ML081420563
| ML081420563 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/27/2008 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| QF-1030-19, Rev 12 | |
| Download: ML081420563 (74) | |
Text
QF-1030-19 Rev. 12 EXAMINATION SCENARIO GUIDE (ESG)
SITE: DAEC START 2ND CONDT & FW PUMPS, RAISE POWER, RR CONTROLLER FAILS UP, RCIC SPURIOUS START, B WW PUMP TRIP, LOSS OF 1D11, STATION BLACKOUT, HPCI INVERTER FAILS, LOCA/ALC ED, SBDG COMES BACK ESG ILT 01 REV. 0 PROGRAM: OPERATIONS COURSE: INITIAL LICENSED OPERATOR 50007 TOTAL TIME:
120 MINUTES Developed by:
Instructor Date Validated by:
SME/Instructor Date Reviewed by:
Operations Manager Date Approved by:
Training Supervisor-Operations Date Retention: Life of policy = 10yrs.
Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 22
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 2 of 22 GUIDE REQUIREMENTS Goal of Training:
The goal of this scenario is to evaluate ILT students during the NRC Exam with 3 man crew.
Learning Objectives:
There are no formal learning objectives Prerequisites:
None Training Resources:
Simulator Simulator Booth Instructor Phone Talker Simulator Floor Instructor
References:
None Commitments:
None Evaluation Method:
Dynamic Simulator Operating Experience:
None Related PRA Information:
Initiating Event with Core Damage Frequency:
N/A due to exam security Important Components:
N/A due to exam security Important Operator Actions with Task Number:
N/A due to exam security Comment [N1]: Fill in the goal for this lesson plan. Based on the learning objectives describe the expected outcome/goal of this training session.
Comment [N2]: Fill in the learning objectives for this lesson plan. Use the information obtained during the design phase.
Comment [N3]: List the courses that need to be completed prior to participating in this training session.
Comment [N4]: List the materials and multi-media needed to perform training. Examples are as follows:
1)furniture arrangement 2)multi-media equipment (VCR, DVD player, monitors, LCD projector, and etc) 3)multi-media software (tapes, CDs, DVDs, disks, and etc) 4)flipcharts, white/black boards 5)markers, pencils, pens, and etc) 6)security clearances 7)equipment and tools 8)number of instructors/guest speakers needed Comment [N5]: List any references used to develop this training session:
1)procedures 2)text Comment [N6]: List any commitments made. INCLUDE recommendations for corrective actions, results of investigations and why the training process was initiated.
Revision 0: List purpose of lesson plan. Revision 1: List reason(s) for development or revision.
Comment [N7]: Include written exams, practical exercises, JPM, OJE, or any other form of evaluating.
Specify method of evaluating individual mastery of learning objectives.
Comment [N8]: Seek applicable external and internal operating experience to include in the lesson plan. Where applicable, Training Instructors shall incorporate plant and industry operating experience into lesson plans, simulator guides, or laboratory guide. The review of the operating experience should include the following elements:
1)Event description 2)Applicability to the site 3)Lessons learned 4)Application of the operating experience to prevent occurrence, or recurrence.
5)Additional supporting information may be included.
6)Operating experience items may also be added as attachments to lesson plan. Reference the
... [1]
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 3 of 22 SCENARIO
SUMMARY
The crew will continue the Startup by starting the second Condensate and Feed Pumps IAW OI-644.
After the second condensate and feed pumps are started, the ROs will continue the startup by raising power via RR pumps.
When the evaluators are satisfied with the reactivity change evolution, then the A Recirc pump controller will fail upscale. When the crew identifies this, the crew will lockup the A RR scoop tube to terminate the transient. The SRO will have to evaluate the RR speed mismatch to determine if TS actions are required. This event is not counted as a TS event, but may require TS actions, depending on how quickly the crew notices the controller failure.
Once the A RR controller failure has been addressed, RCIC will spuriously start. This will require the BOP to manually trip RCIC and the SRO enters Technical Specifications LCO 3.5.3.A - RCIC system inoperable.
Once the RCIC event has been addressed, the B Well Water pump trips. This will require the crew to enter AOP 408 for loss of well water and start an additional well water pump to restore WW parameters. During the loss of WW flow, the Drywell parameters will be elevating due to loss of DW cooling.
Then the 125 VDC Div I panel 1D11 trips, which leads to a 1C05 level event. Feedwater level control response will require manual actions to control RPV water level (select the A FW input).
The SRO will declare Div 1-125 VDC distribution subsystem INOP in accordance with Tech Spec 3.8.7 condition B. If the RO does not select the A FW input, the reactor could scram due to this electrical transient.
A Station Blackout and subsequent reactor scram occurs. The A DG will not start due to the loss of 125 VDC. The B DG starts but fails to pick up the dead bus because of a breaker malfunction. EOPs are entered on low reactor level. The crew enters the Station Blackout AOP and concentrates their activity to power restoration.
The SBDG that is running without the bus being energized is running without cooling water.
The BOP must recognize this and take action to secure the running SBDG.
When HPCI is initiated (manual or automatic) an inverter failure will cause HPCI to operate at low rpm and no flow requiring it to be tripped. RCIC is not available to automatically initiate or inject due to the previous loss of the RCIC. RPV level slowly lowers due to a containment leak.
Due to the lowering RPV water level, Alternate Level Control (ALC) is entered per EOP-1.
Emergency depressurization is required due to low level in vessel (Critical Task). After emergency depressurization is commenced the B DG output breaker is repaired and the DG is placed I/S. RHR and CS are used to restore reactor water level (Critical Task).
The scenario ends when Emergency Depressurization has been completed and RPV level restored and maintained within the normal band.
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 4 of 22 SCENARIO OUTLINE:
BOOTH INSTRUCTOR ACTIONS 1
SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)
1.1 General Instructions
- a.
Restore the IC for ILT-Scenario-1 from the Thumb Drive that it is stored on. This Thumb Drive also has the malfunction and override files on it.
a)
Log onto one of the Computer Terminals using the logon from Lowell b)
With a file manager, go to the \\\\boson\\c$\\opensim directory, and copy the Malfunc-New.dat file into that directory.
c)
Rename the Malfunc.dat file to Malfunc-OLD.dat d)
Rename the Malfunc-NEW.dat file to Malfunc.dat e)
Copy the IC file from the thumb drive to the \\\\boson\\ryan\\ops\\ic directory.
f)
Rename the IC file to d_ic.000. This makes the IC number 000 g)
Reset to IC 000.
(1)
Verify Malfunctions (2)
Verify Overrides (3)
Verify Remote functions (4)
Verify event trigger definitions.
- b.
If the thumbdrive is not available, then reset to IC 13 and perform the following:
a)
Secure the B FW pump and B condensate pump b)
Secure the HWC system for the B side c)
Start the B Well Water pump d)
Secure the D Well Water pump e)
Adjust RR flow to achieve ~55% power (44.0 in Manual).
f)
Swap the SUFRV suction valves using FW1 screen in RNI Extreme.
g)
Close MO-2423/2424
- c.
Have STP 3.4.2-01 available for the crew, if needed/required (unmarked, at booth)
- d.
Have STP 2.5.3-01 available for the crew, if needed/required (unmarked, at booth)
- e.
Have IPOI 3, section 4 marked to step 7, circle step 8
- f.
Have OI 646 (Extraction Steam) Section 3 marked thru step 25.c
- g.
Have OI 644 (Cond and FW) Section 3.8 marked thru step 8.L
- h.
Have OI 683 (Main Steam) section 3 complete.
- i.
Pull sheet setup is as follows:
a)
The reactor is using sequence A1, Step 32, with all step 32 rods at 44
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 5 of 22
- j.
Control panel setups, including valves/equipment to tag out a)
Place a Maintenance In Progress tag on the A SBLC pump b)
Place a Maintenance In Progress tag on the B HWC FIC c)
Swap the SUFRV Suction Magnets d)
Place annunciator magnets on lit annunciators.
e)
Verify B RFP Recirc Valve is set at 1500 gpm in AUTO 1.2 EVENT TRIGGER DEFINITIONS:
Trigger No.
Trigger Logic Statement Trigger Word Description 1, 2, 3, 4, 5, 8
Manual N/A 7
RDPACC(1).LT.1440 CRD Accumulator pressure less than 1440 (SCRAM) Initiates the Station Blackout 9
ZAOHPSI2284.GT. 0.25 HPCI Speed Indicator indicates ~2000 RPMs Initiates the HPCI Inverter Fault
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 6 of 22
1.3 MALFUNCTIONS
Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value Setup AN 1C05A(43) 1C05A (F-03) Annunciator Box (6HX8W) (SBLC Cont Loss)
As Is ON Setup SL02A Squib Valves Fail To Fire Vlv A XS2618A False TRUE Setup SL01A Standby Liquid Pump Trip-Pump A False TRUE Setup ED03 Grid Voltage Instability N/A N/A N/A 50 50 Setup DG02B Diesel Gen Breaker Auto Close Circuit Failure In TRUE As Dir RR17B Recirc M-G Flow Ctrlr Fails, Auto/Man Modes-M-G A 350 sec 1
As Is 100 As Dir RC08 Inadvertent RCIC Initiation 2
False TRUE As Dir RC10B MO2405 Thermal Overload Breaker Trip 3
False TRUE As Dir SW21B Well Water Pump Trip-Pump B 4
False TRUE As Dir ED13A 125 Vdc Distribution Panel Fault-Pnl 1D11 5
False TRUE As Dir ED01A Loss Of Off-Site Power Sources-Bkr M 7
False TRUE As Dir ED01B Loss Of Off-Site Power Sources-Bkr J 7
False TRUE As Dir ED01C Loss Of Off-Site Power Sources-Bkr K 7
False TRUE As Dir ED01D Loss Of Off-Site Power Sources-Bkr X5960 7
False TRUE As Dir ED01E Loss Of Off-Site Power Sources-Bkr X5940 7
False TRUE As Dir RR15A Recirc Loop Rupt-Design Bases LOCA at 100% Loop A 600 8
0 20 As Dir HP07 HPCI Inverter Trouble 9
TRUE 1.4
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 7 of 22 OVERRIDES:
Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Setup SL HS-2613A(1)
A SBLC Light 1P-230A (Green Light)
OFF Setup SL HS-2613A(2)
A SBLC Light 1P-230A (Red Light)
OFF Setup SL XS-2618A(1)
A Squib Valve Ready - W (White)
Continuity Light OFF Setup AO ED X377 Hazelton Line Megavars 25 0
7 As Is 0.50 Setup AO ED X378 Hills Line Megawatts 25 0
7 As Is 0.50 Setup AO ED X379 Auto XFMR Megavars 25 0
7 As Is 0.50 Setup AO ED X380 Hazelton Line Megawatts 25 0
7 As Is 0.50 Setup AO ED X381 Hills Line Megavars 25 0
7 As Is 0.50 Setup AO ED X382 Auto XFMR Megawatts 25 0
7 As Is 0.50 Setup AO ED X383 Hiawatha Line Megavars 25 0
7 As Is 0.50 Setup AO ED X384 Vinton Line Megavars 25 0
7 As Is 0.50 Setup AO ED X385 Fairfax Line Megavars 25 0
7 As Is 0.50 Setup AO ED X386 Hiawatha Line Megawatts 25 0
7 As Is 0.50 Setup AO ED X387 Vinton Line Megawatts 25 0
7 As Is 0.50 Setup AO ED X388 Fairfax Line Megawatts 25 0
7 As Is 0.50 Setup AO ED X392 6th Street Line Megavars 25 0
7 As Is 0.50 Setup AO ED X393 6th Street Line Megawatts 25 0
7 As Is 0.50 Setup LO ED X0710(1) Haz. Hills ACB SW 0710 Grn Lt.
25 N/A 7
OFF ON Setup LO ED X0710(2) Haz. Hills ACB SW 0710 Red Lt.
