report SPTA for PPO per EOP 2525:

Ensures Reactivity safety function is being met:

Reactor is tripped All CEAs are inserted.

Power is going down.

SUR is negative.

Manual reactor trip buttons failed to operate.

Opened the CEDM MG set feeder breakers.

Reports to US.

Verifies RCS Inventory and Pressure safety functions are being met (Reports Letdown is isolated and all available Charging Pumps are running).

If Pressurizer pressure falls to less than 1800 psia, manually initiates SIAS.

Verifies Core Heat Removal established. NO RCPs are operating due to loss of RSST.

Verifies Containment Integrity safety function is being met by verifying CTMT pressure, temperature, and rad monitor readings.

- Observes rad monitors in CTMT are in alarm and rising; all other rad monitors are normal.

Performs and reports subsequent actions.

Completes SPTA for SPO per EOP 2525 correctly:

- Vital Auxiliaries are satisfied:

SPO OP 2260 EOP 2525 EOP 2525 Page 16 of 26

Simulator %am Guide

(

i

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard The Main Turbine is tripped All main stop valves are closed Megawatts are zero 8T & 9T are open Reports to US Reports that a loss of RSST has occurred Buses 25A and B are deenergized Buses 24A and B are deenergized Buses 24C and 24D energized on their respective D/Gs VA-10 and 20 are energized Both DC busses are energized Both facilities of RBCCW & SW are operating.

Verifies RCS heat removal (S/G pressures and RCS Tave).

Starts the A A

N pump, but performance is degraded. (SPO may secure the A AFVV pump.)

B AFW pump breaker will NOT close.

Reports status of Aux Feedwater.

Performs and reports subsequent actions.

and that the A HPSl Pump is degraded. (low discharge pressure)

Determine and report that the Safety Injection flow rate is less than required.

Verifies S/G feed established:

Tq + 55 s I04c Approximately 5 to I O minutes after PPO Observe and report the loss of the C HPSl Pump MP-14-OPS-min.

entry into EOP 2525, insert a malfunction to trip the C HPSl Pump.

GDL02 The direction to start the B HPSl US Direct the PPO to start B HPSI MP-14-OPS-Pump might not be given until after entry into EOP 2540.

GDL02 CT Page 17 of 26

i Simulator,,%am Guide

\\

i

Title:

LOUT 2003 Simulator Exam #I Revision:

j-ID Number ES03LU1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Stand a rd SPTA-4: Manually establish the minimum design Safety Injection System flow.

EGR16 (RES ET)

IARIO (OPEN)

If directed, as a PEO to acknowledge D/G alarms then reset local trouble alarms.

When directed, as a PEO to cross-tie Station Air with U-3, then perform actions to crosstie Station Air.

If directed to investigate the AFW Pumps, report:

B AFW Pump breaker is hung up and cannot be racked down. Must deenergize the bus to troubleshoot.

A AFW Pump is making a grinding noise and is running very hot.

PPO SPO SPO us Start B HPSl and verify Safety Injection flow is adequate.

Requests PEO to check out the DIGS.

Requests PEO to cross-tie SA with U-I Requests PEOlElectrician to check out the A and B AFW pumps.

Direct the SPO to stop the A Aux Feed Pump and place Auto Aux Feed hand switches in Pull-To-Lock.

EOP 2525 MP-14-OPS-GDL02 EOP 2525 MP-14-OPS-GDL02 Need another day to complete repairs to the TDAFP.

US Use the Diagnostic Flow Chart:

EOP 2525 Reactivity Safety Function is met.

At least I vital AC bus and one DC are energized (same train)

NO RCPs are operating (Consider EOP 2528)

Inadequate flow to Steam Generators (Consider EOP 2537)

Pressurizer pressure is less than I850 and is lowering.

Page 18 of 26

%am Guide

Title:

LOUT 2003 Simulator Exam #I ID Number ESO3LU1 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard EAL classification may be asked as a follow-up question after the exam is complete.

SM us us us us SPO us SG pressures are greater than 800 psia CTMT pressure is greater than 1 psig CTMT Rad monitors are going up (Consider EOP 2532)

EU EC Transition to EOP 2540, Functional Recovery Classifies event as Alert/C-I, based on RCB2 (BAI)

MP-26-EPI-FAP06-002 EA1. If vessel level is observed to be less than 7%, then classification is a Site Area Emergency based on RCB2 FCB4 (BSI).

Place Master Alarm silence switch in NORMAL.

Enter the time on the Safety Function Tracking Page.

Ensure SlAS has been initiated and direct the following:

EOP 2540 EOP 2540 EOP 2540 Place both spray valve controllers in MANUAL and closed.

Ensure HIC-4165 is in MANUAL and closed.

Direct the SPO to open the Steam Generator sample valves and direct Chemistry to sample both Steam Generators for Boron and activity.

Open both Steam Generator sample valves.

Direct Chemistry to sample both Steam Generators for Boron and activity, frisk the samples and report the frisk results.

When the frisk results are reported, obtain concurrence form the US and close the Steam Generator sample valves.

Direct the PPO to place both Hydrogen analyzers in operation per Appendix 19.

