Text

Proposed Scenarios for the Duane Arnold Initial Examination - December 2007, Examination Scenario Guide (Esg)
	ML081420563
Person / Time
Site:	Duane Arnold
Issue date:	02/27/2008
From:	; NRC/RGN-III
To:	;
References
	QF-1030-19, Rev 12
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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 ESG ILT 01 REV. 0 TRIP, LOSS OF 1D11, STATION BLACKOUT, HPCI INVERTER FAILS, LOCA/ALC ED, SBDG COMES BACK 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 GUIDE REQUIREMENTS Comment [N1]: Fill in the goal for this lesson plan. Based on the The goal of this scenario is to evaluate ILT students during the NRC learning objectives describe the Goal of Exam with 3 man crew. expected outcome/goal of this training Training: session.

Comment [N2]: Fill in the learning objectives for this lesson plan. Use There are no formal learning objectives the information obtained during the Learning design phase.

Objectives: Comment [N3]: List the courses that need to be completed prior to participating in this training session.

None Prerequisites: Comment [N4]: List the materials and multi-media needed to perform training. Examples are as follows:

1)furniture arrangement 2)multi-media equipment (VCR, Simulator DVD player, monitors, LCD Training Simulator Booth Instructor projector, and etc)

Resources: 3)multi-media software (tapes, Phone Talker CDs, DVDs, disks, and etc)

Simulator Floor Instructor 4)flipcharts, white/black boards 5)markers, pencils, pens, and etc)

None 6)security clearances

References:

7)equipment and tools 8)number of instructors/guest speakers needed Comment [N5]: List any None references used to develop this Commitments: training session:

1)procedures 2)text Comment [N6]: List any Dynamic Simulator commitments made. INCLUDE Evaluation recommendations for corrective actions, results of investigations and Method: why the training process was initiated.

Revision 0: List purpose of lesson plan. Revision 1: List reason(s) for None development or revision.

Operating Comment [N7]: Include written Experience: exams, practical exercises, JPM, OJE, or any other form of evaluating.

Specify method of evaluating Initiating Event with Core Damage Frequency: individual mastery of learning Related PRA N/A due to exam security objectives.

Information: Comment [N8]: Seek applicable external and internal operating Important Components: experience to include in the lesson N/A due to exam security plan. Where applicable, Training Instructors shall incorporate plant and industry operating experience into Important Operator Actions with Task Number: lesson plans, simulator guides, or laboratory guide. The review of the N/A due to exam security 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]

Page 2 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 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.

Page 3 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 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 Page 4 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0

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, Manual N/A 8

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 Page 5 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0

1.3 MALFUNCTIONS

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup AN 1C05A (F-03) Annunciator Box As Is ON 1C05A(43) (6HX8W) (SBLC Cont Loss)

Setup SL02A Squib Valves Fail To Fire Vlv A False TRUE XS2618A 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 TRUE Circuit Failure In As Dir RR17B Recirc M-G Flow Ctrlr Fails, 350 sec 1 As Is 100 Auto/Man Modes-M-G A As Dir RC08 Inadvertent RCIC Initiation 2 False TRUE As Dir RC10B MO2405 Thermal Overload 3 False TRUE Breaker Trip As Dir SW21B Well Water Pump Trip-Pump B 4 False TRUE As Dir ED13A 125 Vdc Distribution Panel Fault- 5 False TRUE Pnl 1D11 As Dir ED01A Loss Of Off-Site Power Sources- 7 False TRUE Bkr M As Dir ED01B Loss Of Off-Site Power Sources- 7 False TRUE Bkr J As Dir ED01C Loss Of Off-Site Power Sources- 7 False TRUE Bkr K As Dir ED01D Loss Of Off-Site Power Sources- 7 False TRUE Bkr X5960 As Dir ED01E Loss Of Off-Site Power Sources- 7 False TRUE Bkr X5940 As Dir RR15A Recirc Loop Rupt-Design Bases 600 8 0 20 LOCA at 100% Loop A As Dir HP07 HPCI Inverter Trouble 9 TRUE 1.4 Page 6 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 OVERRIDES:

Time Override No. Override Title Delay Ramp ET Initial Final Value Value Setup SL HS-2613A(1) A SBLC Light 1P-230A (Green OFF Light)

Setup SL HS-2613A(2) A SBLC Light 1P-230A (Red Light) OFF Setup SL XS-2618A(1) A Squib Valve Ready - W (White) OFF Continuity Light 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 th Setup AO ED X393 6 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 Page 7 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 1.5 REMOTE FUNCTIONS:

Time Remote Remote Title Delay Ramp ET Initial Final No. Value Value Setup FW15 MAN Operation of FEED 7 As-Is OPEN PUMP A (1P-1A Breaker)

Setup FW16 MAN Operation of FEED 7 As-Is OPEN PUMP B (1P-1B Breaker)

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.

