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2011 Quad Cities Nuclear Power Station Initial License Examination Proposed Simulator Scenarios
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Site:	Quad Cities
Issue date:	10/05/2012
From:	Moore C; Operations Branch III
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Quad Cities 2011 NRC EXAM Scenario 1 Exelon Nuclear 2011 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 1 Revision Number: 00 Date: _________

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2011 NRC Scenario 1 Op-Test No.: ILT 09-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 9% power with a startup in progress. The Mode Switch is in RUN.

APRM 4 is out of service and bypassed for repair.

1C RFP is out of service.

Turnover: Continue the Reactor startup per QCGP 1-1.

Event Malf. No. Event Event No. Type* Description 1 None BOP Establish the Drywell Inerting lineup per QCOP N 1600-20 2 None ATC Withdraw control rods to achieve 2-4 Turbine R Bypass Valves open 3 RD02R2627 ATC Stuck rod / raise CRD Drive Pressure C

4 NM08 ATC APRM 5 fails inoperable, but RPS fails to trip TS RP02B&D I 5 RC11 BOP RCIC Leak w/o auto isolation. Crew performs RC13 C QCOA 0201 and QGA 300 to manually isolate the leak. TS 6 RR11A Crew LOCA, restore RPV Water level and respond to M elevated containment pressure and temperature 7 FW04B Crew Loss Feedwater (Degradation of 1B RFP and loss of ED03A M 1A RFP due to loss of Bus 11). Use HPCI to restore and maintain RPV water level.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 5 BOP Normal: E1 Malfunction(s) after EOP (1-2): E7 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E3, 4, 5 BOP I/C (4 per set): E5 Major Transient(s) /E-Plan entry (1-2): E6 ATC I/C (4 per set): E3& 4 EOPs (1-2): QGA 100 / 200 and 300 SRO-I I/C (4 per set inc 2 as ATC): E3, 4, 5 EOP Contingencies (0-2): None SRO Tech Spec (2 per set): E4& 5 Critical Tasks (2-3): 3 ALL Major Transients (2 per set) E6 Quad Cities 2011 NRC EXAM Scenario 1

SUMMARY

Initial Conditions:

o The plant is operating at 9% power just after the Mode Switch was taken to RUN.

o APRM 4 is out of service and bypassed for repair.

o The 1C Feed Pump is Out-of Service.

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

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

Event 3: During rod withdrawal, one rod will not move from position 00. When the ATC raises CRD drive water pressure, the rod can be withdrawn normally. Drive water pressure should then be returned to normal.

Event 4: APRM 5 will fail INOPERABLE but a 1/2 Scram will not occur due to a problem in the APRM Trip Unit. The ATC must manually insert a B RPS 1/2 Scram because it is an Automatic Action that failed to occur. 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.

Event 5: A steam leak in the RCIC Room results in RCIC Steam Line high DP and High area Temperature alarms, but RCIC fails to isolate as designed. A report from the Reactor Building confirms a steam leak. The BOP will manually isolate the RCIC Steam Lines and the Crew will perform the QCOA 0201-05, Primary System Leaks (Slow Leaks) Outside Primary Containment, and QGA 300. The SRO will address Technical Specifications for inoperable RCIC and inoperable PCIV valves/instrumentation.

Event 6: A LOCA inside the Drywell results in a reactor scram and entry into QGA 100 and 200. The crew restores RPV Water Level and controls Drywell Pressure and Temperature with Containment Sprays.

Event 7: A loss of Bus 11 deenergizes the 1A RFP. The 1B RFP degrades and cannot maintain RPV Level. Manual initiation of HPCI is necessary for high-pressure injection to restore RPV water Level.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical Task #1: Given a reactor plant with a reactor building area radiation alarm or temperature alarm, isolate all discharges into the area.

Critical Task #2: Given a shutdown reactor with a LOCA in progress, restore and maintain RPV water level with available high pressure systems IAW with QGA 100.

Critical task #3: 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)

Quad Cities 2011 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-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 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-0001-P40 Given a reactor plant with a reactor building area radiation alarm, temperature alarm, differential pressure at or above 0 inches, or area water level above 1 inch, attempt to isolate all discharges into an area except systems needed for fire fighting or other QGA actions in accordance with QCOA 201-5 and QGA 300.

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-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-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.

Quad Cities 2011 NRC EXAM Scenario 1 Simulator Setup:

1. Reset to IC-14 (Approximately 9% power).

2. Go to RUN.

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

a. Place all IRM/APRM Recorders to APRM.

b. Place all IRM/RBM Recorders to RBM.

c. Withdraw IRM detectors.

