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2012 Quad Cities Nuclear Power Station Initial License Examination Proposed Scenarios
	ML12083A184
Person / Time
Site:	Quad Cities
Issue date:	05/04/2012
From:	; Exelon Nuclear
To:	; Operations Branch III
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Quad Cities 2012 NRC EXAM Scenario 5 Exelon Nuclear 2012 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 5 Revision Number: 00 Date: _03/04/12 Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 5 Op-Test No.: ILT 10-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is starting up at 14% power with the Mode Switch in RUN. Drywell Inerting in progress.

Turnover: Transfer Aux Power to UAT. Withdraw control rods for startup.

Event No.

Malf. No.

Event Type*

Event Description 1

None BOP N

Transfer Aux Power to UAT 2

None ATC R

Withdraw control rods for startup 3

RD11 ATC I

CRD Flow Controller fails low (QCOA 0300-06) 4 DIHS156041A LOHS156041A4 (Overrides)

BOP C

Gland Exhauster trip/start standby 5

None ATC C

Hydraulic leak on the 1B FRV; the ATC will shift to the 1A FRV 6

RH19BR (Remote Function)

SRO TS Breaker failure on a Drywell Spray Valve TS 7

None BOP C

Emergency Swap of RBCCW Pumps 8

SER0698 SRO TS Target Rock Relief bellows failure TS 9

MS04C RP02 RP03 Crew M

A Steam line leak in the Drywell results in a reactor scram per QCOA 0201-01 and entry into QGA 100 and 200. Manual and auto Scram logics fail. ARI Initiation is necessary 10 RH19AR (Remote Function)

DIHS11001S17B (Override)

Crew M

On the opposite division, the Drywell Spray valves fail to open, Emergency Depressurization per QGA 500-1 when PSP exceeded (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:

Total Malfunctions (5-8): 7 Malfunction(s) after EOP (1-2): E9& 10 Abnormal Events (2-4): E 3 & 9 Major Transient(s) /E-Plan entry (1-2): E9 EOPs (1-2): QGA 200/ 100 EOP Contingencies (0-2): E10 Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:

BOP Normal: E1 ATC Reactivity (1 per set): E2 BOP I/C (4 per set): E4 & 7 ATC I/C (4 per set): E3 & 5 SRO-I I/C (4 per set inc 2 as ATC): E3,4,5 & 7 SRO Tech Spec (2 per set): E 6 & 8 ALL Major Transients (2 per set) E9

Quad Cities 2012 NRC EXAM Scenario 5

SUMMARY

Initial Conditions:

o The plant is operating at 14% power (88 MWe).

o Drywell Inerting is in progress.

Event 1: The BOP transfers Aux Power to UAT per QCOP 6500-09.

Event 2: The SRO and ATC withdraw control rods for startup.

Event 3: The CRD Flow Control Valve will fail closed. Per QCOA 0300-06, the ATC will take manual control and adjust drive pressure or shift FCVs in order to continue rod withdrawal.

Event 4: The running Gland Seal Exhauster will trip. The BOP will start the standby Exhauster and adjust Gland Exhaust pressure.

Event 5: The Field Supervisor reports a hydraulic leak on the 1B FRV. The ATC will shift to the 1A FRV per QCOP 0600-18.

Event 6: The breaker to a Drywell Spray Valve is found Deenergized due to an electrical fault. The SRO must address:

o TRM 3.6.a Condition A o T.S. 3.6.1.3 Power operated PCIV o T.S. 3.3.3.1 PAM Instrument Event 7: The BOP performs an emergency swap from the 1B to the 1/2C RBCCW pump per QCOP 3700-02.

Event 8: The Bellows Failure annunciator will alarm for the Target Rock Relief Valve, which makes the Safety Function of this valve inoperable. The SRO will address Tech Specs for one or more Safety valves inoperable, 3.4.3 Condition C.

Event 9: Drywell Pressure starts to rise when a LOCA is initiated. A manual scram should be attempted per QCOA 0201-01 before Drywell Pressure exceeds 2.5 psig. The Manual Scram Pushbuttons, the Mode Switch to SHUTDOWN, and Drywell Pressure >2.5 psig will fail to trip RPS. The ATC must perform Alternate Rod Insertion procedures, most likely ARI initiation, to successfully insert all control rods. After Drywell Pressure exceeds 2.5 psig, QGA 100 and 200 are performed. The crew restores RPV Water Level and attempts to control Drywell Pressure and Temperature with Containment Sprays.

Event 10: When the 2nd Division of Containment Spray valves cannot be opened, the crew will Blowdown in order to avoid exceeding Pressure Suppression Pressure (PSP).

CRITICAL TASKS:

Critical Task #1 With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110oF torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits.

Critical task #2: When Drywell temperature CANNOT be maintained < 280 F OR Torus pressure CANNOT be maintained < the Pressure Suppression Pressure Limit, (PSP),

INITIATE an Emergency Depressurization.

Quad Cities 2012 NRC EXAM Scenario 5 EXERCISE PERFORMANCE OBJECTIVES SR-6500-P02 Given a reactor plant, transfer a 4160 bus from/to T-12 to/from T-11 in accordance with QCOP 6500-09 or QCGP 1-1 or QCGP 2-1.

SR-0002-P04 Given a reactor plant at power, perform a power change discernible on neutron monitors using control rods in accordance with QCOP 0280-01, QCGP 3-1 and QCGP 4-1.

SR-5600-P04 Given a reactor plant during a startup, start the main turbine gland steam seal system in accordance with QOP 5600-01.

SR-1600-P03 Given a reactor plant during a startup, start the drywell and torus differential pressure control system in accordance with QCOP 1600-21.

SR-0600-P04 (Freq: LIC=B) (ILT-MP) Given an operating reactor plant with a normal feedwater level control lineup when a loss of the FWLC master controller output signal occurs, take manual control of the main feedwater regulators and operate the low flow feedwater regulator in automatic in accordance with QCOP 0600-17.

SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.

SR-0001-P11 Given a reactor plant with an ATWS, take action to reduce heat input into the containment in accordance with QGA 101.

SR-1000-P05 Given a reactor plant in an accident condition where RHR-LPCI mode has started automatically, determine if LPCI has responded correctly to a valid initiation and throttle flow to restore RPV water level in accordance QCOA 1000-04.

SR-0203-P07 Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)

SR-1000-P02 Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)

SR-1000-P04 Given a reactor plant with rising containment pressures due to a LOCA or steam leak and RHR is not needed for core cooling, verify parameters are in the safe region of the Drywell Spray Initiation Limit (QGA Figure K), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays when torus pressure exceeds 5 psig in accordance with QGA 200 and QCOP 1000-30. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)

SR-0001-P23 Given a reactor plant with rising containment pressure and temperature due to a LOCA or steam leak, initiate an emergency depressurization when torus pressure cannot be maintained below the Pressure Suppression Pressure (QGA Figure L) or when drywell temperature cannot be restored and held below 280 degrees in accordance with QGA 200 and QGA 500-1.

Quad Cities 2012 NRC EXAM Scenario 5 Simulator Setup:

1. Reset to IC-23 (14% power).

2. Go to RUN.

3. Verify the following RWM Sequence is loaded: C22SU Mark up the Control Rod Move Sheet to reflect all rods withdrawn up to Step 24.

.4. Transfer Aux Power back to the RAT in preparation for Event 1.

5. Transfer from the LFFRV to the 1B FRV per QCOP 0600-02 in preparation for Event 5.

Open both FRV Isolation MOVs on Panel 901-6.

Transfer to B FRV.

Place the LFFRV in Manual and close

6. Complete the following lineup for Drywell Inerting:

On Panel 901-4,:

AO 1-4723 RES SPLY, hang an Equip Status Tag stating that Inst Air is valved in as a backup to Drywell Pneumatic System.

On Panel 912-5 Verify 1B Drywell/Torus Purge Fan is OFF Take the 1A Drywell/Torus Purge Fan Handswitch to OFF Verify GREEN Flag for 1A Drywell/Torus Purge Fan Handswitch Hang an Equipment Status Tag on the 1A Drywell/Torus Purge Fan On Panels 901-55 & 56, verify at least one CAM is in operation sampling the Drywell.

(The following commands to be utilized for this scenario are contained in the CAEP file:

2012 NRC Scenario 5.cae)

7. Insert Commands for setup:

imf ser0986(4) on (On Trigger 4, Gland Exhauster Trip 901-7 E-12 ON) ior dihs156041a(4) trip (On Trigger 4, 1A Gland Exhauster handswitch to TRIP) ior lohs156041a4(4) on (On Trigger 4, 1A Gland Exhauster Amber Trip light ON) imf rp02a (RPS Channel A1 Auto scram failure) imf rp02b (RPS Channel B1 Auto scram failure) imf rp02c (RPS Channel A2 Auto scram failure) imf rp02d (RPS Channel B2 Auto scram failure) imf rp03a (RPS Channel A Manual scram failure) imf rp03b (RPS Channel B Manual scram failure) ior dihs11001s17b off (Division 2 Containment Spray Permissive overridden off) trgset 9 rrpdome.lt. 875 (When Reactor Pressure lowers to <875 psig) imf rp05a(9) (On Event Trigger 9, a spurious Group 1 Isolation) imf rp05b(9) (On Event Trigger 9, a spurious Group 1 Isolation)

8. Verify the following commands for scenario performance:

imf rd11 0 2: CRD Flow Controller Failure downscale over 2 minutes trg! 4 (Trigger 4 used to initiate Event 4 Gland Exhauster Trip) irf rh19ar open (Drywell Spray 23A Breaker open) imf ser0698 (Target Rock Relief bellows failure annunciator on) imf ms04c 0.5 10: (Main Steam break in Drywell at 0.5% severity over 10 min) mmf ms04c 4 (Modify Main Steam break inside Drywell to 4%)

irf rh19br open (As requested, open the breaker to Div 2 DW Spray 23B) irf rh20br open (As requested, open the breaker to Div 2 DW Spray 26B) irf rh23br open ( As requested, open the breaker for MO 1-1001-34B vlv) irf rh24br open (As requested, open the breaker for MO 1-1001-36B vlv)

Quad Cities 2012 NRC EXAM Scenario 5 Simulator Setup:

9. Place the LOCA TRIP ENABLED placard above the 1C Circ Water Pump.

10. Verify SBO alarms clear.

11. Provide a Startup REMA.

12. Provide a current revision of the following procedures, signed off as specified:

QCGP 1-1 Signed off up to Step F.8.p QCGP 4-1 signed off up to Step F.2.c QCOP 0280-01 signed off up to Step F.2 QCOP 0600-02:

Prerequisites, Precautions, and Limitations & Actions circled and slashed Steps F.1 and F.3 circled and slashed and signed off as completed by NSO Step F.2 marked N/A QCOP 6500-09:

Prerequisites, Precautions, and Limitations & Actions circled and slashed Steps F.1 through F.6, F.8, and F.10 marked NA Steps F.7.d and F.7.e marked NA QCOP 1600-20, signed off up to Step F.23.

13. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.

Quad Cities 2012 NRC EXAM Scenario 5 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-16 PRIMARY CONTAINMENT HIGH PRESSURE, Rev. 12 o 901-3 G-4 DRYWELL HIGH PRESSURE, Rev. 8 o 901-4 F-18 TARGET ROCK VALVE 3A BELLOWS FAILURE, Rev. 7 o 901-5 D-11 PRIMARY CNMT HIGH PRESS, Rev. 11 o 901-7 E-12 GLAND STEAM EXH MOTOR TRIP, Rev. 3 QCGP 1-1, Normal Unit Startup, Rev. 87 QCGP 2-3, Reactor Scram, Rev. 74 QCGP 4-1, Control Rod Movement and Control Rod Sequence, Rev. 38 QGA 100, RPV Control, Rev. 9 QGA 200, Primary Containment Control, Rev. 9 QGA 500-1, RPV Blowdown, Rev. 13 QCOA 0300-6, Control Rod Drive Flow Control Valve Failure, Rev. 6 QCOA 0600-08, Feedwater Regulator Positioner Failure, Rev. 11 QCOP 0280-01, Reactor manual Control Operation, Rev. 16 QCOP 0203-01, Reactor Pressure Control Using Manual Relief Valve Actuation, Rev. 13 QCOP 0600-02, Placing Main Feedwater Regulator Online or Offline, Rev. 22 QCOP 0600-18, Main Feedwater Regulator Operation, Rev. 21 QCOP 1000-30, Post-Accident RHR Operation, Rev. 26 QCOP 1600-20, Nitrogen Inerting of Primary Containment Using the Vaporizer(s) and Reactor Building Ventilation System, Rev. 28 QCOP 3700-02, RBCCW System Startup and Operation, Rev. 26 QCOP 6500-09, Transferring 4 KV Switchgear and Transferring Auxiliary Power, Rev. 14 QCOP 5750-19, Drywell Cooler Operation, Rev. 8

Quad Cities 2012 NRC EXAM Scenario 5 CREW TURNOVER 1.) Plant Conditions:

a.) Unit 1 is at 14% Power.

b.) Unit 2 is at 100% Power.

c.) Technical Specification limitations:

(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.

2.) Significant problems/abnormalities:

The LFFRV is in Manual and closed due to erratic operation in Auto o RPV Water level being controlled by B FRV in Auto per QCOP 0600-02.

3.) Evolutions/maintenance for the oncoming shift:

a.) At QCGP 1-1 Step F.8.p, transfer Aux Power per QCOP 6500-09

RAT Tap Changer is in Manual

BPO and Transmission have been notified.

b.) Continue Drywell Inerting per QCOP 1600-20, Step F.22.

c.) Continue Reactor startup per QCGP 1-1 at Step F.9.

All Step 24 control rods withdrawn to target OUT.

d.) EOs on shift:

Burke Parrish Foster Richardson Hughes Brewer Decker Schmidt

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 1 Page 1 of 1 Event

Description:

Transfer Aux Power Time Position Applicants Actions or Behavior SRO Directs and supervises transfer of Aux Power per QCOP 6500-09 BOP Places Synch Switch in XFMR 11 to BUS 11 ACB and turns it ON BOP Verifies XFMR 11 and Bus 11 are in phase with approximately equal voltages BOP Closes XFMR 11 to BUS 11 ACB BOP Verifies Annunciator 901-8 D-1 is LIT BOP Opens XFMR 12 to Bus 11 ACB BOP Verifies Annunciator 901-8 D-1 is resets BOP Places Synch Switch in XFMR 11 to BUS 11 ACB to OFF BOP Places Synch Switch in XFMR 11 to BUS 14 GCB and turns it ON BOP Verifies XFMR 11 and Bus 14 are in phase with approximately equal voltages BOP Closes XFMR 11 to BUS 14 GCB BOP Verifies Annunciator 901-8 B-5 is LIT BOP Opens XFMR 12 to Bus 14 GCB BOP Verifies Annunciator 901-8 B-5 is resets BOP Places Synch Switch in XFMR 11 to BUS 14 GCB to OFF SRO Notifies BPO (Generation and Transmission) that transfer of Aux Power is complete SIMOP ROLE PLAY: As BPO (Generation and Transmission) to acknowledge that Aux Power transfer complete.

SRO Notifies NDO and Transmission that T-12 Load Tap Changer is to be placed in Auto SIMOP ROLE PLAY: As NDO and Transmission to acknowledge that T-12 Load Tap Changer is to be placed in Auto BOP Directs an EO to place the RAT Load Tap Changer in Auto SIMOP ROLE PLAY: As the EO dispatched to the RAT, acknowledge the directive to place the RAT Tap Changer in Auto. (No commands)

Wait 5 minutes and then report that the RAT Load Tap Changer is in Auto.

BOP Checks STATOR OUTPUT VOLT at nominal, 18KV, voltage BOP Verifies UAT load is less than 4100 amps to Bus 11 and less than 2950 amps to Bus 14 ATC Monitors reactor controls and indications End of Event 1

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 2 Page 1 of 1 Event

Description:

Withdraw Control Rods for Startup Time Position Applicants Actions or Behavior EVALUATOR NOTE: See Event 3, which must be initiated during control rod withdrawal.

SRO Directly supervises control rod moves and directs the RO to begin the load increase ATC (CONTINUOUS) Monitors reactor parameters ATC Selects an in-sequence control rod ATC On the RWM verifies proper rod selected, its current position and bounds ATC Communicates to the QV. Ready to withdraw Rod __-__from position

__ to position __ using continuous withdrawal.

QV Replies: Rod __-__ is selected. Understand withdrawing __-__ from position __ to position __ using continuous withdrawal.

ATC Replies: That is correct ATC Verifies control rod and moves it to the desired position ATC/BOP Place keeps rod moves in the rod movement book ATC Repeats above steps as necessary BOP Adjusts DEHC Load Set to maintain it approximately 10% above Main Generator Load BOP Monitors balance of plant parameters EVALUATOR NOTE: After Event 3 and when an adequate reactivity manipulation has been performed, proceed to Event 4.

End of Event 2

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 3 Page 1 of 1 Event

Description:

CRD Flow Control Valve fails closed Time Position Applicants Actions or Behavior This malfunction will be caught either by the CRD parameters or by the inability to move control rods. For this reason it must be inserted while the crew is moving rods.

SIMOP: When 2 rods have been withdrawn to position 48 in Step 25, fail the CRD Flow Control Valve. imf rd11 0 2: Flow Controller Failure to 0 on a 2 minute ramp.

Key Parameter Response: Inability to withdraw control rods, CRD Drive Pressure and Cooling Flow fails to 0 over 2 minutes Expected Annunciator(s): None Automatic Actions: None ATC Reports inability to withdraw rods or CRD parameters abnormal ATC Diagnoses and reports apparent CRD flow controller failure SRO Directs RO to perform actions of QCOA 0300-06 ATC Places CRD flow controller in MAN ATC Adjusts flow to 60 gpm. (Flow adjustments in MANUAL will override the malfunction and flow should respond by increasing.)

ATC/BOP MAY dispatch NLO to swap CRD flow control valves SRO/BOP MAY contact the IM Department to investigate CRD Flow Controller failure EVALUATOR NOTE: Swapping CRD flow control valves will have no effect because the fault is with the controller not the valve.

BOP Monitors panels and provides peer checks if requested EVALUATOR NOTE: Return to Event 2 until an adequate reactivity manipulation has been performed End of Event 3

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 4 Page 1 of 1 Event

Description:

Gland Exhauster trip/start standby Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, trip the running Gland Exhauster: trg! 4 Verify the following commands go active:

imf ser901-7e12(4) on, ior dihs156041a(4) trip, and ior lohs156041a4(4) on Key Parameter Response: 1A Exhauster Amber Trip light on and Red Running light off:

Lowering Vacuum on Gland Seal Exhaust Vacuum indication, 1-5140-70 Expected Annunciator(s): 901-7 E-12 GLAND STEAM EXH MOTOR TRIP Automatic Actions: None BOP Responds to annunciator and informs the Unit Supervisor BOP Identifies and reports the loss of 1A Gland Steam Exhauster SRO Directs BOP to perform the actions of the QCAN SRO/BOP Dispatches an EO and or EMD to the tripped breaker SIMOP ROLE PLAY: As the EO, wait 3 minutes after being dispatched and call back to report there is no obvious problem at the breaker and you have contacted EMD to investigate.

BOP Starts the 1B Gland Steam Exhauster BOP Throttles the MO 1-5405B to obtain 10 inches to 15 inches of vacuum as indicated on the 1-5140-70 BOP Throttles closed MO 1-5405A, (holds control switch for 25 sec after full closed indication is received)

ATC Monitors Panel 901-5 parameters SIMOP ROLE PLAY: If summoned to the control room as EMD, tell the crew the problem appears to be with the control switch and it should be left as is until further troubleshooting can be done.

End of Event 4

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 5 Page 1 of 1 Event

Description:

1B Feed Reg Valve Hydraulic Leak Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, contact the NSO as the Field Supervisor to report the following: The B Feed Reg Valve has developed a hydraulic fluid leak and recommend swapping FRVs. The level in the hydraulic fluid reservoir has dropped slightly.

The leaking fluid is being contained. The leak would be isolable if the 1B FRV was taken off line. Recommend shifting to the A FRV.

Key Parameter Response: Report from the Turbine Building Expected Annunciator(s): None Automatic Actions: None ATC Relays report to the Unit Supervisor SRO Directs shifting to the 1A FRV per QCOP 0600-02 ATC Shifts to the 1A FRV as follows: (QCOP 0600-02, Steps F.4 & F.5)

ATC Verifies 1B FRV in AUTO ATC Verifies 1A FRV is in Remote Manual and is closed ATC Verify the 1A FRV is unisolated /MO-1-3206A is open ATC Verifies on the OWS FWLC Overview Display Second FRV Control is in SEQUENCE MANUAL ATC Slowly increases the position demand signal on the 1A FRV controller until the valve is at the desired position ATC Verifies RPV water Level being properly maintained.

ATC Places 1A FRV controller in AUTO on the controller or via the OWS ATC Places 1B FRV 1-640-19B in MAN on the controller or via the OWS ATC Verifies that 1A FRV is maintaining RPV water Level ATC Slowly closes 1B FRV ATC Verifies RPV water Level being properly maintained SRO Direct the Field Supervisor to isolate the hydraulic leak SIMOP ROLE PLAY: As the Field Supervisor: Acknowledge the directive to isolate the hydraulic leak.

BOP Monitors Balance-of-Plant equipment End of Event 5

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 6 Page 1 of 1 Event

Description:

Breaker failure on a Drywell Spray Valve Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, trip the MO 1-1001-23A breaker:

irf rh19ar open Then contact the Control Room an EO in the Reactor Building with the following report::

There is an acrid odor near MCC 18-1B. There is no fire. When investigating, the breaker to MO-1-1001-23A was found tripped. EMD has been contacted.

ATC Monitors Reactor and Reactor Pressure Vessel indications BOP Confirms that the A RHR Loop Outboard Drywell Spray Valve appears Deenergized BOP Monitors Balance-of-Plant equipment SRO Enters the following Tech Spec / TRM conditions:

Drywell Spray Valve MO 1-1001-23A is inoperable resulting in a 7 Day LCO per TLCO 3.6.a Condition A As a power operated PCIV, it has been closed and deactivated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per TS 3.6.1.3 Condition A TS 3.3.3.1 PAM Instrumentation for PCIV Position indication has also been satisfied by the closed/deactivated valves per Table 3.3.3.1-1 Note (a)

End of Event 6

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 5 Event No: 7 Page 1 of 1 Event

Description:

Emergency Swap of RBCCW Pumps Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, contact the NSO and report the following:

The 1B RBCCW Pump is running without oil due to a broken bubbler and the pump is extremely hot.