Page 8 of 22

QF-1030-19 Rev. 12 2007 NRC Scenario #1 ESG, Rev. 0 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.

Page 9 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover COMPLETE TURNOVER: Get familiar with plant conditions.

Provide Shift Turnovers to the SRO

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

were identified on the shift turnover.

a. Review applicable current Plant Status

b. Review relevant At-Power Risk status

c. Review current LCOs not met and Action Requirements

d. Verify crew performs walk down of control boards and reviews turnover checklists page 10 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Booth Instructor respond as plant SRO personnel and respond as necessary:

Gives Pre-job brief to coordinate and discuss evolution Startup second Role play as the inplant operators to assist Communicate with the Event Response Team Condensate the crew to start the B Condensate Pump and Feed Pump May call Chemistry and direct to verify proper operation of AE-8912A, RR and the B Reactor Feedwater Pump.

IAW OI-644. Water O2 Analyzer When directed to open the B Condensate Pump discharge valve (V-06-04) USE Remote FW05 or the SimVue page. RO Turnover Info - All Condt/Demins ON. Monitoring critical parameters - reactor power, pressure, level Peer checker for BOP operator Role Play: When directed to isolate CRD valves 1P-1803A-V05 and 1P-1803B-V07, then wait two minutes, and inform the crew BOP that both of those valves are CLOSED (simulator does not model) REVERSE Reviewing OI-644 -Condensate and Feedwater.

THIS WHEN DIRECTED TO OPEN THE Reviewing IPOI-3 -Power Operations.

VALVES.

Starts the B condensate pumps per OI-644 section 3.8, step 9.

Role Play: When directed to verify closed the seal water isolation valve V06-11, wait Starts the B RFP per OI-644 Section 3.8, step 14.

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) page 11 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Booth Instructor respond as plant SRO personnel and respond as necessary:

Raises Power Provides a reactivity brief.

10% using Communicates with Real Time Desk and System Operating Center.

Recirculation Flow 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.

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.

page 12 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 Booth Instructor, after a measurable RO will determine that power is going up by itself, and determine that the B power rise, and at the direction of the Lead Recirc M-G speed controller is ramping up by itself. He will take the A Reactor Evaluator: following actions to stop the run away:

Recirc Pump speed controller SINCE the initial value of the ramp

Lock the scoop tube of the B recirc M-G speed controller. [Critical]

fails upscale has changed (RR FCVs have been adjusted) Look at the current

Enter AOP 255.2, Power/Reactivity Abnormal Change.

value of the RR17B malfunction, SRO will direct and the ROs will perform the following actions per DOUBLE CLICK on RR17B, and AOP 255.2:

set the ramp as follows:

Take any necessary steps to bring the reactor power/reactivity transient Trigger 1, 350 sec Ramp Time, under control, including, but not limited to:

Initial value to current value, final value of 100. o The Scoop Tube Lockup stopped the event THEN: SRO will determine if the recirc pump speed mis-match will put them out of compliance with the LPCI Loop Select limits.

Set Event Trigger 1 TRUE IMF RR17B to 100 over 350 sec

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.

If called as: This will cause the B Recirc M-G speed controller to ramp up slowly

Based on the calculation, the SRO will determine if he is in compliance MISC with TS 3.4.1 Condition C. If not, then has 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to restore the Booth Instructor respond as plant mis-match within limits, or Trip one of the recirc pumps.

personnel and respond as necessary:

Plot the current position on the power to flow map.

I&C Respond that you will look at the MOORE controller logic for speed control and get SRO will activate the Event Response Team and ensure that a WRC is back to them soon. written to help mitigate the event. Call Ops Management and REs.