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

4. Mark up the Control Rod Move Sheet to reflect all rods withdrawn up to Step 10, Rod J-9 at position 12.

5. Bypass APRM 4 and hang an Equipment Status Tag; APRM 4 is inoperable.

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

2011 NRC Scenario 1.cae)

6. Insert Commands for setup:

imf rd02r2627 0 (Control Rod G-7 stuck at position 0)

trgset 3 rdpdrivedelta > 340 (Set trigger 1 as CRD drive Pressure > 340#)

trg 3 dmf rd02r2627 (Delete stuck rod on Trigger 1)

ior dihs13201rfpc1 ptl (Override C RFP from Bus 11 in PTL)

ior dihs13201rfpc2 ptl (Override C RFP from Bus 12 in PTL)

imf rp02b (Auto Scram Failure on RPS Channel B1)

imf rp02d (Auto Scram Failure on RPS Channel B2)

imf rc13 (RCIC Group 4 failure to auto isolate)

trgset 7 pcpdwg .ge. 2.5 (Set Trigger 7 as Drywell Pressure > 2.5 psig)

imf fw04b(7) 90 5: (On Trigger 7, 1B RFP degrades to 90% severity on a 5 min ramp)

imf ed03a(7 2:) (On Trigger 7, Loss of Bus 11 with a 2 minute delay)

imf hp11 (HPCI failure to Auto Initiate)

imf mc08 0.3 (Main Condenser air in-leakage at 0.3% severity)

irf pc02r close (Stops flow from N2 Vaporizer until Inerting lineup is established)

ior dihs15708a trip (1A DW/ Torus Purge Fan handswitch in trip/off)

irf hv01r ro (Fail open damper on 1A DW/ Torus Purge Fan)

trgset 29 zdihs10590300(1) .eq. 1 (Set Trigger 29 as Mode Switch to Shutdown)

trgset 30 zdihs10590300(1) .eq. 1 (Set Trigger 30 as Mode Switch to Shutdown)

trg 29 dmf rp02b (Deletes B RPS Auto Scram failure malfunction on Trigger 29)

trg 30 dmf rp02d (Deletes B RPS Auto Scram failure malfunction on Trigger 30)

Quad Cities 2011 NRC EXAM Scenario 1

7. Verify the following commands for scenario performance:

mrf pc02r open (Initiate flow from the N2 Vaporizer when directed)

ior aofr187408 100 1: (Overrides Nitrogen Flow recorder to full scale over 1 minute)

ior dihs10700ap5md 3 (APRM 5 Mode switch overridden to Zero, position 3 )

imf rc11 50 (Steam Leak in RCIC room at 50% severity)

irf sw10r run (Start the U-1 EDG CWP as requested)

imf rc10a 0 (Bind RCIC Steam Supply Valve 1-1301-16 closed, prevents auto re-open)

imf rc10b 0 (Bind RCIC Steam Supply Valve 1-1301-17 closed, prevents auto re-open)

ior lohs11301161 off (On 901-4, override 1-1301-16 Green Light Off as requested)

ior loli11301161 off (On 901-3, override 1-1301-16 Green Light Off as requested)

ior lohs11301171 off (On 901-4, override 1-1301-17 Green Light Off as requested)

ior loli11301171 off (On 901-3, override 1-1301-17 Green Light Off as requested)

imf rr11a 0.5 20: (Recirc Suction Line break in the Drywell to 0.5% severity over 20 min)

8. 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.

CLOSE

AO 1-1601-21 DW PRG VLV

AO 1-1601-22 DW OR TORUS PRG VLV

AO 1-1601-23 DW VENT VLV

AO 1-1601-24 VENT TO RX BLDG EXH SYS

Manually open PIC 1-1640-11 Containment Pressure.

Verify 1B Drywell/Torus Purge Fan is OFF.

Take the 1A Drywell/Torus Purge Fan Handswitch to OFF.

Hang an Equipment Status Tag on the 1A Drywell/Torus Purge Fan.

9. Take the following components Out of Service:

1C Reactor Feed Pump, (Bus 11 and Bus 12 in PTL with Out of Service tags)

10. Provide a Reactor Startup REMA.

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

QCOP 1600-20, signed off up to step F.9.

QCGP 1-1, signed off up to step F.6.kk.

QCOP 5600-04, signed off up to Step F.4.d.

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

13. Ensure procedures are erased and put away including QGAs.

14. Advance recorders.

15. Clean marked up meter/recorder faces and hard cards.

16. Remove any flags placed by the previous crew.

17. Clear the Digital Feedwater and Recirc OWS alarms.

Quad Cities 2011 NRC EXAM Scenario 1 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-16, PRI CNMT HIGH PRESSURE, Rev. 12 o 901-3 H-2, AREA HI TEMP STEAM LEAK DETECTION, Rev. 6 o 901-4 A-15 RCIC STEAM LINE HI DP, Rev. 9 o 901-5 B-11 CHANNEL A/B NEUTRON MONITOR, Rev. 10 o 901-5 C-3 ROD OUT BLOCK, Rev. 11 o 901-5 C-6 APRM DOWNSCALE, Rev. 5 o 901-5 D-13 CHANNEL 4-6 APRM HI HI OR INOP, Rev. 9 o 901-8 A-1 4KV MAIN FEED BREAKER TRIP, Rev. 4 o 901-8 E-1 4KV BUS 11 & 12 LOW VOLTAGE, Rev. 4 o 901-8 F-3 4KV BUS OVRCUR TRIP, Rev. 5 QCGP 1-1, Normal Unit Startup, Rev. 84 QCGP 4-1, Control Rod Movements and Control Rod Sequence, Rev. 36 QCGP 2-3, Reactor Scram, Rev. 72 QGA 100, RPV Control, Rev. 9 QGA 200, Primary Containment Control, Rev. 9 QGA 300, Secondary Containment Control, Rev. 11 QCOA 0201-01, Increasing Drywell Pressure, Rev. 23 QCOA 0201-05, Primary System Leaks (Slow Leaks) Outside Primary Containment, Rev. 8 QCOP 1600-20, Nitrogen Inerting of Primary Containment Using the Vaporizer(s) and Reactor Building Ventilation System. Rev. 28 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 QCOP 1000-30, Post-Accident RHR Operation, Rev. 26 QCOP 2300-06, HPCI System Manual Startup, Rev. 29 QCOP 5600-04, Main Turbine Warming, Rev. 19 Quad Cities 2011 NRC EXAM Scenario 1 CREW TURNOVER