Key Parameter Response: On the 912-1 panel: Pump indications, RBCCW Header Pressure Expected Annunciator(s): None Automatic Actions: None ATC/BOP Relays the report to the Unit Supervisor SRO Directs the BOP to start the 1/2C RBCCW Pump and secure the 1B Pump BOP Places the 1/2C RBCCW Pump in operation per QCOP 3700-02 SIMOP ROLE PLAY: Unit 2 operator as necessary when questioned about the use of the 1/2C RBCCW Pump: The 1/2C RBCCW Pump is not needed for Unit 2.

BOP/SRO Verifies that the 1/2C RBCCW Pump is not required for Unit 2 operation SIMOP ROLE PLAY: As the EO at the RBCCW Pumps: Acknowledge the directives to line up the 1/2C RBCCW Pump.

BOP Directs EO to lineup the 1/2C RBCCW to Unit 1 and vent the pump (QCOP 3700-02 Step F.4.b through F.4.d or Hard Card Steps 1.b-1.d)

Verify the 1/2C RBCCW pump suction and discharge valves to U-2 2-3799-68 and 2-3799-66 are locked closed Open the 1/2C RBCCW pump suction and discharge valves to U-1 1-3799-68 and 1-3799-66 valves Vent the 1/2C RBCCW pump SIMOP ROLE PLAY: As EO, wait 2 minutes and report back the 1/2C RBCCW pump is lined up to Unit 1 and vented per QCOP 3700-02 steps F.4.(b) through F.4.(d).

BOP Starts the 1/2C RBCCW pump from Bus 19 (preferred) or Bus 29 BOP Stops the 1B RBCCW pump BOP Verifies RBCCW header pressure is normal (in green band)

SIMOP ROLE PLAY: As the EO at the RBCCW Pumps: Acknowledge the directives to isolate the 1B RBCCW Pump. (No simulator commands) Wait 2 minutes to report completion.

BOP Directs the EO to close the 1B RBCCW Pump Suction and Discharge Valves, 1-3799-61 & 59 ATC Monitors Reactor controls and indications ATC If directed, monitors Reactor Recirculation pump seal temperatures End of Event 7

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 8 Page 1 of 1 Event

Description:

Target Rock Relief bellows failure Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner Insert Malfunction: imf ser0698 on Key Parameter Response: Annunciator only, no change to Drywell parameters Expected Annunciator(s): 901-4 F-18 TARGET ROCK VALVE 3A BELLOWS FAILURE Automatic Actions: None BOP Responds to Annunciator and informs the Unit Supervisor BOP Verifies that the 3A SRV has not lifted BOP Verifies the 3A SRV indicates closed on the Acoustic Monitor BOP Verifies Point 9 not increasing on TR 1-260-20 (Panel 901-21)

BOP Monitor for increased leakage into the Primary Containment BOP Monitor Drywell Air Temperatures BOP Monitor Drywell Pressure SRO Identify that the bellows leak makes the Target Rock inoperable as a Safety valve SRO Enters Tech Spec 3.4.3 Condition C for one or more Safety Valves inoperable; be in mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Mode 4 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (Note: TS 3.4.3 Condition A applies only to the relief function of the Target Rock valve and TS 3.5.1 applies only to the ADS function of the Target Rock Valve and are therefore not applicable)

ATC Monitors Reactor and Reactor Pressure Vessel indications End of Event 8

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 9 Page 1 of 5 Event

Description:

Drywell Pressure rising, Manual Scram/ Alternate Rod Insertion Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, insert a Main Steam Line break inside the containment: imf ms04C 0.5 10: (0.5% severity ramped over 10 minutes)

Key Parameter Response: Drywell Pressure Rising; RPS Scram Solenoid Group Lights do not extinguish and control rods do not insert Expected Annunciator(s):

901-3 A-14 TORUS HIGH/LOW LEVEL (Clears is 1.5 minutes) 901-3 A-13 DW LOW PRESS CNTM SPRAY INHIBITED (Clears is 2 minutes) 901-3 A-16 PRIMARY CONTAINMENT HIGH PRESSURE (1.5 psig alarm in 2.5 minutes)

Automatic Actions: (Not a complete list) Group 2 Isolation, CR and RB Vents isolate, ECCS systems initiate, EDGs start (Auto Scram disabled)

BOP Respond to annunciators and inform the US BOP Confirms rising Drywell Pressure CREW Determine the rate of Drywell Pressure rise BOP/SRO Enters and performs QCOA 0201-01 BOP/SRO Notify Radiation Protection SIMOP ROLE PLAY: Radiation Protection personnel as necessary BOP May start additional Drywell Cooler Fans SRO May set Scram Criteria of 2 psig Drywell Pressure ATC As directed attempts to manually scram reactor or recognizes that the Auto Scram at 2.5 psig Drywell Pressure did not occur ATC Recognizes that Manual/Auto Scram signals did not trip RPS ATC Announces Reactor Scram and no rod movement SRO Enters QGA 100 and transitions to QGA 101 ATC Takes the Reactor Mode Switch to SHUTDOWN ATC Recognizes that Mode Switch to SHUTDOWN did not trip RPS CT1 ATC Arms and depresses ARI buttons ATC May verify Scram Valve Air Supply Pressure Lowering, Annunciator 901-5 A-1 alarming ATC Verify Control Rods inserting ATC Adjusts both Recirc Pumps to minimum speed Event 9 Continued

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 9 Page 2 of 5 Event

Description:

Drywell Pressure rising, Manual Scram/ Alternate Rod Insertion Time Position Applicants Actions or Behavior ATC Verifies all Control Rods are fully inserted SRO Exits QGA 101 and enters QGA 100 SRO Directs actions of QCGP 2-3 SRO Directs ATC/BOP to verify 0 inches RPV water level isolations ATC/BOP Verifies isolation for 0 inches reactor water level ATC Identifies that the SDV vent and drain valves are NOT closed and closes them with the pushbuttons on Panel 901-5 ATC Attempts to maintain RPV level 0 to +48 inches with high-pressure injection systems Verifies DFWLC in Single Element May isolate Feed Water Reg Valve(s)

May place Low Flow Feed Reg Valve in Service May secure unnecessary Feed and Condensate Pumps ATC (CONTINUOUS) Monitors RPV water level and pressure ATC Recognizes that automatic insertion of SRMs and IRMs did not occur and manually inserts them ATC Verifies Main Turbine trips, all SVs, CVs, ISVs, IVs and extraction steam check valves close ATC Verifies Hood Spray AO 1-3399-559 is open ATC Verifies Main Generator Output Breakers tripped after 30 seconds and places control switches in PTL ATC Verifies Main Generator Field and Exciter Field Breakers (alarm 901-8 H-9) tripped ATC Verifies all 4 KV buses powered from T-12 ATC Verifies both Recirc Pumps running at minimum speed in Manual (may be tripped due to DW pressure)

ATC Starts the Control Room AFU Booster Fan within 40 minutes ATC Dispatches EO to reset the Generator 86 Relays SIMOP ROLE PLAY: As EO, acknowledge the directive to reset 86 Relays as necessary.

Event 9 Continued

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 9 Page 3 of 5 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior BOP Monitors Containment parameters and reports QGA 100 & 200 entry when Drywell pressure is greater than 2.5 psig SRO When DW pressure exceeds 2.5 psig, re-enters QGA 100 and enters QGA 200 SRO Directs ATC/BOP to verify 2.5 psig Drywell pressure isolations and auto starts ATC/BOP Verifies Group 2 and 3 Isolations, RB vent isolation and SBGT start ATC/BOP Verifies 2.5 psig Drywell pressure ECCS initiations ATC/BOP Stabilize RPV Pressure less than 1060 psig with the Turbine Bypass Valves BOP Monitors and reports Primary Containment parameters and trends ATC/BOP Reports ECCS auto started ATC/BOP Controls HPCI injection manually or trip latches HPCI after SRO concurrence ATC/BOP Verifies Diesels auto started BOP As directed, verifies 1A and 1B CAMs operating SRO May direct actions to start all available drywell cooling ATC/BOP As directed, restores RBCCW and DW coolers per QCOP 5750-19 ATC/BOP Verifies Bus 18 and 19 voltage greater than 450 volts ATC/BOP Takes the U1 DIV I DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position ATC/BOP Takes the U1 DIV II DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position ATC/BOP Verifies DIV1/DIV 2 DW CLR/FPC RBCCW TRIP BYP annunciator lit ATC/BOP Checks Drywell temperature is less than 260 °F ATC/BOP Starts 1A and 1/2C RBCCW pumps ATC/BOP Starts drywell coolers one at a time ATC/BOP Starts Drywell Booster Fan ATC/BOP May direct an EO to start previously running Fuel Pool Cooling Pumps (with SRO concurrence)

Event 9 Continued

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 9 Page 4 of 5 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior SRO Verifies Torus level less than 27 ft.

SRO Before Torus Pressure reaches 5 psig, directs BOP to place Torus Sprays on IAW QCOP 1000-30 BOP Maintains the following during Post-Accident RHR Operation:

RHR Service Water Pressure 15-20 psig greater than RHR Pressure RHR Service Water flow less than 3600 gpm/pump RHR Pressure 100-250 psig BOP Prepares RHR for Operation BOP Verifies RHR Pumps running EVALUATOR NOTE: The LOOP B CONTAINMENT COOLING PERMISSIVE switch is overridden off.

BOP Places LOOP A/B CONTAINMENT COOLING PERMISSIVE Switch 17 to ON BOP Places LOOP A/B RHR SW START PERMISSIVE Switch 19 to MANUAL OVERRIDE BOP As directed, initiates Torus Sprays per QCOP 1000-30 BOP Opens MO 1-1001-34A/B BOP Opens MO 1-1001-37A/B BOP Opens/Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure BOP Starts RHR Service Water BOP Opens MO 1-1001-5A/B to approximately 40%

BOP Starts A/B RHR SW Pump BOP Throttles MO 1-1001-5A/B as necessary BOP Throttles MO 1-1001-16A/B as necessary BOP If B Loop Torus Spray is attempted, recognizes and reports that the B Loop Torus Sprays will not open SRO Directs BOP to secure Torus Sprays before Torus Pressure drops to 0 psig SRO If Torus water temperature cannot be held less than 95°F, directs start of all available Torus Cooling Event 9 Continued

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 9 Page 5 of 5 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior BOP As directed, initiates Torus Cooling per QCOP 1000-30 BOP Opens MO 1-1001-34A/B BOP Adjusts Torus H2O Test Valve MO 1-1001-36A/B to maintain RHR SW Pressure 15-20 psig higher than RHR pressure and RHR pressure between 100 and 250 psig BOP If B Loop Torus Cooling is attempted, recognizes and reports that the B Loop Torus Cooling valves will not open SIMOP: If PSP Blowdown conditions will not be met and when directed by Lead Examiner, modify the leak to 4%. mmf ms04C 4 BOP Reports Torus pressure greater than 5 psig.

SRO Verifies Torus level less than 17 ft.

SRO Verifies inside DW Spray Limit Curve SRO Verifies Recirc pumps and DW Coolers are tripped SRO Directs BOP to start DW Sprays BOP As directed, attempts to initiate Drywell Sprays per QCOP 1000-30 by opening MO 1-1001-23B and MO 1-1001-26B BOP Recognizes and reports that the B Loop Drywell Sprays will not open SRO/BOP Directs EO investigate 23B & 26B valve breaker and locally open the Containment spray valve(s)

SIMOP ROLE PLAY: If requested to locally operate the B Drywell Spray valves, wait 2 minutes and then open the breakers for MO 1-1001-23B and 26B:

irf rh19br open and irf rh20br open Wait an additional 5 minutes and report that MO 1-1001-23B and 26B cannot be opened.

BOP May open MO 1-1001-26A and direct the EO to manually open MO 1-1001-23A on the A Loop Drywell Sprays SIMOP ROLE PLAY: If dispatched to manually open the MO 1-1001-23A, wait 5 minutes report back that the declutch lever is broken and you are getting maintenance to assist.

End of Event 9

Quad Cities 2012 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 5 Event No: 10 Page 1 of 1 Event

Description:

Emergency Depressurization when PSP exceeded Time Position Applicants Actions or Behavior SRO Enters QGA 500-1 to blowdown the vessel when it is determined drywell temperature cannot be restored below 280ºF or torus pressure cannot be maintained within PSP limits Crew Recognizes that the MSIVs have closed and may begin investigation SRO Directs actions of QGA 500-1 ATC/BOP Prevent injection from Core Spray and LPCI not needed for Core Cooling by diverting LPCI flow to Torus cooling and/or placing pumps in PTL ATC Maintains Rx water level with Feed/Condensate SRO Verifies Torus level greater than 5 feet CT2 SRO Directs opening of all ADS valves and leaving switches in MAN CT2 ATC/BOP Opens all ADS valves, leaves switches in MAN IAW QCOP 0203-01, Manual Relief Valve Actuation, using hard card BOP Verifies all ADS valves open by acoustic monitor indication on the 901-21 panel ATC If RPV water level exceeds +48 inches, verifies RFPs tripped ATC/BOP Monitors level instrument watching for indications of saturation and informs SRO End of Event 10 SIMOP: When Blowdown has been performed and/or at the discretion of the Lead Examiner, Place the simulator in FREEZE.

(Final)

Quad Cities 2012 NRC EXAM Scenario 4 Exelon Nuclear 2012 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 4 Revision Number: 00 Date: 03/04/12 Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 4 Op-Test No.: ILT 10-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 80% power. Holding power for QNE verification of thermal limits.

The 1C Circ Water Pump is out of service.

Turnover: Perform the Acoustic Monitor Test for SRVs 3A, 3B, and 3C.

Event No.

Malf. No.

Event Type*

Event Description 1

None BOP N

Perform Acoustic Monitor Test 2

FW18C FW19C ATC C

Respond to a Condensate/Cond Booster Pump degraded capacity 3

RM05A SRO TS Drywell Radiation Monitor Fails Upscale TS 4

AIPIC1874011 BOP C

DW N2 pressure control fails upscale (QCOA 0201-01) 5 MC01B ATC R

Loss of a Circ Pump / Emergency Power Reduction for Condenser Backpressure (QCOA 4400-04) 6 ED10 ED11 ATC C

Respond to Loss of ESS Bus TS (QOA 6800-03) 7 CR01 HP12 HP13 Crew M

Fuel failure. QCOA 1700-4 will require the crew to close the MSIVs. An unisolable leak in the HPCI room requires the crew to enter QGA 300 and 100.

8 CR02 Crew M

When the Torus Area also exceeds Max Safe Temperature or Radiation, the crew will Emergency Depressurize per QGA 500-1.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:

Total Malfunctions (5-8): 7 Malfunction(s) after EOP (1-2): E8 Abnormal Events (2-4): E4, 5, 6 & 7 Major Transient(s) /E-Plan entry (1-2): E7 EOPs (1-2): QGA 300, QGA 100 EOP Contingencies (0-2): E8 Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:

BOP Normal: E1 ATC Reactivity (1 per set): E5 BOP I/C (4 per set): E4 ATC I/C (4 per set): E 2 & 6 SRO-I I/C (4 per set inc 2 as ATC): E2,4,& 6 SRO Tech Spec (2 per set): E3 & 6 ALL Major Transients (2 per set) E7

Quad Cities 2012 NRC EXAM Scenario 4

SUMMARY

Initial Conditions:

o The plant is operating at 80% power. Holding power for QNE verification of thermal limits.

o 1C Circ Water Pump out of service for coupling repair.

Event 1: The BOP performs a partial Acoustic monitor test, QCOS 0203-01 for SRVs 3A, 3B, and 3C.

Event 2: The ATC responds to degraded capacity of a Condensate/Condensate Booster pump by shifting to the standby pump.

Event 3: Operators respond to an unexpected 1/2 Group 2 Isolation and determine that the A Drywell Rad Monitor has failed (upscale). The SRO enters Technical Specifications (PCI) 3.3.6.1 Condition A and (PAM) 3.3.3.1 Condition A.

Event 4: Drywell N2 controller fails, causing the makeup valve to open fully. The BOP can take manual control of the valve and close it to stabilize Drywell pressure. Without operator action, Drywell pressure will continue to rise and eventually exceed the Drywell High Pressure alarm setpoint. If drywell pressure exceeded 1.5 psig, the SRO will address Tech Spec 3.6.1.4 Condition A to restore to within limits in one hour.

Event 5: The BOP responds to Loss of a Circ Pump (1 Pump operation) per QCOA 4400-04.

The ATC and SRO perform Emergency Power Reduction for loss of a Circ Pump per QCOA 4400-04. Reducing Reactor power to within the capacity of one Circ Water Pump stabilizes condenser vacuum.

Event 6: ESS UPS failure. The crew will respond per QOA 6800-03. Equipment Operator actions can restore the bus. The BOP will restore the SJAE lineup. The ATC will reset the lockup of a Feed Reg Valve and reset the partial Group 1 Isolation. The SRO should reference Technical Specifications 3.5.1 Conditions G & I and 3.5.3 Conditions A & B for HPCI and RCIC Inoperable.

Event 7: A fuel element failure begins. The crew will respond to High Offgas radiation per QCOA 1700-04. When SJAE Rad levels cannot be maintained less than High-High alarm, the crew will isolate Offgas, Scram, and close the MSIVs/Drains. A leak in the HPCI room then begins that requires the crew to enter QGA 300. The crew will attempt to isolate the leak, but the leak cannot be isolated.

Event 8: When the Torus Area also exceeds Max Safe Radiation level, the crew will Emergency Depressurize the RPV.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical Task #1: The Crew will take action to isolate the RPV and reduce the release of radioactivity by manually closing the MSIVs, Main Steam drains and verifying the Offgas System is isolated as required.

Critical task #2: Given an operating reactor plant with a primary system discharging into the reactor building and the discharge cannot be isolated, INITIATE an emergency depressurization when two or more areas exceed the maximum safe operating levels of the same parameter (radiation, temperature, or water level).

Quad Cities 2012 NRC EXAM Scenario 4 EXERCISE PERFORMANCE OBJECTIVES SR-0203-P04 Given an operating plant, perform the Monthly Safety and Relief Valve Acoustic Monitor Surveillance in accordance with QCOS 0203-01 SR-3300-P01 Given a reactor plant during a startup, start the condensate system in accordance with QCOP 3300-02.

SR-0201-P01 Given a reactor plant at power when a small LOCA inside the drywell occurs, take actions to attempt to locate and isolate the leak in accordance with QCOA 0201-01.

SR-6800-P08 Given an operating reactor plant when a complete loss of ESS power occurs, take actions to control plant parameters and restore ESS power in accordance with QOA 6800-03. (SOER 81-2 r5 / SOER 83-3 r11)

SR-0002-P05 Given a reactor plant at power, perform a power change discernible on neutron monitors using recirc flow in accordance with QCOP 0202-03 and QCGP 3-1.

SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.

SR-1700-P03 Given a reactor plant at power and a fuel clad failure or high activity in off-gas, take action to reduce the release in accordance with QCOA 1700-05 or QCOA 1700-04.

SR-0001-P41 Given an operating reactor plant with a primary system discharging into the reactor building, verify manual scram, enter/re-enter QGA 100 before any area exceeds the maximum safe operating temperature/radiation/water level in accordance with QGA300. (BWROG SC-1.1)

SR-0001-P42 Given a reactor plant with a primary system discharging into the reactor building and the discharge cannot be isolated, verify/initiate an emergency depressurization when two or more areas exceed the maximum safe operating levels of the same parameter (radiation, temperature, or water levels) in accordance with QGA 300 and QGA 500-1.

Quad Cities 2012 NRC EXAM Scenario 4 Simulator Setup:

1. Reset to IC-20. (75% power)

2. Go to RUN.

3. Raise Master Recirc Pump Speed Controller to 66% (80% RTP).

4. Verify the following RWM Sequence is loaded: C22SU Initial the Control Rod Move Sheet as necessary to update to the current rod positions.

(The following commands to be utilized for this scenario are contained in the CAEP file:

2012 NRC Scenario 4.cae)

5. Insert Commands for setup:

ior dihs13302 p2c_off (Cond Pump Select Switch OFF; disables auto start) ior lohs13302a4 on (1A Cond Pump (white) Standby light overridden ON) trgset 2 zdihs13302a(5) (When 1A Cond Pump HS is taken to START) trg 2 dor lohs13302a4 (On Trigger 2, 1A Cond Pump Standby light override deleted) imf ed11(5) (Uninterruptible Power Supply failure on Event Trigger 5) imf ed10(5) (120/240 VAC Essential service Bus Failure on Event Trigger 5) trgset 7 zdihs10590300(1).eq. 1 (When Mode Switch is taken to Shutdown) imf cr02(7) 2 30: (On Trigger 7, Gross Fuel Failure at 2% Severity, 30 minute ramp) imf hp13(7) 100 30: (On Trigger 7, HPCI Steam Leak to 100 Severity, 30 min ramp) imf hp12a 100 (HPCI Steam Supply Isol MO 1-2301-4 binding) imf hp12b 100 (HPCI Steam Supply Isol MO 1-2301-5 binding)

6. Verify the following commands for scenario performance:

imf fw18c 100 (1C Cond Pump degraded capacity at 100% severity) imf fw19c 100 (1C Booster Pump degraded capacity at 50% severity) irf fw29r ackn (Resets Demin Trouble 901-6 F-12 Annunciator) imf rm05a 100 0:10 (A DW Rad Monitor fails upscale on 10 second ramp) ior aipic1874011a 100 2: (DW Pressure controller fails upscale on a 2 minute ramp) imf mc01b (B Circ Water Pump Trip) irf mc18ar bypass (1A Circ Water Pump LOCA Trip switch to BYPASS) trg! 5 (Manually activate Event Trigger 5 to initiate Event 5, Loss of ESS UPS) dmf ed10 (Deleting this malfunction simulates successful local operation of the ABT) irf eg09r ack/rst (Resets the Hydrogen Seal Oil Panel Trouble alarm) imf cr01 100 10: (Fuel element Failure at 100% severity on a 10 minute ramp) mrf sw10r run (Locally start the U1 EDG CWP as requested) imf cr02 2 30: (As needed, Gross fuel failure to 2% severity on a 30 min ramp) bat fireout (Silences Fire Alarm from HPCI Room High Temp) imf rm0115 60 15: (As needed, Torus Area ARM to greater than Max Safe in 15 minutes)

(Continued)

Quad Cities 2012 NRC EXAM Scenario 4 Simulator Setup:

7. Perform the following control panel setups:

Take the 1C Circ Water Pump to PTL and hang an Out of Service Tag.

Place the Condensate Booster Pump Min Flow Valve (CBPMFV) in MANUAL and CLOSED. Hang an EST.

