ML033140118
| 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 Revision:
ID Number:
-1 ES03LU1 (
/ \\ I
\ \
This document is th r Station which controls its distribution. tion of this document is strictly prohibited with illstone Power Station.
A n .e \
Submitted 09/05/03 by:
qwi )
Dehtepef Date Reviewed by:
I R\L. Cimminp, &.,) \/ n
- 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 4
Attach ments
- 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 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:
- a. Evaluate the licensees' ability, as a team and individually, to respond to an emergency event.
- b. Evaluate licensees in the following areas:
- 1) Ability of the crew to perform crew-dependent critical tasks.
- 2) Ability of individuals to perform critical tasks.
- 3) Ability of each applicant to:
a) Respond and correctly interpret annunciators b) Correctly diagnose events J'
c) Properly interpret integrated system response d) Comply with and use Technical Specifications e) Comply with and use procedures 9 Demonstrate a responsible attitude g) 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 J
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 AHPSl 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.
4 Page 5 of 26
Using the Resource Assessment Trees, the US will complete the Safety Function Status Page. If the BHPSl 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 u the BHPSl 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 .
- 3. PlantKimulator differences that may affect the scenario are:
None
- 4. Duration of Exam: 1.5 hours.
Page 6 of 26
SIMULATOR EXAM GUIDE SCENARIO INITIAL CONDITIONS
Title:
LOUT 2003 Simulator Exam #I ID Number: ES03LU1 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:
LOUT 2003 Simulator Exam #I ID Number: ES03LUI Revision: 3 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 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 EDR14 (RO) Bus 24E is powered from bus 24D.
EDR15 (RI)
Ensure all loads powered from bus SWR22 (22F) 24E are properly aligned to Facility 2.
RNR22 Insert remote functions to remove the (LOCL) terry turbine from service.
MSRl3 (RI) Close MS-201 and 202.
MSR12 (RO) Place yellow tags on MS-201,202 MSR13 (RO) and steam supply valve.
ED02 (BTI) Insert malfunction to cause a loss of MA RSST when the reactor is tripped.
W30A Insert malfunctionto cause the A TM EM (100%) AFW pump degraded performance.
W20B B ARN pump trip. MA RC03A Insert a malfunction to cause a small MA (0.2%) (BTI) break LOCA in the Loop 1A cold leg when the reactor is tripped.
S105A (75%) A HPSl Pump degraded TM EM performance.
Page 9 of 26
Simulator Wxam Guide i (
Title:
LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard TO RP04A Manual reactor trip failure TM RPO4B RP04C RP04D RP27B Automatic reactor trip failure. TM AE TO 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 3 5 1 . 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.
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. TM 300 Sec. watch, insert malfunction to cause increasingly divergent oscillations of the Letdown Backpressure Controller PPO/US Note oscillations in letdown backpressure or letdown flow.
us Direct the PPO to take MANUAL control of the Backpressure Controller and stabilize letdown backpressure.
us 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.
us Notifyldirect I&C to investigate the malfunction.
TI + 15 WD03 (0%) After the crew has resolved the SPO Observe the CTMT Norm Sump Level; Hi/Lo MP-14-OPS-min. Ramp = 150 backpressure control problem, insert annunciator and report that the CTMT Sump level GDL02 sec. a malfunction to fail the Containment is trending to or reading zero.
Sump level transmitter to zero. TM AE us Direct the SPO to obtain the appropriate ARP MP-14-OPS-GDL02 us Determine that the level instrument has failed and MP-14-OPS-report failed CTMT Sump level indication to the GDL02 1&C Department.
us Obtain Tech Specs and log into TSAS 3.4.6.1b Tech Specs and 3.3.3.8, Table 3.3-1 I , Action 7.