EOP 2540 EOP 2540 EOP 2540 Page 19 of 26

Simulator %am Guide

(

(

Title:

LOUT 2003 Simulator Exam #I Time IDNMalf Instructor Information / Activity ID Number ESO3LUl Revision: 1 Task Assign Expected Actions Standard

1. If the B HPSl Pump is NOT started prior to this if vessel level is less than 7%, then the first priority will be for Inventory Control, IC-2. When the B HPSl Pump is started and vessel level is 7% or greater, the Inventory Control safety function will be met and RCS Heat Removal, HR-3, will become the next priority.

• If RCS pressure is less than I200 psia, then the acceptance criteria for HR-3 will be met, resulting in a Y, HR-3 will be the first priority.

HR-1: Establish Once-Through-Cooling.

The US should direct early initiation of Once-Through-Cooling due to the unlikelihood of establishing feed to the SlGs and because only one HPSl Pump is runninglavaila ble.

If not performed earlier, the US should direct someone to investigate the status of the Aux Feed Pumps US With the assistance of the crew, identify and prioritize the success paths to be used:

EOP 2540 SAFETY FUNCTION Name Equip Met Name Equip Met RC-1 Y

Y HR-3 Y N

• MVA-DC-1 Y

Y CI-I Y

Y MVA-AC-2 Y

Y CTPC-3 Y

Y I c-2 Y

Y#

CCGC-1 Y

Y PC-2 Y

Y Heat Removal, HR-3 will be the first priority.

US Direct the crew to initiate Once-Through-Cooling:

EOP 25400

1. Ensure all proportional heaters are tripped and CT all backup heaters are in Pull-To-Lock.

2. Open both ADVs.

3. Ensure all RCPs are stopped.

4. Ensure SlAS is actuated.

5. Ensure HPSl Pumps have started.

6. Ensure all HPSl Injection Valves are open.

7. Ensure all available Charging Pumps are running.

8. Ensure both PORV Block Valves are open.

9. Open both PORVs.

Perform the actions directed by the US as listed PPO /

SPO above.

EOP 2540D US Continue efforts to restore Auxiliary Feedwater.

EOP 2540D PaPe 20 of26

Simulator waxam Guide

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(

Title:

LOUT 2003 Simulator Exam #I ID Number ES03LUl Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard

~~

and/or their respective breakers.

US Direct the PPO to ensure Safety Injection is optimized.

EOP 2540D PPO Perform the following:

EOP 2540D 1, Check at least on train of SIAS, CIAS, and EBFAS has actuated on C-OIX.

2. Check Safety Injection Flow is adequate per Appendix 2 of EOP 2541.

3. Ensure all available Charging Pumps are operating.

4. Ensure Vital Switchgear Cooling is operating for each ECCS train.

The session may be terminated when the crew has verified that RCS Heat Removal is being satisfied and efforts are continuing to restore Auxiliary Feedwater.

Page 21 of 26

EXAM GUIDE

SUMMARY

W

Title:

LOUT 2003 Simulator Exam #I ID Number:

Revision: 1 I.

Critical Tasks

1. SPTA-5: Manually shutdown the reactor.

BASES: If the reactor is not shutdown all safety functions may be in jeopardy.

2. SPTA-4: Manually establish the minimum design Safety Injection System flow.

BASES: Inadequate Safety Injection flow may result in loss of subcooled margin and core uncovery, and thus increase the risk of core damage.

3. HR-1:

Establish Once-Through-Cooling.

BASES: If steam generator heat removal is inadequate, then another form of core and RCS heat removal must be implemented to prevent degradation of the fuel cladding barrier to fission product release.

Page 22 of 26

EXAM GUIDE

SUMMARY

- (Continued) 111.

FOLLOW-UP QUESTIONS

1. What was the initial classification prior to the trip of the RCP?

Answer: Unsual Event/D-I (BU2), RCS leakage > 10 gpm.

2. What was the classification at the completion of EOP 2525?

Answer: Classifies event as AleNC-1 (BAI), RCBZ, RCS subcooling OR EAI, Failure of automatic trip and manual trip was successful.

if vessel level was less than 7%, then the classification is a Site Area ErnergencyK-2 (BSI), RCB2, RCS subcooling reading = 0%.

30°F.

30°F. AND FCB4, RVLMS Page 23 of 26

SIMULATOR EXAM GUIDE VAL1 DATl ON CH ECKLl ST

Title:

ID Number:

ES03LU1 LOUT 2003 Simulator Exam #I Revision: 1 Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified ICs.

Test Run:

The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.

Simulator Operating Limits:

The simulator guide has been evaluated for operating limits and/or anomalous response.

For Examination Scenario:

The Scenario Attributes Checklist is complete and attached. This is not required for Progress Review Exams W /

Actio Complete R

9!17/u..

Date Page 24 of 26

SIMULATOR GUIDE REUSE APPROVAL CHECKLIST

Title:

ID Number:

ES03LU1 LOUT 2003 Simulator Exam # I Revision: 1 Review of Simulator Exam Guide Verified (Initials)

The procedure references used in this guide are appropriate and support the learning objectives.