On N2 Flow Controller 1-1640-11:

o Shift to Manual o Adjust potentiometer to 50%

o Return to Auto o Verify SBO alarms clear.

8. Provide a 40% Load Drop REMA.

9. Provide a current revision of the following procedures, signed off as specified:

QCOS 0203-01, filled out to test only A, B & C relief valves for PMTs.

10. Need to have blank EST available for use during the scenario.

11. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.

Quad Cities 2012 NRC EXAM Scenario 4 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-1 RX BLDG HI RADIATION, Rev. 4 o 901-3 C-2 OFFGAS HIGH HIGH RADIATION, Rev. 8 o 901-3 D-2 OFFGAS HI RADIATION, Rev. 12 o 901-3 E-14 ACOUSTIC MON SAFETY RLF VALVES OPEN, Rev. 7 o 901-3 F-12 HPCI PUMP AREA HI TEMP, Rev. 7 o 901-3 H-2 AREA HI TEMP STEAM LEAK DETECTION, Rev. 6 o 901-4 A-5 RRCS/ASD MINOR FAILURE, Rev. 5 o 901-5 A-8 GROUP 2 ISOL CH TRIP, Rev. 14 o 901-5 D-11 PRIMARY CNMT HIGH PRESS, Rev. 11 o 901-5 D-8 CONTROL ROOM VENT ISOLATED, Rev. 2 o 901-6 A-6 COND PUMP DISCHARGE LOW PRESSURE, Rev. 8 o 901-6 F-12 COND DEMIN TROUBLE, Rev. 7 o 901-6 G-5 COND BOOSTER PUMP SUCTION LOW PRESSURE, Rev. 8 o 901-7 A-15 CIRC WATER PUMP AUTO TRIP, Rev. 8 o 901-7 H-3 CONDENSER LO VACUUM 24 IN HG, Rev. 9 o 901-8 B-8 120/240 ESS SERV BUS LOW VOTAGE, Rev. 5 o 901-8 F-8 ESS SERV UPS TROUBLE, Rev. 3 o 901-55/56 A-1 DRYWELL HIGH RAD CONC, Rev. 10 QCGP 2-3, Reactor Scram, Rev. 74 QCGP 3-1, Reactor Power Operations, Rev. 66 QCGP 4-1, Control Rod Movements and Control Rod Sequence, Rev. 38 QGA 100, RPV Control, Rev. 9 QGA 300, Secondary Containment Control, Rev. 12 QGA 500-1, RPV Blowdown, Rev. 13 QCOA 0201-01, Increasing Drywell Pressure, Rev. 23 QCOA 0201-05, Primary System Leaks Outside Primary Containment, Rev. 9 QCOA 1700-04, Abnormal Offgas Radiation, Rev. 16 QCOA 1700-05, Abnormal Main Steam Line Radiation, Rev. 19 QCOA 1800-01, Area High Radiation, Rev. 6 QOA 3300-02, Loss of Condenser Vacuum, Rev. 38 QCOA 4400-04, Reactor Operation With Only One Circ Water Pump Available, Rev. 22 QOA 6800-03, 120/240 VAC Essential Service Bus Failure, Rev. 43 QCOS 0203-01, Safety and Relief Valve Acoustic Monitor Surveillance, Rev. 12 QOP 3300-11, Condensate/Condensate Booster Pump Changeover, Rev. 24

Quad Cities 2012 NRC EXAM Scenario 4 CREW TURNOVER 1.) Plant Conditions:

a.) Unit 1 is at 80% Power after Turbine Testing. Holding power for QNE verification of thermal limits.

b.) Unit 2 is at 100% Power.

c.) Technical Specification limitations:

(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.

2.) Significant problems/abnormalities:

a.) 1C Circ Water Pump out of service for coupling repair.

b.) The Condensate Booster Pump Min Flow Valve (CBPMFV) in MANUAL due to erratic operation in Auto.

3.) Evolutions/maintenance for the oncoming shift:

a.) Perform partial Acoustic monitor test, QCOS 0203-01 for 3A, 3B, and 3C Relief Valves only.

b.) EOs on shift:

Burke Parrish Foster Richardson Hughes Brewer Decker Schmidt

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 1 Page 1 of 2 Event

Description:

Perform Acoustic Monitor Test, QCOS 0203-01 Time Position Applicants Actions or Behavior EVALUATOR NOTE: Be prepared to initiate Event 2 for the ATC operator while this event is in progress.

SRO Directs BOP to perform partial QCOS 0203-01 to test the Acoustic monitors on 3A, 3B and 3C Relief Valves and supervises as necessary BOP Performs partial QCOS 0203-01 to test the Acoustic monitors on A, B and C relief valves only BOP (H.1) Selects desired valve BOP (H.2) Places display switch in I, checks and records INPUT values BOP (H.3) Determines THRESHOLD setpoint BOP Places display switch in T BOP Records THRESHOLD setpoint BOP Returns display switch to I BOP (H.4) Tests alarms and indications BOP Places and holds TEST/RESET switch in TEST BOP Verifies Input level greater than Threshold setpoint BOP Verifies Open (Red) comes ON and Closed (Green) goes OFF as Threshold setpoint is reached BOP Verifies MEMORY (Amber) light comes ON BOP Verifies annunciator at Panel 901-3 E-14 ACOUSTIC MON SAFETY RLF VALVES OPEN is received BOP Verifies Process Computer Alarm SAFETY/ELECTROMAGNETIC VLV 203-XX OPEN Event 1 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 1 Page 2 of 2 Event

Description:

Perform Acoustic Monitor Test, QCOS 0203-01 Time Position Applicants Actions or Behavior BOP Releases TEST/RESET switch BOP Verifies Open (Red) light is OFF BOP Verifies Closed (Green) is ON BOP Verifies annunciator at Panel 901-3 E-14 can be cleared BOP Records satisfactory annunciator response BOP Verifies PPC Alarm SAFETY/ELECTROMAGNETIC VLV 203-3C(3D)(3E) CLOSED BOP Records satisfactory Computer Alarm response BOP Momentarily places TEST/RESET switch in RESET BOP Verifies MEMORY (Amber) light goes OUT BOP (H.5) Verifies proper operation of acoustic monitor:

o Input level less than 0.09 prior to testing o Acoustic Monitor alarms when Threshold setpoint is exceeded o Threshold Setpoint is greater than or equal to.09 and less than or equal to.11 when display switch is in the T position BOP (H.6) Records discrepancies as necessary BOP Repeats Steps H.1 through H.6 for remaining valves ATC Monitors Reactor and Reactor Pressure Vessel indications End of Event 1

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 2 Page 1 of 2 Event

Description:

Respond to a Condensate/Cond Booster Pump degraded capacity Time Position Applicants Actions or Behavior EVALUATOR NOTE: This is an ATC I/C failure, not BOP. Consider initiating this event during Event 1. (The 3rd time that annunciator 901-3 E-14 activates is suggested)

SIMOP: When directed by the Lead Examiner, degrade the capacity of the 1C Condensate/Cond Booster pump as follows:

imf fw18C 100 C Condensate Booster Pump degraded capacity imf fw19C 100 C Condensate Pump degraded capacity Key Parameter Response: 1C amps will be significantly lower than 1B & 1D amps. 1B &1D amps, Booster Pump Discharge Pressure, and RFP Suction Pressure will be unstable Expected Annunciator(s):

901-6 A-6 COND PUMP DISCHARGE LOW PRESSURE 901-6 G-5 COND BOOSTER PUMP SUCTION LOW PRESSURE 901-6 F-9 REACTOR FEED PUMP SUCTION LOW PRESSURE 901-6 F-12, COND DEMIN TROUBLE Automatic Actions: None ATC Responds to the annunciators and informs the US SRO Supervise response to the degraded Condensate/Cond Booster Pump and may authorize starting the 1A pump SRO May set Scram Criteria based on RPV Water level less than +11 inches or greater than +44 inches ATC Starts the (Standby) 1A Condensate/Cond Booster pump per QCAN 901-6 A-6 ATC Verifies the Cond Pump Discharge Header Pressure greater than 104 psig.

ATC Verifies the RFP Suction Header Pressure greater than 145 psig.

ATC Monitors Reactor water level ATC Monitors the individual Condensate/Cond Booster pump amps ATC Dispatches an operator to investigate operation of the Condensate/Cond Booster pumps SIMOP ROLE PLAY: As the dispatched EO: Wait 2 minutes then report that the 1C Cond/Cond Booster Pump is making an unusual grinding noise.

ATC Stops the 1C Pump. (Because 4 pumps are not necessary for plant conditions and because it appears to be degraded)

Event 2 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 2 Page 2 of 2 Event

Description:

Respond to a Condensate/Cond Booster Pump degraded capacity Time Position Applicants Actions or Behavior ATC Responds to 901-6 F-12 COND DEMIN TROUBLE ATC Dispatches an operator to the Condensate Demin Panel to investigate local annunciators SIMOP ROLE PLAY: As the dispatched EO: Wait 2 minutes then report that the Demin Trouble was high DP that is now clear and that you will reset the Annunciator Use the following Remote Function to reset the 901-6 F-12: irf fw29r ackn ATC Monitors Condensate Booster Pumps Suction Pressure ATC Monitors Demin DP ATC Verifies the Demin Bypass valve MO-1-3303 remains closed ATC/BOP May direct the EO to shift Hydrogen Injection points on the Condensate/Condensate Booster Pumps per QOP 3300-11:

Open 1-2799-31A Close 1-2799-31C SIMOP ROLE PLAY: If dispatched EO to shift Hydrogen Injection: Wait 2 minutes then report 1-2799-31A is OPEN and 1-2799-31C is CLOSED.

BOP Monitors balance of plant equipment End of Event 2

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 4 Event No: 3 Page 1 of 1 Event

Description:

Drywell Radiation Monitor Fails Upscale Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner, start the Drywell Rad Monitor failure event by inserting malfunction: rm05a 100 0:10 Key Parameter Response: 1-2419A Drywell Radiation Monitor indicating full upscale Expected Annunciator(s):

901-5 A-8, GROUP 2 ISOL CH TRIP 901-55 A-1, DRYWELL HIGH HIGH RAD CONC Automatic Action: 1/2 Group 2 Isolation BOP Acknowledges annunciator 901-55 A-1, DRYWELL HIGH HIGH RAD CONC and reports the 1-2419A Drywell radiation monitor is indicating full upscale.

ATC Acknowledges annunciator 901-5 A-8, GROUP 2 ISOL CH TRIP and refers to annunciator procedure.

SIMOP: Role Play plant support personnel as necessary to acknowledge the following reports.

Crew Contacts Instrument Maintenance (IMD) about Rad monitor failure Crew Contacts Radiation Protection (RP) about Rad monitor failure SRO Confirms the 1-2419B Drywell radiation monitor is indicating normally and no other indications of increasing radiation levels exist on the following:

Main Steam Line Radiation monitors Offgas Radiation monitors Area Radiation monitors SRO Enters the following Technical Specifications for an inoperable Drywell Radiation monitor:

PCI 3.3.6.1, Condition A, Place the Channel in Trip Within 24 Hours PAM 3.3.3.1, Condition A, Restore Required Channel to Operable Status Within 30 Days End of Event 3

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No: 4 Event No: 4 Page 1 of 1 Event

Description:

Drywell N2 controller failure Time Position Applicants Actions or Behavior NOTE: It takes 8 minutes from the time of initiation until the 901-3 A-16 alarms.

SIMOP: When directed by the lead examiner, fail the 1-1640-11 controller using the following command: ior aipic1874011a 100 2:

Key Parameter Response: Containment Pressure Controller Position at 100%

Expected Annunciator(s): 901-3 A-16 PRI CNMT HIGH PRESSURE Automatic Actions: None BOP May identify that Drywell pressure is rising and report to the Unit supervisor BOP Announces rising drywell pressure and/or alarm 901-3 A-16 at 1.55 psig. if/when it alarms SRO Directs BOP to perform actions of QCAN 901-3 A-16 and/or QCOA 0201-01, Increasing Drywell Pressure SRO May set scram criteria of 2 psig Drywell pressure CREW May notify Rad Protection of high containment pressure SRO IF Drywell pressure reaches 1.5 psig enters TS 3.6.1.4 Condition A, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to reduce drywell pressure to less than or equal to 1.5 psig.

BOP May start last Drywell Cooler fan IAW QCOA 0201-01 BOP Reports drywell pressure controller has failed EVALUATOR NOTE: Taking manual control of a failed controller is allowed by QAP 0300-02, Conduct of Shift Operations.

BOP May take manual control of the drywell pressure controller and close it BOP Close the MO 1-1601-57 valve, N2 Makeup Valve BOP Contacts IMD to investigate controller failure SRO IF drywell pressure exceeded 1.5 psig, addresses Tech Spec 3.6.1.4 Condition A to restore to within limits in one hour.

ATC Monitors DW pressure as BOP investigates and prepares for reactor scram SIMOP: Drywell venting is not part of the scenario. Do not wait until it is done to move on.

End of Event 4

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 5 Page 1 of 2 Event

Description:

Loss of a Circ Pump / Emergency Power Reductions for Condenser Backpressure Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, initiate trip the 1B Circ Water Pump:

imf mc01b Key Parameter Response: Main Condenser backpressure rising on PR 1-5640-79; Generator Mwe lowering, B Circ Water Pump Indications Expected Annunciator(s):

901-7 A-15 CIRC WATER PUMP AUTO TRIP 901-7 H-3 CONDENSER LO VACUUM 24 IN HG (in 12 minutes with no operator action)

Automatic Actions: (If alarms not addressed) Reactor Scram and Turbine trip BOP Respond to annunciator 901-7 A-15 and informs the Unit Supervisor BOP/SRO Enter QCOA 4400-04 for Single Circ Water Pump Operation BOP/SRO May enter QOA 3300-02, Loss of Condenser Vacuum Crew Dispatches an EO to investigate SIMOP ROLE PLAY: As the dispatched EO: Wait 2 minutes and then report that the 1B Circ Water Pump tripped for no apparent reason. EMD has been contacted.

BOP Monitors Condenser Backpressure and informs the US that backpressure is rising BOP Verifies the 1B Circ Water Pump Discharge valve is closed BOP May directs that the 1A Circ Water pump LOCA Trip be placed in BYPASS.

SIMOP ROLE PLAY: If dispatched as the EO to bypass the 1A Circ Pump LOCA Trip: Insert Remote Function irf mc18ar bypass Wait 2 minutes and then report that the 1A Circ Water Pump LOCA Trip is in BYPASS.

SRO Initiates Emergency Power Reduction by reducing total core flow or inserting control rods ATC Reduces Reactor Recirculation flow using the manual Runback Pushbuttons, Master Controller, or Individual Controllers as necessary to attempt to maintain Main Condenser backpressure less than 6 in Hg.

Event 5 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 5 Page 2 of 2 Event

Description:

Loss of a Circ Pump / Emergency Power Reductions for Condenser Backpressure Time Position Applicants Actions or Behavior ATC (For FCL greater than 59.4%) Does not reduce core flow to the point of entry into Instability Region 2 or below 53 Mlb/hr.

ATC May insert control rods to maintain FCL within the MELLLA boundary SRO May set scram criteria of 7.0 in. Hg Main Condenser backpressure or loss of all Circ Water Pumps BOP Confirms that Condenser Backpressure is returning to normal SRO Directs the suspension of Emergency Power Reduction ATC Holds Recirc Flow as directed End of Event 5

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 6 Page 1 of 2 Event

Description:

Respond to Loss of ESS Bus Time Position Applicants Actions or Behavior EVALUATOR NOTE: Verify that the Feed Reg Valve positions and RPV Water level are stable before initiating this event.

SIMOP: When directed by the Lead examiner, simultaneously insert malfunction ed10 and ed11 using Event Trigger 5: trg! 5 Role Play in plant operators as necessary.

Key Parameter Response: None Expected Annunciator(s):

901-8 B-8, 120/240 ESS SERV BUS LOW VOLTAGE 901-8 F-8, ESS SERV UPS TROUBLE (Many other annunciators related to components that have lost power.)

(After Transfer) 901-8 E-9, ESS SERV BUS ON EMERG SPLY Automatic Actions: (Not a comprehensive listing) RWCU isolation, SJAE Suction Valves close, A & B Feed Reg Valves Lockup, RFP Min Flow valves fail open, HPCI and RCIC flow controllers fail to manual BOP Responds to Annunciators and informs the Unit Supervisor BOP Sends an operator to the ESS service panel SIMOP ROLE PLAY: As EO; wait 2 minutes and then report that the Unit 1 ESS UPS normal power supply has apparently failed and the ABT did not automatically swap to the emergency supply.

ATC (Continuous) Monitors RPV Water Level ATC Verifies that feedwater regulating valves have locked up ATC Verifies RFP Minimum Flow Valves fail open ATC May dispatch an EO to perform local-Manual operation of the FRVs ATC Verifies RWCU Isolation SRO Directs actions of QOA 6800-03 to reenergize the ESS Bus SRO May direct Emergency Power Reduction to control RPV water level ATC Lowers Recirc Flow to control RPV water level as directed SRO May set Scram Criteria based on RPV Water level less than +11 inches or greater than +44 inches Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 6 Page 2 of 2 Event

Description:

Respond to Loss of ESS Bus Time Position Applicants Actions or Behavior BOP Directs the EO to place the ESS ASCO ABT Transfer Control Switch to TRANSFER TEST for approximately 15 seconds SIMOP: As EO, when directed to use the TRANSFER TEST switch, delete ESS Bus failure malfunction: dmf ed10 Report that the ESS Bus CONNECTED TO EMERGENCY light is lit.

BOP Verifies Annunciator 901-8 E-8 ESS SERV BUS ON EMERG SPLY is on SRO Directs actions of QOA 6800-03 to restore ESS loads ATC When directed, resets the Feed Reg Valve Lockup ATC When directed, resets the 1/2 Group 1 Isolation BOP When directed, reopens SJAE Suction Valves BOP When directed, resets radiation monitors on panel 901-10 and panel 901-11 BOP When directed, resets Reactor Building ventilation BOP Secures SBGT as necessary BOP When directed, resets Control Room vent isolation BOP When directed, verifies open AO 1-1699-7 Vent to Reactor Bldg BOP When directed, returns HPCI and RCIC controllers to AUTO BOP/ATC May direct an EO to clear the local alarm at the Hydrogen Seal Oil Panel SIMOP ROLE PLAY: As the EO dispatched the Hydrogen Seal Oil Panel: Wait 2 minutes and then Insert Remote Function irf eg09r ack/rst SRO Identifies entry into Technical Specification 3.5.1 Conditions G & I and 3.5.3 Conditions A & B for HPCI and RCIC Inoperable.

Tech Spec 3.8.7 Condition A was applicable when the ESS Bus was Deenergized.

EVALUATOR NOTE: It is not necessary to wait for RWCU, RB Ventilation, or SBGT restoration before proceeding to the next event.

End of Event 6

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 7 Page 1 of 5 Event

Description:

Fuel Failure and QGA 300 Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner insert the following malfunctions: Fuel element failure malfunction cr01 at 100% severity on a 10 minute Ramp: imf cr01 100 10:

If, after 10 minutes, the crew has not scrammed the reactor, insert the Gross Fuel failure Malfunction: imf cr02 2 30:

Key Parameter Response: Rising Rad levels for Offgas, MSL, Drywell, Reactor & Turb Bldg Expected Annunciator(s):

901-3 D-2 OFFGAS HI RADIATION (in 1.5 min) 901-56 A-1, DRYWELL HIGH RAD CONC (in 4 min) 901-5 B-5, GROUP 2 ISOL NOT RESET 901-5 D-8, CONTROL ROOM VENT ISOLATED 901-3 C-2, OFFGAS HIGH HIGH RADIATION (in 14 min)

Automatic Actions: Group 2 Isol, CR Vent Isol, Offgas Isolation 15-Min timer Starts BOP Responds to Annunciator OFF GAS HI RADIATION SRO Enters and directs actions of QCOA 1700-04 and QCOA 1700-05 SRO Directs reactor power be held constant BOP Reports Off Gas radiation levels are steadily rising as indicated on the A & B SJAE Rad monitors (901-10) and Recorder (901-2)

BOP Monitors Main Steam Line Radiation monitors and reports to US BOP Monitors Area Radiation Monitors at the 901-11 panel and reports to US SRO/BOP Evacuates any areas of high radiation and refers to QCOA 1800-01 as needed SRO/BOP Notifies Chemistry and the QNE of abnormal Off Gas activity SRO/BOP Directs Chemistry to draw Reactor Coolant and Recombiner outlet samples within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRO/BOP Checks for indications of high coolant conductivity SRO/BOP Checks Chimney Gas Monitors for trends Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 7 Page 2 of 5 Event

Description:

Fuel Failure and QGA 300 Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: Acknowledge directives as necessary if notified as Rad Protection and Chemistry personnel.