TI + 30 RC04 (5%) Shortly after the crew resolves the PPO Observe and report indications of RCS leak: MP-14-OPS-min. Ramp = 200 level instrument failure, insert a Rising CTMT press, rising CTMT temp, rising gas GDLO2 malfunction to cause a 35 gpm leak Page 11 of 26
Simulator,pxam Guide i t
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. and particulate RM readings. TM AE Also report letdown lowering and backup charging pumps starting.
Determines leak rate of greater than 10 gpm, but less than 50 gpm.
us Enter AOP 2568, Reactor Coolant System Leak: AOP2568 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.
us Direct PPO to obtain a leak rate from PPC or AOP 2568 other indications.
Event classification may be asked SM When it is determined that the RCS leakage MP-26-EPI-as a follow-up question after the exceeds I O gpm, then classify the event as a FAPO6-002 exam is complete. UEID-1 (BU2).
us When leak rate is determined to be greater than Tech Spec allowed value, log into TSAS 3.4.6.2b Action b. Tech Specs us Determine that the plant shutdown must continue. AOP 2568 Because the crew will be able to us Reference AOP 2575, Rapid Downpower, and AOP 2575 determine the location of the leak coordinate a plant shutdown.
from available indications and due to the limited resources, the remaining 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 Standard actions for determining the leak location per AOP 2568 may be performed after commencing the down power.
us Direct SPO to determine whether leakage in into a AOP 2568 Steam Generator per step 5. I.
us Direct PPO to determine whether leakage in into AOP 2568 Containment per step 5.2.
us Direct PPO to determine whether leakage is pasta AOP 2568 PORVs of Pressurizer safeties per step 5.3.
us Direct SPO to determine whether leakage is into AOP 2568 RBCC W per step 5.4.
us Direct SPO fo determine whether leakage is into AOP 2568 the Auxiliary Building per step 5,5.
us Direct PPO to determine whether leakage is into AOP 2568 the Safety Injection system.
us Ensure board operators maintain parameters AOP 2575 specified in Attachments 1, 5, and 6.
us Direct board operator to inform HP of the power AOP 2575 change and rise in Letdown flow.
The required notifications may be us Direct or perform: AOP 2575 completed with one phone call. I. Inform CONVEX and I S 0 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.
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 Standa rd US Inform board operators of manual reactor trip AOP 2575 requirements.
US Direct the SPO to maintain SG levels 55 to 70% AOP 2575 and FRV D/P greater than 20 psid.
The US may opt to borate directly US Determine the appropriate down power rate and AOP 2575 from the RWST. Applicable steps direct the PPO to confirm the corresponding Boric are contained in AOP 2575. Acid addition rate.
However, with an RCS leak, boration to the charging pump suction would Direct the PPO to continue boration to the allow a blended make up to the VCT charging pump suction.
while maintaining a constant down MP-14-OPS-power rate. Direct SPO to maintain temperature control with the main turbine until the PPO is able to do so. GDL02 This action was performed earlier to PPO Perform the following: AOP 2575 commence the down power; 1. Ensure the Makeup Mode Selector switch however, they may be verified by the is in DILUTE and the Primary Makeup PPO. Water Flow controller is set to zero.
- 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 Standa rd and perform a blended make up to the VCT while Attachment 3 maintaining the appropriate boration (down power) rate.
us Direct PPO to insert CEAs as required to maintain AOP 2575 AS1 within 0.01 of ESI.
TI + 45 RCl2A (100%) Shortly after the crew initiates a PPO Observe annunciators associated with loss of oil MP-14-OPS-min. Ramp = 180 down power, insert a malfunction for in A RCP. GDL02 sec. an oil leak on ARCP Obtain ARP 25908 TM TI -I-47 RC11A This action must be performed us Direct PPO to check ARCP upper oil reservoir ARP 2590B min. prior to the US directing a manual level indication and determine the rate of level Reactor trip. Approximately 1-2 decrease.
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.)