1. Plant Conditions:

a.) Unit 1 is at 9% 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.) APRM 4 is inoperable and bypassed for repair.

b.) 1C Reactor Feed Pump is out of service due to a pump casing leak.

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.

Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 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 at the Bulk Nitrogen Storage Tank Skid SIMOP ROLE PLAY:

EO as necessary to acknowledge this directive. Wait 5 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 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 2 Page 1 of 1 Event

Description:

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

Time Position Applicants Actions or Behavior SIMOP: If the crew does not promptly begin the task, call the control room as the Shift Manager and ask them to begin.

Lead Examiner Role Play: Qualified Nuclear Engineer (QNE) as necessary SRO Directly supervises control rod moves and directs the RO to raise power per the REMA BOP Monitors balance of plant parameters ATC (CONTINUOUS) Monitors reactor parameters ATC Begins power increase with control rods ATC Selects an in-sequence control rod EVALUATOR NOTE: Per QCGP 4-1 D.3, continuous rod withdrawal is approved.

On the RWM verifies proper rod selected, its current position and ATC bounds Communicates to the QV Control Rod XX-YY is selected.

ATC Withdrawing from position 12 to position 48. (continuously or by notching)

Replies, Understand Control Rod XX-YY is selected. You are moving QV it from position 12 to position 48. (Continuously or by 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 Repeats above steps as necessary to achieve 2-4 Turbine Bypass ATC Valves open EVALUATOR NOTE: When the second rod will not move from position 00 with normal drive pressure, perform Event 3 and then return to this event.

BOP Monitors balance of plant parameters and adjust EHC Load Set EVALUATOR NOTE: When the Lead Evaluator is satisfied with the reactivity manipulation, proceed to Event 4.

End of Event 2 Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 3 Page 1 of 1 Event

Description:

Stuck rod / raise CRD Drive Pressure Time Position Applicants Actions or Behavior Key Parameter Response: Control Rod G-7 will not move from position 00; CRD Drive Pressure indication on 901-5, 1-340-4 Expected Annunciator(s): None Automatic Actions: None ATC Reports CR G-7 will not move.

SRO Directs RO to perform the actions of QCOA 0300-02 ATC Verifies no CR block exists ATC Verifies no RWM select block exists ATC Verifies the proper control rod is selected Raises CRD drive water pressure in 50 psig increments by throttling ATC closed on the 1-302-8 valve SIMOP: When CRD drive water pressure is >340 psid , verify Event Trigger 3 goes active to delete malfunction dmf rd02r2627.

ATC Attempts to withdraw CR G-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 3 Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 4 Page 1 of 1 Event

Description:

APRM 5 becomes inoperable Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, fail APRM 5 INOPERABLE by overriding the mode switch to the Zero (3) position: ior dihs10700ap5md 3 Key Parameter Response: APRM 5 recorder and meter indicate DN SCL / INOP lights lit on 901-5 and 37 Expected Annunciator(s):

901-5 C-3 ROD OUT BLOCK 901-5 C-6 APRM DOWNSCALE 901-5 H-1 OPRM TROUBLE/INOP 901-5 D-13 CHANNEL 4-6 APRM HI HI OR INOP Automatic Actions: Rod Block (1/2 Scram on RPS Channel B disabled)

Acknowledges annunciators and reports APRM 5 indicates downscale ATC

/inoperable ATC Manually inserts a 1/2 scram in RPS B Refers to QCOA 0700-03 and directs crew to hold Reactor power SRO constant BOP May verify APRM 6 indicates Inop in the 901-37 panel SRO Enters TS 3.3.1.1 Condition A, for 2 APRMs inoperable on RPS Ch B.

Verifies minimum number of APRMs (4) per TRM 3.3.a are operable

` CREW Contacts Instrument Maintenance to troubleshoot APRM 5 SIMOP ROLE PLAY: Instrument Maintenance as necessary: They report a faulty circuit card.