SRO/BOP Notifies Rad Protection to perform surveys SRO/BOP Notifies Chemistry to monitor CAMS BOP Responds to Annunciator DRYWELL HIGH RAD CONC and notifies the Unit Supervisor SRO/BOP (Continuous) Monitor Drywell Radiation Levels BOP Confirms rising rad levels on RIS 1-2419 A& B at Panel 901-55 & 56 BOP Monitors Containment H2 and O2 levels SRO/BOP Notifies Radiation Protection ATC Responds to Annunciators GROUP 2 ISOL CH TRIP, GROUP 2 ISOL NOT RESET, and CONTROL ROOM VENT ISOLATED and informs the Unit Supervisor SRO May direct verification of Group 2 and CR Vent isolation ATC/BOP As directed, verifies the Group 2 and CR Vent isolations BOP Responds to Annunciator OFF GAS HIGH HIGH RADIATION BOP Verifies Offgas 15-Minute Timer has started (at 901-10)

SRO When Offgas activity cannot be reduced less than the Offgas HI HI Rad Alarm, directs actions to shutdown the reactor and isolate the release ATC Manually scrams the reactor (See Page 3 of this event)

CT 1 SRO Directs closing of AO 1-5406 Offgas Discharge to Stack CT 1 BOP Closes AO 1-5406 BOP As directed, verifies that AO 1-5408A and AO 1-5408B close CT 1 BOP Manually initiates a Group 1 Isolation / Closes MSIVs and MSIV Drain valves Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 7 Page 3 of 5 Event

Description:

Fuel Failure and QGA 300/ QCGP 2-3 & QGA 100 Actions Time Position Applicants Actions or Behavior SRO Directs actions QCGP 2-3 ATC Places RX MODE switch to SHUTDOWN position ATC Verifies the SDV vent and drain valves are closed ATC Verifies that all Control Rods have fully inserted ATC Makes scram report including entry into QGA 100 on RPV Water Level less than 0 inches SRO Enters and directs actions of QGA 100 SRO Directs ATC/BOP to verify 0 inches isolations and auto-starts ATC Attempts to maintain RPV level 0 to +48 inches with preferred injection systems ATC Verifies DFWLC in Single Element ATC May isolate Feed Water Reg Valve(s)

ATC May place Low Flow Feed Reg Valve in Service ATC May secure unnecessary Feed and Condensate Pumps ATC (CONTINUOUS) Monitors RPV water level and pressure ATC Verifies automatic insertion of SRMs AND IRMs ATC Verifies both Recirc Pumps running at minimum speed in Manual ATC Reports when all rods are fully inserted ATC/BOP Stabilize RPV Pressure less than 1060 psig with Relief Valves ATC/BOP Verifies Group 2 and 3 Isolations, RB vent isolation and SBGT start ATC Verifies Main Turbine trips, all SVs, CVs, ISVs, IVs and extraction steam check valves close ATC Verifies hood Spray AO 1-3399-559 is open ATC Verifies Main Generator Output Breakers tripped after 30 seconds and places control switches in PTL ATC Verifies Main Generator Field and Exciter Field Breakers ATC Verifies all 4 KV buses powered from T-12 ATC Verifies both Recirc Pumps running at minimum speed in Manual ATC Dispatches EO to reset the Generator 86 Relays Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 7 Page 4 of 5 Event

Description:

Fuel Failure and QGA 300 Time Position Applicants Actions or Behavior SIMOP: When the Reactor Mode Switch is taken to Shutdown, verify that the leak begins in the HPCI Room: imf hp13(7) 100 30: (100% Severity on a 30 minute ramp) and the Gross Fuel Failure begins: imf cr02(7) 2 30: (On Trigger 7, Gross Fuel Failure at 2% Severity, 30 minute ramp)

Key Parameter Response: Increasing Radiation levels and Temperature in the HPCI Room Expected Annunciator(s):

901-3 A-1, RX BLDG HI RADIATION (in approximately 1.5 minutes) 901-3 H-2, AREA HI TEMP STM LEAK DETECT (in approximately 2.5 minutes)

Automatic Actions: None (Malfunctions for HPCI Steam Supply Valve binding)

BOP Responds to annunciators and informs the Unit Supervisor BOP Responds to a Annunciators and informs the Unit Supervisor BOP Monitors Area Radiation levels from the 901-2 and 901-10 panels and reports QGA 300 Entry Conditions SRO Enters and directs applicable actions of QGA 300 SIMOP: When the fire alarm sounds, silence the alarm with the command: bat fireout Role Play as the Unit 2 Operator: the alarm is from the Unit 1 HPCI room.

EVALUATOR NOTE:

The HPCI Room ARM exceeds its Max Safe Value approximately 4 minutes after the Mode Switch to Shutdown.

The Torus Area ARM will be approaching its Max Normal (Alarm) value at that time BOP Reports HPCI Room Radiation levels are greater than Max Normal and increasing BOP/ATC Monitors Reactor Bldg Temperatures at Panel 901-21 (TR 1-1290)

Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 7 Page 5 of 5 Event

Description:

Fuel Failure and QGA 300 Time Position Applicants Actions or Behavior BOP/ATC Recognizes and reports when the HPCI Room exceeds its Max Safe value of 155°F BOP Attempts to isolate HPCI Steam Lines BOP Reports that HPCI 4 and 5 valves have lost light indication SIMOP ROLE-PLAY: When requested to investigate breakers for HPCI 4 & 5, wait 2 minutes and as EO report the thermals are tripped.

If asked to reset them, reply that they keep tripping.

BOP Directs EO to investigate breakers for HPCI 4 & 5 valves SRO Re-enters and directs applicable action of QGA 100 BOP Reports HPCI Room Radiation levels are greater than Max Safe value of 3000 mr/Hr BOP Directs EO with Rad Prot. support to investigate source of leak SIMOP ROLE-PLAY: As EO, report the HPCI room is filled with steam and entry is impossible.

ATC/BOP Dispatches EO to start the U-1 EDG cooling water pump and monitor RB Basement water levels SIMOP: If dispatched as EO, wait 2 minutes and start the Unit 1 EDG CWP: mrf sw10r run Report that the U1 EDG CWP is running and that there is no water in the RB Basement, however, you were unable to enter the HPCI Room because it was full of steam.

SRO/BOP Announces evacuation of Unit 1 Reactor Bldg. over plant page BOP May restart Reactor Bldg. vents End of Event 7

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 8 Page 1 of 2 Event

Description:

QGA 300 Blowdown Time Position Applicants Actions or Behavior SIMOP: Verify that the Torus Area ARM reading exceeds its Max Safe Value in approximately 11 minutes after the Mode Switch to Shutdown.

If necessary use the following malfunction: rm0115 60 15:

Key Parameter Response: Increasing Radiation levels in the Torus Area on ARM 15 Expected Annunciator(s): 901-3 A-1, RX BLDG HI RADIATION (Re-Alarming)

Automatic Actions: None BOP Monitors Reactor Bldg ARMs on Panel 901-11 BOP Recognizes and reports that ARM 15 TORUS AREA is trending higher BOP Recognizes and reports when the second area, the Torus Area, has exceeded its Max Safe Radiation level (3000 MR)

SRO When 2 areas (HPCI Room and Torus Area) exceed Max Safe radiation levels, enter and direct QGA 500-1 SRO Verifies all rods in BOP Reports Drywell pressure less than 2.5 psig and Torus level above 5 ft.

CT 2 SRO Orders all 5 ADS valves opened and leave switches in Manual CT 2 ATC/BOP Opens all 5 ADS valves and leaves all switches in the MAN position ATC/BOP Verifies ADS valve positions at the 901-21 panel ATC/BOP Starts cooldown to cold shutdown per QCOP 1000-05 ATC Monitors and controls RPV water level BOP Monitors Torus Water Temperature and reports QGA 200 entry when Torus Water Temperature exceeds 95°F SRO Enters QGA 200 when Torus Water Temperature exceeds 95°F Event 8 Continued

Quad Cities 2012 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2012 NRC Scenario No.: 4 Event No: 8 Page 2 of 2 Event

Description:

QGA 300 Blowdown Time Position Applicants Actions or Behavior BOP Places RHR in the Torus Cooling Mode as directed BOP If per QCOP 1000-30 Hard Card, establishes RHRSW flow BOP Places RHR LOOP A/B CONTAINMENT CLG permissive switch 17 to the ON position BOP Places RHR LOOP A/B RHR SW START PERMISSIVE SWITCH 19 to the MANUAL OVERRIDE position BOP Throttles open MO-1-1001-5A/B RHR SW HX Discharge Valve, to at least 40% open BOP Starts the first RHRSW Pump in each loop BOP Throttles MO-1-1001-5A/B to establish less than 3600 gpm/pump BOP Throttle closed MO 1-1001-16A/B (HX Bypass) on each Loop BOP May start the second RHRSW Pump in each loop and adjusts as necessary BOP Starts Torus Cooling as directed BOP Verifies RHR Pumps running BOP Opens Torus Test or Spray Valve, MO 1-1001-34A/B BOP Opens Torus H2O Test Valve, MO 1-1001-36A/B BOP Adjusts Torus H2O Test Valve MO 1-1001-36A/B to maintain RHR SW Pressure 15-20 psig higher than RHR pressure and RHR pressure between 100 and 250 psig BOP Closes MO 1-1001-16A/B End of Event 8 SIMOP: When Blowdown has been performed and at the discretion of the Lead Examiner, Place the simulator in FREEZE.

(Final)

Quad Cities 2012 NRC EXAM Scenario 3 Exelon Nuclear 2012 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 3 Revision Number: 00 Date: _03/04/12_

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 3 Op-Test No.: ILT 10-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 75% power.

Turnover: Perform the SSMP POV Test.

Event No.

Malf. No.

Event Type*

Event Description 1

LOHS1290181 (Override)

BOP N

Perform the SSMP POV Test (QCOS 2900-03) TS 2

RD07 ATC C

CRD Pump Trip (QCOA 0300-01) 3 HP10 BOP I

Inadvertent HPCI Initiation TS (QCOA 2300-01) 4 SW12A BOP C

The running TBCCW pump begins to fail (QCOA 3800-03) 5 ED03B ATC R

Loss of Bus 12, Respond to loss of B Recirc Pump TS (QCOA 6500-02 & QCOA 0202-04) Insert control rods to exit Instability Region 2 6

RR10A ED03A Crew M

Large Line Break LOCA. When the plant trips, Bus 11 trips and the remaining Feed Pumps will be lost.

7 RC04 ATC C

RCIC Auto Initiation fails, requiring manual RCIC initiation 8

HP01 Crew M

HPCI trips and Alternate Level Control per QGA100 second leg actions are taken. The crew Emergency Depressurizes per QGA 500-1 at TAF and restores RPV level with Low-pressure systems.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:

Total Malfunctions (5-8): 8 Malfunction(s) after EOP (1-2): E7 & E8 Abnormal Events (2-4): E2,3,4,&5 Major Transient(s) /E-Plan entry (1-2): E6 EOPs (1-2): QGA100/200 EOP Contingencies (0-2): E8 Critical Tasks (2-3): 3 ES-301-5 Quantitative attributes:

BOP Normal: E1 ATC Reactivity (1 per set): E5 BOP I/C (4 per set): E3&4 ATC I/C (4 per set): E2&7 SRO-I I/C (4 per set inc 2 as ATC): E2,3,4&7 SRO Tech Spec (2 per set): E1, 3, & 5 ALL Major Transients (2 per set) E6

Quad Cities 2012 NRC EXAM Scenario 3

SUMMARY

Initial Conditions:

o The plant is operating at 75% power.

Event 1: The BOP performs SSMP Power Operated Valve Test per QCOS 2900-03. The 1-2901-08 valve stroke time exceeds its IST limit requiring the SRO to reference TS 3.7.9 Condition A, enter a 14-Day LCO to restore operability.

Event 2: The A CRD Pump trips. The ATC Operator and US respond per QCOA 0300-01 to start the B CRD Pump and open its discharge valve.

Event 3: The BOP responds to an inadvertent HPCI Initiation per QCOA 2300-01. When HPCI has been trip-latched to prevent restart, the SRO should reference TS 3.5.1 Condition G.

Event 4: The running TBCCW pump begins to fail. The BOP and SRO respond to low pressure in the TBCCW header per the QCAN and QCOA 3800-03 to stabilize the system.

Event 5: The BOP responds to a loss of Bus 12 per QCOA 6500-02. The ATC/BOP respond to loss of B Recirc Pump per QCOA 0202-04. The ATC and SRO insert control rods to exit Instability Region 2.

Event 6: A LOCA inside the Drywell begins. The crew enters and performs QGA 100 and 200. Bus 11 and the remaining Feed Pumps are lost when the UAT trips. Operators will control containment parameters without further challenge.

Event 7: RCIC auto initiation and the Initiation Pushbutton will fail. The ATC must manually initiate RCIC per the QCOP 1300-02 Hard Card for RPV water level control.

Event 8: HPCI fails and the remaining high-pressure systems will not be able to maintain RPV Water level above Top of Active Fuel. The crew will perform Emergency Depressurization and then restore RPV Water Level with available low-pressure systems.

Approximate Run Time: 1.5 Hour CRITICAL TASKS:

Critical task #1: Given the plant with the inability to maintain level above -59 inches, INHIBIT ADS, to prevent an uncontrolled depressurization IAW QGA 100.

Critical task #2: When Torus pressure exceeds 5 psig, INITIATE drywell sprays while in the safe region of the drywell spray initiation limit (DSIL). (BWROG PC-5.1 INIT DW SPRAY)

Critical task #3: Given the plant with an inability to maintain RPV water Level above -142 inches with an injection source lined-up and running, initiate an emergency depressurization before RPV water level drops to -166 inches in accordance with QGA 100 and QGA 500-1.

Quad Cities 2012 NRC EXAM Scenario 3 EXERCISE PERFORMANCE OBJECTIVES SR-0300-P04 Given an operating reactor plant with a CRD pump trip, start the standby CRD pump in accordance with QCOA 0300-01.

SR-0002-P05 Given a reactor plant at power, perform a power change discernible on neutron monitors using recirc flow in accordance with QCOP 0202-03 and QCGP 3-1.

SR-3800-P01 Given a reactor plant at power when a total loss of TBCCW occurs, take action to determine the cause and to remove TBCCW cooled loads from service in accordance with QCOA 3800-3.

SR-0202-P19 Given an operating reactor plant following a loss of single reactor recirculation pump, take action to establish conditions for operating single loop for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in accordance with QCOP 0202-07 and QCOS 0202-09.

SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.

SR-0203-P07 Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)

SR-0001-P45 Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.

SR-1000-P02 Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)

SR-1000-P04 Given a reactor plant with rising containment pressures due to a LOCA or steam leak and RHR is not needed for core cooling, verify parameters are in the safe region of the Drywell Spray Initiation Limit (QGA Figure K), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays when torus pressure exceeds 5 psig in accordance with QGA 200 and QCOP 1000-30. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)

SR-2900-P02 Freq: LIC=A) (ILT-MP) Given Unit 1 in a QGA condition with the SSMP in a standby lineup, start the SSMP from the 912-8 panel and inject to Unit 1 in accordance with QCOP 2900-02. (Important PRA Operator Action - Proper operation of SSMP terminates 19 of the top 100 Core Damage Sequences)

(Switching SSMP between units, aligning FPS to SSMP, and switching AC buses)

SR-1000-P05 Given a reactor plant in an accident condition where RHR-LPCI mode has started automatically, determine if LPCI has responded correctly to a valid initiation and throttle flow to restore RPV water level in accordance QCOA 1000-04.

SR-0001-P02 Given the plant with an inability to maintain RPV water level above -142 inches with an injection source lined-up and running, initiate an emergency depressurization before RPV water level drops to -166 inches in accordance with QGA 100 and QGA 500-1. (Important PRA Operator Action - emergency depressurization terminates 19 of top 100 Core Damage Sequences)

Quad Cities 2012 NRC EXAM Scenario 3 Simulator Setup:

1. Reset to IC-20.

2. Go to RUN.

3. Verify the following RWM Sequence is loaded: C22SU

4. Initial the Control Rod Move Sheet as necessary to update to the current rod positions.

(The following commands to be utilized for this scenario are contained in the CAEP file:

2012 NRC Scenario 3.cae)

5. Insert Commands for setup:

ior lohs1290181 on (SSMP Inject MOV 1-2901-8 Green Light on) trgset 1 zdihs129018(2).eq.1 (When MOV 1-2901-8 switch is taken to OPEN) trg 1 ior lohs1290181(1 :35) off (MOV 1-2901-8 Green light off in 35 seconds) trgset 3 tcvsv3.le.0.1 (Set Event trigger 3 as #3 Stop valve closure/Turbine trip) imf ed03a (3 0) (On Event Trigger 3, Loss of Bus 11) trgset 6 pcpdwg.ge. 2.5 (Set Event Trigger 6 as Drywell Pressure 2.5 psig) imf hp01(6 2:) (On Trigger 6, HPCI Turbine Trip after a 2 minute delay) imf rc04 (RCIC Auto Start & Initiation Pushbutton Failure)

6. Verify the following commands for scenario performance:

dor lohs1290181 (Deletes MOV 1-2901-8 Green light override) imf rd07a (A CRD Pump Trip) imf hp10 (HPCI inadvertent initiation) imf sw12a 100 10: (1A TBCCW Pump degradation at 100% severity on a 10 min ramp) imf ed03b (Loss of Bus 12) imf rr10a 1 20: (Recirc Suction Pipe Rupture Loop A at 1% severity on a 20 min ramp)

7. Verify SBO alarms clear.

8. Provide a 40% load Drop REMA.

9. Provide a current revision of the following procedures, signed off as specified:

QCOS 2900-03 with Prerequisites and authorization signed off.

o Attach the applicable IST Data sheet.

o PROVIDE A STOPWATCH.

10. Need to have blank EST available for use during the scenario.

11 Perform the applicable Post Simulator Exam Security Actions of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.

Quad Cities 2012 NRC EXAM Scenario 3 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-9 HPCI TURBINE TRIPPED, Rev. 5 o 901-3 D-12 HPCI PUMP LOW FLOW, Rev. 7 o 901-3 A-16 PRI CNMT HIGH PRESSURE, Rev. 12 o 901-4 B-6 RECIRC DRIVE B TRIP, Rev. 8 o 901-5, B-2, CRD PP TRIP, Rev. 5 o 901-5, F-2, CRD CHARGING WATER LOW PRESSURE, Rev. 5 o 901-5 E-8 RX VESSEL HIGH LEVEL, Rev. 9 o 901-8 E-1 4KV BUS 11&12 LOW VOLTAGE, Rev. 4 o 901-8 F-3 4KV BUS OVERCUR TRIP, Rev. 5 o 912-1 D-2 TURB BLDG CLG WATER LOW PRESSURE, Rev. 3 QCGP 2-3, Reactor Scram, Rev. 74 QCGP 3-1, Reactor Power Operations, Rev. 66 QCGP 4-1, Control rod Movements and Control Rod Sequence, Rev. 38 QGA 100, RPV Control, Rev. 9 QGA 200, Primary Containment Control, Rev. 9 QGA 500-1, RPV Blowdown, Rev. 13 QCOA 0201-01, Increasing Drywell pressure, Rev. 23 QCOA 0202-04, Reactor Recirc Pump Trip - Single Pump, Rev. 38 QCOA 0300-01, CRD Pump Failure, Rev. 16 QCOA 0400-02, Core Instabilities, Rev. 21 QCOP 1400-02, Core Spray System Automatic Initiation, Rev. 11 QCOA 3800-03, Total Failure of the TBCCW System, Rev. 9 QCOA 6500-2, 4KV Bus Failure, Rev. 12 QCOP 0300-16, Addition of Water to Reactor Vessel using CRD Hydraulic System, Rev. 7 QCOP 1000-30, Post-Accident RHR Operation, Rev. 26 QCOP 1100-02, Injection of Standby Liquid Control, Rev. 12 QCOP 1300-02, RCIC System Manual Startup, Rev. 29 QCOP 2900-02, Safe Shutdown Makeup Pump system Startup, Rev. 23 QCOS 2900-03, SSMP Power Operated Valve Test, Rev. 17

Quad Cities 2012 NRC EXAM Scenario 3 CREW TURNOVER

1. Plant Conditions:

a.) Unit 1 is at 75% Power, still holding after Turbine testing.

b.) Unit 2 is at 100% Power.

c.) Technical Specification limitations:

(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.

2.) Significant problems/abnormalities:

a.) None 3.) Evolutions/maintenance for the oncoming shift:

a.) Holding power while waiting for QNE to check predictor codes, prior to power ascension.

b.) Perform SSMP Power Operated Valve Test per QCOS 2900-03.

c.) EOs on shift:

Burke Parrish Foster Richardson Hughes Brewer Decker Schmidt

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 1 Page 1 of 1 Event

Description:

SSMP POV Test Time Position Applicants Actions or Behavior SRO Directs BOP to perform QCOS 2900-03 ATC Monitors Reactor and Reactor Pressure Vessel indications BOP Opens and times MO 1/2-2901-7 (THROTTLED TEST VALVE)

BOP Records opening time of MO 1/2-2901-7 valve BOP Verifies MO 1/2-2901-7 opening time meets IST criteria BOP Closes and times MO 1/2-2901-7 BOP Records closing time of MO 1/2-2901-7 BOP Verifies MO 1/2-2901-7 closing time meets IST criteria SIMOP: The setup overrides MO 1-2901-8 Green light ON. When MO 1-2901-8 handswitch is taken to OPEN, Event Trigger 1 goes True to modify the override to OFF in 35 seconds.

This effectively extends the stroke time from 27 seconds to 35 seconds.

After MO 1-2901-8 indicates OPEN and before the BOP closes it, delete the Override on the Green Light : dor lohs1290181 BOP Opens and times MO 1-2901-8 (U1 REACTOR SUPPLY VALVE)

BOP Records opening time of MO 1-2901-8 BOP Identifies that MO 1-2901-8 opening time exceeds its IST value and informs the US BOP Closes MO 1-2901-8 SRO References TS 3.7.9 Condition A, enter a 14-Day LCO to restore operability SRO May abort surveillance due to failure of MO 1-2901-8 BOP Opens and times MO 2-2901-8 (U2 REACTOR SUPPLY VALVE)

BOP Records opening time of MO 2-2901-8 BOP Verifies MO 2-2901-8 opening time meets IST criteria BOP Closes MO 2-2901-8 BOP Verifies SSMP in a standby lineup at Local Panel / Dispatches an EO SIMOP ROLE-PLAY: As the dispatched EO The SSMP standby lineup has been verified.

End of Event 1

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 2 Page 1 of 1 Event

Description:

CRD Pump Trip Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, trip the 1A CRD Pump: imf rd07a Key Parameter Response: 1A CRD Pump indication lights off, Lowering CRD pressures Expected Annunciator(s):

901-5, B-2, CRD PP TRIP 901-5, F-2, CRD CHARGING WATER LOW PRESSURE Automatic Actions: None ATC Acknowledges annunciator 901-5 B-2, CRD PP TRIP, and reports the 1A CRD pump has tripped SRO Enters and directs QCOA 0300-01 SRO May set scram criteria of 2 or more accumulator trouble alarms AND charging water header pressure less than 940 psig for 20 minutes (This scram criteria comes from TS 3.1.5 Conditions B & D)

ATC Verifies the MO 1-301-2B, 1B PMP DISCH VLV, is closed for the standby pump ATC Starts the 1B CRD pump and verifies current is less than 34 amps on the 1-302-1B ATC Throttles MO 1-301-2B to maintain 1400-1500 psig discharge pressure ATC Closes the MO 1-301-2A on the tripped pump ATC Dispatches EO to verify proper operation of running pump BOP Monitors Balance-of-Plant equipment SIMOP ROLE PLAY: As EO dispatched to the CRD pump, wait 2 minutes and report the 1B CRD pump sounds normal, no leaks, and oil levels are in band.

ATC Dispatches EO to CLOSE the MIN FLOW ISOLATION Valve on A CRD Pump and OPEN the MIN FLOW ISOLATION Valve on B CRD Pump SIMOP ROLE PLAY: As EO dispatched to the CRD pump, wait 2 minutes and report the 1B CRD pump Min Flow valve is Open and the 1A CRD Pump Min Flow Valve is Closed.

ATC May adjust CRD Drive Water Pressure to 260-350 psig per QCOP 0300-1 SIMOP ROLE PLAY: If also requested to check the 1A CRD pump breaker at Bus 13, report the breaker tripped on overcurrent.