25 N/A 7
ON OFF Setup LO ED X2690(1) Auto XFMR OCB SW 2690 Grn Lt.
25 N/A 7
OFF ON Setup LO ED X2690(2) Auto XFMR OCB SW 2690 Red Lt.
25 N/A 7
ON OFF Setup LO ED X2820(1) Hills Auto ACB 2820 Green Lt.
25 N/A 7
OFF ON Setup LO ED X2820(2) Hills Auto ACB 2820 Red Lt.
25 N/A 7
ON OFF Setup LO ED X4730(1) Hazelton Auto ACB 4730 Grn Lt.
25 N/A 7
OFF ON Setup LO ED X4730(2) Hazelton Auto ACB 4730 Red Lt.
25 N/A 7
ON OFF Setup LO ED X6780(1) Auto XFMR OCB SW 6780 Grn Lt.
25 N/A 7
OFF ON Setup LO ED X6780(2) Auto XFMR OCB SW 6780 Red Lt.
25 N/A 7
ON OFF Setup LO ED X9180(1) Hia. Line OCB SW 9180 Grn Lt.
25 N/A 7
OFF ON Setup LO ED X9180 (2) Hia. Line OCB SW 9180 Red Lt.
25 N/A 7
ON OFF Setup DI EG 352HSS H Breaker OCB 0220 Sync Switch 25 N/A 7
As Is OFF Setup DI EG 352ISS I Breaker OCB 4290 Sync Switch 25 N/A 7
As Is OFF Setup DI ED 352JSS J Breaker OCB 5550 Sync Switch 25 N/A 7
As Is OFF Setup DI ED 352KSS K Breaker OCB 5560 Sync Switch 25 N/A 7
As Is OFF Setup DG 152-411 1G21 Control Switch to NAT NAT NAT
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 8 of 22 1.5 REMOTE FUNCTIONS:
Time Remote No.
Remote Title Delay Ramp ET Initial Value Final Value Setup FW15 MAN Operation of FEED PUMP A (1P-1A Breaker) 7 As-Is OPEN Setup FW16 MAN Operation of FEED PUMP B (1P-1B Breaker) 7 As-Is OPEN FLOOR INSTRUCTOR ACTIONS 2
Simulator Pre-brief:
2.1 Individual position assignments 2.2 Simulator Training Changes Since Last Module 2.3 Simulator hardware and software modifications/problems that may impact training 3
TURNOVER INFORMATION The plant is operating at 57% power near the end of the current fuel cycle.
The plant is in a normal configuration with the B Well Water pump is in service to support the startup of the B feedwater pump.
The B Side Condensate and Feed Pump is to be placed back in service to support raising power per IPOI 3.
Outage Control Center (OCC) is still manned, due to second RFP is not started.
QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 Page 9 of 22 4
TURNOVER INFORMATION Day of week and shift Wednesday Day Shift Weather conditions Hot Severe weather predicted later tonight (Plant power levels) 55%
MWT 1117 MWE 348 CORE FLOW 31.7 Thermal Limit Problems/Power Evolutions Startup the 2nd Condensate and Feedwater Pumps Once both condensate and feedwater pumps are running, continue to raise RR flow to reach 35 Mlbm flow, then hold for Xenon (per the REs).
The Reactor Engineers informed us that we DONT have to run a 3D case every 5%,
we will run one once we reach 35 Mlbm.
RE wants to use a slow ramp rate (2-3 MWe per minute)
Plant Risk Status CDF 2.09E-5 Color Yellow Existing LCOs, date of next surveillance A SBLC Pump out for pre-planned maintenance STPs in progress or major maintenance Reactor power was reduced yesterday due to a leak on the casing of the B RFP.
The leak has been repaired.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment B HWC FIC - I & C is troubleshooting the B HWC FIC. When you get the step to place the B HWC system in service, circle the step and wait for I & C to get done with their troubleshooting. Then you can perform the step as written (OI 644, section 3.8, step 27).
Comments, evolutions, problems, core damage frequency, etc.
B Well Water pump is running to support the start of the B RFP.
All 5 Condensate Demins are IN SERVICE Load dispatcher would like power to be raised expeditiously.
OCC is manned, but will disband as soon as the 2nd RFP is started.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 10 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover COMPLETE TURNOVER:
Provide Shift Turnovers to the SRO and ROs.
- a. Review applicable current Plant Status
- b. Review relevant At-Power Risk status
- c. Review current LCOs not met and Action Requirements
- d. Verify crew performs walk down of control boards and reviews turnover checklists Get familiar with plant conditions.
SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 11 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Startup second Condensate and Feed Pump IAW OI-644.
Booth Instructor respond as plant personnel and respond as necessary:
Role play as the inplant operators to assist the crew to start the B Condensate Pump and the B Reactor Feedwater Pump.
When directed to open the B Condensate Pump discharge valve (V-06-04) USE Remote FW05 or the SimVue page.
Turnover Info - All Condt/Demins ON.
Role Play: When directed to isolate CRD valves 1P-1803A-V05 and 1P-1803B-V07, then wait two minutes, and inform the crew that both of those valves are CLOSED (simulator does not model) REVERSE THIS WHEN DIRECTED TO OPEN THE VALVES.
Role Play: When directed to verify closed the seal water isolation valve V06-11, wait two minutes and inform the crew that both valves are CLOSED (simulator does not model). (Valve V06-12 is already closed)
Role Play: When directed to verify the Shaft Driven Aux Oil Pump (SDAOP) running, inform the crew the SDAOP is running. (local oil pressure is pegged high)
SRO Gives Pre-job brief to coordinate and discuss evolution Communicate with the Event Response Team May call Chemistry and direct to verify proper operation of AE-8912A, RR Water O2 Analyzer RO Monitoring critical parameters - reactor power, pressure, level Peer checker for BOP operator BOP Reviewing OI-644 -Condensate and Feedwater.
Reviewing IPOI-3 -Power Operations.
Starts the B condensate pumps per OI-644 section 3.8, step 9.
Starts the B RFP per OI-644 Section 3.8, step 14.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 12 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Raises Power 10% using Recirculation Flow Booth Instructor respond as plant personnel and respond as necessary:
If 1C04B (C-1), B RR Pump Motor Oil Hi/LO Level annunciator comes in:
Role Play as the 2nd Assistant, and when directed to investigate, wait 2 minutes and inform MCR that B RR pump has high level of oil in the upper bearing.
SRO Provides a reactivity brief.
Communicates with Real Time Desk and System Operating Center.
Provide direct oversight of power increase.
RO Raises power with Recirc Pump Flow Controllers IAW IPOI-3, Section 4.
Monitors critical plant parameters - power, pressure, level BOP Monitors balance of plant equipment.
Provides peer check for RO during power increase.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 13 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 A Reactor Recirc Pump speed controller fails upscale If called as:
MISC I&C WCC ERT Booth Instructor, after a measurable power rise, and at the direction of the Lead Evaluator:
SINCE the initial value of the ramp has changed (RR FCVs have been adjusted) Look at the current value of the RR17B malfunction, DOUBLE CLICK on RR17B, and set the ramp as follows:
Trigger 1, 350 sec Ramp Time, Initial value to current value, final value of 100.
THEN:
Set Event Trigger 1 TRUE IMF RR17B to 100 over 350 sec This will cause the B Recirc M-G speed controller to ramp up slowly Booth Instructor respond as plant personnel and respond as necessary:
Respond that you will look at the MOORE controller logic for speed control and get back to them soon.
Report that you will call in a licensed operator to take manual control of the locked up recirc scoop tube but it will be about an hour.
Go along with what the crew wants to do, and tell them that ERT will take over the repairs of the B speed control problem.
RO will determine that power is going up by itself, and determine that the B Recirc M-G speed controller is ramping up by itself. He will take the following actions to stop the run away:
Lock the scoop tube of the B recirc M-G speed controller. [Critical]
Enter AOP 255.2, Power/Reactivity Abnormal Change.
SRO will direct and the ROs will perform the following actions per AOP 255.2:
Take any necessary steps to bring the reactor power/reactivity transient under control, including, but not limited to:
o The Scoop Tube Lockup stopped the event SRO will determine if the recirc pump speed mis-match will put them out of compliance with the LPCI Loop Select limits.
TS SR 3.4.1.1 states that the speed of the faster pump shall be 122%
of the speed of the slower pump when operating at 69.4% RTP.
Based on the calculation, the SRO will determine if he is in compliance with TS 3.4.1 Condition C. If not, then has 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore the mis-match within limits, or Trip one of the recirc pumps.
Plot the current position on the power to flow map.
SRO will activate the Event Response Team and ensure that a WRC is written to help mitigate the event. Call Ops Management and REs.
Crew (if the Recirc Flow is outside of the Mismatch limits), will discuss how they will restore the mismatch to within its limits.
Either raise the speed of the unlocked Recirc Pump to match the locked Recirc Pump. OR Send a licensed operator to the Recirc M-G Set room and take manual control of the locked Recirc Pump and lower it to within the limits.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 14 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 RCIC spurious start Booth Instructor:
After the crew has addressed the RR Flow Controller event:
Set Event Trigger 2 TRUE IMF RC08 This will initiate the RCIC Spurious Start After the crew trips the RCIC system:
Set Event Trigger 3 TRUE IMF RC10B This will insert malfunction for thermal overload for MO-2405 (prevents RCIC from being used for injection)
NOTE: This thermal overload will NOT reset.
Booth Instructor responds as plant personnel as necessary.