Crew Observe the trip of the A RCP, but the reactor MP-14-OPS-does NOT automatically trip. GDL02 AE SPTA-5: MANUALLY SHUT DOWN us Direct a manual reactor trip and carry out EOP MP-14-OPS-THE REACTOR. 2525, Standard Post Trip Actions. GDL02 CT PPO I Push the 4 reactor trip push buttons and observe EOP 2525 SPO a failure to trip.
EC The PPO may open the CEDM MG us Direct a manual reactor trip by opening the CEDM EOP 2525 output breakers without direction MG output breakers.
from the US.
Pace 15 of 26
Simulato wxam Guide
(
L; (
Title:
LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: 1 Task Assign Expected Actions Time IDNMalf Instructor Information / Activity Standard US Place Master Alarm Silence in SILENCE. OP 2260 Announce Unit 2 trip on the plant paging system.
PPO Complete and report SPTA for PPO per EOP EOP 2525 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 PPO may report degradation of A psia, manually initiates SIAS.
HPSl Pump.
- 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.
SPO Completes SPTA for SPO per EOP 2525 EOP 2525 correctly:
- Vital Auxiliaries are satisfied:
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).
- Verifies S/G feed established:
- Starts the AA N pump, but performance is degraded. (SPOmay secure the A AFVV pump.)
B AFW pump breaker will NOT close.
Reports status of Aux Feedwater.
- Performs and reports subsequent actions.
Tq + 55 sI04c 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 and that the AHPSl Pump is degraded. (low GDL02 malfunction to trip the C HPSl discharge pressure)
Pump.
Determine and report that the Safety Injection flow rate is less than required.
The direction to start the B HPSl US Direct the PPO to start B HPSI MP-14-OPS-Pump might not be given until GDL02 after entry into EOP 2540.
CT Page 17 of 26
i
\
Simulator,,%am Guide i
Title:
LOUT 2003 Simulator Exam #I ID Number ES03LU1 Revision: j-Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standa rd SPTA-4: Manually establish the minimum design Safety Injection System flow.
PPO Start BHPSl and verify Safety Injection flow is EOP 2525 adequate.
EGR16 If directed, as a PEO to acknowledge SPO Requests PEO to check out the DIGS. MP-14-OPS-(RESET) D/G alarms then reset local trouble GDL02 alarms.
IARIO (OPEN) When directed, as a PEO to cross-tie SPO Requests PEO to cross-tie SA with U-I EOP 2525 Station Air with U-3, then perform actions to crosstie Station Air.
If directed to investigate the AFW us Requests PEOlElectricianto check out the A MP-14-OPS-Pumps, report: and BAFW pumps. GDL02 BAFW Pump breaker is hung up Direct the SPO to stop the AAux Feed Pump and cannot be racked down. Must and place Auto Aux Feed hand switches in Pull-deenergize the bus to troubleshoot. To-Lock.
AAFW Pump is making a grinding noise and is running very hot.
Need another day to complete repairs to the TDAFP.
US Use the Diagnostic Flow Chart: EOP 2525 Reactivity Safety Function is met.
At least Ivital 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 SG pressures are greater than 800 psia CTMT pressure is greater than 1 psig CTMT Rad monitors are going up (Consider EOP 2532)
Transition to EOP 2540, Functional Recovery EU EC EAL classification may be asked SM Classifies event as Alert/C-I , based on RCB2 MP-26-EPI-as a follow-up question after the (BAI) EA1. If vessel level is observed to be FAP06-002 exam is complete. less than 7%, then classification is a Site Area Emergency based on RCB2 FCB4 (BSI).
us Place Master Alarm silence switch in NORMAL. EOP 2540 us Enter the time on the Safety Function Tracking EOP 2540 Page.
us Ensure SlAS has been initiated and direct the EOP 2540 following:
- Place both spray valve controllers in MANUAL and closed.
- Ensure HIC-4165 is in MANUAL and closed.
us Direct the SPO to open the Steam Generator EOP 2540 sample valves and direct Chemistry to sample both Steam Generators for Boron and activity.