End of Event 2

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 3 Page 1 of 1 Event

Description:

Inadvertent HPCI Initiation Time Position Applicants Actions or Behavior SIMOP: At the direction of the Lead Examiner, insert malfunction: imf hp10 (Inadvertent HPCI Initiation.)

Key Parameter Response: HPCI Turbine speed 4000 rpm, Turb Steam Supply 1-2301-3 Valve open, Pump Discharge 1-2301-8 valve open, RPV water level rising Expected Annunciator(s):

901-3 F-9 HPCI OIL FILTER HIGH DP 901-3 D-12 HPCI PUMP LOW FLOW 901-5 D-7 LPRM HIGH 901-5 E-8 RX VESSEL HIGH LEVEL Automatic Actions: HPCI system responds as designed to an Auto Initiation signal BOP Responds to Annunciator 901-3 D-12, HPCI PUMP LOW FLOW BOP Reports alarm to US; refers to annunciator procedure BOP Reports HPCI System initiating CREW Determine that HPCI injection is not necessary:

Report Drywell pressure normal Reports RPV water level normal by all indicators ATC Monitors RPV water level and APRMs SRO Directs actions of QCOA 2300-01 SRO Determines initiation is NOT valid and directs the BOP to trip-latch REMOTE HPCI TURB TRIP pushbutton BOP Actuates the trip-latch REMOTE HPCI TURB TRIP pushbutton BOP Reports HPCI is tripped BOP Place MO 1-2301-14 MIN FLOW BYP VLV in P-T-L BOP Contacts EMD/IMD to investigate HPCI auto-start SRO Enters TS 3.5.1 Cond G, HPCI System Inop. Also enters 14 day ATR LCO for HPCI Inoperable.

ROLE PLAY: As Maintenance and EOs as necessary.

EVALUATOR NOTE: Notifications, event reporting and risk assessment change are not evaluated here.

BOP/SRO (CONTINUOUS) If HPCI operation is subsequently required after it has been trip latched, then release the REMOTE HPCI TURB TRIP pushbutton and place the MIN FLOW BYP VLV in NORMAL End of Event 3

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 4 Page 1 of 1 Event

Description:

1A TBCCW Pump degradation Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner initiate the 1A TBCCW pump degradation at 100% over 10 minutes: imf sw12a 100 10:

Key Parameter Response: TBCCW Header pressure lowering Expected Annunciator(s): 912-1 D-2 TURB BLDG CLG WATER LOW PRESSURE Automatic Actions: None BOP Acknowledges annunciator 912-1 D-2, Turb Bldg Cooling Water Low Pressure and reports the U-1 TBCCW Discharge Header pressure is 35 psig and lowering BOP Starts the 1B TBCCW pump per QCAN 912-1 D-2 and reports TBCCW Discharge Header pressure is stable at 40 psig BOP Dispatches EO to the 1A TBCCW pump to investigate SIMOP ROLE PLAY: As the EO dispatched to the 1A TBCCW pump, wait 2 minutes and report The 1A TBCCW pump is running hot and sounding noisy. No leaks were found.

If asked, report the 1B TBCCW pump is operating properly.

BOP Secures the 1A TBCCW pump and verifies TBCCW discharge header pressure is stable at approximately 40 psig SRO May reference QCOA 3800-03 for Total Loss of TBCCW SRO May set scram criteria of 35 psig TBCCW Header pressure ATC Monitors Reactor controls and indications End of Event 4

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 5 Page 1 of 2 Event

Description:

Respond to Loss of Bus 12 and B Recirc Pump Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner trip Bus 12: imf ed03b Key Parameter Response: Loss of B RFP and B Recirc Pump, BUS 12 LIVE white light out, Loss of voltage on Bus 12 Expected Annunciator(s):

901-8 E-1 4KV BUS 11&12 LOW VOLTAGE 901-8 F-3 4KV BUS OVERCUR TRIP 901-6 E-7 & F-7 RFP AUTO START & RFP AUTO TRIP 901-4 B-6 RECIRC DRIVE B TRIP Automatic Actions: Trip of all Bus 12 loads, 1C RFP starts BOP Responds to Panel 901-8 annunciators, diagnoses the loss of Bus 12 and informs the US SRO Enters and directs QCOA 6500-02 BOP Performs actions of QCOA 6500-02 BOP Recognizes that Bus 12 did not transfer to the UAT BOP Recognizes 901-8 F-3 4KV BUS OVERCUR TRIP and does NOT attempt to transfer to the UAT BOP Attempts to determine the cause of the Bus 12 overcurrent by dispatching an EO to investigate SIMOP ROLE PLAY: As EO dispatched to Bus 12: Wait 2 minutes and then report that the T12 to Bus 12 feed breaker target shows instantaneous overcurrent and there is the odor of burnt insulation, but no fire.

BOP Verifies the UAT load: To Bus 11 less than 4100 amps, to Bus 14 less than 2950 amps ATC Responds to Annunciator 901-6 E-7 & F-7 ATC Verifies RPV Water Level is being maintained SRO Enters and directs actions of QCOA 0202-04 SRO May set Scram Criteria of observed core oscillations SRO May set Scram Criteria based on RPV Water level less than +11 inches or greater than +44 inches ATC Performs actions of QCOA 0202-04 for single Loop Operations ATC Monitors for indications of thermal hydraulic instabilities on SRM period or LPRM levels Event 5 Continued

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 5 Page 2 of 2 Event

Description:

Loss of Bus 12 / Insert Control Rods to Exit Instability Region 2 Time Position Applicants Actions or Behavior SRO Enters and directs QCOA 0400-02, Core Instabilities ATC Per QCOA 0400-02, determines operating position on the Power Flow Map as inside Instability region 2 (Core Flow 41 Mlb/Hr, Reactor Power 56%, FCL 98%)

SRO Directs actions to lower the Flow Control Line as necessary to avoid Instability Regions 1 or 2 SRO Supervises control rod insertion ATC Monitors for core oscillations ATC If necessary, bypasses RWM IAW QCOA 0202-04 ATC Continuously inserts control rods until Reactor operation is outside of Instability Region 2 In-Sequence rods inserted to Target-In position (Approximately 7 rods)

ATC/BOP Responds to Annunciator 901-4 B-6 ATC/BOP Verifies A Recirc Pump flow Control is in MANUAL ATC/BOP Verifies A Recirc Pump speed is less than 78%

ATC/BOP Performs actions of QCOA 0202-04 for Single Loop Operation ATC/BOP Closes the 1-0202-5B valve B Recirc Pump Discharge Valve ATC/BOP After 5 minutes, re-opens the 1-0202-5B valve SRO Enters Tech Spec 3.4.1 Condition C, which allows 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy the requirements of the LCO for Single Loop Operation BOP Verifies Reactor feed Pump response BOP Verifies the 1B RFP Aux Oil Pump auto starts BOP Verifies the 1C RFP (Standby Pump) auto starts BOP Verifies no indicated flow on the 1B RFP BOP May direct realignment of Zinc Injection per QCOP 3200-11 SIMOP ROLE PLAY: Plant support personnel as necessary when directed to realign Zinc Injection.

End of Event 5

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 6 Page 1 of 5 Event

Description:

LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner initiate the Recirc Suction Line LOCA at 1%

severity on a 20 minute ramp: imf rr10a 1 20:

Key Parameter Response: Rising Drywell Pressure Expected Annunciator(s): 901-3 A-16, PRI CNMT HIGH PRESSURE Automatic Actions: Reactor Scram Initiation of SBGT, HPCI, LPCI, Core Spray, EDGs Isolation of Group 2 & 3 valves, Reactor Bldg and Control Room Ventilation BOP Responds to annunciator 901-3, A-16, PRI CNMT HIGH PRESSURE SRO Enters and directs QCOA 0201-01 BOP May start the seventh DW cooler SRO May set Scram Criteria of 2.0 psig in Drywell SRO Directs ATC to Perform QCGP 2-3 ATC (When directed) Depresses RX SCRAM CH A and CH B Pushbuttons ATC Places RX MODE switch to SHUTDOWN position ATC Verifies the SDV vent and drain valves are closed ATC Verifies all Control Rods are fully inserted ATC Makes scram report ATC Informs US of QGA 100 entry on RPV Water Level less than 0 inches SRO Enters QGA 100 when RPV Water Level less than 0 inches SRO Directs ATC/BOP to verify 0 inches isolations ATC Verifies Group 3 (RWCU) Isolation BOP Verifies Group 2 Isolations, RB vent isolation and SBGT start SRO Directs ATC to maintain RPV water level with high pressure systems ATC Attempts to maintain RPV level 0 to +48 inches with high-pressure injection systems ATC Verifies DFWLC in Single Element ATC May isolate Feed Water Reg Valve(s)

ATC May place Low Flow Feed Reg Valve in Service ATC May secure unnecessary Feed and Condensate Pumps Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 6 Page 2 of 5 Event

Description:

LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior ATC (CONTINUOUS) Monitors RPV water level and pressure ATC Recognizes loss of all Feed Pumps and informs the US ATC Verifies automatic insertion of SRMs AND IRMs EVALUATOR NOTE: The remaining steps from QCGP 2-3 may not be taken due to the pace of the scenario because the UAT trips when the Turbine Trips ATC Verifies Main Turbine trips, all SVs, CVs, ISVs, IVs and extraction steam check valves close ATC Verifies Hood Spray AO 1-3399-559 is open ATC Verifies Main Generator Output Breakers tripped after 30 seconds and places control switches in PTL ATC Verifies Main Generator Field and Exciter Field Breakers (alarm 901-8 H-9) tripped QGA 200 BOP/ATC Reports Drywell pressure above 2.5 psig.

SRO Re-enters QGA 100 and enters and directs QGA 200 on High Drywell Pressure SRO Directs ATC and BOP to verify 2.5 psi actuations BOP Verifies EDGs, Core Spray, HPCI and RHR running CREW Makes a PA announcement to evacuate Reactor Building Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 6 Page 3 of 5 Event

Description:

LOCA in the Drywell / QGA 100 actions Time Position Applicants Actions or Behavior SRO Directs QGA 100 RPV Control actions CT1 SRO Directs that ADS be inhibited CT1 ATC/BOP Inhibits ADS ATC Attempts to start RCIC (See Event 7)

ATC Starts SSMP per QCOP 2900-02 / Hard Card ATC Verifies the NORMAL FEED CONTROL from Bus 14-1 to Bus 31, ACB 151-3101 is available ATC Verify Pump suction pressure is available ATC OPEN MOV 1/2-2901-7, Throttled Test Valve ATC Start the SSMP ATC Verify increasing Pump Discharge Pressure ATC Place the FCV in AUTO ATC Slowly increase flow controller setpoint to 400 gpm ATC OPEN MOV 1-2901-8, U1 Reactor Supply Valve ATC CLOSE MOV 1/2-2901-7, Throttled Test Valve ATC Directs and Equipment Operator to close the Service Water to SSMP Room Cooler Bypass, 1/2-2999-9 SIMOP ROLE PLAY: As Equipment Operator dispatched to close 1/2-2999-9. After 5 minutes, report that 1/2-2999-9 is CLOSED.

EVALUATOR NOTE: HPCI trips 2 minutes after 2.5 psig in DW. Also, the exhaust drain pot high level alarms after Event 3, in which case operators may choose not to re-start HPCI.

BOP/ATC Operators may release the Trip-Latch on HPCI BOP/ATC Verify automatic actions for HPCI Initiation BOP/ATC Adjust HPCI Flow Controller for maximum injection flow as necessary SRO Directs crew to stabilize RPV Pressure with Turbine Bypass Valves/ADS Valves ATC/BOP Stabilizes RPV Pressure with Turbine Bypass Valves/ADS valves as directed SRO Directs a cooldown at less than 100°F/Hr with Turbine Bypass Valves/ADS Valves ATC/BOP Initiates a RPV cooldown as directed Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 6 Page 4 of 5 Event

Description:

LOCA in the Drywell / QGA 200 actions Time Position Applicants Actions or Behavior BOP (Continuous) Monitors and reports Primary Containment Parameters and trends SRO Directs the actions of QGA 200 PRIMARY CONTAINMENT CONTROL SRO Verifies Torus water level less than 27 ft.

SRO Directs BOP to initiate Torus Sprays BOP Uses QCOP 1000-30 to Start RHR BOP Verifies RHR Pumps running BOP Places the Containment Cooling Permissive Switch 17 to ON for the available RHR Loop BOP Places the RHR SW Start Permissive Switch 19 to MANUAL OVERRIDE for the available RHR Loop BOP Starts Torus Spray BOP Opens Torus Test or Spray Valve, MO 1-1001-34A/B BOP Opens Torus Spray Shutoff Valve, MO 1-1001-37A/B BOP Throttles Torus H2O Test Valve MO 1-1001-36A/B to establish RHR Discharge Pressure of 100-250 psig SRO Verifies Torus level less than 17 ft. and inside DW Spray Initiation Limit curve SRO Verifies Recirc pumps and DW coolers tripped CT2 SRO Directs BOP to initiate DW Sprays CT2 BOP Initiates Drywell Sprays BOP Opens Outboard Spray Isolation, MO 1-1001-23A/B BOP Opens Inboard Spray Isolation, MO 1-1001-26A/B BOP Opens Torus Test or Spray Valve, MO 1-1001-34A/B BOP Adjusts Torus H2O Test Valve MO 1-1001-36A/B to maintain RHR SW Pressure 15-20 psig higher than RHR and RHR Discharge Pressure of 100-250 psig Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 6 Page 5 of 5 Event

Description:

LOCA in the Drywell / QGA 200 actions Time Position Applicants Actions or Behavior SRO May Direct Torus Cooling initiation BOP Uses QCOP 1000-30 to start RHR Service Water BOP Opens the available RHR HX SW Discharge Valve MO 1-1001-5A/B to 40%

BOP Starts Loop A/B RHR SW Pump(s)

BOP Adjusts MO 1-1001-5A/B to maintain RHR SW Pressure 15-20 psig higher than RHR and less than 3600 gpm per pump BOP Throttles RHR HX Bypass Valve MO 1-1001-16A/B as necessary BOP Starts Torus Cooling as directed BOP Opens Torus Test or Spray Valve, MO 1-1001-34A/B BOP Opens Torus H2O Test Valve, MO 1-1001-36A/B BOP Adjusts Torus H2O Test Valve MO 1-1001-36A/B to maintain RHR SW Pressure 15-20 psig higher than RHR pressure and RHR pressure between 100 and 250 psig BOP Closes MO 1-1001-16A/B End of Event 6

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 7 Page 1 of 1 Event

Description:

RCIC Auto Start Failure Time Position Applicants Actions or Behavior SRO Directs QGA 100 RPV Control actions ATC Depresses the RCIC MANUAL INITIATION pushbutton for at least 30 seconds and recognizes that RCIC has failed to initiate ATC Manually starts RCIC per QCOP 1300-02 ATC Starts the Turbine Vacuum Pump ATC Opens MO 1-1301-62, Turbine Cooling Water Valve ATC Verifies open MO 1-1301-48, Pump Discharge Valve ATC Opens MO 1-1301-49, Pump Discharge Valve ATC Opens MO 1-1301-60, Min Flow Valve ATC Opens MO 1-1301-61, Steam to Turbine Valve ATC Adjust RCIC Flow Controller in Manual or AUTO as necessary BOP Addresses challenges to Primary Containment End of Event 7

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 8 Page 1of 2 Event

Description:

Alternate Level Control / Emergency Depressurization Time Position Applicants Actions or Behavior EVALUATOR NOTE: HPCI trips 2 minutes after Drywell exceeds 2.5 psig.

Key Parameter Response: RPV water level lowering, HPCI speed indication reading 0 Expected Annunciator(s): 901-3 A-9 HPCI TURBINE TRIPPED Automatic Actions: None BOP/ATC (Continuous) Monitor and report RPV water level and trends BOP/ATC Recognizes the loss of HPCI and informs the Unit Supervisor BOP/ATC May dispatch an EO to investigate SIMOP ROLE PLAY: As EO dispatched to HPCI, Wait 5 minutes and then report that there is no obvious problem with HPCI.

SRO Direct use of Alternate Injection Systems ATC If directed, starts SBLC for injection per QCOP 1100-02 ATC As directed, starts both SBLC pumps by selecting Either SYS 1&2 or SYS 2&1 ATC Verifies applicable Squib light off ATC Verifies Flow Light On ATC Verifies Tank level decreasing ATC Verifies pump discharge pressure greater than or equal to Reactor Pressure ATC Verifies Annunciator 901-5 H-6 is on Event 8 Continued

Quad Cities 2012 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No: 3 Event No: 8 Page 2 of 2 Event

Description:

Alternate Level Control / Emergency Depressurization Time Position Applicants Actions or Behavior ATC Reports when RPV water level reaches -142 inches SRO Before RPV water level drops to -166 inches, enters QGA 500-1 CT3 SRO Directs actions of QGA 500-1 SRO Verifies Torus level greater than 5 feet CT3 ATC/BOP Opens all ADS valves, leaves switches in MAN BOP Verifies all ADS valves open by acoustic monitor indication on the 901-21 panel SRO Directs ATC/ BOP actions to restore RPV water level with Low Pressure systems SRO Directs BOP to secure Drywell, Torus Sprays, and Torus Cooling and inject at maximum ATC/BOP Restore RPV water level as directed ATC/BOP Control injection from Core Spray and LPCI after Reactor Water Level is greater than -142 inches ATC/BOP Monitors level instrument watching for indications of saturation and informs SRO SRO When Reactor Water Level is greater than -142 inches, directs re-initiation of containment sprays BOP Re-initiates containment sprays as directed End of Event 8 SIMOP: When Blowdown has been performed and/or the discretion of the Lead Examiner, Place the simulator in FREEZE.

(Final)

Quad Cities 2012 NRC EXAM Scenario 2 Exelon Nuclear 2012 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 2 Revision Number: 00 Date: _03/04/12_

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 2 Op-Test No.: ILT 10-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 100% power.

The 1A EHC Pump is out of Service.

1B Service Water Pump is out of service.

Turnover: QCIS 0600-01, Unit 1 Reactor Pressure 0 to 1200 psig Indication Calibration, is in progress.

Event No.

Malf. No.

Event Type*

Event Description 1

None BOP N

QCIS 0600-01 performed from the DFWLC OWS 2

None ATC R

Lower power with Rods and Recirc for Load Following 3

SW02A BOP C

Service Water Pump degradation (QCOA-3900-01) 4 RD04 ATC C

Rod Drift Out TS (QCOA-0300-11) 5 None SRO TS Torus Water Level PAM Instrument inoperable TS 6

PC05 RR03A RD13A Crew M

A RBCCW leak in the drywell requires a manual scram (QCOA-3700-06). After RPS has been tripped, approximately 1/2 of the control rods remain withdrawn. (Hydraulic ATWS) 7 TC05B Crew M

QGA 101 Level/Power Control. Turbine Bypass valves become unavailable, requiring manual RPV Pressure control with Relief Valves 8

SL01 ATC C

Malfunction after Major: Failure of 1st SBLC Pump to start (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:

Total Malfunctions (5-8): 5 Malfunction(s) after EOP (1-2): E7&8 Abnormal Events (2-4): E 3, 4, & 6 Major Transient(s) /E-Plan entry (1-2): E6 EOPs (1-2): QGA 100 & 101 EOP Contingencies (0-2): E7 Critical Tasks (2-3): 3 ES-301-5 Quantitative attributes:

BOP Normal: E1 ATC Reactivity (1 per set): E2 BOP I/C (4 per set): E3 ATC I/C (4 per set): E4 & 8 SRO-I I/C (4 per set inc 2 as ATC): E3,4 & 8 SRO Tech Spec (2 per set): E4 & 5 ALL Major Transients (2 per set) E6

Quad Cities 2012 NRC EXAM Scenario 2

SUMMARY

Initial Conditions:

o The plant is operating at 100% power.

o The 1A EHC Pump is out of service.

o The 1B Service Water pump is out of service.

Event 1: The BOP performs QCIS 0600-01 from the DFWLC OWS and returns FWLC to 3-Element.

Event 2: SRO and ATC insert control rods and lower Recirc Pump Speed and Reactor Power for Load Following.

Event 3: The 1A Service Water Pump capacity will degrade to the point that the low-pressure alarm is received in the Control Room. Reports from the Equipment Operator confirm a problem with the pump. The BOP will start the 1/2 or the 2A Service Water Pump and secure the 1A pump.

Event 4: Control Rod B-6 drifts out from position 00. The ATC and SRO respond per QCANs and QCOA 300-11. The rod should be inserted and scrammed. The SRO will declare control rod B-6 inoperable per TS 3.1.3, Condition C, requiring the inoperable rod to be fully inserted within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and disarmed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Event 5: The IMD Supervisor calls the US to report that an unqualified replacement part was recently used for the Torus Level Transmitter for Control Room Narrow Range indications.

Determines that TS 3.3.3.1 Condition A applies; 30 days to restore the PAM instrument to operable Event 6: A RBCCW leak in the Drywell requires the crew to manually scram the reactor per QCOA 3700-06. After RPS has been tripped, approximately 1/2 of the control rods remain withdrawn. (Hydraulic ATWS)

Event 7: The crew terminates and prevents injection per QGA 101 (Level/Power Control).

During this period, the running EHC pump trips which closes the Turbine Bypass valves. The crew must manually control RPV Pressure with Relief Valves. Torus Cooling will be placed in service.

Event 8: When SBLC is initiated for the ATWS, the 1st pump selected will fail to start. The ATC will recognize this malfunction and start the other SBLC Pump.

Scenario ends when actions are being taken to shutdown the reactor and RPV water level is being controlled in the specified band.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical Task #1 With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110oF torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)

Critical task #2: During at ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION, with the exception of boron, CRD and RCIC into the RPV until conditions are met to re-establish injection.

Critical task #3: When conditions are met to re-establish injection, use available injection systems to MAINTAIN RPV water level above the Minimum Steam Cooling RPV Water Level

(-166).

(Conditional Critical Task) If RPV water level lowers to less than -59 inches, inhibit ADS in accordance with QGA 100 or QGA 101.

Quad Cities 2012 NRC EXAM Scenario 2 EXERCISE PERFORMANCE OBJECTIVES SR-0202-P25 Given an operating reactor plant, perform the following RRCS operations on the Operator Work Station (OWS) in accordance with QCOP 0202-36:

- Activate/restore from 'calibrate mode' for analog inputs SR-0002-P05 Given a reactor plant at power, perform a power change discernible on neutron monitors using recirc flow in accordance with QCOP 0202-03 and QCGP 3-1.