Role Play: When called as ERT, inform the crew that the ERT will investigate any potential issue with Tech Specs on the Level 2 switches that caused the RCIC spurious start.
CREW Recognizes RCIC start SRO Determines Adequate Core Cooling exists by two independent indications and direct that RCIC be tripped.
Re-enter AOP 255.2, if the crew had exited this procedure already.
Enters TS 3.5.3. A and declares RCIC INOP - 14 day LCO Verifies HPCI operable per STP 3.5.3-01 Notifies the Event Response Team Assesses risk BOP Trips RCIC per Quick Response Card OI 150 QRC 2 and depresses RCIC Manual Turbine Trip PB.
Verifies that MO-2405, RCIC Turbine Stop Valve closes RO Monitors power, pressure and level.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 15 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 B Well Water Pump trips Booth Instructor:
Once the RCIC spurious start event has been addressed, then:
Set Event Trigger 4 TRUE IMF SW21B This will trip the B Well Water pump Booth Instructor respond as plant personnel and respond as necessary.
CREW Responds to Annunciators:
1C21 A11 - Panel 1C23 A1C07A C11-Drywell Cooling Panel trouble BOP Will check annunciator response for 1C23 Reports to SRO that a loss of the B well water pump occurred.
Starts additional Well Water pump and restores WW system parameters to normal SRO Enters AOP 408 for loss of well water Directs starting of additional Well Water pump and restores system parameters.
Directs monitoring drywell temperature and pressure.
Assess change in Risk May direct venting of the DW May start ESW pumps
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 16 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Loss of the 125 VDC panel 1D11 When called to investigate the loss of 1D11 feeder breaker:
If called to investigate any other abnormal conditions for div 1 125vdc Booth Instructor:
When the Well Water event has been addressed, then:
Set Event Trigger 5 TRUE IMF ED13A This initiates a loss of 1D11 Role Play: When called to investigate the 1D11 Feeder breaker, report that the breaker is tripped free (molded case breaker type). 1D11 feeder breaker is 1D1 breaker 06.
Role Play: After a three minute delay, report that you can find no abnormal conditions for the Div 1 125 Vdc system.
CREW Responds to Annunciator 1C08 D-9 A DG Control Power Failure SRO Enters AOP 302.1 - Loss of 125 VDC Power, Tab 1 - Loss of 125 VDC Div 1.
Directs RO to take manual control of reactor level and try to restore to normal band.
Enters TS LCO 3.8.7.B - 8 Hr LCO (1D11)
Directs transferring non-essential power to the startup transformer.
RO Takes manual control of FW and attempts to restore reactor water level to the normal band BOP Transfers non-essential power to the startup transformer per OI 304.1, section 4.2.
Monitors Balance of plant equipment.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 17 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #7 Station Blackout When called as SOC:
When operator called to investigate SBDG:
When called for assistance on the SBDG output breaker:
Booth Instructor:
When the evaluation team is ready to initiate the Station Blackout, then:
Set ED03 Initial Severity to 40 and set Final Severity to 30, with a ramp time of 180 sec.
When the reactor scrams, verify that Event Trigger 7 activates to initiate the Loss of Offsite Power.
Booth Instructor:
Role Play: as plant personnel and use simulator remote functions as necessary to carry out directed actions.
Role Play: Inform DAEC will be priority 1 for power restoration. Estimate is 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for power restoration.
Role Play: When sent to investigate the SBDG output breaker, you see nothing abnormal.
Role Play: Wait five minutes, then inform the crew that electrical maintenance is in the switchgear room.
RO:
Perform IPOI-5 immediate actions.
Notifies the SRO that a loss of feed has occurred (RCIC/HPCI not available)
SRO:
Enter EOP 1 due to RPV level <170".
Use HPCI/RCIC to maintain RPV water level 170-211".
Use SRVs to control RPV pressure (allow LLS to cycle).
Enter, direct and perform AOP 301.1, Station Blackout, Immediate and Follow-up Actions Notify the SOC and request Priority 1 power restoration.
Bypass HPCI/RCIC temperature isolations.
Investigate the loss of the A SBDG and direct emergency maintenance support.
Use SRVs, HPCI and RCIC to start depressurizing the RPV at 80° to 100°/hr and then stop the cooldown when RPV pressure is in the 150
- 200 psig range.
Attempt to use HPCI/RCIC to maintain RPV level per the EOPs.
BOP: (Evaluator CUE: When BOP bypasses RCIC/HPCI Temp Isolations -
inform him that backpanel doors are all simulated open)
SBDG 1G31 will NOT start due to the loss of 1D11 (previous event)
Verifies SBDG 1G21 starts, but the output circuit breaker is mechanically bound up, and will not shut Recognizes that the B SBDG is running without cooling water, and secures B SBDG.
Bypass HPCI/RCIC temperature isolations.
Use SRVs to start depressurizing the RPV at 80° to 100°/hr and then stop the cooldown when RPV pressure is in the 150 - 200 psig range.
Monitor containment parameters
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 18 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #9 (Continued)
When called as plant personnel to perform SBO attachments:
Role-play: as plant personnel performing the SBO attachments and report after being directed:
HPCI doors; Wait 4 minutes and report HPCI doors 204 and 220 are blocked open. ; Report completed in 30 minutes. ; Wait 30 minutes and report complete with no unexpected findings.
Event #8 DG running without cooling water BOP:
SBDG 1G31 will NOT start due to the loss of 1D11 (previous event)
Verifies SBDG 1G21 starts, but the output circuit breaker is mechanically bound up, and will not shut Recognizes that the B SBDG is running without cooling water, and secures B SBDG.
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 19 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #9 HPCI Inverter Failure Booth Instructor:
When HPCI is started (manually or automatically),
Verify that TRIGGER 9 goes TRUE This inserts the HPCI Inverter Trouble condition (HPCI runs at minimum speed and does not inject)
BOP Notes that HPCI has an inverter failure (causes the HPCI turbine to run below the minimum acceptable RPM)
Secures the HPCI system
Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE page 20 of 22 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #10 Leak in containment, Loss of feed, ED required Booth Instructor:
When the evaluation team is ready to initiate the LOCA, then (shortly after SBO):
Set Event Trigger 8 TRUE IMF RR15A to 20% over 600 sec This starts a LOCA in the DW Booth Instructor:
Delete the malfunction and override:
DMF DG02B and DOR DG152-411 This will allow the B SBDG output breaker to work Role Play:
When the crew opens the SRVs, call the control room as Electrical Maintenance and inform them that the B SBDG output breaker is fixed and can be closed in.
Crew:
Notices PC pressure increasing SRO:
Enters EOP-2 for containment control Enters the ALC portion of EOP-1:
Lock out ADS When RPV level lowers to 15", and prior to -25", Emergency depressurization will be directed. (Critical Task)
For ED o Torus level verified >4.5.
o 4 ADS SRVs are opened and verified open.
Directs the B SBDG started and closed onto the bus Directs ECCS pumps be used to restore RPV level to normal level band.
BOP:
Monitors containment parameters, and keeps SRO advised of parameter trends and values.
Opens 4 ADS SRVs When SBDG is carrying its bus, uses ECCS pumps to restore RPV water level (Critical Task)
Scenario Termination Criteria Emergency Depressurization has been completed and RPV water level is rising and above TAF.
- END OF SCENARIO ***
SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________
Rev. _____0________
Scenario 1.doc Page 21 of 22 Correct IC or plant status identified.
Shift turnover forms filled out (both CRS/OSM and NSOE) if required.
Additional documents are prepared (STPs, Work Orders, LCO Paperwork).
Tasks and Objectives have been verified to be correct.
Plant PRA initiating events, important equipment and important tasks are identified.
SOMS tags identified and included in setup instructions.
Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.
Setup files correctly called out.
Malfunction list is accurate.
Override list is accurate.
Remote function list is accurate.
Event triggers are accurate.
Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.
Instructor Activity section is accurate and complete:
Actions are clearly defined for Booth or Floor instructor.
Role-playing is clearly noted.
The sequence of events is completely and concisely narrated even if it takes no instructor action.
Automatic actions that require verification are noted.
Reasonable alternate paths are considered and included.
Event trigger activation is distinguished from narrative text (Bold font)
Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.
Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.
Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.
SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________
Rev. _____0________
Scenario 1.doc Page 22 of 22 Expected Student Response Section is accurate and complete:
Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)
Tasks are clearly noted and properly numbered as appropriate.
Knowledge objectives are clearly noted and properly numbered as appropriate.
Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)
Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)
Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.
Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.
Actions are listed using a logical order; by position and chronology. (N/A as appropriate)
Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.
Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)
For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.
Turnover information (as required) is correct:
Day and shift are appropriate.
Weather conditions do not conflict with malfunctions.
Power levels are correct.
Thermal limit problems and power evolutions are realistic and include a reason for any downpower.
Existing LCOs include start date, remaining time and actions.
Plant Risk Assessment (CDF and Color).
STPs are appropriate for day and shift.
Core Damage Frequency has been properly calculated and listed to 3 decimal places.
Maintenance is realistic for plant conditions.
Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.
SME/Instructor Date SME/Instructor Date
SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________
Rev. _____0________
Crew:
Instructors:
OSM ____________________________ Booth ________________________________
____________________________ Floor __________________________
STA Extra 1C05 ____________________________
1C03 ____________________________
BOP Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________
Rev. _____0________
Crew Comment:
Resolution:
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
Page 2: [1] Comment [N8]
NSP Seek applicable external and internal operating experience to include in the lesson plan.
Where applicable, Training Instructors shall incorporate plant and industry operating experience into lesson plans, simulator guides, or laboratory guide. The review of the operating experience should include the following elements:
- 1) Event description
- 2) Applicability to the site
- 3) Lessons learned
- 4) Application of the operating experience to prevent occurrence, or recurrence.
- 5)
Additional supporting information may be included.
- 6) Operating experience items may also be added as attachments to lesson plan.
Reference the attachment here.
QF-1030-19 Rev. 12 EVALUATION SCENARIO GUIDE (ESG)
SITE: DAEC SCRAM SURVEILLANCE, SBLC LEAK, EARTHQUAKE, TS3.0.3, FRV FAILURE, VENT THE PRIMARY CONTAINMENT, DUAL CONDENSATE PUMP TRIP, STEAM LEAK IN PC, GROUP 3 FAILURE, HPCI CONTROLLER FAILURE 2007 ILT 02 REV. 0 PROGRAM: OPERATIONS COURSE: INITIAL LICENSED OPERATOR 50007 TOTAL TIME:
90 MINUTES Developed by:
Instructor Date Validated by:
SME/Instructor Date Reviewed by:
Operations Manager Date Approved by:
Training Supervisor-Operations Date Retention: Life of policy = 10yrs.