SPO Open both Steam Generator sample valves. EOP 2540 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.
us Direct the PPO to place both Hydrogen analyzers EOP 2540 in operation per Appendix 19.
Page 19 of 26
Simulator %am Guide
( (
Title:
LOUT 2003 Simulator Exam #I ID Number ESO3LUl Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard
- If the B HPSl Pump is NOT US With the assistance of the crew, identify and EOP 2540 started prior to this if vessel level prioritize the success paths to be used:
is less than 7%, then the first SAFETY FUNCTION priority will be for Inventory Control, Name Equip Met Name Equip Met IC-2. When the B HPSl Pump is started and vessel level is 7% or RC-1 Y Y HR-3 Y N
- greater, the Inventory Control MVA-DC-1 Y Y CI-I Y Y safety function will be met and RCS Heat Removal, HR-3, will become MVA-AC-2 Y Y CTPC-3 Y Y the next priority.
Ic-2 Y Y# CCGC-1 Y Y
- If RCS pressure is less than I200 PC-2 Y Y psia, then the acceptance criteria for HR-3 will be met, resulting in a Heat Removal, HR-3 will be the first priority.
Y, HR-3 will be the first priority.
HR-1: Establish Once-Through- US Direct the crew to initiate Once-Through-Cooling: EOP 25400 Cooling. 1. Ensure all proportional heaters are tripped and CT The US should direct early all backup heaters are in Pull-To-Lock.
initiation of Once-Through-Cooling 2. Open both ADVs.
due to the unlikelihood of 3. Ensure all RCPs are stopped.
establishing feed to the SlGs and 4. Ensure SlAS is actuated.
because only one HPSl Pump is 5. Ensure HPSl Pumps have started.
runninglavailable. 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.
PPO / Perform the actions directed by the US as listed EOP 2540D SPO above.
If not performed earlier, the US US Continue efforts to restore Auxiliary Feedwater. EOP 2540D should direct someone to investigate the status of the Aux Feed Pumps PaPe 20 of26
Simulator waxamGuide
( (
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 EOP 2540D optimized.
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 30°F.
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 30°F. AND FCB4, RVLMS reading = 0%.
Page 23 of 26
SIMULATOR EXAM GUIDE VAL1DATlON CHECKLlST
Title:
LOUT 2003 Simulator Exam #I ID Number: ES03LU1 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.
R Simulator Operating Limits:
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
/ Actio Complete 9!17/u..
Date Page 24 of 26
SIMULATOR GUIDE REUSE APPROVAL CHECKLIST
Title:
LOUT 2003 Simulator Exam # I ID Number: ES03LU1 Revision: 1 Review of Simulator Exam Guide Verified (Initials)
The procedure references used in this guide are appropriate and NA support the learning objectives.
There are no simulator model changes that would negatively NA impact the reuse of this guide.
There are no simulator discrepancies that would negatively impact NA the reuse of this guide.
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 Total 7
- 2. Malfs after EOP entry (EMS) - 1 to 2 required Total 4
- 3. Abnormal Events (AE) - 2 to 4 required Total 4
- 4. Major Transients (MA) - Ito 2 required Total 3
- 5. EOPs Used (EU) beyond primary scram response - 1 to 2 Total I 6 . EOP Contingencies/Transitions (EC) - 0 to 3 required Total 2 4
- 7. Crew Critical Task (CT)- 2 to 3 required Total 3
- 8. Approximate Scenario Run Time: 60 to 90 min. Total 90
- 9. EOP run time: 40 to 70 percent of scenario run time 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 Unit Supervisor /NIGHT Shift SHIFT 18:OO 06~00 I PLANT STA TUS:
b MODE: 1 RXPOWER: 28/.