SIMOP ROLE PLAY: Plant support personnel as necessary End of Event 4 Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 5 Page 1 of 2 Event

Description:

RCIC Leak without auto isolation Time Position Applicants Actions or Behavior SIMOP: When the BOP is near Panel 901-4 and when directed by the Lead Examiner Insert Malfunction: imf rc11 50 Key Parameter Response: RCIC Room Area Temperatures 901-21 Expected Annunciator(s):

901-4 A-15 RCIC STEAM LINE HI DP (in approximately 20 seconds) 901-3 H-2, AREA HI TEMP STEAM LEAK DETECTION (in approximately 25 seconds) 901-3 C3, CORE SPRAY PUMP AREA HI TEMP (in approximately 35 seconds)

Automatic Actions: None (Group 5 auto isolation is disabled)

BOP Responds to annunciator and informs the US BOP Verifies Automatic action occurred / recognizes that the Group V isolation failed to occur CT1 BOP Isolates RCIC by closing the 1-1301-16 and 1-1301-17 valves SRO Directs BOP to perform the actions of the QCAN BOP Checks Panel 901-21 and determines leak in RCIC SRO Enters QGA 300 CT1 SRO Directs/verifies closing of RCIC 1-1301-16 and 1-1301-17 valves SRO Directs ATC/BOP to dispatch an NLO to start the U1 EDG CWP and check basement water levels SIMOP: When directed, wait until the RCIC steam lines have been isolated, then start the U1 EDG CWP; irf sw10r run and then report that the pump is running. Also report no water in Reactor Bldg Basement.

SIMOP ROLE-PLAY: If dispatched to investigate, wait 2 minute and then report that there is a steam leak in the RCIC Room near the Turbine. The Room has been evacuated.

Event 5 Continued Quad Cities 2011 NRC EXAM Scenario 1 Quad Cities Scenario No.: 1 Event No.: 5 Page 2 of 2 Event

Description:

RCIC Leak without auto isolation Time Position Applicants Actions or Behavior SRO Directs BOP to take the actions of QCOA 0201-05 BOP Evacuates the reactor building basement and notifies RP BOP Trips hydrogen water chemistry system SIMOP: When the RCIC steam lines have been isolated, then insert the following malfunctions to bind the 16 & 17 valves closed: imf rc10a 0 and imf rc10b 0 SIMOP: If directed to deenergize 16 & 17 valves, wait 3 minutes and then insert the following overrides: ior lohs11301161 off and ior loil11301161 off; then ior lohs11301171 off and ior loil11301171 off Then report that the RCIC 16 and 17 valves are deenergized.

BOP Verifies RCIC room temperature is lowering SRO Refers to TS 3.5.3 Condition A, identifies RCIC inoperable Refers to TS 3.6.1.3 Condition B, identifies 2 PCIVs inoperable Refers to TS 3.3.6.1 Condition B, identifies Auto Isolation capability was not operable.

ATC Provides requested peer checks and monitors Panel 901-5 parameters End of Event 5 Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 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 a large line break at 0.5% severity on a 20 minute ramp: imf rr11a 0.5 20:

Key Parameter Response: Rising Drywell Pressure Expected Annunciator(s):

901-3 A-14, TORUS HIGH/LOW LEVEL (Resetting) 901-3 A-13, DW LOW PRESS CNMT SPRAY INHIBITED (Resetting) 901-3 A-16, PRI CNMT HIGH PRESSURE Automatic Actions: Reactor Scram (failed). Initiation of SBGT, HPCI, LPCI, Core Spray, Emergency Diesel Generators. Isolation of Group 2 valves, Reactor Bldg and Control room Ventilation.

BOP Responds to the resetting of annunciators 901-3 A-14 TORUS HIGH/LOW LEVEL and 901-3 A-13 DW LOW PRESS CNMT SPRAY INHIBITED BOP Identifies rising Drywell Pressure (Containment air purge in progress)

CREW Responds to 901-3 A-16, PRI CNMT HI PRESS SRO Enters and directs actions of QCOA 0201-01 CREW Monitors and reports Drywell Pressure and trend CREW Investigates the cause SRO May set scram criteria of 2.0 psig DW pressure ATC/BOP Monitors drywell pressure for scram criteria CREW Notifies Radiation Protection of elevated drywell pressure CREW Makes announcement to evacuate the Reactor Building ATC/BOP Monitors leak rate BOP May start the seventh DW cooler SRO May briefs crew on expected auto actions at 2.5 psig DW pressure ATC When directed, manually scrams the reactor Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 6 Page 2 of 5 Event

Description:

LOCA in the Drywell, QCGP 2-3 actions Time Position Applicants Actions or Behavior SRO May direct a manual scram prior to exceeding 2.5 psig in Drywell ATC (If directed) Depresses both RX SCRAM CH A and CH B Pushbuttons 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 including entry into QGA 100 on RPV Water Level

< 0 inches ATC Attempts to maintain RPV level 0 to +48 with preferred 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 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 Bus 11 trips 2 minutes after the Drywell exceeds 2.5 psig.