Disposition: Reviewer and Approver Retain in: Training Program File 2007 NRC Scenario 2 Page 1 of 23
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 2 of 23 GUIDE REQUIREMENTS Goal of Training:
The goal of this scenario is to evaluate ILT students during the NRC Exam with 3 man crew.
Learning Objectives:
There are no formal learning objectives Prerequisites:
None Training Resources:
Simulator Simulator Booth Instructor Phone Talker Simulator Floor Instructor
References:
None Commitments:
None Evaluation Method:
Dynamic Simulator Operating Experience:
None Related PRA Information:
Initiating Event with Core Damage Frequency:
N/A due to exam security Important Components:
N/A due to exam security Important Operator Actions with Task Number:
N/A due to exam security Comment [N1]: Fill in the goal for this lesson plan. Based on the learning objectives describe the expected outcome/goal of this training session.
Comment [N2]: Fill in the learning objectives for this lesson plan. Use the information obtained during the design phase.
Comment [N3]: List the courses that need to be completed prior to participating in this training session.
Comment [N4]: List the materials and multi-media needed to perform training. Examples are as follows:
1)furniture arrangement 2)multi-media equipment (VCR, DVD player, monitors, LCD projector, and etc) 3)multi-media software (tapes, CDs, DVDs, disks, and etc) 4)flipcharts, white/black boards 5)markers, pencils, pens, and etc) 6)security clearances 7)equipment and tools 8)number of instructors/guest speakers needed Comment [N5]: List any references used to develop this training session:
1)procedures 2)text Comment [N6]: List any commitments made. INCLUDE recommendations for corrective actions, results of investigations and why the training process was initiated.
Revision 0: List purpose of lesson plan. Revision 1: List reason(s) for development or revision.
Comment [N7]: Include written exams, practical exercises, JPM, OJE, or any other form of evaluating.
Specify method of evaluating individual mastery of learning objectives.
Comment [N8]: Seek applicable external and internal operating experience to include in the lesson plan. Where applicable, Training Instructors shall incorporate plant and industry operating experience into lesson plans, simulator guides, or laboratory guide. The review of the operating experience should include the following elements:
Event description Applicability to the site Lessons learned Application of the operating experience to prevent occurrence, or recurrence.
Additional supporting
... [1]
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 3 of 23 QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
- 1. Leak in SBLC Tank
- 2. Earthquake
- 3. FRV Failure
- 4. Small Steam Leak in Containment requires venting
- 1. Steam leak in Containment (bigger)
- 2. ECCS fails to start on high containment pressure Abnormal Events:
- 1. Earthquake
- 2. Failure to Isolate the vent lineup Major Transients:
- 1. Steam Leak
- 2.
Critical Tasks:
- 1. Crew will have to manually start all ECCS pumps (failed to auto initiate)
- 2. Crew manually isolates the vent lineup (failed to auto isolate)
- 3. Crew will have to initiate DW Sprays
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 4 of 23 SCENARIO
SUMMARY
Current plant operating status:
The plant is operating at 100% power with A SBLC and B CS are out of service for maintenance and are tagged out. They wont be available for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Scenario segments:
The plant is operating at 100% power with A SBLC and B Core Spray pump tagged out when the crew assumes the shift.
The RO will perform the A Manual Scram Surveillance as scheduled. Following the test a leak will occur in the SBLC tank requiring an 8 HR shutdown LCO per TS 3.1.7.B.
An earthquake will occur in the DAEC area. The C RHR pump will inadvertently start and the min flow valve will fail to open requiring the operator to trip the pump. The A CS keepfill system will have a pipe break, which will lead to low pressure and the declaration of the A CS pump INOP. On the post earthquake inspection, the in plant operator will report a small leak on the discharge header of the C RHR pump. The SRO will declare both pumps inoperable per Technical Specifications and determine safety function is maintained but a 3.0.3 shutdown is required.
Once the power reduction is started, one feed regulating valve fails causing a reduction in Reactor Water Level that the BOP will respond and take manual control to stabilize level.
Once the FRV issue is addressed, a small Steam Leak inside Primary Containment will occur, requiring the crew to vent the drywell per OI-573.
When the level is stable both condensate pumps trip, which will result in a reactor scram signal on low level. The reactor will fail to automatically scram and the manual scram pushbutton will also fail, but the Mode Switch can scram the reactor. This will be transparent to the operators if they scram the reactor prior to the automatic setpoint.
The Steam Leak will get substantially larger on the scram. All ECCS will fail to automatically start on high DW pressure, requiring the crew to manually initiate it (Critical Task). The HPCI flow controller is failed at 0 gpm in automatic, but will work in manual.
The drywell/torus vent lineup will fail to automatically isolate. The crew will have to manually isolate the vent lineup (Critical Task).
Drywell Pressure will rise to the point requiring Torus Sprays and Drywell Temperature will rise to require Drywell Sprays (Critical Task).
The scenario ends when the primary containment has been manually isolated, Drywell Sprays are in service, RPV level is being maintained within the normal band.
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 5 of 23 SCENARIO OUTLINE:
BOOTH INSTRUCTOR ACTIONS 1
SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)
1.1 General Instructions
- a.
Restore the IC for ILT-Scenario-2 from the Thumb Drive that it is stored on. This Thumb Drive also has the malfunction and override files on it.
a)
Log onto one of the Computer Terminals using the logon from Lowell b)
With a file manager, go to the \\\\boson\\c$\\opensim directory c)
Rename the Malfunc.dat file to Malfunc-OLD.dat d)
Rename the Malfunc-NEW.dat file to Malfunc.dat e)
Copy the IC file from the thumb drive to the \\\\boson\\ryan\\ops\\ic directory.
f)
Rename the IC file to d_ic.000. This makes the IC number 000 g)
Reset to IC 000.
(1)
Verify Malfunctions (2)
Verify Overrides (3)
Verify Remote functions (4)
Verify event trigger definitions. DO NOT ACCEPT Triggers 20 and 21 yet. These are controlled inside the body of the ESG.
- b.
Place Maintenance In Progress tags on the A SBLC pump and the B CS pump.
- c.
LCO and Safety Function Determination paperwork, for any outstanding LCOs
- d.
Have STP 3.3.1.1-21, Manual Scram Surveillance available for the crew to perform. Markup the STP thru section 7.1. The crew will have to finish the STP section 7.2, RPS Channel B3 Manual Scram Functional Test.
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 6 of 23 1.2 EVENT TRIGGER DEFINITIONS:
Trigger No.
Trigger Logic Statement Trigger Word Description 1-8 Manually Activated N/A 9
PCPDWG.gt. 2.0 Drywell pressure greater than 2.0 psig 10 Event:
ZDIPCPB4.EQ. 1 Command:
DOR ZDIPCPB3 When the Seismic Alarm Acknowledge pushbutton is pushed, delete the override of the Seismic Alarm Test pushbutton to turn the audible alarm off.
20 Event:
ZDIPCHS4303(2)== 2**
Command:
DMF MS24BD DO NOT ACCEPT DURING SETUP When the handswitch for CV 4303 goes to AUTO, Delete malfunction for fails as is
- NOTE-The real value is== 0 but cannot be typed in yet, so this is a way of preventing a lot of typing when it is time to accept these triggers during the ESG.
21 Event:
ZDIPCHS4310(2)== 2**
Command:
DMF MS24AE DO NOT ACCEPT DURING SETUP When the handswitch for CV 4310 goes to AUTO, Delete malfunction for fails as is
- NOTE-The real value is== 0 but cannot be typed in yet, so this is a way of preventing a lot of typing when it is time to accept these triggers during the ESG.