Report that you will call in a licensed Crew (if the Recirc Flow is outside of the Mismatch limits), will discuss how WCC operator to take manual control of the they will restore the mismatch to within its limits.

locked up recirc scoop tube but it will be

Either raise the speed of the unlocked Recirc Pump to match the locked about an hour. Recirc Pump. OR Go along with what the crew wants to do, ERT

Send a licensed operator to the Recirc M-G Set room and take manual and tell them that ERT will take over the control of the locked Recirc Pump and lower it to within the limits.

repairs of the B speed control problem.

page 13 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 Booth Instructor: CREW RCIC spurious After the crew has addressed the RR Flow Recognizes RCIC start start Controller event:

Set Event Trigger 2 TRUE SRO IMF RC08 Determines Adequate Core Cooling exists by two independent indications This will initiate the RCIC Spurious and direct that RCIC be tripped.

Start 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 After the crew trips the RCIC system:

Verifies HPCI operable per STP 3.5.3-01 Set Event Trigger 3 TRUE IMF RC10B Notifies the Event Response Team This will insert malfunction for Assesses risk thermal overload for MO-2405 (prevents RCIC from being used for injection) BOP NOTE: This thermal overload will Trips RCIC per Quick Response Card OI 150 QRC 2 and depresses RCIC NOT reset. Manual Turbine Trip PB.

Verifies that MO-2405, RCIC Turbine Stop Valve closes Booth Instructor responds as plant personnel as necessary. RO Monitors power, pressure and level.

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.

page 14 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 B Well Water Booth Instructor: CREW Pump trips Once the RCIC spurious start event has Responds to Annunciators:

been addressed, then:

1C21 A11 - Panel 1C23 Set Event Trigger 4 TRUE A1C07A C11- Drywell Cooling Panel trouble IMF SW21B This will trip the B Well Water pump BOP Will check annunciator response for 1C23 Booth Instructor respond as plant Reports to SRO that a loss of the B well water pump occurred.

personnel and respond as necessary. 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 page 15 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Booth Instructor: CREW Loss of the When the Well Water event has been Responds to Annunciator 1C08 D-9 A DG Control Power Failure 125 VDC addressed, then:

panel 1D11 Set Event Trigger 5 TRUE SRO IMF ED13A Enters AOP 302.1 - Loss of 125 VDC Power, Tab 1 - Loss of 125 VDC This initiates a loss of 1D11 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.

When called to Role Play: When called to investigate the RO investigate the 1D11 Feeder breaker, report that the loss of 1D11 breaker is tripped free (molded case Takes manual control of FW and attempts to restore reactor water level to feeder breaker: breaker type). 1D11 feeder breaker is the normal band 1D1 breaker 06.

BOP If called to Role Play: After a three minute delay, Transfers non-essential power to the startup transformer per OI 304.1, investigate any report that you can find no abnormal section 4.2.

other abnormal conditions for the Div 1 125 Vdc system.

conditions for div 1 125vdc Monitors Balance of plant equipment.

page 16 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Booth Instructor: RO:

Event #7

Perform IPOI-5 immediate actions.

Station When the evaluation team is ready to initiate the Station Blackout, then:

Notifies the SRO that a loss of feed has occurred (RCIC/HPCI not Blackout available)

Set ED03 Initial Severity to 40 and set Final Severity to 30, with a ramp SRO:

time of 180 sec.

Enter EOP 1 due to RPV level <170".

When the reactor scrams, verify that

Use HPCI/RCIC to maintain RPV water level 170-211".

Event Trigger 7 activates to initiate

Use SRVs to control RPV pressure (allow LLS to cycle).

the Loss of Offsite Power.

Enter, direct and perform AOP 301.1, Station Blackout, Immediate and Follow-up Actions Booth Instructor:

Notify the SOC and request Priority 1 power restoration.

Role Play: as plant personnel and use

Bypass HPCI/RCIC temperature isolations.

simulator remote functions as necessary

Investigate the loss of the A SBDG and direct emergency to carry out directed actions.

maintenance support.

When called as

Use SRVs, HPCI and RCIC to start depressurizing the RPV at 80° to SOC: Role Play: Inform DAEC will be priority 1 100°/hr and then stop the cooldown when RPV pressure is in the 150 for power restoration. Estimate is 3.5

- 200 psig range.

hours for power restoration.

Attempt to use HPCI/RCIC to maintain RPV level per the EOPs.

When operator Role Play: When sent to investigate the BOP: (Evaluator CUE: When BOP bypasses RCIC/HPCI Temp Isolations -

called to SBDG output breaker, you see nothing inform him that backpanel doors are all simulated open) investigate abnormal.