NA There are no simulator model changes that would negatively impact the reuse of this guide.

NA There are no simulator discrepancies that would negatively impact the reuse of this guide.

NA Validation, if necessary, has been accomplished.

NA Authorization for reusinq this Simulator Exam Guide NA NA Operator Training Branch Supervisor Date Page 25 of 26

SIMULATOR EXAM GUIDE SCENARIO ATTRIBUTES CHECKLIST ID Number:

ES03LU1 Revision: 1 Date:

Technical Reviewer:

SIMULATOR EXAM GUIDE SCENARIO ATTRIBUTES CHECKLIST

1. Total Malfunctions (TM) - Include EMS - 5 to 8 required

2. Malfs after EOP entry (EMS) - 1 to 2 required

3. Abnormal Events (AE) - 2 to 4 required

4. Major Transients (MA) - I to 2 required

5. EOPs Used (EU) beyond primary scram response - 1 to 2

6. EOP Contingencies/Transitions (EC) - 0 to 3 required

7. Crew Critical Task (CT)- 2 to 3 required

8. Approximate Scenario Run Time: 60 to 90 min.

4

9. EOP run time: 40 to 70 percent of scenario run time Total 7

Total 4

Total 4

Total 3

Total I

Total 2

Total 3

Total 90 Total 50 Technical Specifications are exercised during the scenario.

(Y/N)

Y Page 26 of 26

FOR TRAINING USE ONLY DATE-TIME Todav 0515 PREPARED BY SHIFT Unit Supervisor /NIGHT Shift 18:OO - 06~00 I

PLANT STA TUS:

b MODE: 1 RXPOWER: 28/.

0900 MEGAWATTS: Thermal: 770 MWTH RCS LEAKAGE: Identified: 0.005 gpm Electric: 257 MWe Item A, B, and C perform actions b. 1 and b.2 for fire area R-1, R-2, R-3, R-11, R-13, R-16, and R-17 TRMAS 7.1.1, c

With P18B inoperable for >60 days, P 18B, Compliance with Item B prepare an Engineering evaluation for B Charging Charging System OD continued operation. Engineering Pump assessment carried on OD No. MP2-043-03 for 60 day TRM requirement.

PZR PRESS: 2250 psia RCS T-A YE: =degrees F

PROTECTED: TrainEacility Continuous TS LCO and TRM ACTION Statements in effect (if more than one ACTION requirement per LCO, list each separately)

Action Requirement LCO Action Equipment Reason Maintain the inoperable vent path closed with TSAS 3.4.1 1.b a

Pzr Vent Manually isolated due to leakage power removed from the valves. Maintain one PORV and block valve OPERABLE.

Infinite action: Establish hourly fire watch.

Item B: Ensure P I8C is operable from C10 and TRM 7.1.1, Item a

P 18B Compliance with Charging System perform b. 1 and b2 for Fire Area R-4 B

OD Solenoids (2-RC-440 is closed).

TRMAS 3.7.10 a

See AIL See Active Impairment List.

L--

22 (YELLOW)