MEGAWATTS: Thermal: 770 MWTH PZR PRESS: 2250 psia Electric: 257 MWe RCS T-A YE: =degrees F RCS LEAKAGE: Identified: 0.005 gpm PROTECTED: TrainEacility Unidentified: 0.036 gpm Date/Time:Todav 0015 2 2 (YELLOW)
TS LCO and TRM ACTION Statements Coming Due (if more than one ACTION requirement per LCO, list each sena ratelv)
Date I Time I LCO 1 Action 1 Action Requirement I Equipment I Reason Today I 1334 I 3.7.1.2 I a IRestore 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 I IHot 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 Today I334 I TRMAS 7.1.15, I a I Restore to Operable within 7 days or 1 TDAFP I Bearingreplacement 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 3120103 0900 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.
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 Solenoids (2-RC-440 is closed).
PORV and block valve OPERABLE.
L--
Infinite action: Establish hourly fire watch. TRMAS 3.7.10 a See AIL See Active Impairment List.
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 -
~~~ ~~
OD COMPENSATORY ACTIONS / Temp LOGS @old: Tech Specs, Italics: TRM)
None I -,
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 Parameter Reading Parameter Reading Power 100 % Fluoride 0.81 ppb Tave 545 deg F Chloride 1.75 ppb Boron 1 175 ppm Oxygen <5 ppb Unif 2 MP-14-OPS-GDL200 Rev. 000
MILLSTONE POWER STATION n
SIMULATOR E M Lesson
Title:
LOUT 2003 S Revision: -1 ID Number: ES03LU2 This document e Power Station which\controls its distribution. odification of this document is strictly prohibite the Millstone Power Station.
W v I
Submitted R. J. Ashey 09/05/03 by:
Date 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 Revision: 1 1.
Purpose:
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:
- a. Evaluate the licensees' ability, as a team and individually, to respond to an emergency event.
- b. Evaluate licensees in the following areas:
- 1) Ability of the crew to perform crew-dependent critical tasks.
- 2) Ability of individuals to perform critical tasks.
- 3) Ability of each applicant to:
a) Respond and correctly interpret annunciators b) Correctly diagnose events c) Properly interpret integrated system response d) Comply with and use Technical Specifications e) Comply with and use procedures 9 Demonstrate a responsible attitude g) 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. 6Charging 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 d 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.
v The scenario may be terminated when #2 SG is isolated.
Page 5 of 26
- 3. PlantlSimulator differences that may affect the scenario are:
4 None
- 4. Duration of Exam: 1.5 hours.
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:
LOUT 2003 Simulator Exam #2 ID Number: ES03LU2 Revision: 1 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 Initial Conditions Initialize the simulator to IC-24, 100% power, MOL,simulator in run.
EDR14 (RO) Bus 24E is powered from bus 24D.
EDR15 (RI)
Ensure all loads powered from SWR22 (22F) bus 24E are properly aligned to Facility 2.
ED02 Insert malfunction to cause a loss of BT 1 the RSST when the reactor is tripped.
EG08A A DG output breaker fails to close TM EM on the LNP.
RCO5A (15%) A Pressurizer Safety valve sticks TM EM MA BT 21 partially open after the trip.
RP28D Failure of RPS to automatically trip TM EM RP28E on low SG level or high RCS RP28H pressure.
SG02B (20%) SGTR in #2 SG on the trip. TM EM MA BT I
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. TM 300 Sec. insert a malfunction to slowly fail the Main Feed Flow Transmitter low.
USlSPO 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.
us Direct SPO to take MANUAL control of #2 SG FRV and stabilize or select Alternate Feed Flow Transmitter.
SPO 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.
us Once level is stabilized and failed transmitter is deselected, return FRV control to auto if required us Direct/Notify I&C of Feed Control System failure.
TZ RXGB (0) Once FRV control failure is Crew Observe indications and diagnose a failure of the MP-14-OPS-Ramp = 180 mitigated and system has been channel Y Tave calculator. GDL02 and sec. returned to automatic control, Lowering Tave reading on Channel Y. various ARPs insert malfunction for a failure of Annunciators on C-02/3 to include:
0 TM AE channel Y of Reactor Reg. - PRESSURIZER CH X LEVEL HI/LO (A38)
- PRESSURIZER CH Y LEVEL HVLO (A391 PZR PRESSURE SELECTED CHANNEL DEVIATION HVLO (D37) us Direct the PPO to take manual control of ARP 2590B Letdown Flow Controller, HIC-110 and restore Letdown to 40 gpm.