SBDG 1G31 will NOT start due to the loss of 1D11 (previous event)

SBDG:

Verifies SBDG 1G21 starts, but the output circuit breaker is mechanically bound up, and will not shut When called for Role Play: Wait five minutes, then inform

Recognizes that the B SBDG is running without cooling water, assistance on the crew that electrical maintenance is in and secures B SBDG.

the SBDG the switchgear room.

Bypass HPCI/RCIC temperature isolations.

output breaker:

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 page 17 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #9 (Continued)

When called as Role-play: as plant personnel performing plant personnel the SBO attachments and report after to perform SBO being directed:

attachments: HPCI doors; Wait 4 minutes and report HPCI doors 204 and 220 are blocked open.

Attachment 1; Report completed in 30 minutes.

Attachment 6; Wait 30 minutes and report complete with no unexpected findings.

Event #8 BOP:

DG running

SBDG 1G31 will NOT start due to the loss of 1D11 (previous event) without cooling

Verifies SBDG 1G21 starts, but the output circuit breaker is water mechanically bound up, and will not shut

Recognizes that the B SBDG is running without cooling water, and secures B SBDG.

page 18 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #9 Booth Instructor: BOP HPCI Inverter When HPCI is started (manually or

Notes that HPCI has an inverter failure (causes the HPCI turbine to Failure automatically), run below the minimum acceptable RPM)

Verify that TRIGGER 9 goes TRUE

Secures the HPCI system This inserts the HPCI Inverter Trouble condition (HPCI runs at minimum speed and does not inject) page 19 of 22

Rev. 0 2007 NRC ILT Scenario #1 SCENARIO TIMELINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #10 Booth Instructor: Crew:

Leak in When the evaluation team is ready to

Notices PC pressure increasing containment, initiate the LOCA, then (shortly after SBO):

Loss of feed, Set Event Trigger 8 TRUE ED required SRO:

IMF RR15A to 20% over 600 sec This starts a LOCA in the DW

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 Booth Instructor: o Torus level verified >4.5.

Delete the malfunction and override: o 4 ADS SRVs are opened and verified open.

DMF DG02B and DOR DG152-411

Directs the B SBDG started and closed onto the bus

Directs ECCS pumps be used to restore RPV level to normal This will allow the B SBDG output level band.

breaker to work BOP:

Role Play:

Monitors containment parameters, and keeps SRO advised of When the crew opens the SRVs, call the parameter trends and values.

control room as Electrical Maintenance and inform them that the B SBDG output

Opens 4 ADS SRVs breaker is fixed and can be closed in.

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 ***

page 20 of 22

SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________ Rev. _____0________

Correct IC or plant status identified.

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

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

Tasks and Objectives have been verified to be correct.

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

SOMS tags identified and included in setup instructions.

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

Setup files correctly called out.

Malfunction list is accurate.

Override list is accurate.

Remote function list is accurate.

Event triggers are accurate.

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

Instructor Activity section is accurate and complete:

Actions are clearly defined for Booth or Floor instructor.

Role-playing is clearly noted.

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

Automatic actions that require verification are noted.

Reasonable alternate paths are considered and included.

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

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

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

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

Scenario 1.doc Page 21 of 22

SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________ Rev. _____0________

Expected Student Response Section is accurate and complete:

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

Tasks are clearly noted and properly numbered as appropriate.

Knowledge objectives are clearly noted and properly numbered as appropriate.

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

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

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

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

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

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

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

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

Turnover information (as required) is correct:

Day and shift are appropriate.

Weather conditions do not conflict with malfunctions.

Power levels are correct.

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

Existing LCOs include start date, remaining time and actions.

Plant Risk Assessment (CDF and Color).

STPs are appropriate for day and shift.

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

Maintenance is realistic for plant conditions.

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

SME/Instructor Date SME/Instructor Date Scenario 1.doc Page 22 of 22

SEG Validation Checklist SEG ________2007 NRC Exam Scenario #1_________ Rev. _____0________

Crew: Instructors:

OSM ____________________________ Booth ________________________________

CRS ____________________________ Floor __________________________

STA __________________________________ Extra ________________________________

1C05 ____________________________

1C03 ____________________________

BOP ____________________________

Crew Comment:

Resolution:

Crew Comment:

Resolution:

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

SEG Validation Checklist SEG ________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, 2007 ILT 02 REV. 0 DUAL CONDENSATE PUMP TRIP, STEAM LEAK IN PC, GROUP 3 FAILURE, HPCI CONTROLLER FAILURE 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 GUIDE REQUIREMENTS Comment [N1]: Fill in the goal for The goal of this scenario is to evaluate ILT students during the NRC this lesson plan. Based on the learning objectives describe the Goal of Exam with 3 man crew. expected outcome/goal of this training Training: session.