Unidentified: 0.036 gpm Date/Time:Todav 0015

~~~

~~

OD COMPENSATORY ACTIONS / Temp LOGS @old: Tech Specs, Italics: TRM)

None I

TS LCO and TRM ACTION Statements Coming Due (if more than one ACTION requirement per LCO, list each sena ratelv)

Parameter Reading Power 100 %

Tave 545 deg F Boron 1 175 ppm Date I Time I LCO 1 Action 1 Action Requirement I Equipment I Reason Today I 1334 I 3.7.1.2 I

a I Restore within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least I

TDAFP I Bearing replacement Parameter Reading Fluoride 0.81 ppb Chloride 1.75 ppb Oxygen

<5 pp b Today 3120103 I

I Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I

I I334 I TRMAS 7.1.15, I a

I Restore to Operable within 7 days or 1

TDAFP I Bearingreplacement EVOLUTIONS IN PROGRESS & NOTES I

ReferencdDate Holding power @ 28% for turnover. A MFW Pump operating, A Condensate Pump, GP 7 CEAs at I OPS/Today 152 steps. Xenon building in. Diluting 20 gals every IS minutes.

Bus 24E is aligned to Bus 24D to allow for planned maintenance on C RBCCW Pump I

OPSlToday I

Unit 2 Chemistry ON-LINE STATUS REPORT Unif 2 MP-14-OPS-GDL200 Rev. 000

n MILLSTONE POWER STATION I

Submitted R. J. Ashey by:

SIMULATOR E M Lesson

Title:

LOUT 2003 S 1

Revision:

ID Number:

ES03LU2 09/05/03 Date W

This document its distribution.

strictly prohibite e Power Station which\\controls odification of this document is the Millstone Power Station.

v ager, Operations (Optional)

Date

\\

Approved by: \\ -

Supervisor, Training Date 3

SIMULATOR EXAM GUIDE

SUMMARY

OF CHANGES

1.

Modified per NRC review comments. Removed the initial Normal action and replaced it with a Component malfunction.

Page 2 of 26

SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1.

Exam Overview

2.

Scenario Initial Conditions Sheet

3.

Exam Guide

4.

Exam Guide Summary

5.

Follow-up Questions v

Attachments I. Validation Checklists

2.

Shift Turnover Sheet

3.

Scenario Attribute Checklist Page 3 of 26

EXAM OVERVIEW

Title:

LOUT 2003 Simulator Exam #2 ID Number:

ES03LU2 1.

Purpose:

Revision: 1 This examination is used to evaluate crewhndividual performance in the simulator to satisfy the requirements of NUREG 1021 for SRO-U applicants. To meet these requirements, this exam is designed to:

Evaluate the licensees' ability, as a team and individually, to respond to an emergency event.

Evaluate licensees in the following areas:

1)

2)

3)

a.

b.

Ability of the crew to perform crew-dependent critical tasks.

Ability of individuals to perform critical tasks.

Ability of each applicant to:

a) b)

Correctly diagnose events c) d)

e) 9 Demonstrate a responsible attitude g)

Respond and correctly interpret annunciators Properly interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly communicate information and interact with the rest of the crew Page 4 of 26

EXAM OVERVIEW

~.-

Title:

LOUT 2003 Simulator Exam #2 ID Number:

ES03LU2 Revision: 1

2.

Exam brief:

The simulator and room will be prepared for the exam.

1. The Simulator will be initialized at IC-24, 100% power, MOL, or an equivalent IC.

2. 6 Charging Pump is tagged to prevent automatic start.

3. Bus 24E is aligned to bus 24D to allow for C HPSl Pump work later today.

Shortly after the Crew takes the watch, Main Feed Flow transmitter on #2 SG will begin to fail low. This will result in a slow rise in SG level requiring the selection of the Alternate Feed Flow transmitter to mitigate. Alternatively, the #2 SG Main FRV can be controlled in manual until level is stabilized at setpoint, at which time the Alternate Feed Flow transmitter can be selected and the system returned to auto.

Approximately 2 minutes after the SG level control failure has been mitigated, Channel Y of Reactor Reg will fail. The crew will respond to the failure by entering the applicable ARPs for pressurizer level.

When the required actions to stabilize pressurizer level and pressure have been completed, the #I SIT will develop a nitrogen leak requiring entry into Technical Specifications.

When the crew has completed logging TSAS 3.5.1, action b, the Main Control Valves will ramp close causing a rapid rise in RCS pressure and temperature. When the control valves close, the steam dump valves will NOT receive a quick open signal (previous Reactor Reg. Failure) resulting in a continued rise in RCS temperature and pressure. The reactor will fail to automatically trip on high RCS pressure requiring a manual reactor trip.

As a result of the trip, a Steam Generator Tube Rupture will occur on #2 S/G. As a result of the high RCS pressure, a Pressurizer Safety will stick partially open.

Additionally, the RSST will be lost and the A DG breaker will fail to close resulting in the need to emergency trip the A DG and the loss of vital bus 24C.

The crew should perform the actions of EOP 2525, Standard Post Trip Actions, and diagnose a LOCA with a SGTR on the #2 S/G. This will require entry in EOP 2540, Functional Recovery.

The crew will determine that Containment Integrity is NOT met and must implement EOP 2540E, Functional Recovery of Containment Isolation.