ATC Verifies Main Turbine trips, all SVs, CVs, ISVs, IVs and extraction steam check valves close ATC Verifies Main Generator Output Breakers tripped after 30 seconds and places control switches in PTL Verifies Main Generator Field and Exciter Field Breakers (alarm 901-8 ATC 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 necessary, the EO dispatched to reset 86 Relays Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 6 Page 3 of 5 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior SRO Enters QGA 100, RPV Control on 2.5 psig DW pressure SRO Enters QGA 200, Primary Containment Control, on 2.5 psig DW pressure BOP Monitors and reports Primary Containment parameters and trends ATC/BOP Reports Core Spray and RHR auto started BOP Recognizes and reports that HPCI did not auto start 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 Verifies Bus 18 and 19 voltage >450 volts Takes the U1 DIV I DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position Takes the U1 DIV II DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position Checks Drywell temperature is less than 260 °F Starts 1A and 1B RBCCW pump Starts drywell coolers one at a time Starts Drywell Booster Fan Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 6 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 <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 > RHR Pressure

RHR Service Water flow <3600 gpm/pump

RHR Pressure 100-250 psig BOP Prepares RHR for Operation Verifies RHR Pumps running Places LOOP A/B CONTAINMENT COOLING PERMISSIVE Switch 17 to ON Places LOOP A/B RHR SW START PERMISSIVE Switch 19 to MANUAL OVERRIDE BOP Starts RHR Service Water Opens MO 1-1001-5A/B to approximately 40%

Starts A/B RHR SW Pump Throttles MO 1-1001-5A/B as necessary Throttles MO 1-1001-16A/B as necessary BOP As directed, initiates Torus Sprays per QCOP 1000-30 Opens MO 1-1001-34A/B Opens MO 1-1001-37A/B BOP Opens/Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure SRO Directs BOP to secure Torus Sprays before Torus Pressure drops to 0 psig Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 6 Page 5 of 5 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior BOP Reports Torus pressure >5 psig.

SRO Verifies Torus level <17 ft.

SRO Verifies inside DW Spray Limit Curve SRO Verifies Recirc pumps and DW Coolers are tripped CT3 SRO Directs BOP to start DW Sprays CT3 BOP As directed, initiates Drywell Sprays per QCOP 1000-30 Opens MO 1-1001-23A/B Opens MO 1-1001-26A/B Opens MO 1-1001-34A/B Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure SRO Directs BOP to secure DW Sprays before DW Pressure drops to 0 psig BOP Before DW Pressure drops to 0 psig, secures DW Sprays Closes MO 1-1001-23A/B Closes MO 1-1001-26A/B Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure SRO If Torus water temperature cannot be held <95°F, directs start of all available Torus Cooling BOP As directed, initiates Torus Cooling per QCOP 1000-30 Opens MO 1-1001-34A/B Opens/Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure End of Event 6 Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 1 of 2 Event

Description:

Loss of Feedwater Time Position Applicants Actions or Behavior SIMOP: When Drywell pressure exceeds 2.5 psig, verify the following malfunctions begin to time down/ramp in: imf ed03a(5 2:) and imf fw04b(5) 90 5:

Key Parameter Response: Low Voltage on Bus 11, RPV Water level lowering Expected Annunciator(s):

901-8 A-1 4KV MAIN FEED BREAKER TRIP 901-8 E-1 4KV BUS 11 & 12 LOW VOLTAGE 901-8 F-3 4KV BUS OVRCUR TRIP Automatic Actions: Bus 11 deenergizes BOP Responds to annunciators and reports the loss of Bus 11 to the Unit Supervisor BOP Dispatch an operator to determine the cause of the trip SIMOP ROLE PLAY: As the operator dispatched to investigate Bus 11: wait 3 minutes and then report that Bus 11 has an overcurrent condition and that EMD has been contacted.

EVALUATOR NOTE: QCOA 6500-01 for loss of Bus 11 is applicable, but there are no further operator actions to be taken.

SRO Directs RPV level be maintained 0 to +48 with preferred injection systems ATC Attempts to maintain RPV level 0 to +48 with preferred injection systems ATC/SRO Recognize that the 1B RFP is not maintaining RPV Water Level ATC/BOP May dispatch an operator to investigate 1B RFP SIMOP ROLE PLAY: If dispatched to investigate the 1B RFP, wait 2 minutes and then report that the pump is very noisy and suggest that it be secured.

CT2 ATC/BOP Manually initiate HPCI for injection into the RPV per QCOP 2300-06 Verify REMOTE HPCI TURB TRIP is not Trip-Latched Depresses and holds HPCI MANUAL INITIATION pushbutton for at leas 30 seconds ATC/BOP Adjusts HPCI Flow as necessary to Maintain RPV Water level Event 7 Continued Quad Cities 2011 NRC EXAM Scenario 1 Quad Cities Scenario No.: 1 Event No.: 7 Page 2 of 2 Event

Description:

Loss of Feedwater Time Position Applicants Actions or Behavior ATC/BOP May start SSMP per QCOP 2900-02 Verify Pump suction pressure is available OPEN MOV 1-2901-7, 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 1-2901-7, 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.

SIMOP: When RPV Water Level is being Maintained and at the discretion of the Lead Examiner, Place the simulator in FREEZE.

Quad Cities 2011 NRC EXAM Scenario 2 Exelon Nuclear 2011 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 2 Revision Number: 00 Date: _________

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2011 NRC Scenario 2 Op-Test No.: ILT 09-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 100% power.