Comment [N2]: Fill in the learning There are no formal learning objectives objectives for this lesson plan. Use the information obtained during the Learning design phase.

Objectives: Comment [N3]: List the courses that need to be completed prior to None participating in this training session.

Prerequisites: Comment [N4]: List the materials and multi-media needed to perform training. Examples are as follows:

1)furniture arrangement Simulator 2)multi-media equipment (VCR, DVD player, monitors, LCD Training Simulator Booth Instructor projector, and etc)

Resources: Phone Talker 3)multi-media software (tapes, CDs, DVDs, disks, and etc)

Simulator Floor Instructor 4)flipcharts, white/black boards 5)markers, pencils, pens, and etc)

None 6)security clearances

References:

7)equipment and tools 8)number of instructors/guest speakers needed Comment [N5]: List any None references used to develop this Commitments: training session:

1)procedures 2)text Comment [N6]: List any Dynamic Simulator commitments made. INCLUDE Evaluation recommendations for corrective Method: actions, results of investigations and why the training process was initiated.

Revision 0: List purpose of lesson None plan. Revision 1: List reason(s) for Operating development or revision.

Experience: Comment [N7]: Include written exams, practical exercises, JPM, OJE, or any other form of evaluating.

Initiating Event with Core Damage Frequency: Specify method of evaluating Related PRA individual mastery of learning N/A due to exam security objectives.

Information:

Comment [N8]: Seek applicable Important Components: external and internal operating N/A due to exam security experience to include in the lesson plan. Where applicable, Training Instructors shall incorporate plant and Important Operator Actions with Task Number: industry operating experience into lesson plans, simulator guides, or N/A due to exam security 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]

2007 NRC Scenario 2 Page 2 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 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

5. Both FW pumps trip After EOP Entry:

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 2007 NRC Scenario 2 Page 3 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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.

2007 NRC Scenario 2 Page 4 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 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.

2007 NRC Scenario 2 Page 5 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 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 When the Seismic Alarm Acknowledge Command: DOR ZDIPCPB3 pushbutton is pushed, delete the override of the Seismic Alarm Test pushbutton to turn the audible alarm off.

20 Event: ZDIPCHS4303(2) == 2** When the handswitch for CV 4303 goes to Command: DMF MS24BD AUTO, Delete malfunction for fails as is DO NOT ACCEPT DURING SETUP **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** When the handswitch for CV 4310 goes to Command: DMF MS24AE AUTO, Delete malfunction for fails as is DO NOT ACCEPT DURING SETUP **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.

2007 NRC Scenario 2 Page 6 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0

1.3 MALFUNCTIONS

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup AN 1C05A(43) 1C05A (F-03) Annunciator Box As Is ON (6HX8W) {SBLC Valve Continuity Loss}

Setup AN 1C03C(2) 1C03C (A-02) Annunciator As Is ON Box {B CS pump trip}

Setup SL01A Standby Liquid Pump Trip- TRUE TRUE Pump A Setup RH10A RHR A Pump Fail to Auto- TRUE Actuate Setup RH10B RHR B Pump Fail to Auto- TRUE Actuate Setup RH10C RHR C Pump Fail to Auto- TRUE Actuate Setup RH10D RHR D Pump Fail to Auto- TRUE Actuate Setup CS05A Core Spray Pump A-Failure to TRUE Auto-Initiate Setup CS05B Core Spray Pump B-Failure to TRUE Auto-Initate As Dir RP05A Auto Scram Failure 1 TRUE As Dir AN 1C05A(35) 1C05A (E-03) Annunciator 15 sec 2 As Is ON Box (6HX8W) {SBLC Tank Level Hi/Lo Level}

As Dir AN 1C03B (36) 1C03B (D-09) Annunciator 3 Crywolf Box {Torus Hi/Lo Level}

As Dir AN 1C03A(17) 1C03A (B-08) Annunciator 200 sec 3 As Is ON Box (4HX9W) {A CS Discharge Line Lo Pressure}