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 7 of 23
1.3 MALFUNCTIONS
Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value Setup AN 1C05A(43) 1C05A (F-03) Annunciator Box (6HX8W) {SBLC Valve Continuity Loss}
As Is ON Setup AN 1C03C(2) 1C03C (A-02) Annunciator Box {B CS pump trip}
As Is ON Setup SL01A Standby Liquid Pump Trip-Pump A TRUE TRUE Setup RH10A RHR A Pump Fail to Auto-Actuate TRUE Setup RH10B RHR B Pump Fail to Auto-Actuate TRUE Setup RH10C RHR C Pump Fail to Auto-Actuate TRUE Setup RH10D RHR D Pump Fail to Auto-Actuate TRUE Setup CS05A Core Spray Pump A-Failure to Auto-Initiate TRUE Setup CS05B Core Spray Pump B-Failure to Auto-Initate TRUE As Dir RP05A Auto Scram Failure 1
TRUE As Dir AN 1C05A(35) 1C05A (E-03) Annunciator Box (6HX8W) {SBLC Tank Level Hi/Lo Level}
15 sec 2
As Is ON As Dir AN 1C03B (36) 1C03B (D-09) Annunciator Box {Torus Hi/Lo Level}
3 Crywolf As Dir AN 1C03A(17) 1C03A (B-08) Annunciator Box (4HX9W) {A CS Discharge Line Lo Pressure}
200 sec 3
As Is ON As Dir FW12B FW Reg Valve Controller Failure (AUTO) FWRV B 300 sec 4
As Is 20 As Dir MS02 Small Steam Leak Inside the Pri Containment (VI) 300 sec 5
0.03 As Dir MS24BD Group 3 Isolation Component Failure(s)-CV-4303 Fail As Is 6
TRUE As Dir MS24AE Group 3 Isolation Component Failure(s)-CV-4310 Fail As Is 6
TRUE As Dir FW02A Condensate Pump Trip -
Pump A 7
TRUE As Dir FW02B Condensate Pump Trip -
Pump B 7
TRUE As Dir SW22A Dw Clg Units Well Water Flow Blockage-Clg Unit 1A 120 8
100
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 8 of 23 Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value As Dir SW22B Dw Clg Units Well Water Flow Blockage-Clg Unit 2A 120 8
100 As Dir SW22H Dw Clg Units Well Water Flow Blockage-Clg Unit 1B 120 8
100 As Dir SW22I Dw Clg Units Well Water Flow Blockage-Clg Unit 2B 120 8
100 As Dir SW22G Dw Clg Units Well Water Flow Blockage-Clg Unit 7A 120 8
100 As Dir SW22N Dw Clg Units Well Water Flow Blockage-Clg Unit 7B 120 8
100 As Dir HP03 HPCI Flow Controller Fails (VI) 120 9
0
1.4 OVERRIDES
Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Setup CS HS-2123(2)
Pump 1P211B (Green)
OFF Setup CS HS-2123(1)
Pump 1P211B (White)
OFF Setup SL XS-2618A(1)
Squib Valve Ready-W(White)
OFF Setup SL HS-2613A(1)
A SBLC Pump 1P-230A (Green)
OFF Setup SL HS-2613A(2)
A SBLC Pump 1P-230A (Red)
OFF As Dir ZLORPC71AS3A Manual Scram PB System A 1
OFF OFF As Dir ZLORPC71AS3B Manual Scram PB System B 1
OFF OFF As Dir ZAOSLLI2600A SBLC Tank Level Indicator 120 sec 2
As Is
.65 As Dir PC01G Seismic Alarm.01G(A) 0 0
3 OFF ON As Dir PCOBE Seismic Alarm OBE(A) 0 0
3 OFF ON As Dir PCDBE Seismic Alarm DBE(A) 0 0
3 OFF OFF As Dir PCPB3 Seismic Alarm System Test 0
0 3
NORM TEST As Dir ZDIRHHS2018(4)
RHR Pump 1P-229C Hand Switch 2
3 TRUE
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 9 of 23 File: EARTHQUAKE (inserted during the scenario)
Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Per SEG: LO PC 01G Seismic Alarm System.01G (A)
ON Per SEG: LO PC OBE Seismic Alarm System OBE (A)
ON Per SEG: DI PC PB3 Seismic Alarm System Test TEST Per SEG: AO PC LI-4397A Suppression Pool Water Level
.65 Per SEG: AO PC LI-4397B Suppression Pool Water Level
.65 Per SEG: AO PCLR4397A Water Level Torus Pen 2
.65 Per SEG: AO PC LR-4397B Water Level Drywell Pen 2
.65 Per SEG: AO PC LR-4385B Torus Water Level Pen 2
.45 Per SEG: AO PC07(2)
Narrow Range Torus Water Level
.45 Per SEG: AO PC07(3)
Narrow Range Torus Water Level
.45 Per SEG: AO PC LI-4396A Drywell Water Level
.12 Per SEG: AO PC LI-4396B Drywell Water Level
.12 Per SEG: AO PC LR-4396A Water Level Torus Pen 1
.12 Per SEG: AO PC LR-4396B Water Level Drywell Pen 1
.12 Per SEG: AO SW LR-4395A A ESW/RHRSW Pit Level
.65 Per SEG: AO SW LR-4395B B ESW/RHRSW Pit Level
.5 Per SEG: AO PC LR-4384C Torus Level Pen 3
.45 File: EARTHQUAKE1 (inserted during the scenario)
Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Per SEG: AO PC LI-4397A Suppression Pool Water Level
.55 Per SEG: AO PC LI-4397B Suppression Pool Water Level
.55 Per SEG: AO PCLR4397A Water Level Torus Pen 2
.55 Per SEG: AO PC LR-4397B Water Level Drywell Pen 2
.55 Per SEG: AO PC LR-4385B Torus Water Level Pen 2
.52 Per SEG: AO PC07(2)
Narrow Range Torus Water Level
..52 Per SEG: AO PC07(3)
Narrow Range Torus Water Level
.52 Per SEG: AO PC LI-4396A Drywell Water Level
.08 Per SEG: AO PC LI-4396B Drywell Water Level
.08 Per SEG: AO PC LR-4396A Water Level Torus Pen 1
.08 Per SEG: AO PC LR-4396B Water Level Drywell Pen 1
.08
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 10 of 23 Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Per SEG: AO SW LR-4395A A ESW/RHRSW Pit Level
.52 Per SEG: AO SW LR-4395B B ESW/RHRSW Pit Level
.6 Per SEG: AO PC LR-4384C Torus Level Pen 3
.52 1.5 REMOTE FUNCTIONS:
Time Remote No.
Remote Title Delay Ramp ET Initial Value Final Value Setup CS04 Manual Oper of B CS Pump (1P-211B) Breaker OPEN FLOOR INSTRUCTOR ACTIONS 2
Simulator Pre-brief:
2.1 Individual position assignments
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 2007 NRC Scenario 2 Page 11 of 23 4
TURNOVER INFORMATION Day of week and shift Thursday Dayshift Weather conditions Fair and breezy (Plant power levels) 97% Pwr MWT 1844 MWE 632 CORE FLOW 46.5 Thermal Limit Problems/Power Evolutions None Plant Risk Status CDF 2.2E-5 Color YELLOW Existing LCOs, date of next surveillance A SBLC pump tagged out for maintenance B Core Spray pump tagged out for maintenance STPs in progress or major maintenance STP 3.3.1.1-21 was started last shift, but not completed. You will have to finish the STP when you take the shift.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment None Comments, evolutions, problems, core damage frequency, etc.
Scaffold being built in SBLC area to rig out the A SBLC pump.
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 12 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE COMPLETE TURNOVER:
Provide Shift Turnovers to the SRO and ROs.
- a.
Review applicable current Plant Status
- b.
Review relevant At-Power Risk status
- c.
Review current LCOs not met and Action Requirements
- d.
Verify crew performs walk down of control boards and reviews turnover checklists.
Get familiar with plant conditions.
SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 13 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 A Manual Scram Surveillance Booth Instructor:
AFTER the surveillance is complete, and the 1/2 scram is RESET, then insert the ATWS malfunctions by:
Insert Trigger 1 TRUE This overrides the Manual Scram PBs in OFF, and inserts Failure to Auto Scram (this sets up the mode switch to scram).
SRO Gives Pre-job brief to coordinate and discuss evolution RO Completes A Manual Scram Surveillance (section 7.2 needs to be completed)
BOP Acts as peer checker for RO
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 14 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 SBLC Tank Leak Booth Instructor:
When the Manual Scram event has been completed, then initiate the SBLC tank leak:
Set TRIGGER 2 TRUE This ramps the SBLC Tank Level Indicator from 85% to 65% in 120 sec and after a 15 sec TD alarms the SBLC Tank Lo Level ROLE PLAY as the person sent to investigate:
Riggers were rigging the SBLC pump and lost control of the load. A small hole has been created in the suction piping to the SBLC pumps, and is isolable by shutting the SBLC pump isolation valve, V-26-01.
Ask if the crew wants you to unlock and shut V-26-01 to isolate the leak.
RO Notices the SBLC tank low level condition Refers to ARP 1C05A (E-3)
BOP Sends an in-plant operator to check out the SBLC area Might call Radwaste and inform them of the borated water leak.
Might dispatch Chemistry to investigate/respond to the borated water leak.
SRO Refers to Technical Specifications 3.1.7.B (8 Hour Action statement to restore one subsystem to operable status)
Notifies Duty Manager / OM / OSM of issue, Activates the Event Response Team Setup for the Earthquake Booth Instructor Utilize both instructor station screens and using the expert command function do the following:
On one screen expert command window type in ror earthquake.
DO NOT hit enter.
On the other screen expert command window type ror earthquake1.
DO NOT hit enter.
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 15 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 Small Earthquake Booth Instructor:
When ready to start the earthquake event:
Hit ENTER on the monitor that has ROR EARTHQUAKE typed in the expert command window.
Set Event Trigger 3 TRUE (This starts the earthquake alarm)
When the seismic alarm sounds, hit ENTER on the monitor that has ROR EARTHQUAKE1 typed in the expert command window.
Select the LAST 14 OVERRIDES and DELETE THEM (these are the overrides that place level recorders HIGH for the sloshing in the TORUS, ESW pits, etc.
DELETE the OVERRIDE FOR the C RHR Handswitch in START WHEN the RO acknowledges the Seismic Alarm at 1C35, OBSERVE that ET10 activates and the Seismic alarm silences; if not, DELETE PCPB3.
Floor Instructor Inform the crew that they felt the building shake.
[CONTINUED ON NEXT PAGE]
SRO Direct operators to perform immediate actions of AOP 901.
Determine no hazardous condition exists on the refuel floor.
Direct operators to perform the follow-up actions of AOP 901.
Commence shutting down the reactor to be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Direct the inspection and radiological surveying/sampling all plant areas and required systems.
Direct surveying and sampling of high priority areas, structures, systems and components.
Verify any heavy loads being handled (within the turbine building or LLRWSF) are landed in safe location.
Direct Health Physics to perform radiation surveys of the normally accessible areas inside main DAEC Buildings and the site grounds.
Direct chemist to review KAMAN data and perform sensor checks.
Direct the inspection and radiological surveying/ sampling of all plant areas and required systems in accordance with AOP 901, Earthquake.
Have Radwaste monitor for abnormal pump ups or rising leak rates.
RO Respond to Earthquake condition.
Monitor Reactor power, pressure and level on 1C05.
Monitor for any Control Rod out of position.
[CONTINUED ON NEXT PAGE]
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 16 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Small Earthquake (CONTINUED)
Booth Instructor Role Play: As the crew sends various people in the plant instructions, respond that you will do the requested actions. As NSPEOs, perform desired investigations.
Booth Instructor:
ROLE PLAY: When an appropriate time has passed, call the control room and inform them that there is a water leak coming off of the discharge pipe of the C RHR pump. The leak is downstream of the discharge isolation valve for the pump.
ROLE PLAY: When sent to investigate the Core Spray system, report a pipe leak on the discharge pipe of the A CS pump in the SECR. The leak is downstream of the discharge isolation valve for the pump.
BOP Acknowledge seismic alarm and reset.
Notice and inform crew of RHR pump spurious start Notice and inform crew of RHR min flow valve SHUT Secure C RHR pump Dispatch an operator to check the event indicators on accelographs.
Verify RWS availability.
Monitor Process and Area Radiation Monitoring System channels on Panels 1C10 and 1C11.
Monitor Torus Water Level on Panels 1C03, 1C29, 1C09, and SPDS.
Monitor Area Water Levels on Panel 1C21.
Monitor water levels of Drywell Equipment and Floor Drain sumps.
Take a complete set of NSPEO and control room logs and compare them with prior logs specifically to look for indications of hidden damage, system leakage, or unusual indications.
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 17 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 Power Reduction to Comply with Tech Spec 3.0.3 Booth Instructor:
Once the CRS determines that TS 3.0.3 applies to situation, IF the crew is taking too long to downpower, call the crew as the Ops Manager and inform the crew that you want them to start lowering power promptly.
SRO:
Perform brief for downpower May direct the circuit breakers for the A CS and C RHR pump to be racked down.
RO:
Perform downpower maneuver BOP:
Peer check downpower maneuver Event #5 FRV Controller Failure Booth Instructor:
When the Exam Team is satisfied with the power reduction, initiate the FRV controller failure by:
Set TRIGGER 4 TRUE This will Fail the B FWRV controller to 20% over 5 minutes RO
- Recognizes and reports Feedwater Level control is not responding as expected.
- Takes manual control of FWRVs by placing the B FWRV in manual.
- Enters AOP 644 Feedwater/Condensate Malfunctions
- Directs an RO to take manual control of B FRV Feedwater controller to restore reactor water level (186 to 195 inches):
- Monitors and supervises the ROs.