HPCI maintenance complete. Working to restore and test, then exit 14-Day LCO and ATR.

Drywell Spray Valve 23A is inoperable, Day 2 of a 7-Day LCO.

Turnover: Restore HPCI to its standby lineup. Post Maintenance Surveillance later in shift.

Event Malf. No. Event Event No. Type* Description 1 None BOP Re-pressurize HPCI Steam Lines and restore HPCI N to standby lineup 2 ANO9121G12 SRO Toxic Gas Monitor Inoperablity. TS TS (Optional for Surrogate) 3 AIFC103401B ATC CRD FCV Fails High causing a control rod to drift IN.

RD03R C 4 AIPIC1874011 BOP Drywell N2 controller failure C

5 None SRO Torus Water Level PAM Instrument Inoperability TS TS (Optional for Surrogate) 6 DIHS156041A BOP Gland Exhauster trip/start standby LOHS156041A4 C 7 MC08 ATC Emergency Power Reduction of Loss of Main MC15R R Condenser vacuum (Recoverable) 8 RP02 ATC Drywell pressure starts to rise slowly. Manual and RP03 C auto Scram logics fail. ARI Initiation is necessary 9 MS04C Crew LOCA; A Steam line leak in the Drywell results in a M reactor scram and entry into QGA 100 and 200 10 DIHS11001S17B Crew Div 2 Drywell Spray valves fail to open, Emergency M Depressurization per QGA 500-1 when PSP exceeded

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 8 BOP Normal: E1 Malfunction(s) after EOP (1-2): E10 ATC Reactivity (1 per set): E7 Abnormal Events (2-4): E3, 4, 7 BOP I/C (4 per set): E4 & 6 Major Transient(s) /E-Plan entry (1-2): E9 ATC I/C (4 per set): E3 & 8 EOPs (1-2): QGA 200/ 100 SRO-I I/C (4 per set inc 2 as ATC): E3, 4, 6, 8 EOP Contingencies (0-2): E10 SRO Tech Spec (2 per set): E2 & 5 Critical Tasks (2-3): 2 ALL Major Transients (2 per set) E9 Quad Cities 2011 NRC EXAM Scenario 2

SUMMARY

Initial Conditions:

o The plant is operating at 100% power.

o HPCI maintenance complete. Restore HPCI to its standby lineup.

o Drywell Spray Valve MO 1-1001-23A is inoperable, on Day 2 of a 7-Day TLCO.

Event 1: The BOP re-pressurizes the HPCI Steam Lines and restores HPCI to its standby lineup per QCOP 2300-01 Step F.5.

Event 2: (Optional for Surrogate) The BOP responds to Annunciator 912-1 G-12 CONTROL ROOM STANDBY HVAC SYS. MAJOR TRBL and determines that the Toxic Gas Monitor is inoperable. The SRO refers to Technical Requirements Manual TLCO 3.3.e, Cond A and QCOS 5750-06. If the signal from the faulty monitor is inhibited within 40 minutes, TS 3.7.4 Condition A for inoperable CREV system will not apply.

Event 3: The CRD Flow Controller Auto output will fail upscale, which raises Drive Pressure and Cooling Flow. This causes a single control rod to drift INWARD to position 12. The ATC must fully insert the rod per the QCAN and QCOA for Rod Drift. The ATC may also restore CRD parameters to normal by taking the controller to MANUAL per the QCOA for a failed CRD Flow Control valve.

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.

Event 5: (Optional for Surrogate) The IMD Supervisor calls the US to report that an unqualified replacement part was recently used the Torus Level Transmitter for Control Room Narrow Range indications. The SRO will address Technical Specifications for an inoperable Post Accident Monitoring (PAM) instrument.

Event 6: The running Gland Seal Exhauster will trip. The BOP will start the standby Exhauster and adjust Gland Exhaust pressure.

Event 7: An air leak will result in lowering Main Condenser Vacuum. The crew performs QOA 3300-02 and Emergency Power Reduction. Prompt action by Equipment Operators to re-fill a loop seal line will stabilize Main Condenser Vacuum.

Event 8: Drywell Pressure starts to rise when a LOCA is initiated. 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. QCGP 2-3 actions for the Scram Discharge Volume, SRMs and IRMs are different will be different with the failure of RPS to trip.

Event 9: A LOCA inside the Drywell results in a reactor scram and entry into QGA 100 and 200. The crew restores RPV Water Level and attempts to control Drywell Pressure and Temperature with Containment Sprays.

Event 10: When Division 2 Containment Spray valves cannot be opened, the crew must 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 2011 NRC EXAM Scenario 2 EXERCISE PERFORMANCE OBJECTIVES SR-2300-P04 Given a reactor plant being started up, warmup the HPCI lines and align the system for standby in accordance with QCOP 2300-01.

SR-0300-P24 Given a reactor plant at power with a mispositioned control rod, restore the rod to the correct position or insert to 00 in accordance with QCOA 0300-4 or QCOA 0300-11.

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-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.