SR-3900-P02 Given a reactor plant at power when a loss of service water occurs, take action to scram and control RPV parameters in accordance with QCOA 3900-01, 3700-01 and 3800-03.

SR-0300-P03 Given an operating reactor plant with a drifting control rod, insert/disarm the drive and attempt to determine the cause in accordance with QCOA 0300-04 and QCOA 0300-11.

SR-3700-P03 Given a reactor plant at power and indications of an RBCCW leak inside primary containment, trip the recirc pumps and isolate the RBCCW leak in accordance with QCOA 3700-06.

SR-1100-P02 Given a reactor plant with an ATWS, inject boron prior to exceeding 110 degrees torus water temperature OR if core instability is observed in accordance with QGA 101 and QCOP 1100-02.

SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.

SR-0001-P11 Given a reactor plant with an ATWS, take action to reduce heat input into the containment in accordance with QGA 101. (ATWS is a key event in 1 of the 100 most probable PRA Core Damage Sequences)

SR-0203-P07 Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)

SR-0001-P14 Given a reactor plant with an ATWS with RPV level lowered and being maintained between -166 inches and the level to where it was lowered and SBLC tank level has dropped by 16 percent, raise RPV injection rate to attempt to restore RPV water level to between +0 and +48 inches; stop injection if power starts and continues to rise in accordance with QGA 101.

SR-1000-P01 Given a reactor plant, start the RHRSW system and RHR system in torus cooling in accordance with QCOP 1000-4 and QCOP 1000-9 or QCOP 1000-

30. (Important PRA Operator Action - starting torus cooling in conjunction with other actions has a RAW of 4320) (Recovery of torus cooling after failure terminates 19 of top 100 core damage sequences)

Quad Cities 2012 NRC EXAM Scenario 2 Simulator Setup:

1. Reset to IC-21 (100% power).

2. Go to RUN.

3. Verify the following RWM Sequence is loaded: C22SU 4.Take the following equipment out of service:

Start the 1B EHC pump, take the 1A EHC Pump to PTL and hang an OOS INFO card on 1A EHC pump.

Take 1B Service Water Pump to PTL and hang an OOS INFO card.

Set up for QCIS 0600-01 as follows:

o Place FWLC in Single Element.

o At OWS, place 1-PT-0647-B in Activate per QCIS 0600-01, Step 5.7.3.

o Leave computer screens on RRCS Overview and FWLC Overview.

(The following commands to be utilized for this scenario are contained in the CAEP file:

2012 NRC Scenario 2.cae)

5. Insert Commands for setup:

imf rd13a 100 (SDV North Hydraulic lock) trgset 8 rdv10305118.lt.0.99 (When B RPS is tripped) imf tc05b(8 5:) (5 minutes after Trigger 8, 1B EHC pump trips) ior dihs13901b ptl (Override B Service Water Pump in PTL) imf sl01a (1A SBLC Pump trip) imf sl01b (1B SBLC Pump trip) trgset 10 (zaoai111403b.le.0.01).and. zaoai111403a.le.0.01) (Both Squib lights off) trgset 11 (zaoai111403b.le.0.01).and. zaoai111403a.le.0.01) (Both Squib lights off) trg 10 dmf sl01a (On Trigger 10, pump trip is deleted, selected pump starts) trg 11 dmf sl01b (On Trigger 11, pump trip is deleted, selected pump starts)

6. Verify the following commands for scenario performance:

imf sw02a 34 1: (1A SWP capacity degrades to 34% severity on a 1 min ramp) imf rd04r1431 (Rod D-8 drift Out) irf rd06r1431r inop (Disables rod D-8 at HCU) dmf rd04r1431 (Deletes Rod Drift Out Malfunction) imf pc05 40 (RBCCW leak in Drywell at 40% severity) irf rd04r close (As requested, close the CRD 1-301-25 valve) irf qg09r 1 (As requested, install MSIV Lo-Lo Level Isolation bypass jumpers) irf qg08r 1 (As requested, install jumpers to bypass all scrams) irf qg14r 1 (As requested, pull ARI fuses)

7. Verify SBO alarms clear.

8. Provide the Scram Key, Panel 901-16, to the BOP Evaluator.

9. Provide a prepared copy of a 100% OD-20 to the Lead Evaluator.

10. Provide a Holding Load and a Load Following REMA.

11. Provide a current revision of the following procedures, signed off as specified:

QCIS 0600-01, Unit 1 Reactor Pressure 0 to 1200 psig Indication Calibration, marked up to Step 5.7.16

12. Provide blank ESTs for use during the scenario.

13. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.

Quad Cities 2012 NRC EXAM Scenario 2 LIST OF POTENTIAL PROCEDURES Annunciator Procedures:

o 901-4 A-17 DRYWELL FLOOR DRAIN SUMP HIGH LEVEL, Rev. 7 o 901-5 A-3, ROD DRIFT, Rev. 7 o 912-1 B-3 SERVICE WATER LOW PRESSURE, Rev. 6 o 912-1 F-1 RX BUILDING CW EXP TANK HI/LO LEVEL, Rev. 3 QCGP 2-3, Reactor Scram, Rev. 74 QCGP 3-1, Reactor Power Operations, Rev. 66 QGA 100, RPV Control, Rev. 9 QGA 101, RPV Control (ATWS) Rev. 13 QGA 200, Primary Containment Control, Rev. 9 QCOA 3900-01, Service Water System Failure, Rev. 16 QCOA 0300-11, Control Rod Drift, Rev. 22 QCOA 3700-04, RBCCW Expansion Tank high/Low Level, Rev. 7 QCOA 3700-06, RBCCW Line Break Inside Containment, Rev. 6 QCOP 0201-16, Terminate and Prevent RPV Injection, Rev. 5 QCOP 0300-28, Alternate Control Rod Insertion, Rev. 30 QCOP 0203-01, Reactor Pressure Control Using Manual Relief Valve Actuation, Rev. 13 QCOP 1100-02, Injection of Standby Liquid Control, Rev. 12 QCIS 0600-01, Unit 1 Reactor Pressure 0 to 1200 psig Indication Calibration, Rev. 6

Quad Cities 2012 NRC EXAM Scenario 2 CREW TURNOVER 1.) Plant Conditions:

a.) Unit 1 is at 100% Power.

b.) Unit 2 is at 100% Power.

c.) Technical Specification limitations:

(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.

2.) Significant problems/abnormalities:

a.) 1A EHC pump is Out-of-Service for motor bearing replacement.

b.) The 1B Service Water pump is Out-of-Service for repair of cracked terminal leads.

3.) Evolutions/maintenance for the oncoming shift:

a.) There is a potential that QC Unit 1 may have to drop load for load following.

Load Holding and Load Following REMAs are provided.

b.) BOP, assist with completion QCIS 0600-01 Unit 1 Reactor Pressure 0 to 1200 psig Indication Calibration, starting at Step 5.7.16.

A TIC has been written to allow the BOP (rather than the Unit NSO) to support this operation.

Place FWLC back in 3-Element per QCOP 0600-12.

c.) EOs on shift:

Burke Parrish Foster Richardson Hughes Brewer Decker Schmidt

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 1 Page 1 of 1 Event

Description:

QCIS 0600-01 performed from the DFWLC OWS Time Position Applicants Actions or Behavior SRO Directs and supervises the completion of QCIS 0600-01 BOP Navigate to the screen titled FWLC_2 Measuring Points BOP Verify correct 1-PT-0647-B parameter pressure indication for current plant status BOP Select box on screen corresponding to 1-PT-0647-B parameter BOP Select Deactivate at bottom of AS500 OS screen BOP Verify box associated with parameter in deactivate mode is clear in color BOP Places FWLC in 3-Element per QCOP 0600-12 BOP Verifies FWLC system is not in Forced 1-Element control mode on OWS BOP Momentarily depress the THREE pushbutton on the RX LEVEL MASTER CONTROLLER, 1-0640-18 and verifies the correct pushbutton indication ATC Monitors reactor controls and indications End of Event 1

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 2 Page 1 of 1 Event

Description:

Lower power with Recirc for Load Following Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, contact the Control Room as the Shift Manager and inform the US to lower power by 50 MWe. Inform the US that the Power Team and NDO have been notified.

ATC/BOP Dispatch an EO to set the mechanical travel stop for the Stator cooling TCV in the FULL-UP position SIMOP ROLE PLAY: As the dispatched EO. Wait 2 minutes and then report that the mechanical travel stop for the Stator cooling TCV are in the FULL-UP position.

SRO Provides SRO oversight for lowering reactor power using core flow SRO Deactivates the Holding Load REMA and activates the Load Drop REMA. (Notch control rods to lower FCL prior to reducing flow.)

Lead Examiner Role Play: Qualified Verifier (QV) as necessary.

After operators have demanded an OD-20 from the PPC, provide a prepared copy of a 100%

OD-20.

ATC/BOP Demands an OD-20 in order to verify initial conditions for the REMA.

ATC On the RWM verifies proper rod selected, its current position &bounds ATC Communicates to the QV. Ready to insert Rod __-__from position __

to position __ (continuous or notching).

QV Replies: Rod __-__ is selected. Understand inserting rod __-__ from position __ to position __ (continuous or notching).

ATC Replies: That is correct ATC Verifies control rod and moves it to the desired position ATC/BOP Place keeps rod moves in the rod movement book ATC Repeats above steps as necessary ATC Depresses LOWER pushbutton on Recirc MASTER SPEED DEMAND ATC Verifies Reactor pressure (PR 640-28 preferred) in the acceptable region of the CORE Power vs. Reactor Pressure Curve ATC Closely monitors power decrease on APRMs ATC Verifies POWERPLEX is operating and monitors outputs for peaking ATC Verifies Reactor Recirc Pumps remain at approximately equal flows BOP Adjusts LOAD SET as necessary by performing steps on Att. D step 2 for DEHC on the 901-7 panel BOP Provides peer check as requested for power changes End of Event 2

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 3 Page 1 of 1 Event

Description:

Service Water Pump Degradation Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner Insert Malfunction: imf sw02a 34 1:

Key Parameter Response: Service Water Pressures on Panel 912-1; 1/2 -3940-4 & 18 Expected Annunciator(s): 912-1 B-3 SERVICE WATER LOW PRESSURE Automatic Actions: None (Note: The normal standby pump, 1B, is out of Service)

BOP Responds to annunciator and informs the Unit Supervisor BOP Identifies and reports that Service Water pressure is at the alarm point but steady SRO Supervises actions of the QCAN and/or QCOA 3900-01 SRO May set Scram Criteria at 80 psig Service Water Header Pressure BOP Dispatches an EO to investigate SIMOP ROLE PLAY: As the EO dispatched to the Crib House: Wait 2 minutes and then report that that the 1A Service Water Pump is very noisy and feels warmer than normal.

If asked, report that the 1A SW pump discharge pressure is 75 psig. Report all other running SW pump discharge pressures at 115 psig.

BOP Monitors Service Water pressure on PI 1/2-3940-18 BOP Recognizes that the 1B pump will not start at 75 psig as header pressure lowers SRO May direct starting the 1/2 or 2A SWP BOP Verifies closed the FIRE PROT SW SPLY VLV, MO-1/2-3906 BOP Starts standby Service Water Pumps to restore normal system pressure BOP Secures the 1A SWP ATC Monitors Panel 901-5 indications End of Event 3

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 4 Page 1 of 2 Event

Description:

Rod Drift Out Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner initiate the Rod Drift Out on rod D-8 (14-31):

imf rd04r1431 Key Parameter Response: Rod D-8 position changing on Full Core Display; Rated thermal power rising (up to 5%)

Expected Annunciator(s): 901-5 A-3, ROD DRIFT Automatic Actions: None ATC Acknowledges annunciator 901-5 A-3, Rod Drift, and reports control rod D-8 is drifting out SRO Directs actions of QCOA 0300-11, Control Rod Drift SRO May give Scram Criteria of 2 or more Control Rods drifting ATC Bypasses RWM and inserts control rod D-8 using the RMCS to position 00 (Immediate operator action)

SIMOP ROLE PLAY: If contacted as Shift Manager and/or QNE in the next steps, Role play as necessary to acknowledge the report.

SRO Notifies Shift Manager SRO Notifies QNE BOP Demands an OD-20 ATC Releases RMCS, observes rod D-8 begins to drift out from position 00, then applies continuous insert signal to keep rod D-8 at position 00 ATC Reports control rod D-8 will NOT latch at position 00 SRO Directs control rod D-8 scrammed using the Rod Scram Test Switch BOP EVALUATOR: Provide the Scram Key to the BOP.

BOP Places the individual Control Rod Scram Test Switch for D-8 into the scram position at the 901-16 panel ATC Confirms blue scram light for control rod D-8 is lit and release RMCS Event 4 Continued

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 4 Page 2 of 2 Event

Description:

Rod Drift Out Time Position Applicants Actions or Behavior BOP Dispatches EO to close the 1-305-105, CRD EXH VLV, for HCU 14-31 SIMOP ROLE PLAY: As EO dispatched to the North CRD Bank, wait approximately 2 minutes, then insert the Remote Function to close the 1-305-105 valve: irf rd06r1431r inop and delete the Rod Drift Out Malfunction: dmf rd04r1431.

Call the NSO to report that the 1-305-105 valve for HCU 14-31 is closed.

SRO Declares control rod D-8 inoperable and enters TS 3.1.3, Condition C, which is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to fully insert and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to disarm and may direct an EO to disarm the Control Rod per QCOP 300-07 SIMOP ROLE PLAY: If contacted as an EO to disarm the rod, acknowledge the direction.

SIMOP ROLE PLAY: If contacted as System Engineer; Acknowledge report and state that you will start troubleshooting SRO Enters QCOS 0300-14 to track inoperable rod and electrically disarm End of Event 4

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 5 Page 1 of 1 Event

Description:

Torus Water Level PAM Instrument inoperable Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: When directed by the lead examiner, as IMD Supervisor, notify the Unit Supervisor that a vendor has reported the following:

A recently installed replacement part in the instrument loop for LI 1-1640-10A, TORUS LVL, is un-qualified. The indication probably reads correctly now but its performance cannot be assured during an accident.

If asked about its affect on other indicators/recorders, state that the LI 1-1640-10A is the ONLY indicator affected.

SRO Refers to QCOS 1600-05 and Technical Specifications 3.3.3.1 for Post Accident Monitoring requirements SRO Determines that TS 3.3.3.1 Condition A applies; 30 days to restore the PAM instrument to operable ATC Monitors Panel 901-5 controls and indications BOP Monitors Balance of Plant parameters End of Event 5

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 6 Page 1 of 4 Event

Description:

RBCCW Leak Inside Drywell / Manual Scram / Hydraulic ATWS Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner initiate a Reactor Building Closed Cooling Water leak in the Drywell: imf pc05 40 Key Parameter Response: Drywell Pressure rises from 1.23 psig to 1.26 psig in first 4 min.

Expected Annunciator(s):

901-4 A-17 DRYWELL FLOOR DRAIN SUMP HIGH LEVEL (Alarms in 4 minutes) 912-1 F-1 RX BUILDING CW EXP TANK HI/LO LEVEL (alarms in 5 minutes and clears 4 minutes after RBCCW to DW is isolated)

Automatic Actions: None BOP Responds to unexpected annunciator 901-4 A-17 and informs the US SRO May direct pumping of DW Floor Drain Sumps BOP If directed, pumps DW Floor Drain Sumps per QCAN 901-4 A-17 BOP Notes DW FDS Running Total BOP Opens DW FDS Discharge Valves AO-2001-3 & 4 BOP Verifies Pump starts BOP Verifies Pump discharge Valve lineup and discharge flow BOP Responds to unexpected annunciator 912-1 F-1 and informs the US BOP/ATC Checks Event recorder (SER Point for RBCCW Expansion Tank low Level) to determine which unit is affected and whether level is high or low SRO Enters and directs QCOA 3700-04 BOP/ATC Dispatches an EO to determine which unit is affected SIMOP ROLE PLAY: As the dispatched EO; Wait 2 minutes to report that Unit 1 RBCCW Expansion Tank level is at 20 inches and lowering slowly.

Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 6 Page 2 of 4 Event

Description:

RBCCW Leak Inside Drywell / Manual Scram / Hydraulic ATWS Time Position Applicants Actions or Behavior BOP/ATC Notifies Chemistry that RBCCW draining or filling is taking place SIMOP ROLE PLAY: As the contacted Chemistry Tech; Acknowledge this report BOP/ATC Directs the EO to determine LCV 1-3701 operation SIMOP ROLE PLAY: As the dispatched EO; If asked about the Level Control Valve that the Makeup Valve is open but not keeping up.

BOP/ATC Directs the EO to check the RBCCW System for leaks SIMOP ROLE PLAY: As the dispatched EO; If directed to inspect RBCCW for leaks, Acknowledge this directive, wait 5 minutes and then report no RBCCW leaks have been found Crew May identify slightly higher Drywell pressure SRO May enter QCOA 0201-01 for rising Drywell pressure SRO May set Scram Criteria at 2 psig Drywell pressure Evaluator Note: DW FDS high level, RBCCW Expansion Tank Low Level and DW Pressure rising are 3 of 6 Symptoms listed for QCOA 3700-06 entry.

SRO Enters and directs QCOA 3700-06, RBCCW Line Break Inside Drywell SRO Directs the ATC/BOP to manually scram the reactor and trip the Recirc Pumps SRO Directs the BOP to close the RBCCW Supply and Return Valves to the Drywell ATC Depresses both Manual Scram pushbuttons ATC/BOP Trips both Recirc Pumps BOP At Panel 912-1, takes Unit 1 RBCCW switch to CLOSE and verifies that the 3 associated valves close (MO-1-3702, 3703 & 3706)

Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 6 Page 3 of 4 Event

Description:

RBCCW Leak Inside Drywell / Manual Scram / Hydraulic ATWS Time Position Applicants Actions or Behavior ATC Reports control rods did NOT insert SRO Enters QGA 100, transitions to QGA 101 ATC Places the Mode Switch in SHUTDOWN ATC Arms and depresses ARI SRO Directs BOP to inhibit ADS BOP Inhibits ADS SRO Directs BOP to place both Core Spray pumps in PTL BOP Places both Core Spray pumps in PTL SRO Directs actions for Power Leg of QGA 101 SRO Directs control rod insertion per QCOP 0300-28 ATC May dispatch EO to close the 1-301-25, U-1 CRD CHARGING WTR SV if control rods cannot be inserted SIMOP ROLE PLAY: If requested as EO, close the 1-301-25 valve using: irf rd04r close ATC Inserts all CRAM rods to position 00 ATC Continues to insert control rods spiraling outward from center of core SRO Directs actions of QGA 101 Level Control Leg SRO Directs verification of auto actions and isolations for 0 inches RPV water level BOP Verifies auto actions and isolations for 0 inches RPV water level SRO Directs isolations bypassed per QCOP 0250-02 BOP Contacts EO/SS to bypass RPV low water level MSIV and high offgas radiation isolations per QCOP 0250-02 SIM OP: If requested, bypass isolations per QCOP 0250-02: irf qg09r 1 Wait 1 minute and report completion Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 6 Page 4 of 4 Event

Description:

RBCCW Leak Inside Drywell / Manual Scram / Hydraulic ATWS Time Position Applicants Actions or Behavior ATC Directs operator to bypass all reactor scrams per QCOP 0300-28 SIMOP ROLE PLAY: If requested, wait approx. 2 minutes and bypass all reactor scrams using: irf qg08r 1 Then report completion.

ATC (If RPV Water Level drops below -59 inches) Dispatches EO to de-energize ARI by removing fuses in 2201-70A and 2201-70B panels per QCOP 0300-28 SIMOP ROLE PLAY: If requested as EO, pull the ARI fuses in the 2201-70A and 2201-70B panels in Aux Electric Room using: irf qg14r 1 Then report completion.

ATC Verifies scram is reset and inserts another manual scram ATC Verifies NO control rod movement and resets reactor scram ATC Directs personnel to individually scram control rods from the 901-16 panel SIMOP ROLE PLAY: Attempt to individually scram 3 control rods, then contact the ATC operator and report, Control rods will not insert from the 901-16 panel.

CT1 SRO Directs SBLC Injection prior to exceeding 110°F Torus Water Temperature CT1 ATC Initiates SBLC Injection as directed (See Event 8)

End of Event 6

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 7 Page 1 of 3 Event

Description:

QGA 101 Level/Power Control Time Position Applicants Actions or Behavior SRO Verifies reactor power greater than 5% and RPV water level greater than -35 inches CT2 SRO Directs all injection except boron, CRD, and RCIC terminated and RPV water level lowered to at least -35 inches. (Terminate and prevent from 901-3 and 901-5)

CT2 BOP Performs Terminate and Prevent Injection from Panel 901-3 BOP Places HPCI in Trip-Latch BOP (If RHR is running) Verifies RHR Discharge Pressure < Reactor Pressure by throttling RHR 36A/B, or places RHR Pumps in Pull-To-Lock CT2 ATC Performs Terminate and Prevent Injection from Panel 901-5 ATC Places A and B Feed Reg Valve Controllers in MANUAL and reduces output to 0 (zero)

ATC Places the Low Flow Feed Reg Valve Controller in MANUAL and reduces output to 0 (zero)

ATC Closes A and B Feed Reg Valve isolations, MO-1-3206-A/B ATC/BOP Reports RPV Water level when Rx power less than 5%, RPV water level at TAF or ADS valves are closed with DW pressure less than 2.5 psig.

SRO Establishes a RPV Water level control band below -35 inches ATC/BOP Maintains RPV water level as directed.

Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 7 Page 2 of 3 Event

Description:

QGA 101 Level/Power Control Time Position Applicants Actions or Behavior CT3 SRO Directs RPV water level maintained between -166 inches and the level to which it was lowered CT3 ATC/BOP (CONTINUOUS) Maintains level between -166 inches and level lowered to with Preferred Injection systems EVALUATOR NOTE: Depending on how long the scenario continues, the Hot Shutdown Boron Weight may not be injected. If it is not, the following two steps will not be performed.

SRO When Hot Shutdown Boron Weight has been injected (SBLC tank lowers by 16% in approximately 21 minutes), directs RPV water level restoration to the band of 0-48 inches ATC Restores RPV water level to the band of 0-48 inches SRO Directs actions for Pressure Leg of QGA 101 CREW (CONTINUOUS) Monitor RPV pressure CREW Determines RPV pressure rising out of the established range BOP/ATC May report that the Turbine Bypass valves have closed and ADS valves cycled to control RPV pressure BOP/ATC Diagnoses the loss of Turbine Bypass Valves due to the (only available) EHC Pump tripping SRO Directs BOP to lower RPV pressure to 940 psig using ADS valves SRO Establishes a RPV Pressure control band and directs BOP to control RPV pressure in that ban using ADS valves (typically 800-1000 psig)

BOP Opens ADS valves to lower RPV pressure to < 940 psig.