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 18 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Small Steam Leak/Vent PC Booth Instructor:
When the FRV Controller Failure has been addressed, initiate the small steam leak by:
Set TRIGGER 5 TRUE This will initiate a small steam leak to force the operators to vent the Primary Containment Booth Instructor:
Before moving on to the next event, wait for the crew to cycle the vent valves open (may have to increase the MS02 leak size), then fail the vent valves AS IS by:
Set TRIGGER 6 TRUE This inserts CV 4303 and CV 4310 FAILURE AS IS.
Booth Instructor:
Change the Event Triggers 20 and 21 to
== 0 and then accept event triggers 20 and 21. This will allow the automatic deletion of the Vent Valves Failure based upon the valve handswitch position.
Booth Instructor:
WHEN the crew REPOSITIONS the DW Vent Valve Handswitches to CLOSE, verify that malfunctions MS24BD and MS24AE DELETE.
Crew:
Notices rising DW pressure SRO:
Enters AOP 573, Primary Containment Control o Directs venting of the DW IAW OI 573, Primary Containment Control, to maintain DW pressure between 1.0 and 1.5 psig o Directs Chemistry to evaluate the isotopic makeup of the Drywell atmosphere/sump discharge to assist in determining the source of the leak in the DW BOP:
Vents the primary containment per OI 573 o Verify that NW and SOUTH DRYWELL AREA HI RANGE RAD MONITORS RIM-9184A and RIM-9184B on 1C09 are reading less than 20 R/hr.
o Start one train of the Standby Gas Treatment System with the Test pushbutton per OI 170.
o Monitor drywell and torus pressure indications on 1C03 and pressure trend indications on 1C09 and 1C29.
o Line up to vent drywell [torus] by positioning the following switch (Valves will indicate dual position):
HS-4303, OUTBD DRYWELL VENT ISOL CV-4303 AUTO/OPEN HS-4301, OUTBD TORUS VENT ISOL CV-4301 AUTO/OPEN o Cycle valves as necessary to maintain drywell pressure between 1.0 and 1.5 psig.
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 19 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Condensate Pumps Trip Event 7 (C-RO, C-SRO)
Booth Instructor:
When the primary containment vent valves are failed as is, trip both condensate pumps by:
Set TRIGGER 7 TRUE This will trip both condensate pumps SRO:
Identifies the loss of FW Orders manual reactor scram Enters EOP 1 due to <170 RPV water level Orders RPV level and pressure be controlled IAW EOP 1 RO:
Identifies the loss of FW SCRAMS the reactor IAW ARP 1C06A A-12/13 Controls RPV water level using RCIC/HPCI Carries out IPOI 5 Scram actions BOP:
Sends in-plant operator to investigate condensate pump trips
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 20 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Steam Leak in Primary Containment (bigger)
Event 8 (M-ALL)
Booth Instructor:
After the scram, increase the DW steam leak by:
Modify MS02 Malfunction to:
Ramp to 2 over 120 secs This ramps up the DW steam leak AND Set TRIGGER 8 TRUE This ramps in DW Coolers flow blockage to help drive DW temp up SRO:
Enters EOP 2 on Primary Containment parameters Orders Torus Sprays prior to DW pressure exceeding 11 psig Orders DW Sprays prior to DW temperature exceeding 280F.
RO:
BOP:
Identifies rising DW pressure Communicates trends and values to the SRO Places RHR in torus spray lineup Places DW sprays in service Drywell Vent Valves Fail to Isolate Event 9 (C-BOP)
Booth Instructor:
The DW vent valves are already stuck open from a previous event.
Booth Instructor:
Watch the CV 4303 and CV 4310 using the soft-panel displays:
WHEN the crew REPOSITIONS the DW Vent Valve Handswitches to CLOSE, VERIFY malfunctions MS24BD and MS24AE delete so that the valves will CLOSE SRO:
Identifies ECCS pumps do NOT automatically start on 2 psig signal Orders BOP to start all available Core Spray pumps and RHR pumps with their control handswitches BOP:
Notices ECCS pumps do NOT automatically start on 2 psig signal Starts all available Core Spray pumps and RHR pumps with their control handswitches
Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE 2007 NRC Scenario 2 page 21 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE HPCI Flow Controller Failure Event 9 (C-BOP)
Booth Instructor:
Verify that trigger 9 goes active at 2 psig DW pressure. This will fail the HPCI AUTOMATIC flow controller to 0 over 120 secs.
BOP Identifies the failed HPCI Automatic controller and transfers the controller to manual Identifies that HPCI responds in MANUAL control Communicates status of HPCI to SRO Coordinates control of RPV water level with RO Controls HPCI system with MANUAL control o
Ensures HPIC remains above 2000 rpm Scenario Completion Criteria:
Primary Containment has been manually isolated DW Sprays are in service maintaining temperature below 280F RPV water level is being maintained in the normal band
- END OF SCENARIO ***
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
2007 NRC Scenario 2 Page 22 of 23 Correct IC or plant status identified.
Shift turnover forms filled out (both CRS/OSM and NSOE) if required.
Additional documents are prepared (STPs, Work Orders, LCO Paperwork).
Tasks and Objectives have been verified to be correct.
Plant PRA initiating events, important equipment and important tasks are identified.
SOMS tags identified and included in setup instructions.
Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.
Setup files correctly called out.
Malfunction list is accurate.
Override list is accurate.
Remote function list is accurate.
Event triggers are accurate.
Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.
Instructor Activity section is accurate and complete:
Actions are clearly defined for Booth or Floor instructor.
Role-playing is clearly noted.
The sequence of events is completely and concisely narrated even if it takes no instructor action.
Automatic actions that require verification are noted.
Reasonable alternate paths are considered and included.
Event trigger activation is distinguished from narrative text (Bold font)
Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.
Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.
Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
2007 NRC Scenario 2 Page 23 of 23 Expected Student Response Section is accurate and complete:
Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)
Tasks are clearly noted and properly numbered as appropriate.
Knowledge objectives are clearly noted and properly numbered as appropriate.
Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)
Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)
Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.
Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.
Actions are listed using a logical order; by position and chronology. (N/A as appropriate)
Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.
Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)
For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.
Turnover information (as required) is correct:
Day and shift are appropriate.
Weather conditions do not conflict with malfunctions.
Power levels are correct.
Thermal limit problems and power evolutions are realistic and include a reason for any downpower.
Existing LCOs include start date, remaining time and actions.
Plant Risk Assessment (CDF and Color).
STPs are appropriate for day and shift.
Core Damage Frequency has been properly calculated and listed to 3 decimal places.
Maintenance is realistic for plant conditions.
Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.
SME/Instructor Date SME/Instructor Date
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
Crew:
Instructors:
OSM ____________________________ Booth ________________________________
____________________________ Floor __________________________
STA Extra 1C05 ____________________________
1C03 ____________________________
BOP Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
Crew Comment:
Resolution:
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
Page 2: [1] Comment [N8]
NSP 09/07/2007 11:18:00 AM Seek applicable external and internal operating experience to include in the lesson plan.
Where applicable, Training Instructors shall incorporate plant and industry operating experience into lesson plans, simulator guides, or laboratory guide. The review of the operating experience should include the following elements:
Event description Applicability to the site Lessons learned Application of the operating experience to prevent occurrence, or recurrence.
Additional supporting information may be included.
Operating experience items may also be added as attachments to lesson plan.
Reference the attachment here.
QF-1030-19 Rev. 12 EVALUATION SCENARIO GUIDE (ESG)
SITE: DAEC SWAP CRD, SPURIOUS GROUP 5, CRD PUMP TRIP, GSW PUMP TRIP W/ NO AUTO START, TURBINE HI HI VIBES, HIGH POWER ATWS W/ GROUP 1, BOTH FRVS LOCKUP, SCRAM-RESET-SCRAM STOPS WORKING ESG ILT 03 REV. 0 PROGRAM: OPERATIONS COURSE: INITIAL LICENSED OPERATOR 50007 TOTAL TIME:
90 MINUTES Developed by:
Instructor Date Validated by:
SME/Instructor Date Reviewed by:
Operations Manager Date Approved by:
Training Supervisor-Operations Date Retention: Life of policy = 10yrs.
Disposition: Reviewer and Approver Retain in: Training Program File 2007 NRC Scenario 3 Page 1 of 20
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #3, Rev. 0 2007 NRC Scenario 3 Page 2 of 20 GUIDE REQUIREMENTS Goal of Training:
The goal of this scenario is to evaluate ILT students during the NRC Exam with 3 man crew.
Learning Objectives:
There are no formal learning objectives Prerequisites:
None Training Resources:
Simulator Simulator Booth Instructor Phone Talker Simulator Floor Instructor
References:
None Commitments:
None Evaluation Method:
Dynamic Simulator Operating Experience:
None Related PRA Information:
Initiating Event with Core Damage Frequency:
N/A due to exam security Important Components:
N/A due to exam security Important Operator Actions with Task Number:
N/A due to exam security Comment [N1]: Fill in the goal for this lesson plan. Based on the learning objectives describe the expected outcome/goal of this training session.
Comment [N2]: Fill in the learning objectives for this lesson plan. Use the information obtained during the design phase.
Comment [N3]: List the courses that need to be completed prior to participating in this training session.
Comment [N4]: List the materials and multi-media needed to perform training. Examples are as follows:
furniture arrangement multi-media equipment (VCR, DVD player, monitors, LCD projector, and etc) multi-media software (tapes, CDs, DVDs, disks, and etc) flipcharts, white/black boards markers, pencils, pens, and etc) security clearances equipment and tools number of instructors/guest speakers needed Comment [N5]: List any references used to develop this training session:
2procedures 3text Comment [N6]: List any commitments made. INCLUDE recommendations for corrective actions, results of investigations and why the training process was initiated.
Revision 0: List purpose of lesson plan. Revision 1: List reason(s) for development or revision.
Comment [N7]: Include written exams, practical exercises, JPM, OJE, or any other form of evaluating.
Specify method of evaluating individual mastery of learning objectives.
Comment [N8]: Seek applicable external and internal operating experience to include in the lesson plan. Where applicable, Training Instructors shall incorporate plant and industry operating experience into lesson plans, simulator guides, or laboratory guide. The review of the operating experience should include the following elements:
- 1.
Event description
- 2.
Applicability to the site
- 3.
Lessons learned
- 4.
Application of the operating experience to prevent occurrence, or recurrence.
- 5.
Additional supporting
... [1]
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #3, Rev. 0 2007 NRC Scenario 3 Page 3 of 20
- 1. SCENARIO
SUMMARY
Current plant operating status:
The plant is operating at 100% power. The plant is in a normal configuration with A Core Spray pump out of service. After taking the watch, swap the CRD Pumps to obtain an oil sample on the B CRD pump.