PPO Place HIC-110 in manual and lower Letdown flow ARP 25908 to 40 gpm.
us Direct the PPO to perform either of the following: ARP 25908
- 1. Commence forcing sprays
- 2. Place Backup heaters in Pull-To-Lock.
PPO Performs either: ARP 25908 0 Places all Backup Heaters in Pull-To-Lock Lowers Pressurizer pressure controller to obtain a 50% output on the controller.
Simulator Exam Guide
Title:
LOUT 2003 Simulator Exam #2 ID Number ESO3LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information/ Activity Expected Actions Standard
~.
us Direct the PPO to shift Reactor Reg to Channel ARP 2590B (X'.
PPO Places Reactor Reg switch in Channel 'XI. ARP 25908 The US may decide to continue us When pressurizer level is restored to 65%, direct ARP 2590B forcing sprays. the PPO to return HIC-110 to automatic and to restore pressurizer pressure control to normal.
PPO Shifts HIC-110 to automatic and performs one of AOP 2590B 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.
T3 S103A ( I 00%) When pressurizer pressure and PPO Observe and report value and trend of pressure MP-14-OPS-level are returned to normal, insert on # I SIT along with SAFETY INJECTION TANK GDL02 and a malfunction for a Nitrogen leak 1 PRESS LO annunciator. various ARPs o n # l SIT. TM AE us Direct PPO to perform the following: ARP 2590A Ensure level indicates between 55.2 and 59.7%
Ensure Leakage Drain Stop, SI-618, closed.
Attempt to determine the cause of the low pressure.
Simulator Exam Guide
(
Title:
LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standard PPO 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.
us Request maintenance to investigate the cause of ARP 2590A the low SIT pressure Log into TSAS 3.5.1.
7-4 TCOGA-D When the US has logged into Crew Observe rising RCS temperature, rising RCS MP-14-OPS-(10%) TSAS 3.5.1,insert a malfunction to pressure, and numerous annunciators. GDL02 30 sec. ramp cause the Main Control Valves to MA close.
Crew Observe RCS pressure rising to the trip set point MP-14-OPS-and a failure to automatically trip. GDL02 SPTA-5: Manually shutdown the us Direct the PPO to manually trip the plant and the MP-14-OPS-reactor. crew to perform EOP 2525, Standard Post Trip GDL02 Actions.
This action may be performed by CT the PPO WITHOUT direction from the US.
us Place Master Alarm Silence in SILENCE. OP 2260 Announce Unit 2 trip on the plant paging system.
us Begin querying board operators on the status of EOP 2525 EOP 2525.
Simulator Exam Guide
Title:
LOUT 2003 Simulator Exam #2 ID Number ES03 U2 RevIa1m: .
Task Assign Time IDNMalf Instructor Information / Activity Expected Actions Standa rd PPO Complete and report SPTA for PPO per EOP EOP 2525 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 Completes SPTA for SPO per EOP 2525 EOP 2525 correctly:
- Vital Auxiliaries are satisfied:
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 ADG 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.
SPO - 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.
EGRIG If directed as a PEO, acknowledge SPO Requests PEO to check out the D/Gs. MP-14-OPS-(RESET) D/G alarms, then reset local alarms. 7 GDL02 IARIO (OPEN) When directed as a PEO to cross-tie SPO Requests PEO to cross-tie SA with U-I EOP 2525 Station Air with U-3,then perform actions to crosstie Station Air.