As Dir FW12B FW Reg Valve Controller 300 sec 4 As Is 20 Failure (AUTO) FWRV B As Dir MS02 Small Steam Leak Inside the 300 sec 5 0.03 Pri Containment (VI)

As Dir MS24BD Group 3 Isolation Component 6 TRUE Failure(s)-CV-4303 Fail As Is As Dir MS24AE Group 3 Isolation Component 6 TRUE Failure(s)-CV-4310 Fail As Is As Dir FW02A Condensate Pump Trip - 7 TRUE Pump A As Dir FW02B Condensate Pump Trip - 7 TRUE Pump B As Dir SW22A Dw Clg Units Well Water Flow 120 8 100 Blockage-Clg Unit 1A 2007 NRC Scenario 2 Page 7 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value As Dir SW22B Dw Clg Units Well Water Flow 120 8 100 Blockage-Clg Unit 2A As Dir SW22H Dw Clg Units Well Water Flow 120 8 100 Blockage-Clg Unit 1B As Dir SW22I Dw Clg Units Well Water Flow 120 8 100 Blockage-Clg Unit 2B As Dir SW22G Dw Clg Units Well Water Flow 120 8 100 Blockage-Clg Unit 7A As Dir SW22N Dw Clg Units Well Water Flow 120 8 100 Blockage-Clg Unit 7B As Dir HP03 HPCI Flow Controller Fails (VI) 120 9 0

1.4 OVERRIDES

Time Override No. Override Title Delay Ramp ET Initial Final Value 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- OFF W(White)

Setup SL HS-2613A(1) A SBLC Pump 1P-230A OFF (Green)

Setup SL HS-2613A(2) A SBLC Pump 1P-230A OFF (Red)

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 2 3 TRUE Switch 2007 NRC Scenario 2 Page 8 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 File: EARTHQUAKE (inserted during the scenario)

Time Override No. Override Title Delay Ramp ET Initial Final Value 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 .45 Level Per SEG: AO PC07(3) Narrow Range Torus Water .45 Level 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 Final Value 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 ..52 Level Per SEG: AO PC07(3) Narrow Range Torus Water .52 Level 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 2007 NRC Scenario 2 Page 9 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 Time Override No. Override Title Delay Ramp ET Initial Final Value 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 Remote Title Delay Ramp ET Initial Final No. Value Value Setup CS04 Manual Oper of B CS Pump OPEN (1P-211B) Breaker FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments 2007 NRC Scenario 2 Page 10 of 23

QF-1030-19 Rev. 12 ESG 2007 NRC ILT #02, Rev. 0 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.

2007 NRC Scenario 2 Page 11 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE COMPLETE TURNOVER:

Get familiar with plant conditions.

Provide Shift Turnovers to the SRO

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

were identified on the shift turnover

a. Review applicable current Plant Status

b. Review relevant At-Power Risk status

c. Review current LCOs not met and Action Requirements

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

2007 NRC Scenario 2 page 12 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 SRO A Manual Gives Pre-job brief to coordinate and discuss evolution Scram Surveillance RO Completes A Manual Scram Surveillance (section 7.2 needs to be completed)

BOP Acts as peer checker for RO 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).

2007 NRC Scenario 2 page 13 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Booth Instructor: RO SBLC Tank When the Manual Scram event has been

Notices the SBLC tank low level condition Leak completed, then initiate the SBLC tank leak:

Refers to ARP 1C05A (E-3)

Set TRIGGER 2 TRUE This ramps the SBLC Tank Level BOP Indicator from 85% to 65% in 120 sec

Sends an in-plant operator to check out the SBLC area and after a 15 sec TD alarms the SBLC Tank Lo Level

Might call Radwaste and inform them of the borated water leak.

ROLE PLAY as the person sent to

Might dispatch Chemistry to investigate/respond to the borated water investigate: leak.

Riggers were rigging the SBLC pump and lost control of the load. A small hole has been created in the suction piping to the SRO SBLC pumps, and is isolable by shutting

Refers to Technical Specifications 3.1.7.B (8 Hour Action statement the SBLC pump isolation valve, V-26-01. to restore one subsystem to operable status)

Ask if the crew wants you to unlock and shut V-26-01 to isolate the leak.

Notifies Duty Manager / OM / OSM of issue, Activates the Event Response Team Setup for the Booth Instructor Earthquake 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.