During the performance of EOP 2540E, The C Service Water Pump will trip, requiring the crew to start the B Service Water Pump on Facility 2.

The scenario may be terminated when #2 SG is isolated.

d v

Page 5 of 26

3.

PlantlSimulator differences that may affect the scenario are:

4 None

4.

Duration of Exam:

1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

e Page 6 of 26

SIMULATOR EXAM GUIDE SCENARIO INITIAL CONDITIONS L--

Title:

LOUT 2003 Simulator Exam #2 ID Number:

ES03LU2 Revision: 1 Out of Service Equipment B Charging Pump Crew Instructions Maintain the plant at 100% power, steady state.

Page 7 of 26

SIMULATOR EXAM GUIDE

Title:

ID Number:

ES03LU2 Revision: 1 LOUT 2003 Simulator Exam #2 All Control Room Conduct, Operations and Communications shall be in accordance applicable Unit Procedures.

"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Page 8 of 26

Simulator Exam Guide

\\

J\\

Title:

LOUT 2003 Simulator Exam #2 ID Number ESO3LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Stand a rd EDR14 (RO)

EDR15 (RI)

SWR22 (22F)

ED02 BT 1 EG08A RCO5A (1 5%)

BT 21 RP28D RP28E RP28H SG02B (20%)

BT I Initial Conditions Initialize the simulator to IC-24, 100% power, MOL, simulator in run.

Bus 24E is powered from bus 24D.

Ensure all loads powered from bus 24E are properly aligned to Facility 2.

Insert malfunction to cause a loss of the RSST when the reactor is tripped.

A DG output breaker fails to close on the LNP.

A Pressurizer Safety valve sticks partially open after the trip.

Failure of RPS to automatically trip on low SG level or high RCS pressure.

SGTR in #2 SG on the trip.

TM EM TM EM MA TM EM TM EM MA

Simulator Exam Guide

\\

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard TO Using the turnover sheet, brief the "oncoming" US. In addition to the Turnover Sheet, provide the following:

The plant is at 100% power and has been at 100% power for the past 9 months.

RCS Boron concentration is 820 ppm with a blend ratio of 6.3:l.

Bus 24E is being supplied by bus 24D in preparation for removing "C" HPSl Pump from service for inspection later today. All other conditions are normal.

When you are ready to take the shift, please inform me.

TI RXIOC (50%)

Shortly after Crew takes the watch, Inst.

300 Sec.

insert a malfunction to slowly fail the Main Feed Flow Transmitter low.

USlSPO us SPO TM Observe rising water level in #2 SG.

Note: The ARP for SG Level HVLo (C05 A8) should be referenced at some time by the Crew to verify actions taken are correct and complete.

Direct SPO to take MANUAL control of #2 SG FRV and stabilize or select Alternate Feed Flow Transmitter.

Performs above actions as directed by US.

Simulator Exam Guide I

(

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard us Note failure of Main Feed Flow Transmitter and (if not already done so) direct SPO to select Alternate Feed Flow Transmitter.

Once level is stabilized and failed transmitter is deselected, return FRV control to auto if required Direct/Notify I&C of Feed Control System failure.

us us TZ RXGB (0)

Once FRV control failure is Crew Ramp = 180 sec.

returned to automatic control, mitigated and system has been insert malfunction for a failure of channel Y of Reactor Reg.

us PPO us PPO Observe indications and diagnose a failure of the channel Y Tave calculator.

Lowering Tave reading on Channel Y.

0 Annunciators on C-02/3 to include:

- PRESSURIZER CH X LEVEL HI/LO (A38)

(A391

- PRESSURIZER CH Y LEVEL HVLO PZR PRESSURE SELECTED CHANNEL Direct the PPO to take manual control of Letdown Flow Controller, HIC-110 and restore Letdown to 40 gpm.

Place HIC-110 in manual and lower Letdown flow to 40 gpm.

Direct the PPO to perform either of the following:

DEVIATION HVLO (D37)

1. Commence forcing sprays

2. Place Backup heaters in Pull-To-Lock.

Performs either:

0 Places all Backup Heaters in Pull-To-Lock Lowers Pressurizer pressure controller to obtain a 50% output on the controller.

MP-14-OPS-GDL02 and various ARPs TM AE ARP 2590B ARP 25908 ARP 25908 ARP 25908

Simulator Exam Guide

Title:

LOUT 2003 Simulator Exam #2 ID Number ESO3LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard T3 us PPO us The US may decide to continue forcing sprays.

PPO S103A ( I 00%)

When pressurizer pressure and PPO level are returned to normal, insert a malfunction for a Nitrogen leak on#l SIT.

us Direct the PPO to shift Reactor Reg to Channel (X'.

Places Reactor Reg switch in Channel 'XI.

When pressurizer level is restored to 65%, direct the PPO to return HIC-110 to automatic and to restore pressurizer pressure control to normal.

Shifts HIC-110 to automatic and performs one of the following:

Returns the pressurizer pressure controller to the previous set point and secures the backup heaters 0

Removes backup heaters from PuII-To-Lock.

~.

pressure.

Observe and report value and trend of pressure on # I SIT along with SAFETY INJECTION TANK 1 PRESS LO annunciator.

Direct PPO to perform the following:

Ensure level indicates between 55.2 and 59.7%

Ensure Leakage Drain Stop, SI-618, closed.

Attempt to determine the cause of the low ARP 2590B ARP 25908 ARP 2590B AOP 2590B MP-14-OPS-GDL02 and various ARPs TM AE ARP 2590A

Simulator Exam Guide

(

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Standard Time IDNMalf Instructor Information / Activity Expected Actions 7-4 TCOGA-D When the US has logged into (10%)

30 sec. ramp TSAS 3.5.1, insert a malfunction to cause the Main Control Valves to close.

SPTA-5: Manually shutdown the reactor.

This action may be performed by the PPO WITHOUT direction from the US.

PPO us Crew Crew us us us PPO reports:

ARP 2590A Ensure level indicates between 55.2 and 59.7%

Ensure Leakage Drain Stop, SI-618,

closed, 0

Attempt to determine the cause of the low pressure.

Request maintenance to investigate the cause of ARP 2590A the low SIT pressure Log into TSAS 3.5.1.

pressure, and numerous annunciators.

GDL02 Observe rising RCS temperature, rising RCS MP-14-OPS-MA Observe RCS pressure rising to the trip set point and a failure to automatically trip.

MP-14-OPS-GDL02 Direct the PPO to manually trip the plant and the crew to perform EOP 2525, Standard Post Trip Actions.

MP-14-OPS-GDL02 CT Place Master Alarm Silence in SILENCE.

Announce Unit 2 trip on the plant paging system.

OP 2260 Begin querying board operators on the status of EOP 2525.

EOP 2525

Title:

LOUT 2003 Simulator Exam #2 Simulator Exam Guide ID Number ES03 U2 RevIa1m:.

Task Expected Actions Stand a rd Assign Time IDNMalf Instructor Information / Activity PPO Complete and report SPTA for PPO per EOP 2525:

EOP 2525 Ensures Reactivity safety function is being met:

Reactor is tripped All CEAs are inserted Power is going down.

SUR is negative.

Verifies RCS Inventory and Pressure safety functions are being met (Reports Letdown is isolated, all available Charging Pumps are running, a Pressurizer Safety indicates open, and SlAS has actuated on Facility 2.)

Verifies Core Heat Removal established. NO RCPs are operating due to loss of RSST.

Verifies Containment Integrity safety function is being met by verifying CTMT pressure, temperature, and rad monitor readings.

Observes CTMT temperature and pressure rising; rad monitors in CTMT are in alarm and rising; all other rad monitors are normal.

Performs and reports completion of subsequent actions.

Simulator Exam Guide

(\\

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Time IDA/Malf Instructor Information / Activity Expected Actions Standard SPO SPO EGRIG If directed as a PEO, acknowledge SPO (RESET)

D/G alarms, then reset local alarms.

IARIO (OPEN) When directed as a PEO to cross-tie SPO Station Air with U-3, then perform actions to crosstie Station Air.

Completes SPTA for SPO per EOP 2525 correctly:

Vital Auxiliaries are satisfied:

EOP 2525 The Main Turbine is tripped All main stop valves are closed Megawatts are zero 8T & 9T are open Reports that a loss of RSST has occurred Buses 25A and B are deenergized Buses 24A and B are deenergized A

DG breaker failed to close, bus 24C is deenergized Bus 240 is energized by its respective diesel generator.

Buses 201A and B are energized.

Buses VA-10 and VA-20 are energized.

- Verifies RCS heat removal (S/G pressures EOP 2525 and RCS Tave).

- Verifies S/G feed established by starting Aux feedwater.

- Reports unusual rise in #2 SG level with NO (or very little) feed flow.

- Performs and reports completion of subsequent actions.

Requests PEO to check out the D/Gs.

MP-14-OPS-7 GDL02 EOP 2525 Requests PEO to cross-tie SA with U-I

Title:

LOUT 2003 Simulator Exam #2 Simulator Exam Guide i

ID Number ES03LU2 Revision: 1 Task Assign Stand a rd Time I DA/Malf Instructor Information / Activity Expected Actions If the unusual rise in #2 SG is initially missed or determined to be not significant enough to warrant attention, the US may direct entry into EOP 2532, LOCA. When the unusual rise is determined to be indicative of a SGTR, the US will transition to EOP 2540.

us Use the Diagnostic Flow Chart:

EOP 2525 Reactivity Safety Function is met.

At least 1 vital AC bus and one DC are energized (same train)

NO RCPs are operating (Consider EOP 2528)

Adequate flow to Steam Generators Pressurizer pressure is less than 1850 and is lowering.

SG pressures are greater than 800 psia with lowering subcooling.

CTMT pressure is greater than 1 psig and rising.

CTMT Rad monitors are going up (Consider EOP 2532)

Other SGTR indications: feed flow - steam flow mismatch and unusual rise in #2 SG level.

Transition to EOP 2540, Functional Recovery, based on LOCA and SGTR.

EU EAL classification may be asked SM Classifiy event as an Alert/Charlie-I based in MP-26-EPI-as a follow-up question after the FAP06-002 RCB3, RCB4, or EA1 exam is complete.

US Place Master Alarm silence switch in NORMAL.

EOP 2540 US EOP 2540 US Enter the time on the Safety Function Tracking Page.

Ensure SlAS has been initiated and direct the following:

EOP 2540 Place both spray valve controllers in MANUAL and closed.