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

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-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 2011 NRC EXAM Scenario 2 Simulator Setup:

1. Reset to IC-21.

2. Go to RUN.

3. Close the HPCI Steam supply Valves, 1-2301-4 & 5. (Lines depressurize in 3.5 minutes)

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

2011 NRC Scenario 2.cae)

4. Insert Commands for setup:

ior dihs11001s17b off (Division 2 Containment Spray Permissive overridden off)

irf rh19ar open (Containment Spray 23A Breaker open)

irf rh20ar open (Containment Spray 26A Breaker open)

imf ser0986(6) on (On Trigger 6, Gland Exhauster Trip 901-7 E-12 ON)

ior dihs156041a(6) trip (On Trigger 6, 1A Gland Exhauster handswitch to TRIP)

ior lohs156041a4(6) on (On Trigger 6, 1A Gland Exhauster Amber Trip light ON)

trgset 4 zdihs103023a(2) .eq. 1 (When the A CRD Pump is taken to STOP)

trg 4 dmf rd03r4223 (Rod Drift Malfunction deleted on Trigger 4)

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)

trgset 8 rrpdome .lt. 875 (When Reactor Pressure lowers to <875 psig)

imf rp05a(8) (On Event Trigger 8, a spurious Group 1 Isolation)

imf rp05b(8) (On Event Trigger 8, a spurious Group 1 Isolation)

5. Verify the following commands for scenario performance:

imf ano9121g12 on (912-1 G-12 Annunciator for Toxic Gas Monitor inop,

imf ano9121h12 on (912-1 H-12 Annunciator for Toxic Gas Monitor inop)

dmf ano9121g12 (Deletes 912-1 G-12 Annunciator)

dmf ano9121h12 (Deletes 912-1 H-12 Annunciator)

ior aifc103401b 100 (CRD Flow Controller Overridden to 100% in Auto)

imf rd03r4223 (Rod L-6 Drifts IN)

dmf rd03r4223 (Deletes Rod Drift Malfunction)

ior aipic1874011a 100 2: (DW Pressure controller fails upscale on a 2 minute ramp)

trg! 6 (Trigger 6 used to initiate Event 6 Gland Exhauster Trip)

imf mc08 100 25: (Condenser Air Leak at 100 severity on a 25 minute ramp)

dmf mc08 (Deletes Condenser Air Leak, simulates filled loop seals)

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)

(Continued)

Quad Cities 2011 NRC EXAM Scenario 2 Simulator Setup:

6. Install out of Service tags on:

A Loop Drywell Spray Valves

7. Install Protected System placards and/or rings on the following equipment:

SSMP

RCIC

ADS

A&B Core Spray

A&B LPCI

T-12

8. Provide a Holding Load REMA.

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

QCOP 2300-01, signed off up to Step F.5.u.

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

11. Ensure procedures are erased and put away including QGAs.

12. Advance recorders.

13. Clean marked up meter/recorder faces and hard cards.

14. Remove any flags placed by the previous crew.

Quad Cities 2011 NRC EXAM Scenario 2 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-16 PRIMARY CONTAINMENT HIGH PRESSURE, Rev. 12 o 901-3 D-2 OFF GAS HI RADIATION, Rev. 12 o 901-3 G-4 DRYWELL HIGH PRESSURE, Rev. 8 o 901-5 D-11 PRIMARY CNMT HIGH PRESS, Rev. 11 o 901-5 A-3 ROD DRIFT, Rev. 7 o 901-7 E-12 GLAND STEAM EXH MOTOR TRIP, Rev. 3 o 912-1 G-12 CONTROL ROOM STANDBY HVAC SYS. MAJOR TRBLE, Rev. 2 o 912-1 H-12 CONTROL ROOM STANDBY HVAC SYS. MINOR TRBLE, Rev. 2 QCGP 2-3, Reactor Scram, Rev. 72 QCGP 3-1, Reactor Power Operations, Rev. 63 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 0300-4, Mispositioned Control Rod, Rev. 16 QCOA 0300-6, Control Rod Drive Flow Control Valve Failure, Rev. 6 QCOA 0300-11, Control Rod Drift, Rev. 22 QCOA 3300-02, Loss of Condenser Vacuum, Rev. 37 QCOA 5400-04, Loss of Steam Pressure or Off-Gas Flow, Rev. 7 QOA 5750-T01, Control Room Standby HVAC System Local Panel 1-9400-105 Annunciator Procedures, Rev. 23 QCOP 2300-01, HPCI Preparation for Standby Operation, Rev. 58 QCOS 1600-05, Post Accident Monitoring Instrumentation Outage Report, Rev. 18 QCOS 5750-06, Toxic Gas Monitoring Channel/System Inoperable Outage Report, Rev. 19 Quad Cities 2011 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:

1. HPCI is in Day 2 of a 14-day LCO and 14 Day ATR during pump casing leak repair. Tech spec 3.5.1 Condition G.

a. Repairs are complete and HPCI is being returned to its Standby lineup.

b. The next step is to re-pressurize the HPCI Steam Lines.

c. Post Maintenance testing is being planned for later in the shift.