BOP (CONTINUOUS) Operates ADS valves as necessary to maintain the established pressure band BOP (CONTINUOUS) Monitor and reports Torus Water Temperature BOP Informs the Unit Supervisor if Torus Water Temperature exceeds 95°F EOP Entry Condition SRO Enters and directs actions of QGA 200 as necessary Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 7 Page 3 of 3 Event

Description:

QGA 101 Level/Power Control Time Position Applicants Actions or Behavior BOP Places RHR in the Torus Cooling Mode as directed BOP If per QCOP 1000-30 Hard Card, establishes RHRSW flow BOP Places RHR LOOP A/B CONTAINMENT CLG permissive switch 17 to the ON position BOP Places RHR LOOP A/B RHR SW START PERMISSIVE SWITCH 19 to the MANUAL OVERRIDE position BOP Throttles open MO-1-1001-5A/B RHR SW HX Discharge Valve, to at least 40% open BOP Starts the first RHRSW Pump in each loop BOP Throttles MO-1-1001-5A/B to establish less than 3600 gpm/pump BOP Throttle closed MO 1-1001-16A/B (HX Bypass) on each Loop BOP May start the second RHRSW Pump in each loop and adjusts as necessary BOP Starts Torus Cooling as directed BOP Verifies RHR Pumps running BOP Opens Torus Test or Spray Valve, MO 1-1001-34A/B BOP Opens Torus H2O Test Valve, MO 1-1001-36A/B BOP Adjusts Torus H2O Test Valve MO 1-1001-36A/B to maintain RHR SW Pressure 15-20 psig higher than RHR pressure and RHR pressure between 100 and 250 psig BOP Closes MO 1-1001-16A/B End of Event 7

Quad Cities 2012 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 2 Event No: 8 Page 1 of 1 Event

Description:

Failure 1st SBLC Pump to start Time Position Applicants Actions or Behavior SIMOP: Verify that the 1st SBLC pump selected for injection does NOT start but the 2nd SBLC pump does start.

ATC Reports SBLC tank level and selects a SBLC pump for injection by placing the control switch to SYS 1 or SYS 2 ATC May report that the SBLC pump has failed to inject CT1 ATC Selects the other SBLC pump ATC Verifies and reports the 2nd SBLC pump is injecting ATC Squib B light is off ATC Flow Light is on ATC RWCU System isolated ATC SBLC Tank level lowering ATC Pump discharge pressure slightly high than reactor pressure ATC Annunciator 901-5 H-6 SBLC Squib valve circuit failure is on ATC Neutron flux is decreasing ATC Monitors SBLC Tank level for 16% decrease (in approximately 21 minutes)

BOP Performs other operator actions of QGA 101 End of Event 8 SIMOP: When RPV water level is being restored and/or at the discretion of the Lead Examiner, place the simulator in FREEZE.

(Final)

Quad Cities 2012 NRC EXAM Scenario 1 Exelon Nuclear 2012 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 1 Revision Number: 00 Date: 03/04/12 Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 1 Op-Test No.: ILT 10-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

A Startup is in progress at 7% Power in RUN (After a forced outage for a Recirc pump seal repair)

Turnover:

Establish Drywell inerting. Continue the startup by withdrawing control rods to open the Turbine Bypass Valves further.

Event No.

Malf. No.

Event Type*

Event Description 1

None BOP N

Establish the Drywell Inerting lineup per QCOP 1600-20 2

dihs10700ap4md 4 (Override)

NM08E ATC I

Multiple APRM Failures. APRM 4 fails inoperable. Later, APRM 5 Fails slowly Downscale TS (QCOA 0700-03) 3 None ATC R

Withdraw control rods to achieve 2-4 Turbine Bypass Valves open 4

RD02R4211 ATC C

Recoverable Stuck Rod / Raise CRD Drive Pressure (QCOA 0300-02) 5 MC15R (Remote Function)

BOP I

Loss of SJAE Steam (Recoverable)

(QCOA 5400-04) 6 ED02 ED03D ED04K DG03B Crew M

Station Blackout is entered. The SBO diesel will be used to reenergize Bus 14-1.

(QCOA 6100-04) 7 RR10A HP08 RC01 Crew M

The transient initiates a small LOCA in the Drywell; QGA 100 and 200 are performed.

RCIC trips, the SSMP must be manually initiated, and local action is necessary to make HPCI available. When essential bus power is restored, the challenges to the Primary containment will be addressed.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:

Total Malfunctions (5-8): 5 Malfunction(s) after EOP (1-2): 2, E7 Abnormal Events (2-4): E2, 4, 5,& 6 Major Transient(s) /E-Plan entry (1-2): E6 EOPs (1-2): QGA 100 and 200 EOP Contingencies (0-2): None Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:

BOP Normal: E1 ATC Reactivity (1 per set): E3 BOP I/C (4 per set): E5 ATC I/C (4 per set): E2 & 4 SRO-I I/C (4 per set inc 2 as ATC): E2,4&5 SRO Tech Spec (2 per set): E2 ALL Major Transients (2 per set) E6

Quad Cities 2012 NRC EXAM Scenario 1

SUMMARY

Initial conditions:

o The plant is operating at 7% power just after the Mode Switch was taken to RUN.

(After a forced outage for a Recirc pump seal repair)

Event 1: The BOP establishes the Drywell Inerting lineup per QCOP 1600-20.

Event 2: Multiple APRM Failures. Part 1: APRM 4 fails inoperable, resulting in a 1/2 Scram and Rod Block. Since no other Channel B APRMs are out of service, APRM 4 can be bypassed and the 1/2 Scram reset. (Note: This event continues after the stuck rod is resolved in Event 4.)

Event 3: The crew resumes control rod withdrawal to achieve 2 to 4 Turbine Bypass Valves opened per QCGP 1-1 Step F.6.kk.

Event 4: During rod withdrawal, one rod will not move from position 08. When the ATC raises CRD drive water pressure, the rod can be withdrawn. Drive water pressure should then be returned to normal.

Event 2, Part 2: APRM 5 will fail downscale over a 1-minute period. The failure will result in a Rod Block and downscale alarms. The SRO must address Tech Specs 3.3.1.1, RPS Instrumentation, for a second APRM inoperable on RPS Channel B and address TRM 3.3.a for Rod Block Instrumentation. If directed, the ATC will manually insert a B RPS 1/2 Scram.

Event 5: Loss of SJAE steam results in the North Condenser Suction valves closing.

(Condenser vacuum remains stable at low power) The BOP and SRO work through QCAN 901-7 A-14, QCOA 3300-02 and QCOA 5400-04 to identify the loss of steam to the in service SJAE. Bypassing the steam supply PCV will be successful. The BOP will reopen the SJAE Suction Valves.

Event 6: A Loss of Offsite Power occurs. Bus 13-1 locks out and the U1 Diesel cannot be started. When Bus 14-1 to Bus 24-1 crosstie fails, Station Blackout is entered. The SBO diesel must be used to reenergize Bus 14-1, which may be used to backfeed Bus 14 and Bus 19.

Event 7: The transient initiates a small LOCA in the Drywell; QGA 100 and 200 are performed. The crew will attempt to manually initiate RCIC but it will trip on a mechanical overspeed fault that cannot be reset. Local action is necessary to make HPCI available. The crew will start the SSMP to maintain RPV Water level. When essential bus power is restored, the challenges to the Primary containment will be addressed.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical task #1: Given a shutdown reactor with a LOCA in progress, restore and maintain RPV water level with available high-pressure systems IAW with QGA 100 before RPV water level reaches TAF.

Critical task #2: When Torus pressure exceeds 5 psig, INITIATE drywell sprays while in the safe region of the drywell spray initiation limit (DSIL). (BWROG PC-5.1 INIT DW SPRAY)

(Conditional Critical Task) If RPV water level lowers to less than -59 inches, inhibit ADS in accordance with QGA 100.

Quad Cities 2012 NRC EXAM Scenario 1 EXERCISE PERFORMANCE OBJECTIVES SR-1600-P01 Given a reactor plant during a startup, inert the primary containment using the electric vaporizers and the reactor building ventilation system in accordance with QCOP 1600-20.

SR 0700-P07 Given an operating reactor plant with an APRM failure, take actions to bypass the failed APRM and meet TS requirements in accordance with QCOP 0700-04 and QCAP 0230-19. (SOER 90-3 r1)

SR-0002-P04 Given a reactor plant at power, perform a power change discernible on neutron monitors using control rods in accordance with QCOP 0280-01, QCGP 3-1 and QCGP 4-1.

SR- 0300-P05 Given a reactor plant during a startup with a stuck control rod, restore the ability to drive the control rod or declare the rod inoperable in accordance with QCOA 0300-02.

SR-3300-P09 Given a reactor plant at power with a loss of condenser vacuum, take action to attempt to locate and correct the cause for lowering vacuum in accordance with QOA 3300-02 and/or QOA 5450-05. (PRA Initiating Event %TC - Loss of Vacuum accounts for 4.2% of total CDF and initiates 4 of the top 100 Core Damage Sequences)

SR-0001-P45 Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.

SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.

SR-0203-P07 Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)

SR-0001-P01 Given the plant with a loss of normal feedwater resulting in the inability to restore RPV water level above 0 inches, inject with Alternate Injection Systems (QGA Detail E) to attempt to hold RPV water level above -142 inches in accordance with QGA 100.

SR-1000-P02 Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)

SR-1000-P04 Given a reactor plant with rising containment pressures due to a LOCA or steam leak and RHR is not needed for core cooling, verify parameters are in the safe region of the Drywell Spray Initiation Limit (QGA Figure K), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays when torus pressure exceeds 5 psig in accordance with QGA 200 and QCOP 1000-30. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)

SR-1000-P05 Given a reactor plant in an accident condition where RHR-LPCI mode has started automatically, determine if LPCI has responded correctly to a valid initiation and throttle flow to restore RPV water level in accordance QCOA 1000-04.

SR-6100-P08 Given an operating reactor plant when a station blackout occurs, take actions to monitor plant parameters and restore electrical power using the emergency DGs, SBO DGs, or unit 4KV crossties in accordance with QCOA 6100-04, QCOA 6100-03 and/or QCOP 6500-08.

Quad Cities 2012 NRC EXAM Scenario 1 Simulator setup:

1. Reset to IC-14 (Approximately 7% power).

2. Go to RUN.

3. Verify the following RWM Sequence is loaded: C22SU

a. Mark up the Control Rod Move Sheet to reflect all rods withdrawn up to Step 17

b. Markup Step 17 Rods E-9 and L-7 at position 12.

4. Transfer the Mode Switch to RUN per QCGP 1-1 Step F.6.ii:

a. Place the Mode Switch in RUN

b. Place all IRM/APRM Recorders to APRM.

c. Place all IRM/RBM Recorders to RBM.

d. Withdraw IRM detectors.

e. Verify all APRM/RBM Recorders on LOW Speed.

5. Select the 1A RFP for STANDBY.

(Commands to be utilized during this scenario are contained in the CAEP file:

2012 NRC Scenario 1.cae)

6. Insert Commands for setup:

imf rd02r1827 08 (Control Rod E-7 stuck at position 08) trgset 1 rdpdrivedelta > 340 (Set trigger 1 as CRD drive Pressure > 340#)

trg 1 dmf rd02r1827 (Delete stuck rod on Trigger 1) imf ed04k (Bus 14-1 to 24-1 crosstie breaker failure) imf dg03a (U1 EDG start failure) imf ed03d(3) (On Event Trigger 3, Bus 13-1 Lockout) imf ed02(3) (On Event Trigger 3, Loss of RAT) imf rr10a(3 3:) 0.13 7:30 (On Event Trigger 3, Recirc Suction Line Break at 0.13%

severity on a 7.5 min ramp after a 3 minute delay) imf rc01(7 :10) (RCIC trips on Overspeed 10 seconds after initiation.)

imf hp08 (HPCI Aux Oil Pump overload during auto start) trgset 7 zlohs1130161(2) (When RCIC Steam to Turbine Valve Red light comes on) irf hv01r ro (Rack out 1A DW/Torus Purge Fan breaker for inerting)

7. Verify the following commands for scenario performance:

irf pc02r open (Opens the 1-8799-85 Cold Valve) ior aofr187408 100 1: (Provides indication of nitrogen flow in inerting lineup) ior dihs10700ap4md 3 (Overrides APRM 4 MS to ZERO, in effect APRM INOP) imf nm08e 0 1: (APRM 5 downscale failure on a 1 minute ramp) irf mc15r closed (Closes the steam supply to the B (in-service) SJAE) mrf mc15r open (Re-opens the steam supply to B SJAE, in effect bypassing PCV) trg! 3 (Initiates the Station Blackout and then a LOCA 3 minutes later) irf ed34r close (Bus 24-1 to bus 14-1 breaker on U2 as requested dmf hp08 (Upon request, deletes HPCI Aux Oil Pump fault, allows HPCI auto start) irf rp02r mg_set and irf rp29r reset (Restores A RPS as requested) irf rp03r mg_set and irf rp28r reset (Restores B RPS as requested)

(Continued)

Quad Cities 2012 NRC EXAM Scenario 1

8. Take the following equipment OOS (hang OOS Card):

None

9. Complete the following Control Panel setup items:

Remove the LOCA TRIP ENABLED labels from above the Circ Water Pumps.

Display the Power/Flow Map on Monitor 3.

Clear all SBO Panel alarms.

10. Verify Shell Warming in service per QCOP 5600-02, completed to Step F.2.j.

11. Complete the following lineup for Drywell Inerting:

On Panel 901-4,:

AO 1-4723 RES SPLY, hang an Equip Status Tag stating that Inst Air is valved in as a backup to Drywell Pneumatic System.

At Panel 901-3:

Close AO 1-1601-21 DW PRG VLV Close AO 1-1601-22 DW OR TORUS PRG VLV Close AO 1-1601-23 DW VENT VLV Close AO 1-1601-24 VENT TO RX BLDG EXH SYS Set PIC 1-1640-11 Containment Pressure to 20% open On Panel 912-5 Verify 1B Drywell/Torus Purge Fan is OFF Take the 1A Drywell/Torus Purge Fan Handswitch to OFF Verify GREEN Flag for 1A Drywell/Torus Purge Fan Handswitch Hang an Equipment Status Tag on the 1A Drywell/Torus Purge Fan

12. Provide a current revision of the following procedures, signed off as specified:

(Entire) QCGP 1-1 signed off up to Step F.6.kk.

QCGP 4-1 signed off up to Step F.2.c QCOP 0280-01 signed off up to Step F.2 QCOP 1600-20, signed off up to step F.9.

QCOP 5600-02, signed off up to step F.2.j

13. Provide a Reactor Startup REMA.

14. Provide blank ESTs for use during the scenario. (See Event 2 Part 1)

15. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.

Quad Cities 2012 NRC EXAM Scenario 1 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-16, PRI CNMT HIGH PRESSURE, Rev.12 o 901-4 G-15, RCIC TRIP THROTTLE VALVE CLOSED, Rev. 2 o 901-5 D-13 CHANNEL 4-6 APRM HI-HI OR INOP, Rev. 9 o 901-5 C-3, ROD OUT BLOCK, Rev. 11 o 901-5 C-6 APRM DOWNSCALE, Rev. 5 o 901-7 A-7, TURB BRG OIL LOW PRESS, Rev. 5 o 901-7 E-9, TURNING GEAR OIL PUMP AUTO TRIP, Rev. 3 o 901-7 G-9, TURB BRG LIFT PUMP AUTO TRIP, Rev. 4 o 901-8 A-4, DIESEL GEN 1/2 TROUBLE, Rev. 5 o 901-8 A-7, DIESEL GEN 1 TROUBLE, Rev. 5 o 901-8 C-7, DIESEL GEN 1 FAIL TO START, Rev. 3 o 901-8 E-2, RESERVE TRANS 12 TRIP, Rev. 3 o 901-8 G-2, RESERVE AUX TRANS 12 LOW VOLTAGE, Rev. 4 o 901-8 F-3, 4KV BUS OVERCUR TRIP, Rev. 5 QCGP 1-1, Normal Unit Startup, Rev. 87 QCGP 4-1, Control Rod Movements and Control Rod Sequence, Rev. 38 QCGP 2-3, Reactor Scram, Rev. 74 QGA 100, RPV Control, Rev. 9 QGA 200, Primary Containment Control, Rev. 9 QCOA 0201-01, Increasing Drywell Pressure, Rev. 23 QCOA 0300-02, Inability to Drive a Control Rod: Control Rod Stuck, Rev. 17 QCOA 0700-03, Loss of Neutron Flux Indication. Rev. 8 QCOA 1000-04, LPCI Automatic Initiation, Rev. 15 QCOA 1300-01, RCIC Turbine Trip/Isolation Recovery, Rev. 15 QCOA 6100-03, Loss of Offsite Power, Rev. 27 QCOA 6100-04, Station Blackout, Rev. 15 QOA 6700-01, 480 V Bus 15, 16, or 17 Failure, Rev. 11 QCOP 0280-01, Reactor manual Control Operation, Rev. 16 QCOP 0700-04 APRM System Operation, Rev. 16 QCOP 1000-30, Post-Accident RHR Operation, Rev. 26 QCOP 1300-02, RCIC System Manual Startup, Rev. 29 QCOP 1600-20, Nitrogen Inerting of Primary Containment Using the Vaporizer(s) and Reactor Building Ventilation System, Rev. 28 QCOP 2300-06, HPCI System Manual Startup, Rev. 31 QCOP 2700-02, Hydrogen Water Chemistry System Shutdown, Rev. 14 QCOP 2900-02, SSMP System Startup, Rev. 23 QCOP 5600-04, Main Turbine Warming, Rev. 21 QCOP 6500-08, 4KV Bus Crosstie Operation, Rev. 24 QCOP 6620-14, Energizing Bus 14-1 From SBO DG 1, Rev. 14

Quad Cities 2012 NRC EXAM Scenario 1 CREW TURNOVER

1. Plant Conditions:

a.) Unit 1 is at 7% power with the Mode Switch in RUN.

(1) After a forced outage for a Recirc pump seal repair b.) Unit 2 is at 100% power.

c.) Technical Specification limitations:

(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.

2.) Significant problems/abnormalities:

a.) None 3.) Evolutions/maintenance for the oncoming shift:

a.) Resume QCOP 1600-20. The EO just opened the breaker for the 1A DW/TORUS PURGE FAN per Step F.6.d and verified that Nitrogen Vaporizer valves in the 1/2 DG Room are closed per Step F.8. Establish inerting of the Drywell.

b.) Continue Reactor startup per QCGP 1-1. Currently withdrawing Control Rods to achieve 2-4 Bypass valves open per Step F.6.kk.

Step 17 Rods E-9 and L-7 at position 12.

c.) Continue Shell Warming per QCOP 5600-04.

d.) EOs on shift:

Burke Parrish Foster Richardson Hughes Brewer Decker Schmidt

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 1 Page 1 of 1 Event

Description:

Establish the Drywell Inerting lineup per QCOP 1600-20 Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: Equipment Operators supporting Containment Inerting as necessary SRO Directs and supervises the initiation of Drywell inerting ATC Monitors Panel 901-5 parameters during Startup BOP Verifies AO 1-1699-7 VENT TO RX BLDG is OPEN BOP Opens AO 1-1601-24 VENT TO RX BLDG EXH SYS BOP Opens AO 1-1601-23 DW VENT VLV BOP Opens AO 1-1601-21 DW PRG VLV BOP Opens AO 1-1601-55 N2 PRG VAP VLV BOP Directs the EO to perform step F.11, F12, and F.13 at the Bulk Nitrogen Storage Tank Skid SIMOP ROLE PLAY:

EO as necessary to acknowledge this directive. Wait 3 minutes and then establish N2 Vaporizer flow by opening the 1-8799-85 Cold Valve: irf pc02r open And by providing indication of nitrogen flow: ior aofr187408 100 1:

End of Event 1

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 2, Part 1 Page 1 of 2 Event

Description:

Loss of APRM 4 Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner, fail APRM 4 INOP: ior dihs10700ap4md 3 Key Parameter Response: APRM 4 recorder indicates DOWNSCALE, APRM 4 white DNSCL OR INOP light, 4 White Scram solenoid Group B lights out Expected Annunciator(s):

901-5 D-13 CHANNEL 4-6 APRM HI-HI OR INOP 901-5 B-11 CHANNEL A/B NEUTRON MONITOR (Red) 901-5 D-15 CHANNEL B REACTOR SCRAM 901-5 C-3 ROD OUT BLOCK Automatic Actions: 1/2 Scram, Rod Block ATC Responds to unexpected annunciators and informs the Unit Supervisor ATC Acknowledges annunciator 901-5 D-13, APRM HI-HI OR INOP and reports APRM 4 indicates Downscale or Inop SRO Enters and directs actions of QCOA 0700-03 SRO Directs crew to hold Reactor power constant BOP Verifies APRM 4 indicates INOP in the 901-37 panel SRO Refers to T.S. 3.3.1.1. and TRM 3.3.a and determines that minimum operable channels requirement is met SRO Directs APRM Ch 4 to be bypassed ATC Bypasses APRM 4 per QCOP 0700-04 Position APRM 4 bypass joystick to BYPASS Verify white BYPASS light comes on for APRM 4 Places an EST on APRM bypass joystick for APRM 4 ATC Resets the 1/2 Scram per QCOP 0500-03 ATC Momentarily places the Scram Reset Switch to position GR 2+3 then to position GR 1+4 ATC Verifies annunciator 901-5 D-15 clears ATC Verifies Scram Solenoid Group Channel A and Channel B (white) indicating lights lit ATC Verifies computer points W536 and 537 indicate reset ATC Resets APRM, Rod Block and RPS annunciators ATC/BOP Contacts Instrument Maintenance to troubleshoot APRM 4 SIMOP: Role-Play IM as necessary. A Work Order will be prepared.

Crew May place an EST Tag or an Orange Ring on the APRM joystick SRO May refer to QCAP 0230-19, Equipment Operability End of Event 2, Part 1

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 3 Page 1 of 1 Event

Description:

Raise power using control rods (Notch Withdrawal)

Time Position Applicants Actions or Behavior EVALUATOR NOTE: After Rod L-09 is withdrawn to position 12, the next rod (E-7) will stick at position 08 to initiate Event 4. When the problem with E-7 has been resolved, resume rod withdrawal per this event.

SIMOP ROLE PLAY: Qualified Verifier (QV) as necessary. If the crew does not promptly begin the task, call the control room as the Shift Manager and ask them to begin.