Ensure HIC-4165 is in MANUAL and closed.

Simulator Exam Guide

(

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Standard Time IDNMalf Instructor Information / Activity Expected Actions Approximately 20-30 minutes after a request is made to sample both SGs for activity, report as Chemist:

1. I SG - <MDA

1. 2 SG - 250 cpm above background.

T6 SWOIC While the SPO is performing steps to obtain SG samples, insert a malfunction to trip the C Service Water Pump.

MVAZ: Energize at least one vital electrical AC bus.

us SPO SPO us SPO us Direct the SPO to open the Steam Generator sample valves and direct Chemistry to sample both Steam Generators for Boron and activity.

- Open both Steam Generator sample valves.

- Direct Chemistry to sample both Steam Generators for Boron and activity, frisk the samples and report the frisk results.

- When the frisk results are reported, obtain concurrence form the US and close the Steam Generator sample valves.

Observe indications of a loss of Facility 2 Service water.

- SW PUMP C OVERLOAD/TRIP annunciator.

- B Service Water header low flow.

Report loss of Service Water.

Direct SPO to start 6 Service Water Pump on Facility 2.

Start B Service Water Pump on Facility 2, place IC Service Water Pump hand switch in Stop, and report restoration of Service Water.

Direct the PPO to place both Hydrogen analyzers in operation per Appendix 19.

EOP 2540 EOP 2540 MP-14-OPS-GDL02 TM EM MP-14-OPS-GDL02 AOP 2565 CT AE MP-14-OPS-GDL02 AOP 2565 EOP 2540

Simulator Exam Guide i

(

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard The US will determine that Containment Integrity, (21-1, acceptance criteria are NOT met and immediately enter EOP 2540E.

CVROS (RI)

When requested, rack in B Charging Pump breaker on Facility

2.

US With the assistance of the crew, identify and prioritize the success paths to be used:

SAFETY FUNCTION RC-1 Y

Y HR-2 Y

Y MVA-DC-1 Y

Y CI-I N

Y MVA-AC-2 Y

Y CTPC-2 Y

Y IC-2 Y

Y CCGC-1 Y

Y PC-2 Y

Y Name Met Equip Name MetEquip Containment integrity, CI-I, will be the first priority.

Ensure SIAS, ClAS EBFAS, and MSI have actuated. Direct the following:

- Ensure all required Facility 2 components are in their accident condition.

- Ensure at least one train of Control Room Air Conditioning is in recirc.

- Ensure facility vital switchgear cooling is operating.

US EOP 2540 EOP 2540E EC

Simulator Exam Guide ID Number ESO3LU2 Revision: 1

Title:

LOUT 2003 Simulator Exam #2 Task Instructor Information / Activity Assign Expected Actions Standard Time IDNMalf PPO I SPO HR-7: Perform a plant cooldown.

us SPO us PPO To ensure Facility 2 CRAC is in recirc, perform the following:

1. F21 B Exhaust Damper, HV 203B is open.

2. CRACS Supply Fan, F21B is running.

3. F31B Exhaust Damper, HV 206B, is open.

4. CRACS Exhaust Fan, F31B, is running.

5. F32B Exhaust Damper, HV 2128, is open.

6. CRACS Filter Fan, F32B, is running.

7. Fresh Air Makeup Damper, HV 495 is closed.

8. Exhaust Air Damper, HV-496, is closed

9. Cable Vault Exhaust Damper, HV-497 is closed.

Direct the SPO to initiate a cool down at the maximum controllable rate to a Th of 6 1 5°F using the ADVs.

Commence a cool down by throttling open both ADVs.

Direct the PPO to depressurize the RCS while maintaining the following parameters:

- RCS pressure less than 920 psia

- Within 50 psia of #2 S/G

- Within the confines of the P/T curve.

Operate Pressurizer heaters and auxiliary spray to ensure RCS pressure is maintained within the directed parameters.

EOP 2540E EOP 2541, Appendix 12 CT EC EOP 2541, Appendix 12 EOP 2541, Appendix 12 EOP 2541,

Appendix 12

Simulator Exam Guide

Title:

LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision:

I-Task Assign Expected Actions Standard Time IDNMalf instructor Information / Activity HR-6: Isolate the affected or most affected Steam Generator.

US When both hot leg temperatures are less than 515"F, then direct the SPO to:

- Record the time and Tc in the operating loop.

- Isolate the #2 S/G per step 6 of EOP 2541, Appendix 12.

US/SPO Direct a PEO to close the disconnect for Steam Supply to the Turbine Driven Aux Feed Pump, 2-EOP 2541,

Appendix 12 CT MSRl3 (RI)

When directed, close the disconnect for MS-202.

M S-202.

SPO I. Ensure #2 ADV is in AUTO and closed with a EOP 2541, set point of 920 psia.

2. Ensure #2 MSlV is closed.

3. Ensure #2 MSlV Bypass Valve is closed.

4. Close Main Feed Reg Valve Bypass Valve, 2-

5. Ensure Main Feedwater Block Valve, 2-FW-42B, is closed.

0 Ensure Feedwater Reg Valve, 2-FW-51 B is closed.

6. Place Main Feed Isolation Air Assist Check Valve, 2-FW-5B, in CLOSE.

7. Ensure SG Blowdown Isolation Valve, 2-MS-2208, is closed.

8. Place both Aux Feed OVERRlDE/MAN/STRART/RESET hand switches are in Pull-To Lock.

9. Close Aux Feed Reg Valve, 2-FW-43B.

I O. Place Aux Feed Isolation Air Assist Check Valve, 2-FW-I2B, to CLOSE.

11. Close the Steam Suppl;y Valve to the Turbine Appendix 12 FW-41 B.

E 3

a U

a, a,

L L x 2 c

a,

.- b N

u) 0 0

2 m

u) a, P

tj m

a, Y

0 Q) 5

EXAM GUIDE