Simulator Exam Guide i
Title:
LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: 1 Task Assign Time IDA/Malf Instructor Information/ Activity Expected Actions Standard If the unusual rise in #2 SG is us Use the Diagnostic Flow Chart: EOP 2525 initially missed or determined to be Reactivity Safety Function is met.
not significant enough to warrant At least 1 vital AC bus and one DC are attention, the US may direct entry energized (same train) into EOP 2532, LOCA. When the NO RCPs are operating (Consider EOP 2528) unusual rise is determined to be Adequate flow to Steam Generators indicative of a SGTR, the US will Pressurizer pressure is less than 1850 and is transition to EOP 2540. 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, EU based on LOCA and SGTR.
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 RCB3, RCB4, or EA1 FAP06-002 exam is complete.
US Place Master Alarm silence switch in NORMAL. EOP 2540 US Enter the time on the Safety Function Tracking EOP 2540 Page.
US Ensure SlAS has been initiated and direct the EOP 2540 following:
- 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 Time IDNMalf Instructor Information/ Activity Expected Actions Standard us Direct the SPO to open the Steam Generator EOP 2540 sample valves and direct Chemistry to sample both Steam Generators for Boron and activity.
Approximately 20-30 minutes after a SPO - Open both Steam Generator sample valves. EOP 2540 request is made to sample both SGs - Direct Chemistry to sample both Steam for activity, report as Chemist: Generators for Boron and activity, frisk the
- I SG - <MDA samples and report the frisk results.
- When the frisk results are reported, obtain
- 2 SG - 250 cpm above concurrence form the US and close the background.
Steam Generator sample valves.
T6 SWOIC While the SPO is performing steps SPO Observe indications of a loss of Facility 2 Service MP-14-OPS-to obtain SG samples, insert a water. GDL02 malfunctionto trip the C Service - SW PUMP C OVERLOAD/TRIP annunciator. TM EM Water Pump.
- B Service Water header low flow.
Report loss of Service Water.
MVAZ: Energize at least one vital us Direct SPO to start 6 Service Water Pump on MP-14-OPS-electrical AC bus. Facility 2. GDL02 AOP 2565 CT AE SPO Start B Service Water Pump on Facility 2, place MP-14-OPS-IC Service Water Pump hand switch in Stop, GDL02 and report restoration of Service Water. AOP 2565 us Direct the PPO to place both Hydrogen analyzers EOP 2540 in operation per Appendix 19.
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 US With the assistance of the crew, identify and EOP 2540 Containment Integrity, (21-1, prioritize the success paths to be used:
acceptance criteria are NOT met SAFETY FUNCTION and immediately enter EOP Name Met Equip Name MetEquip 2540E.
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 Containment integrity, CI-I, will be the first priority.
CVROS (RI) When requested, rack in B US Ensure SIAS, ClAS EBFAS,and MSI have EOP 2540E Charging Pump breaker on Facility actuated. Direct the following:
2.
EC
- 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.
Simulator Exam Guide
Title:
LOUT 2003 Simulator Exam #2 ID Number ESO3LU2 Revision: 1 Task Time IDNMalf Instructor Information / Activity Assign Expected Actions Standard PPO I To ensure Facility 2 CRAC is in recirc, perform EOP 2540E SPO the following:
- 2. CRACS Supply Fan, F21B is running.
- 4. CRACS Exhaust Fan, F31B, is running.
- 6. CRACS Filter Fan, F32B, is running.
- 8. Exhaust Air Damper, HV-496, is closed
- 9. Cable Vault Exhaust Damper, HV-497 is closed.
HR-7: Perform a plant cooldown. us Direct the SPO to initiate a cool down at the EOP 2541, maximum controllable rate to a Th of 6 15°F Appendix 12 using the ADVs.
CT EC SPO Commence a cool down by throttling open both EOP 2541, ADVs. Appendix 12 us Direct the PPO to depressurize the RCS while EOP 2541, maintaining the following parameters: Appendix 12
- RCS pressure less than 920 psia
- Within 50 psia of #2 S/G
- Within the confines of the P/T curve.