2007 NRC Scenario 2 page 14 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 Booth Instructor: SRO Small When ready to start the earthquake event:

Direct operators to perform immediate actions of AOP 901.

Earthquake Hit ENTER on the monitor that has

Determine no hazardous condition exists on the refuel floor.

ROR EARTHQUAKE typed in the expert command window.

Direct operators to perform the follow-up actions of AOP 901.

Set Event Trigger 3 TRUE

Commence shutting down the reactor to be in cold shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(This starts the earthquake alarm)

When the seismic alarm sounds, hit

Direct the inspection and radiological surveying/sampling all plant areas and ENTER on the monitor that has ROR required systems.

EARTHQUAKE1 typed in the expert command window.

Direct surveying and sampling of high priority areas, structures, systems and components.

Select the LAST 14 OVERRIDES and DELETE THEM (these are the overrides that

Verify any heavy loads being handled (within the turbine building or LLRWSF) place level recorders HIGH for the are landed in safe location.

sloshing in the TORUS, ESW pits, etc.

Direct Health Physics to perform radiation surveys of the normally accessible DELETE the OVERRIDE FOR the C RHR areas inside main DAEC Buildings and the site grounds.

Handswitch in START WHEN the RO acknowledges the Seismic

Direct chemist to review KAMAN data and perform sensor checks.

Alarm at 1C35, OBSERVE that ET10 activates

Direct the inspection and radiological surveying/ sampling of all plant areas and and the Seismic alarm silences; if not, required systems in accordance with AOP 901, Earthquake.

DELETE PCPB3.

Have Radwaste monitor for abnormal pump ups or rising leak rates.

Floor Instructor Inform the crew that they felt the building shake.

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] [CONTINUED ON NEXT PAGE]

2007 NRC Scenario 2 page 15 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Small Booth Instructor BOP Earthquake Role Play: As the crew sends various people

Acknowledge seismic alarm and reset.

(CONTINUED) in the plant instructions, respond that you will do the requested actions. As NSPEOs,

Notice and inform crew of RHR pump spurious start perform desired investigations.

Notice and inform crew of RHR min flow valve SHUT

Secure C RHR pump

Dispatch an operator to check the event indicators on accelographs.

Booth Instructor:

ROLE PLAY: When an appropriate time has

Verify RWS availability.

passed, call the control room and inform them that there is a water leak coming off of the

Monitor Process and Area Radiation Monitoring System channels on Panels discharge pipe of the C RHR pump. The leak 1C10 and 1C11.

is downstream of the discharge isolation valve for the pump.

Monitor Torus Water Level on Panels 1C03, 1C29, 1C09, and SPDS.

ROLE PLAY: When sent to investigate the Core Spray system, report a pipe leak on the

Monitor Area Water Levels on Panel 1C21.

discharge pipe of the A CS pump in the SECR. The leak is downstream of the

Monitor water levels of Drywell Equipment and Floor Drain sumps.

discharge isolation valve for the pump.

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.

2007 NRC Scenario 2 page 16 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 Booth Instructor: SRO:

Power Once the CRS determines that TS 3.0.3 Perform brief for downpower Reduction to applies to situation, IF the crew is taking Comply with May direct the circuit breakers for the A CS and C RHR pump to be too long to downpower, call the crew as Tech Spec racked down.

the Ops Manager and inform the crew that 3.0.3 you want them to start lowering power promptly. RO:

Perform downpower maneuver BOP:

Peer check downpower maneuver Event #5 Booth Instructor: RO FRV Controller When the Exam Team is satisfied with the

Recognizes and reports Feedwater Level control is not responding as Failure power reduction, initiate the FRV controller expected.

failure by:

Takes manual control of FWRVs by placing the B FWRV in manual.

Set TRIGGER 4 TRUE This will Fail the B FWRV controller CRS to 20% over 5 minutes

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):

CRS

Directs the ROs on feedwater and recirc to coordinate power reduction.

Monitors and supervises the ROs.