SUMMARY

V v

Title:

LOUT 2003 Simulator Exam #2 ID Number:

ES03iU2 Revision: 1 I.

Critical Tasks

1. SPTA-5: Manually shutdown the reactor.

BASES: If the reactor is not shutdown all safety functions may be in jeopardy

2. MVAZ: Energize at least one vital electrical AC bus BASES: Loss of vital AC bus is a significant reduction in safety margin.

3. CI-I : Maintain Containment Isolation.

BASES: Failure to adequately isolate the containment in the event of a failure of the RCS and fuel cladding fission product barriers, may increase the potential for release to the environment.

4. HR-7: Perform a plant cooldown.

BASES: If steam generator heat removal is inadequate, then another form of core and RCS heat removal must be implemented to prevent degradation of the fuel cladding barrier to fission product release.

5. HR-6: Isolate the affected or most affected Steam Generator.

BASES: Isolation of the affected Steam Generator is assumed in the Safety Analysis. Failure to identify the most affected Steam Generator can result in the inability to isolate the most affected Steam Generator and reestablish the barrier to fission release.

Page 22 of 26

EXAM GUIDE

SUMMARY

- (Continued) 111.

FOLLOW-UP QUESTIONS

1. What was the classification for this event at the completion of EOP 2525?

Answer: Classify event as an Alert/C-1 based on BSI RCB2 (or RCB4)

EAI.

RCB2 - RCS subcooling < 30°F.

RCB4 - Reactor coolant leak > CVCS capacity and entry into EOP 2525, Standard Post Trip Actions.

EA1 - Failure of automatic reactor trip and manual trip was successful.

Page 23 of 26

SIMULATOR EXAM GUIDE VAL1 DATION CHECKLIST W

Title:

ID Number:

ES03LU2 LOUT 2003 Simulator Exam #2 Revision: 1 Initial Conditions:

V e F By:

The initial condition(s) contained in the guide are certified or have been developed from certified ICs.

Test Run:

The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.

A Simulator Operating Limits:

n The simulator guide has been evaluated for operating limits and/or anomalous response.

w For Examination Scenario:

The Scenario Attributes Checklist is complete and attached. This is not required for Progress Review Exams Action CorB;piete K!? &

9/[7/&

Date Page 24 of26

SIMULATOR GUIDE REUSE APPROVAL CHECKLIST v

Title:

LOUT 2003 Simulator Exam #2 ID Number:

ES03LU2 Revision: 1 Review of Simulator Exam Guide Verified

( I n it ia is) 0 The procedure references used in this guide are appropriate and support the learning objectives.

NA There are no simulator model changes that would negatively impact the reuse of this guide.

0 There are no simulator discrepancies that would negatively impact the reuse of this guide.

NA NA 0

Validation, if necessary, has been accomplished.

NA Authorization for reusing this Simulator Exam Guide NA NA Operator Training Branch Supervisor Date Page 25 of 26

SIMULATOR EXAM GUIDE SCENARIO ATTRIBUTES CHECKLIST ID Number:

ES03LU2 Revision: 1 Date:

Technical Reviewer:

SIMULATOR EXAM GUIDE SCENARIO ATTRIBUTES CHECKLIST

1. Total Malfunctions (TM) - Include EMS - 5 to 8 required Total 9

2. Malfs after EOP entry (EMS) - 1 to 4 required Total 6

3. Abnormal Events (AE) - 2 to 4 required Total 4

4. Major Transients (MA) - 1 to 2 required Total 4

5. EOPs Used (EU) beyond primary scram response - I to 2 required Total I

6. EOP ContingenciesKransitions (EC) - 0 to 2 required Total 2

iJ

7. Crew Critical Task (CT)- 2 to 3 required Total 4

8. Approximate Scenario Run Time: 60 to 90 min.

9. EOP run time: 40 to 70 percent of scenario run time Technical Specifications are exercised during the scenario.

Total 90 Total 60 (Y/N)

Y

\\--

Page 26 of 26

FOR TRAINING USE ONLY DATE-TIME PREPARED BY Todav 0515 Unit Supervisor PNIGHT Shift SHIFT 18100 - 06100 1 PLANT STA TUS:

MODE:

1.

RXPOWER: 100%

Action Requirement LCO Action Maintain the inoperable vent path closed with TSAS 3.4.11.b a

power removed from the valves. Maintain one PORV and block valve OPERABLE.

Infinite action: Establish hourly fire watch.

TRMAS 3.7.10 a

Item B: Ensure P18C is operable from C10 and a

perform b. 1 and b2 for Fire Area R-4 TRM 7.1.1, Item B

MEGA WATTS: Thermal: 2699 MWTH Electric: 903 MWe RCS LEAKAGE: Identified: o.005 gpm Equipment Reason Pzr Vent Solenoids (2-RC-440 is closed).

See AIL Manually isolated due to leakage See Active Impairment List.

OD P18B Compliance with Charging System PZR PRESS: 2250 psia RCS T-A YE: =degrees F

PROTECTED:

TraidFacility EVOLUTIONS IN PROGRESS & NOTES None 22 (YELLOW) I Unidentified: 0.036 gpm Date/Time:Todav 0015 Referemmate I TS LCO and TRM ACTION Statements Coming Due (if more than one ACTION requirement per LCO, list each I

Parameter Reading Power 100 %

Tave 545 degF Boron 821 ppm 3/20/03 TRMAS 7.1.1, Parameter Reading Fluoride 0.81 ppb Chloride 1.75 ppb Oxygen 4 pp b Item B continued operation. Engineering assessment carried on OD No. MP2-043-Reason Compliance with Charging System OD 1 Unit 2 Chemistry ON-LINE STATUS REPORT

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Unit 2 MP-1 4-OPS-G D L200 Rev. 000