SRO Directly supervises control rod moves and directs the RO to begin the load increase ATC (CONTINUOUS) Monitors reactor parameters ATC Selects an in-sequence control rod ATC On the RWM verifies proper rod selected, its current position and bounds ATC Communicates to the QV. Ready to withdraw Rod __-__from position

__ to position __ using single notch withdrawal.

QV Replies: Rod __-__ is selected. Understand withdrawing __-__ from position __ to position __ using single notch withdrawal.

ATC Replies: That is correct ATC Verifies control rod and moves it to the desired position ATC/BOP Place keeps rod moves in the rod movement book ATC Repeats above steps as necessary BOP Monitors balance of plant parameters End of Event 3

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 4 Page 1 of 1 Event

Description:

Recoverable Stuck Rod / Raise CRD Drive Pressure Key Parameter Response: Control Rod E-7 will not move from position 08 with normal drive water pressure; CRD Drive Pressure indication on 901-5, 1-340-4 Expected Annunciator(s): None Automatic Actions: None ATC Reports CR L-3 will not move.

SRO Directs RO to perform the actions of QCOA 0300-02 ATC Verifies no Rod Block exists ATC Verifies no RWM select block exists ATC Verifies the proper control rod is selected ATC Raises CRD drive water pressure in 50 psig increments by throttling closed on the 1-302-8 valve SIMOP: When CRD drive water pressure is greater than 340 psid, verify Event Trigger 1 goes active to delete malfunction dmf rd02r1827.

ATC Attempts to withdraw Control Rod E-7 ATC Continues normal control rod withdrawal ATC Restores drive water pressure to normal QV/BOP Provides peer check as required BOP Monitors balance of plant parameters End of Event 4

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 2, Part 2 Page 2 of 2 Event

Description:

Loss of APRM 5 Time Position Applicants Actions or Behavior SIMOP: At the direction of the Lead Examiner, insert malfunction: nm08e 0 1: to fail APRM 5 Downscale over a 1 minute period.

Key Parameter Response: APRM 5 recorder indication trending lower Expected Annunciator(s):

901-5 C-6, APRM DOWNSCALE 901-5 C-3, ROD OUT BLOCK 901-5 H-1, OPRM TROUBLE/INOP Automatic Actions: Rod Block ATC Responds to unexpected annunciators and informs the Unit Supervisor ATC Acknowledges annunciator 901-5 C-6, APRM DOWNSCALE and 901-5 C-3, Rod Out Block. and reports APRM 5 indicates trending downscale ATC Confirms APRM 5 indicates DNSCL or INOP at 901-5 SRO Enters and directs actions of QCOA 0700-03 SRO Directs crew to hold Reactor power constant BOP Verifies APRM 5 indicates downscale at the 901-37 panel ATC/BOP Contacts Instrument Maintenance to troubleshoot APRM 5 SIMOP ROLE PLAY: The IM Foreman as necessary. You will have to get some test equipment and get a work package started.

SRO Reviews Tech Specs. Applicable T.S. - 3.3.1.1 for RPS trip functions.

Determines that the minimum number of APRM channels for T.S. is NOT met. TRM Section 3.3.a for Rod Block functions is met.

SRO May direct that a Channel B 1/2 Scram be inserted per QCOP 0500-04.

(12 Hour Action Statement)

ATC When directed, depresses the B RPS Manual Scram Pushbutton ATC Verifies the Scram Solenoid Group Channel B lamps are off ATC May respond to 901-5 H-1, OPRM Trouble/Inop.

BOP May investigate OPRM trouble at the 901-37 panel. If so, finds OPRMs 5 and 8 with trouble lights lit.

SRO May refer to QCAP 0230-19 End of Event 2, Part 2

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 5 Page 1 of 2 Event

Description:

Loss of SJAE Steam Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner, implement the loss of SJAE steam by using the Remote Function to close the steam supply: irf mc15r closed Key Parameter Response: North SJAE Suction Valves close Expected Annunciator(s):901-7 A-14 AIR EJECTOR NORTH SUCTION VALVES CLOSED Automatic Actions: North SJAE Suction Valves close BOP Responds to annunciator 901-7, A-14 and informs the US BOP Verifies North Suction Valves Close BOP Attempts to re-open North Suction Valves by taking the SJAE SUCT VLV switch to OPEN BOP Trips Hydrogen Water Chemistry System BOP Trips HWCS by one of the following:

Touch SHUTDOWN on PLC Screen and CONFIRM

Depress TRIP on HWCS Control Console BOP Verify HWCS tripped:

Amber TRIP indicator light ON

Blue ENABLE READY light OFF

Annunciator B-1, H2 SYSTEM SHUTDOWN active

Hydrogen flow approximately 0 (zero)

BOP Monitor Main Condenser Vacuum and enters QCOA 3300-02 SRO Enters and directs actions of QCOA 3300-02 SRO May set Scram Criteria at 7 inches Hg Condenser backpressure BOP Checks Offgas Rad Levels BOP May check fuse F-2 at 901-7, TB-H EVALUATOR: If necessary, cue candidate that fuse F-2 at 901-7, TB-H is intact (not blown)

Event 5 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No: 5 Page 2 of 2 Event

Description:

Loss of SJAE Steam Time Position Applicants Actions or Behavior BOP Refers to QCOA-5400-04 for loss of pressure to Dilution Steam or SJAE SRO Enters and directs actions of QCOA 5400-04 BOP Dispatches an EO to start Sparge Air to the in-service Off-gas Train SIMOP ROLE PLAY: When dispatched to start Sparge Air to the in-service Off-gas Train, acknowledge this directive.

SRO/BOP Dispatches the Field Supervisor or an EO to investigate the SJAE Primary/Secondary Steam supply SIMOP ROLE PLAY: As the FS/EO dispatched to investigate the SJAE Primary/Secondary Steam supply, wait 2 minutes and then report:

Dilution Steam pressure is normal, 125 psig As found SJAE pressure is 20 psig BOP Directs the EO to adjust SJAE controller to maintain 120 to 135 psig SIMOP ROLE PLAY: As the EO dispatched to adjust SJAE controller, wait 1 minute and then report that:

SJAE pressure cannot be adjusted using the pressure controller BOP When SJAE pressure cannot be adjusted, directs bypassing the in-service SJAE PCV SIMOP ROLE PLAY: As the FS/EO dispatched to the SJAE Controller:

Bypass the SJAE as directed using Remote Function: mrf mc15r open.

Wait 2 minutes and report that bypassing the SJAE PCV has been successful and that 120-135 psig is being controlled manually.

SRO/BOP Re-enter QCAN 901-7, A-14 BOP Re-opens North Suction Valves by taking the SJAE SUCT VLV switch to OPEN BOP Cancels the directive to start Sparge Air to the in-service Off-gas Train SIMOP ROLE PLAY: When the directive to start Sparge Air is cancelled, acknowledge this directive.

ATC Stops control rod withdrawal and monitors reactor parameters End of Event 5

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 6 Page 1 of 5 Event

Description:

Station Blackout Initial Actions Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Evaluator, initiate the Station Blackout using manual Trigger 3: trg! 3 Key Parameter Response: 0 Voltage on 4KV Busses, Transformer 12 Breakers to Busses 11, 12, 13, & 14 indicate OPEN, Loss of lighting in Control Room/Simulator, No output voltage on U1 EDG, 1/2 EDG output breaker open Expected Annunciator(s): (Not a complete list) 901-8 A-7, DIESEL GEN 1 TROUBLE 901-8 C-7, DIESEL GEN 1 FAIL TO START 901-8 E-2, RESERVE TRANS 12 TRIP 901-8 G-2, RESERVE AUX TRANS 12 LOW VOLTAGE 901-8 F-3, 4KV BUS OVERCUR TRIP Automatic Actions: Reactor Scram, Group 1 Isolation, (Note: Faults prevent EDGs from restoring power)

SRO Directs ATC to Perform QCGP 2-3 ATC Places RX MODE switch to SHUTDOWN position ATC Verifies the SDV vent and drain valves are closed ATC Verifies all Control Rods are fully inserted ATC Makes scram report QGA 100 ATC When RPV Water Level lowers to less than 0 inches, notifies the US of the QGA 100 entry SRO Enters and directs QGA 100 actions SRO Directs ATC/BOP to verify 0 inches isolations and auto-starts ATC/BOP Verifies Group 2 Isolation (Containment Auxiliaries)

ATC/BOP Verifies Group 3 Isolation (RWCU)

ATC/BOP Verifies RB vent isolation and SBGT start ATC/BOP Verify Drywell Inerting lineup has isolated ATC Stabilize RPV Pressure less than 1060 psig with ADS valves SRO Directs RPV Water Level be maintained 0 inches to 48 inches with high pressure systems ATC (CONTINUOUS) Monitors and maintains RPV water level and pressure ATC Maintains RPV water level with high pressure systems Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 6 Page 2 of 5 Event

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Station Blackout / Crosstie Operations Time Position Applicants Actions or Behavior BOP Responds to Annunciators and reports the Loss of T-12 and the failure of the U1 EDG to start SRO/BOP Verify applicable actions of QCOA 6100-03, Loss of Offsite Power, have been performed BOP Attempts to start U1 EDG from panel 901-8 BOP Dispatches an operator to attempt to start U1 EDG locally SIMOP ROLE PLAY: The EO dispatched to the U1 EDG; Wait 3 minutes then report that the U1 EDG is cranking but not starting and it has used up most of its starting air. Mechanical Maintenance has been contacted and they are on the way.

BOP Dispatch an operator to investigate the loss of T-12 SIMOP ROLE PLAY: The EO dispatched to T-12; Wait 5 minutes and then report that you cannot determine why T-12 tripped and that you have contacted OAD.

BOP May dispatch an EO to investigate the loss of Bus 13-1 SIMOP ROLE PLAY: The EO dispatched to Bus 13-1. Wait 5 minutes and then report that Bus 13-1 is locked out on an overcurrent trip.

BOP Recognizes the Bus Lockout on Bus 13-1 and informs the US SRO/BOP If Bus 13-1 or Bus 14-1 are not energized and power is available from a non-EDG source on Unit 2, attempt to re-energize busses per QCOP 6500-08, 4KV Bus Crosstie Operation BOP Attempt to crosstie Bus 14-1 to Bus 24-1 as follows:

BOP Take the following Control Switches to PTL:

o U1 EDG to Bus 14-1 GCB o Bus 14-1 & Bus 61 Tie Breaker o Busses 14 and 14-1 Tie GCB o 1B Core Spray Pump o 1C RHR Pump o 1D RHR Pump Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 6 Page 3 of 5 Event

Description:

Station Blackout / Crosstie Operations Time Position Applicants Actions or Behavior BOP Request U2 to close the Bus 24-1 to Bus 14-1 Tie Breaker SIMOP: Role Play as necessary and use the following Remote function to close the tie breaker and then report that it has been closed: irf ed34r close NOTE: This Remote Function is necessary to provide correct indications on Unit 1. However, (Setup) Malfunction ed04k will prevent Bus 14-1 to Bus 24-1 crosstie on Unit 1.

BOP Place Synch Switch to ON for Bus 14-1 and Bus 24-1 Tie Breaker BOP Attempt to close Bus 14-1 and Bus 24-1 Tie Breaker and recognize the failure BOP Inform the Unit supervisor of the Bus 14-1 failure SRO/BOP Evaluate status. If Unit is Blacked Out, exit QCOA 6100-03 and perform QCOA 6100-04 Station Blackout.

SRO Direct starting and loading of the SBO Diesel per the Hard Card to Bus 14-1 Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 6 Page 4 of 5 Event

Description:

Station Blackout / SBO Startup to Bus 14-1 Time Position Applicants Actions or Behavior BOP When directed, energizes Bus 14-1 from the SBO DG per QCOP 6620-14 Hard Card BOP Places or verifies the following control switches PTL:

o U1 Diesel Gen to Bus 14-1 GCB o Busses 14-1 and 24-1 Tie GCB o Busses 14 and 14-1 Tie GCB o Bus 13-1 & Bus 61 Tie Breaker o 1B Core Spray Pump o 1C RHR Pump o 1D RHR Pump BOP Place the SBO DG 1 Mode Switch in SBO mode BOP Momentarily place SBO DG 1 C/S to START BOP Verify Voltage 3900-4580, Freq 58.8-61.2, RPM 900 BOP Close the DG BKR on the DCS screen BOP Close the Bus 14-1 & Bus 61 Tie Breaker BOP Close Bus 14-1 Feed from the DCS Screen BOP Verify Busses 14-1 and 19 are energized BOP Remove ECCS pumps from PTL as directed by the Unit Supervisor, allowing 5 seconds between starts BOP Verify proper DCS Panel indications for SBO operation SRO May direct the BOP to Backfeed Bus 14 from Bus 14-1 BOP If directed to backfeed Bus 14:

BOP Place 1B Service Water Pump control switch in PTL BOP Place 1C & 1D Condensate Pump control switches in PTL BOP Place SYNCHROSCOPE switch for BUSSES 14 AND 14-1 TIE GCB to ON BOP Close BUSSES 14 AND 14-1 TIE GCB BOP Verifies BUS 14 is energized BOP Place SYNCHROSCOPE switch for BUSSES 14 AND 14-1 TIE GCB to OFF Event 6 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 6 Page 5 of 5 Event

Description:

Station Blackout / Re-energizing Bus 14 and 480 V Busses Time Position Applicants Actions or Behavior SRO Directs the BOP to crosstie Busses 18 and 19 per the Hard Card BOP When directed, crossties Busses 18 and 19 per the Hard Card BOP Verifies Bus 19 is energized BOP Opens Bus 13-1 to XFMR 18 GCB BOP Closes Busses 18 and 19 TIE BKR at Bus 18 BOP Closes Busses 18 and 19 TIE BKR at Bus 19 BOP Verifies both Busses 18 and 19 are energized SIMOP: If RPS restoration is requested, Role Play as necessary. Wait 3 minutes and then use the following commands to restore RPS:

A RPS: irf 02r mg_set and irf r29r reset B RPS: irf 03r mg_set and irf r28r reset Then contact the Control Room to report completion of RPS restoration.

BOP May direct the EO to re-energize RPS A and RPS B Busses per QCOP 7000-01 SRO May direct the BOP to re-energize Bus 16 and/or Bus 17 per the Hard Card BOP When directed, re-energizes Bus 16 per the Hard Card BOP Closes the Bus 14 to XFMR 16 GCB BOP When directed, re-energizes Bus 17 per the Hard Card BOP Closes the Bus 14 to XFMR 17 GCB SRO May direct the BOP to re-energize Bus 15 from Bus 16 or Bus 17 per the Hard Card BOP When directed, re-energizes Bus 15 per the Hard Card BOP Verifies open transformer main feed to Bus 15 BOP Verifies open Bus 15 to Bus 17 and Bus 15 to Bus 16 crosstie breakers BOP Closes Bus 16 or Bus 17 to Bus 15 crosstie breaker End of Event 6

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 7 Page 1 of 5 Event

Description:

LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior SIMOP: Verify the LOCA malfunction goes active 3 minutes after the SBO event:

imf rr10a 0.13 7:30 (Recirc Suction Line LOCA at 0.13% severity on a 7.5 minute ramp)

Key Parameter Response: Rising Drywell Pressure Expected Annunciator(s): 901-03B A-16, PRI CNMT HIGH PRESSURE Automatic Actions: None due to the SBO and system malfunctions BOP Responds to annunciator 901-3, A-16, PRI CNMT HIGH PRESSURE SRO Enters and directs QCOA 0201-01 SRO/ATC Notifies Radiation Protection of elevated containment pressure SRO May make a PA announcement to evacuate Reactor Building QGA 200 ATC/BOP Reports Drywell pressure above 2.5 psig.

SRO Re-enters QGA 100 and enters QGA 200 on high drywell pressure SRO Directs BOP/ATC to verify 2.5 psig isolations/actuations BOP/ATC Verifies 2.5 psig isolations/actuations ATC/BOP (For systems that have power) Core Spray, HPCI and RHR running Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 7 Page 2 of 5 Event

Description:

LOCA in the Drywell / QGA 100 actions Time Position Applicants Actions or Behavior SRO Directs QGA 100 RPV Control actions CT1 SRO Directs ATC to maintain RPV water level with high pressure systems CT1 ATC Maintains RPV water level with high pressure systems ATC/BOP Recognizes and reports to US that the HPCI Initiation has failed (Aux Oil Pump lockout)

ATC/BOP Dispatches an EO to troubleshoot HPCI and/or the Aux Oil Pump breaker SIMOP: If requested to troubleshoot HPCI Aux Oil Pump breaker, Role Play as necessary.

Wait until the SBO Diesel is providing power and at least 2 minutes, then delete malfunction dmf hp08 and report that the Aux Oil Pump Breaker is reset.

ATC When Aux Oil Pump is restored, restarts HPCI ATC If necessary, depresses the HPCI TURB TRIP RESET pushbutton ATC Depresses the HPCI MANUAL INITIATION pushbutton and/or verifies HPCI Auto Start ATC Adjust HPCI Flow Controller in Manual or AUTO as necessary ATC May place HPCI in Trip-Latch if HPCI makeup is unnecessary ATC Starts RCIC per QCOP 1300-02 ATC Depresses the RCIC MANUAL INITIATION pushbutton for at least 30 seconds and recognizes the failure to start ATC Responds to Annunciator 901-4 G-15 ATC Dispatches an EO to investigate the Trip Throttle Valve failure SIMOP ROLE PLAY: As the EO dispatched to RCIC: Wait 2 minutes and then report that the RCIC Trip Throttle overspeed mechanism will not reset.

SRO Directs ATC to stabilize RPV Pressure with ADS valves (following LOOP event)

ATC Stabilizes RPV Pressure with ADS valves as directed SRO If RPV water level cannot be maintained greater than -59 inches directs ADS inhibited BOP/ATC When directed, inhibits ADS Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 7 Page 3 of 5 Event

Description:

LOCA in the Drywell / QGA 100 actions Time Position Applicants Actions or Behavior ATC/BOP May start SSMP per QCOP 2900-02 Switches power supply to Bus 24-1 Verify CLOSED the RESERVE FEED CONTROL from Bus 24-1 to Bus 31, GCB 151-2425 OPEN the NORMAL FEED CONTROL from Bus 14-1 to Bus 31, ACB 151-3101 CLOSE the RESERVE FEED CONTROL from Bus 24-1 to Bus 31, ACB 151-3102 Verify Pump suction pressure is available OPEN MOV 1/2-2901-7, Throttled Test Valve Start the SSMP Verify increasing Pump Discharge Pressure Place the FCV in AUTO Slowly increase flow controller setpoint to 400 gpm OPEN MOV 1-2901-8, U1 Reactor Supply Valve CLOSE MOV 1/2-2901-7, Throttled Test Valve Directs and Equipment Operator to close the Service Water to SSMP Room Cooler Bypass, 1/2-2999-9 SIMOP ROLE PLAY: As Equipment Operator dispatched to close 1/2-2999-9. After 5 minutes, report that 1/2-2999-9 is CLOSED.

SRO May direct use of alternate injection systems ATC May restart the B CRD Pump per QCAN 901-5 B-2 (After power is restored)

ATC Close the Pump Discharge Valve MO 1-301-2A/B ATC Start the available CRD Pump ATC Throttle open the Pump Discharge Valve MO 1-301-2A/B ATC May start available SBLC pump Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 7 Page 4 of 5 Event

Description:

LOCA in the Drywell / QGA 200 actions Time Position Applicants Actions or Behavior EVALUATOR NOTE: The QGA 200 actions will most likely be taken after power has been restored with the SBO Diesel.

BOP (Continuous) Monitors and reports Primary Containment Parameters and trends SRO/BOP May dispatch an EO to Aux Electric Room to 2201-5 rack to monitor Reactor water level and Drywell Pressure during the Station Blackout SRO Directs the actions of QGA 200 PRIMARY CONTAINMENT CONTROL SRO Verifies Torus Water level less than 27 ft.

SRO May direct BOP/ATC to monitor SBO loading.

BOP/ATC Monitor SBO loading as directed SRO Directs BOP to initiate Torus Sprays BOP Uses QCOP 1000-30 to Start RHR BOP Takes the available RHR Pumps out of PTL BOP Places the Containment Cooling Permissive Switch 17 to ON for the B RHR Loop BOP Places the RHR SW Start Permissive Switch 19 to MANUAL OVERRIDE for the B RHR Loop BOP Starts Torus Spray BOP Opens Torus Test or Spray Valve, MO 1-1001-34B BOP Opens Torus Spray Shutoff Valve, MO 1-1001-37B BOP Throttles Torus H2O Test Valve MO 1-1001-36B to establish RHR Discharge Pressure of 100-250 psig BOP (If power is restored) Uses QCOP 1000-30 to start RHR Service Water BOP Opens The available RHR HX SW Discharge Valve MO 1-1001-5B to approximately 40%

BOP Starts 1C/D RHR SW Pump(s)

BOP Adjusts MO 1-1001-5B to maintain RHR SW Pressure 15-20 psig higher than RHR and less than 3600 gpm per pump BOP Throttles RHR HX Bypass Valve MO 1-1001-16B as necessary Event 7 Continued

Quad Cities 2012 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities NRC Scenario No.: 1 Event No.: 7 Page 5 of 5 Event

Description:

LOCA in the Drywell / QGA 200 actions Time Position Applicants Actions or Behavior SRO Verifies Torus level less than 17 ft. and inside DW Spray Initiation Limit curve SRO Verifies Recirc pumps and DW coolers tripped CT2 SRO Directs BOP to initiate DW Sprays CT2 BOP Initiates Drywell Sprays Opens Outboard Spray Isolation, MO 1-1001-23B Opens Inboard Spray Isolation, MO 1-1001-26B Opens Torus Test or Spray Valve, MO 1-1001-34B Adjusts Torus H2O Test Valve MO 1-1001-36B to maintain RHR Discharge Pressure 100-250 psig and RHR SW Pressure 15-20 psig higher than RHR pressure SRO May Direct Torus Cooling initiation BOP Starts Torus Cooling as directed Opens Torus Test or Spray Valve, MO 1-1001-34B Opens Torus H2O Test Valve, MO 1-1001-36B Adjusts Torus H2O Test Valve MO 1-1001-36B to maintain RHR SW Pressure 15-20 psig higher than RHR pressure and RHR pressure between 100 and 250 psig Closes MO 1-1001-16B BOP (Continuous) Monitors Torus Water level and, if less than -2 inches, notifies US of QGA entry SRO If Torus Water Level lowers to less than -2 inches, re-enters QGA 200 End of Event 7 SIMOP: When Drywell sprays have been initiated and RPV Water level has been restored or as directed by the Lead Evaluator, place the simulator in FREEZE.

(Final)

ML12083A184

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