PPO Operate Pressurizer heaters and auxiliary spray EOP 2541, to ensure RCS pressure is maintained within the Appendix 12 directed parameters.
Simulator Exam Guide
Title:
LOUT 2003 Simulator Exam #2 ID Number ES03LU2 Revision: I-Task Time IDNMalf instructor Information / Activity Assign Expected Actions Standard HR-6: Isolate the affected or most US When both hot leg temperatures are less than EOP 2541, affected Steam Generator. 515"F, then direct the SPO to: Appendix 12
- Record the time and Tc in the operating loop. CT
- Isolate the #2 S/G per step 6 of EOP 2541, Appendix 12.
MSRl3 (RI) When directed, close the disconnect US/SPO Direct a PEO to close the disconnect for Steam for MS-202. Supply to the Turbine Driven Aux Feed Pump, 2-MS-202.
SPO I. Ensure #2 ADV is in AUTO and closed with a EOP 2541, set point of 920 psia. Appendix 12
- 2. Ensure #2 MSlV is closed.
- 3. Ensure #2 MSlV Bypass Valve is closed.
- 4. Close Main Feed Reg Valve Bypass Valve, 2-FW-41B.
- 5. Ensure Main Feedwater Block Valve, 2-FW-42B, is closed.
0 Ensure Feedwater Reg Valve, 2-FW-51B 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/RESEThand 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
N u) 0 0
2 m
u) a, P
E 3
a U m a, a, a, tj LL x
2c Y a, 0
.-> Q) b 5
EXAM GUIDE
SUMMARY
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.
v 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 VAL1DATION CHECKLIST W
Title:
LOUT 2003 Simulator Exam #2 ID Number: ES03LU2 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 K!? &
Action CorB;piete 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 (Initiais) 0 The procedure references used in this guide are appropriate and NA support the learning objectives.
There are no simulator model changes that would negatively NA impact the reuse of this guide.
0 There are no simulator discrepancies that would negatively impact NA the reuse of this guide.
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
- 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. Total 90
- 9. EOP run time: 40 to 70 percent of scenario run time Total 60 Technical Specifications are exercised during the scenario. (Y/N) Y
\--
Page 26 of 26
FOR TRAINING USE ONLY DATE-TIME PREPARED BY SHIFT Todav 0515 Unit Supervisor PNIGHT Shift 18100- 06100 1 PLANT STA TUS:
MODE: 1. RXPOWER: 100%
MEGA WATTS: Thermal: 2699 MWTH PZR PRESS: 2250 psia Electric: 903 MWe RCS T-A YE: =degrees F RCS LEAKAGE: Identified: o.005gpm PROTECTED: TraidFacility Unidentified: 0.036 gpm Date/Time:Todav 0015 2 2 (YELLOW) I ITS LCO and TRM ACTION Statements Coming Due (if more than one ACTION requirement per LCO, list each I 3/20/03 TRMAS 7.1.1, Item B Action Requirement continued operation. Engineering assessment carried on OD No. MP2-043-LCO Action Equipment 1
Reason Reason Compliance with Charging System OD Maintain the inoperable vent path closed with TSAS 3.4.11.b a Pzr Vent Manually isolated due to leakage power removed from the valves. Maintain one Solenoids (2-RC-440 is closed).
PORV and block valve OPERABLE.
Infinite action: Establish hourly fire watch. TRMAS 3.7.10 a See AIL See Active Impairment List.
Item B: Ensure P18C is operable from C10 and TRM 7.1.1, Item a P18B Compliance with Charging System perform b. 1 and b2 for Fire Area R-4 B OD EVOLUTIONS IN PROGRESS & NOTES Referemmate None Unit 2 Chemistry ON-LINE STATUS REPORT Parameter Reading Parameter Reading Power 100 % Fluoride 0.81 ppb Tave 545 degF Chloride 1.75 ppb Boron 821 ppm Oxygen 4 ppb
\/
Unit 2 MP-14-OPS-G DL200 Rev. 000