Scenario segments:
The plant is operating at 100% power when the crew assumes the shift. The plant is in a normal configuration with A Core Spray pump out of service.
After taking the watch the RO swaps the CRD Pumps for routine maintenance. The RO performs the procedure for starting the standby CRD Pump and securing the running pump for maintenance. The breaker is tagged out preventing it from being immediately returned to service.
A spurious full Group 5 PCIS isolation occurs. This will cause the RWCU system to isolate. One PCIS Group 5 valve fails to isolate requiring manual actions to shut.
Technical Specifications 3.6.1.3 condition A and TRM 3.3.4 condition A will be entered for this PCIS group failure.
Due to a problem with the newly started CRD Pump, it trips and at least three HCU Accumulator Pressures fall to less than the Tech Spec required setpoint. The SRO enters TS LCO 3.1.5. Conditions A and B and orders the return to service of the tagged out CRD Pump.
After technical specification determination one of the operating General Service Water Pumps trips without the standby pump automatically starting, which causes the BOP to start the standby pump. The flow perturbation causes a flow blockage in the in service Turbine Lube Oil Coolers causing Lube Oil Temperature to rise. Subsequently the elevated LO temperature causes the main turbine vibration to rise activating the high vibration alarm and the RO will perform a rapid power reduction. The vibration problem continues, requiring a manual reactor scram be performed.
When the reactor is scrammed, the control rods fail to insert, requiring the crew to enter EOP ATWS and attempt to insert rods per Rod Insertion Procedures (RIPs) for Hydraulic ATWS. A spurious Group 1 isolation occurs requiring level and pressure control with RCIC and SRVs. SBLC must be initiated to lower power before Torus temperature reaches 110 degrees F (BIIT) (Critical Task).
Per EOP ATWS, injection must be Terminated and Prevented to lower level (Critical Task). Before the FRVs fully close, they both lockup. As the RO attempts to terminate and prevent injection, compensatory actions are required such as tripping of the feedwater pumps or closure of the block valves to prevent injection.
After some success with repeated scrams and scram resets this method fails and prevents the insertion of rods. Control rods will be required to be manually inserted (Critical Task).
The scenario ends when the control rods are being inserted, RPV water level is being restored and maintained between -25 and the level set in EOP-ATWS actions.
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #3, Rev. 0 2007 NRC Scenario 3 Page 4 of 20 SCENARIO OUTLINE:
BOOTH INSTRUCTOR ACTIONS 1
SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)
1.1 General Instructions
- a.
Identify any extra copies of student materials (STPs, OIs) that are needed for this training activity.
- b.
Reset to IC 20
- c.
Restore the IC for ILT-Scenario-3 from the Thumb Drive that it is stored on. This Thumb Drive also has the malfunction and override files on it.
a)
Log onto one of the Computer Terminals using the logon from Lowell b)
With a file manager, go to the \\\\boson\\c$\\opensim directory c)
Rename the Malfunc.dat file to Malfunc-OLD.dat d)
Rename the Malfunc-NEW.dat file to Malfunc.dat e)
Copy the IC file from the thumb drive to the \\\\boson\\ryan\\ops\\ic directory.
f)
Rename the IC file to d_ic.000. This makes the IC number 000 g)
Reset to IC 000.
(1)
Verify Malfunctions (2)
Verify Overrides (3)
Verify Remote functions (4)
Verify event trigger definitions.
- d.
Control panel setups, including valves/equipment to tag out
- e.
Mark up OI255, section 6.1, steps 1a. thru 1c. are complete.
- f.
Verify that OI-880, section J-1 is available for the crew in the hanging file folders.
- g.
Verify that the simulator driver has a copy of OI-880 section J-1 to use.
- h.
LCO and Safety Function Determination paperwork, for any outstanding LCOs 1.2 EVENT TRIGGER DEFINITIONS:
Trigger No.
Trigger Logic Statement Trigger Word Description 1-5, 7, 11 Manually Initiated N/A 6
ZAOFWZI1579.LT. 0.30.OR.
ZAOFWZI1621.LT. 0.30 When the A FRV Position Indicating Meter is less than 15%, trigger 6 goes true (this locks up the FRVs before they close) 9 ZDIRPC71AS1(1)== 1 When the Mode Switch is taken to SHUTDOWN, trigger 9 goes true to insert spurious group 1.
15 ZDIADPB4401== 1 OR ZDIADPB4407== 1 When either of the ADS override switches are placed in override, trigger 15 goes true.
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #3, Rev. 0 2007 NRC Scenario 3 Page 5 of 20
1.3 MALFUNCTIONS
Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value Setup AN 1C03A(9) 1C03A (A-09) Annunciator Box (4HX9W) {A CS Pump Trip or Motor Overload}
TRUE Setup RP05F Hydraulic Lock Scram Discharge Volume TRUE Setup MS28C Group 5 Isolation Valve(s)
Fail(s) to Close-MO2740 TRUE Setup RD24 All Rods Stuck TRUE Setup SW37C GSW Pump 1P89C Fail To Auto-Actuate TRUE As Dir MS27A Spurious Group 5 Isolation-Loose Connection BB23 2
TRUE As Dir MS27B Spurious Group 5 Isolation-Loose Connection BB24 2
TRUE As Dir RD11A CRD Hydraulic Pump Trip-Pump A 3
TRUE As Dir SW01B General Service Water Pump Trip-Pump B 4
TRUE As Dir SW04B Main Turb Lube Oil Coolers GSW FLW Blockage-CLR B 300 4
0 70 As Dir TU01A Main Turbine Bearing #1 High Temperature 300 5
0 80 As Dir TU01E Main Turbine Bearing #5 High Temperature 300 5
0 80 As Dir TU02A Main Turbine Bearing #1 High Vibration 300 5
0 80 As Dir TU02E Main Turbine Bearing #5 High Vibration 300 5
0 80 As Dir FW16A FW Reg Valve Lockup-FWRV A 6
TRUE As Dir FW16B FW Reg Valve Lockup-FWRV B 6
TRUE As Dir RP03 Spurious Scram 7
TRUE As Dir MS19A Spurious Group I Isolation-Relay A71-K7A 15 TRUE As Dir MS19B Spurious Group I Isolation-Relay A71-K7B 15 TRUE As Dir RD25 All Rods Unstuck 11 TRUE
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #3, Rev. 0 2007 NRC Scenario 3 Page 6 of 20
1.4 OVERRIDES
Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Setup CS HS-2103(1)
Pump 1P-211A (White)
As Is OFF Setup CS HS-2103(2)
Pump 1P-211A (Green)
As Is OFF Setup CS HS-2103 Pump 1P-211A STOP Setup CS HS-2103(3)
Pump 1P-211A (Amber)
OFF As Dir RD HS-1807B CRD Pump 1P-209B 1
OFF As Dir RD HS-1807B(1)
CRD PUMP 1807B Breaker Tripped (Green) 1 OFF As Dir RD HS-1807B(2)
CRD Pump 1807B Breaker Tripped (White) 1 OFF As Dir RD HS-1807B(3)
CRD Pump 1807B Breaker Tripped (Red) 1 OFF As Dir RD HS-1830 DRV WTR Pressure Control Valve 9
NORM 1.5 REMOTE FUNCTIONS:
Time Remote No.
Remote Title Delay Ramp ET Initial Value Final Value Setup CS03 Manual Oper of A CS Pump (1P-211A Breaker)
As Is OPEN FLOOR INSTRUCTOR ACTIONS 2
Simulator Pre-brief:
2.1 Individual position assignments
QF-1030-19 Rev. 12 ESG 2007 NRC ILT #3, Rev. 0 2007 NRC Scenario 3 Page 7 of 20 4
TURNOVER INFORMATION Day of week and shift Wednesday Dayshift Weather conditions Fair Sunny (Plant power levels) 97% Pwr MWT 1850 MWE 635 CORE FLOW 46.5 Thermal Limit Problems/Power Evolutions None Plant Risk Status CDF 7.95E-6 Color GREEN Existing LCOs, date of next surveillance A Core Spray pump OOS. Day 2 of 7. Expected return to service - 2 days.
STPs in progress or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Need to switch running CRD pumps after turnover for oil sample. WCC waiting to hang clearance on the B CRD pump for the oil sample, so call them as soon as you get the pumps swapped.
Two NSPEOs are dedicated for the CRD task Comments, evolutions, problems, core damage frequency, etc.
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 8 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE COMPLETE TURNOVER:
Provide turnover information to the SRO and the ROs:
- a.
Review applicable current Plant Status
- b.
Review relevant At-Power Risk status
- c.
Review current LCOs not met and Action Requirements
- d.
Verify crew performs walk down of control boards and reviews turnover checklists.
Crew:
Walkdown the panels to familiarize themselves with the status of the simulator
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 9 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Swap CRD Pumps Booth Instructor:
Role Play: Remove & Restore A & B reference leg backfill as requested. (NOT SIMULATED) Use OI 880, section J-1 to do this... there is MCR interface in this procedure (the RPV water level selector switch has to be moved, as well as relays verified)
Role Play: Perform local CRD A pump checks - oil level, discharge valve open -
as requested.
Examiner CUE:
When BOP is requested to check the relays energized on back panel 1C18 and proceeds to the panel location, provide a cue that the relays that need to be verified are energized.
Booth Instructor:
When the crew has swapped the CRD pump, wait until the crew has called the WCC to inform them they can hang the clearance before proceeding to the next event. If the crew does not do this, then:
Role Play: Call the control room as the WCC, and ask if they have the B CRD pump off and ready to be tagged out.
SRO Gives Pre-job brief to coordinate and discuss evolution Directs swapping CRD pumps form B to A RO Performs OI 255 - CRD Hydraulic system, Section 6.1 to swap pumps Makes page announcement to stand clear while starting pump Starts the A CRD pump Restores reference leg backfill by using OI 880 - Non Nuclear Instrumentation Section J.1. - Isolates and restores reference leg backfill BOP Performs peer check of RO actions.
Per OI 880 when requested - verifies relays C31A-K003 and C31A-K-004 energized on panel 1C18.
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 10 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Swap CRD Pumps (CONTINUED)
Role Play: When the control room informs the WCC they can hang the clearance on the B CRD pump, inform them you will send out the NSPEO, and he will be opening the B CRD pump breaker. Instruct them to hang a Maintenance in Progress Tag on B CRD pump.
Booth Instructor:
Simulate Racking Down the B CRD pump breaker by:
Set TRIGGER 1 TRUE This will override the Green and White lights for the B CRD pump, as well as override the B CRD pump handswitch to OFF.