2007 NRC Scenario 2 page 17 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Booth Instructor: Crew:

Small Steam When the FRV Controller Failure has been

Notices rising DW pressure Leak/Vent PC addressed, initiate the small steam leak by: SRO:

Set TRIGGER 5 TRUE

Enters AOP 573, Primary Containment Control This will initiate a small steam leak o Directs venting of the DW IAW OI 573, Primary Containment to force the operators to vent the Control, to maintain DW pressure between 1.0 and 1.5 psig Primary Containment o Directs Chemistry to evaluate the isotopic makeup of the Drywell atmosphere/sump discharge to assist in determining Booth Instructor: the source of the leak in the DW Before moving on to the next event, wait BOP:

for the crew to cycle the vent valves open (may have to increase the MS02 leak

Vents the primary containment per OI 573 size), then fail the vent valves AS IS by: o Verify that NW and SOUTH DRYWELL AREA HI RANGE Set TRIGGER 6 TRUE RAD MONITORS RIM-9184A and RIM-9184B on 1C09 are reading less than 20 R/hr.

This inserts CV 4303 and CV 4310 FAILURE AS IS. o Start one train of the Standby Gas Treatment System with the Test pushbutton per OI 170.

Booth Instructor:

o Monitor drywell and torus pressure indications on 1C03 and Change the Event Triggers 20 and 21 to pressure trend indications on 1C09 and 1C29.

== 0 and then accept event triggers 20 and 21. This will allow the automatic o Line up to vent drywell [torus] by positioning the following deletion of the Vent Valves Failure based switch (Valves will indicate dual position):

upon the valve handswitch position. HS-4303, OUTBD DRYWELL VENT ISOL CV-4303 Booth Instructor: AUTO/OPEN WHEN the crew REPOSITIONS HS-4301, OUTBD TORUS VENT ISOL CV-4301 the DW Vent Valve Handswitches AUTO/OPEN to CLOSE, verify that malfunctions o Cycle valves as necessary to maintain drywell pressure MS24BD and MS24AE DELETE. between 1.0 and 1.5 psig.

2007 NRC Scenario 2 page 18 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Condensate Booth Instructor: SRO:

Pumps Trip When the primary containment vent valves

Identifies the loss of FW are failed as is, trip both condensate pumps by:

Orders manual reactor scram Event 7 Set TRIGGER 7 TRUE

Enters EOP 1 due to <170 RPV water level (C-RO, C-SRO)

This will trip both condensate

Orders RPV level and pressure be controlled IAW EOP 1 pumps 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 2007 NRC Scenario 2 page 19 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Steam Leak in Booth Instructor: SRO:

Primary After the scram, increase the DW steam

Enters EOP 2 on Primary Containment parameters Containment leak by:

(bigger)

Modify MS02 Malfunction to:

Orders Torus Sprays prior to DW pressure exceeding 11 psig Ramp to 2 over 120 secs

Orders DW Sprays prior to DW temperature exceeding 280F.

Event 8 This ramps up the DW steam leak RO:

(M-ALL) AND

Set TRIGGER 8 TRUE BOP:

This ramps in DW Coolers flow blockage to help drive DW temp up

Identifies rising DW pressure

Communicates trends and values to the SRO

Places RHR in torus spray lineup

Places DW sprays in service Drywell Vent Booth Instructor: SRO:

Valves Fail to The DW vent valves are already stuck

Identifies ECCS pumps do NOT automatically start on 2 psig signal Isolate open from a previous event.

Orders BOP to start all available Core Spray pumps and RHR pumps with their control handswitches Event 9 Booth Instructor:

(C-BOP) Watch the CV 4303 and CV 4310 using BOP:

the soft-panel displays:

Notices ECCS pumps do NOT automatically start on 2 psig signal WHEN the crew REPOSITIONS

Starts all available Core Spray pumps and RHR pumps with their the DW Vent Valve Handswitches control handswitches to CLOSE, VERIFY malfunctions MS24BD and MS24AE delete so that the valves will CLOSE 2007 NRC Scenario 2 page 20 of 23

Rev. 0 ESG 2007 NRC ILT Scenario 02 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE HPCI Flow Booth Instructor: BOP Controller Verify that trigger 9 goes active at

Identifies the failed HPCI Automatic controller and transfers the controller to Failure 2 psig DW pressure. This will fail manual the HPCI AUTOMATIC flow

Identifies that HPCI responds in MANUAL control controller to 0 over 120 secs.

Communicates status of HPCI to SRO Event 9

Coordinates control of RPV water level with RO (C-BOP)

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 ***

2007 NRC Scenario 2 page 21 of 23

SEG/ESG Validation Checklist SEG/ESG __________________________ Rev. ______________

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.

2007 NRC Scenario 2 Page 22 of 23