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 11 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Spurious incomplete Group 5 PCIS isolation Booth Instructor:
When the CRD pump has been de-energized, then initiate the next event by:
Set TRIGGER 2 TRUE This will result in a spurious FULL Group 5 (RWCU) isolation, with a failure of MO-2740 to shut.
Role Play: When called about the status of the RWCU C/D beds, wait 5 minutes, and call back to inform the crew that the RWCU beds are in hold, and the lineup is the normal lineup for the isolated condition.
CREW Recognizes Group 5 isolation SRO Directs response to annunciator 1C05B - E-8 PCIS Group 5 Isolation initiated.
Directs closure of RWCU valve MO-2740 Enters TS 3.6.1.3. - Condition A for an inoperable valve - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> TRM 3.3.4 Instrumentation, Condition A - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> May call chemistry to verify conductivity monitoring is on recirc RO Monitors Reactor power, Pressure and Level BOP Recognizes an incomplete Group 5 isolation has occurred.
Recognizes a Full RWCU isolation should have occurred but did not and Closes RWCU valve MO-2740 Directs the 2nd Assistant to verify the status of RWCU C/D beds (ensure they went into hold properly.)
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 12 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 Running CRD Pump trips Booth Instructor:
When the Group 5 event has been addressed, initiate the next event by:
Set TRIGGER 3 TRUE This will insert an overcurrent trip of the A CRD pump Role Play: When requested to check pump locally report that the breaker is tripped on overcurrent and the pump appears to have no damage Role Play: When requested to check accumulator pressure, report that local pressure is between 900 and 935 psig for all alarming HCUs.
Role Play: When the WCC is called to restore the B CRD pump, inform them that you will get right on getting the pump back. Estimate 15 minutes to restore.
Role Play: Wait until after TS are addressed by the SRO, before reporting back as maintenance that the B CRD pump is ready to have the B CRD circuit breaker racked up. (Takes 11 mins for HCU alarms to come in.)
Booth Instructor:
When the crew orders you to rack up the breaker for the B CRD pump, select the FOUR OVERRIDES and delete them to simulate racking up the B CRD breaker.
SRO Directs response to the following annunciator:
1C05 A-6 A CRD PUMP TRIP OR MOTOR OVERLOAD Directs a call to work control center to return the B CRD for service Directs response to subsequent annunciator:
1C05 E-6 CRD DRIVE MECH HI TEMP When Accumulator Alarms are received and after the accumulators are checked locally enters TS 3.1.5.B. - within 1 hr it must be recharged or declared inoperable.
Directs start of the B CRD pump RO Recognizes trip of A CRD pump Reviews 1C05 A-6 annunciator response Reports Accumulator Alarms as they come in Coordinates with field operator and Starts B CRD pump BOP Monitors Reactor Power Pressure and Level Directs field operator to check local indications (breaker and pump)
Checks CRD Mech temperatures on back panel Peer checks RO on CRD pump start
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 13 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 (cont)
Running CRD Pump trips Booth Instructor:
Role Play: When directed to throttle the CRD pump discharge valve 1/2 turn open, then close the CRD discharge valve (using simvue) to 20% open. (V-17-10)
Role Play: When directed to slowly open the CRD pump discharge valve (V-17-10),
open the valve using a 120 second ramp.
Role Play: When directed to vent both CRD pump discharge filters, wait 2 minutes, and call the crew to inform them that the CRD pump discharge filters are vented.
Role Play: If asked to verify HCU pressures AFTER the pump is running, then wait approximately 4 minutes, and inform the crew that all HCU pressures have returned to normal.
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 14 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 One of the running GSW Pumps trip.
Standby pump fails to auto start.
Booth Instructor:
When the CRD pump trip event has been addressed, initiate the GSW pump trip by:
Set TRIGGER 4 TRUE This trips the B GSW pump and starts a ramp to plug the Main Turbine LO Cooler B to 70%
SRO Directs response to annunciator:
1C06A C B GSW Pump trip.
Enters and directs actions of AOP 411 - Loss of GSW Direct the ROs to contact field operator to check GSW B pump RO Recognizes trip of B GSW pump and failure of standby pump to start.
Starts C GSW pump.
BOP Contacts field operator to check GSW B pump and breaker.
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 15 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 Main Turbine Vibration Rapid power reduction required.
Booth Instructor:
NOTE: The Turbine LO cooler clogging will result in Turbine High Vibes as the LO heats up, but Trigger 5 is used to ensure the crew gets the indications to force them to Fast Power Reduction/Scram.
Shortly after the Standby GSW pump is started:
Set TRIGGER 5 TRUE This increases turbine bearing 1 and 5 temperatures and vibrations CREW Recognizes increasing Main Turbine Vibration SRO AOP 693 - Main Turbine/EHC Failure Directs Fast Power reduction With vibrations> 12 mils and another bearing rising directs taking unit offline RO Takes core flow to 27 Mlbm per IPOI 4 for Power Reduction BOP Monitors reactor level
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 16 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Hydraulic ATWS Group 1 isolation Booth Instructor:
When either of the ADS Override Switches are positioned to OVERRIDE, verify:
TRIGGER 15 goes TRUE This trigger ensure the Spurious Group I isolation goes active When the MODE SWITCH is taken to SHUTDOWN, verify:
TRIGGER 9 goes TRUE This inserts all rods stuck malfunction until P/L leg entered When CRS announces that Power/Level leg of ATWS is being entered, then:
Set TRIGGER 11 to TRUE This deletes the all rods stuck malfunction.
Booth Instructor:
Role Play: When directed to install Defeat 12, then wait 2 minutes, and insert REMOTEs RP02 and RP03 to TEST, inform crew that Defeat 12 is installed.
SRO Directs Reactor Scram due to Hi turbine vibration Enters EOP-1 on the Failure to Scram condition Enters EOP-ATWS Directs Lock out of ADS Directs installation of Defeat 11 Directs installation of Defeat 12 and 3 Directs performance of ATWS QRC Directs Lockout of HPCI RO Scrams the reactor and takes Immediate actions of IPOI 5 Recognizes a Hydraulic ATWS condition exists Notifies SRO of ATWS Performs ATWS QRC as directed Monitors and Controls reactor level BOP Locks out ADS as directed Recognizes MSIV closure Installs Defeat 11 Installs Defeat 12 and 3.
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 17 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 (cont)
Hydraulic ATWS Group 1 isolation SRO Directs Terminate and Prevent Injection when power is > 5% (CT)
Directs Performing Hydraulic RIPs Directs initiation of SBLC prior to Torus Temp reaching 110 Degrees F. (CT)
Directs placing RHR in Torus Cooling RO Initiates SBLC Performs scram-reset-scram to insert rods Terminates and Prevents injection BOP Terminates and Prevents injection to allow level to lower (CT)
Places RHR in Torus Cooling
Rev. 0 ESG 2007 NRC ILT Scenario #03 SCENARIO TIME-LINE 2007 NRC Scenario 3 page 18 of 20 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #7 Failure of FRVs to close during Terminate and Prevent actions Booth Instructor:
Watch the A FRV position indication meter on 1C06, ensure the FRVs lockup (trigger 6 goes true). It is important to have the FRVs lockup prior to the valves going completely shut.
SRO Directs operators to terminate and prevent injection to lower level RO When directed to terminate and prevent injection recognizes the failure of the FRV controllers to function and stops feedwater pumps and/or closes block valves to prevent injection from feed and condensate. (CT)
Informs SRO of FRV failure to close.
Event #8 Alternate method required to insert control rods.
Booth Instructor:
When the crew has completed TWO successful SCRAM-RESET-SCRAM cycles (have scrammed twice), then:
Set TRIGGER 7 TRUE This sets a spurious scram signal, which does NOT allow the scram to be reset.
RO Recognizes scram-reset-scram is no longer working and takes action to individually insert control rods Informs SRO that manual rod insertion is being performed. (CT)
Scenario Completion Criteria:
When the control rods are being inserted, RPV water level is being restored and maintained between -25 and the level set at step in EOP-ATWS the scenario can be terminated.
- END OF SCENARIO ***
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
2007 NRC Scenario 3 Page 19 of 20 Correct IC or plant status identified.
Shift turnover forms filled out (both CRS/OSM and NSOE) if required.
Additional documents are prepared (STPs, Work Orders, LCO Paperwork).
Tasks and Objectives have been verified to be correct.
Plant PRA initiating events, important equipment and important tasks are identified.
SOMS tags identified and included in setup instructions.
Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.
Setup files correctly called out.
Malfunction list is accurate.
Override list is accurate.
Remote function list is accurate.
Event triggers are accurate.
Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.
Instructor Activity section is accurate and complete:
Actions are clearly defined for Booth or Floor instructor.
Role-playing is clearly noted.
The sequence of events is completely and concisely narrated even if it takes no instructor action.
Automatic actions that require verification are noted.
Reasonable alternate paths are considered and included.
Event trigger activation is distinguished from narrative text (Bold font)
Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.
Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.
Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
2007 NRC Scenario 3 Page 20 of 20 Expected Student Response Section is accurate and complete:
Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)
Tasks are clearly noted and properly numbered as appropriate.
Knowledge objectives are clearly noted and properly numbered as appropriate.
Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)
Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)
Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.
Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.
Actions are listed using a logical order; by position and chronology. (N/A as appropriate)
Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.
Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)
For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.
Turnover information (as required) is correct:
Day and shift are appropriate.
Weather conditions do not conflict with malfunctions.
Power levels are correct.
Thermal limit problems and power evolutions are realistic and include a reason for any downpower.
Existing LCOs include start date, remaining time and actions.
Plant Risk Assessment (CDF and Color).
STPs are appropriate for day and shift.
Core Damage Frequency has been properly calculated and listed to 3 decimal places.
Maintenance is realistic for plant conditions.
Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.
SME/Instructor Date SME/Instructor Date
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
Crew:
Instructors:
OSM ____________________________ Booth ________________________________
____________________________ Floor __________________________
STA Extra 1C05 ____________________________
1C03 ____________________________
BOP Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
SEG/ESG Validation Checklist SEG/ESG __________________________
Rev. ______________
Crew Comment:
Resolution:
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
Page 2: [1] Comment [N8]
NSP 09/08/2007 3:32:00 PM Seek applicable external and internal operating experience to include in the lesson plan.
Where applicable, Training Instructors shall incorporate plant and industry operating experience into lesson plans, simulator guides, or laboratory guide. The review of the operating experience should include the following elements:
- 1. Event description
- 2. Applicability to the site
- 3. Lessons learned
- 4. Application of the operating experience to prevent occurrence, or recurrence.
- 5.
Additional supporting information may be included.
- 6. Operating experience items may also be added as attachments to lesson plan.
Reference the attachment here.