2. Drywell Spray Valve MO 1-1001-23A is inoperable resulting in a 7 Day LCO per TLCO 3.6.a Condition A. On Day 2 of 7.

a. OOS due to binding that occurred during QCOS 1000-09, RHR Power Operate Valve Test.

b. As a power operated PCIV, it has been closed and deactivated per TS 3.6.1.3 Condition A.

c. 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).

(2) Unit 2: None d.) On Line Risk is YELLOW (due to HPCI & 1 loop of DW Spray unavailable) 2.) Significant problems/abnormalities:

a.) Protected Systems:

SSMP

ADS

RCIC

A&B Core Spray

A&B LPCI

T12 3.) Evolutions/maintenance for the oncoming shift:

a.) Re-pressurize the HPCI Steam Lines and restore HPCI to its standby lineup per QCOP 2300-01 Step F.5.u.

The discharge piping was filled and vented per step F.2 and F.3. on the previous shift.

b.) Continue normal Full Power Operation.

Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 1 Page 1 of 1 Event

Description:

Restore HPCI to standby lineup per QCOP 2300-01 Step F.5.

Time Position Applicants Actions or Behavior SRO Directs and supervises QCOP 2300-01, starting at Step F.5.u ATC Provides requested peer checks and monitors Panel 901-5 parameters BOP Re-pressurizes HPCI Steam Lines per QCOP 2300-01 Step F.5.u Opens MO 1-2301-5, STM SPLY ISO VLV Slowly throttles open MO 1-2301-4, STM ISOl VLV Monitors PI 1-2340-04 HPCI TURB INLET PRESS for a slow increase in pressure Fully open MO 1-2301-4 when Turbine Inlet Pressure stops increasing and Annunciator 901-3 B-11 is clear BOP Verifies HPCI TURB STOP VLV is closed BOP Presses the HPCI TURB TRIP RESET pushbutton BOP Verifies REMOTE HPCI TURB TRIP is not Trip-Latched BOP Places the TURNING GEAR MOTOR in AUTO BOP Places the HPCI FLOW CONTROLLER in AUTO BOP Places the HPCI FLOW CONTROLLER flowrate setpoint at 5600 gpm BOP Verifies all HPCI annunciators cleared SIMOP ROLE-PLAY: As the supporting EO as necessary BOP Dispatches an EO for the following:

Listen for motor and gear noise at the MSC and MGU motors Verify the HPCI Water Tight Door is closed Verify the Fill and Vent Valves are closed per Steps F.7 and F.8 EVALUATOR NOTE: Proceed to Event 2 End of Event 1 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 2 Page 1 of 2 Event

Description:

Inop Toxic Gas Monitor (Optional for Surrogate)

Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, fail the Toxic Gas Monitor:

imf ano9121g12 on and imf ano9121h12 on Key Parameter Response: Reports from the field Expected Annunciator:

912-1 G-12 CONTROL ROOM STANDBY HVAC SYS. MAJOR TRBLE 912-1 H-12 CONTROL ROOM STANDBY HVAC SYS. MINOR TRBLE Automatic Actions: None BOP Responds to annunciator and informs the Unit Supervisor BOP Dispatches NLO to "B" Control Room HVAC to determine which annunciator is illuminated on local panel 1/2-9400-105 SIMOP ROLE-PLAY: As EO dispatched, wait 2 minutes then:

Report that annunciators 1/2-9400-105 A-7, TOXIC GAS CONCENTRATION HIGH, and A-15 TOXIC GAS ANALYZER TROUBLE, are in alarm.

The AU 0-9400-122B monitor indicates 100 ppm and the fail light is lit. The other 3 monitors, AU 0-9400-121A,B and AU 0-9400-122A indicate 0 ppm.

If asked,

Report the following Control Room HVAC dampers indicate CLOSED at the 1/2-9400-105 panel: AO 1/2-5741-324A, AO 1/2-5741-324B, AO 1/2-5741-325A, AO 1/2-5741-325B,AO 1/2-5741-327A, AO 1/2-5741-327B, AO 1/2-5741-331.

If asked, the Control room Ventilation system is in Recirc mode.

BOP May contact Radiation Protection to sample the A Train outside air intake for ammonia SIMOP ROLE PLAY: If dispatched as Radiation Protection, wait 5 minutes and report NH3 concentration is 0 ppm BOP Contact Instrument Maintenance to investigate the Control Room HVAC Toxic Gas Analyzer SIMOP ROLE PLAY: As IM Supervisor contacted, report the 0-9400-122B NH3 XMTR has failed and you will start a work package BOP Refer to QOA 5750-T01, Control Room Standby HVAC System, local panel 1/2-9400-105 annunciator procedures ATC Monitors Panel 901-5 parameters Event 2 Continued Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 2 Page 2 of 2 Event

Description:

Inop Toxic Gas Monitor Time Position Applicants Actions or Behavior SRO Refers to Technical Requirements Manual TLCO 3.3.e, Cond B; restore the inoperable channel within 30 days SRO References QCOS 5750-06, Toxic Gas Monitoring Channel/System Inoperable Outage Report SRO If the Inhibit switch is NOT taken to INHIBIT within 40 minutes, the US enters TS 3.7.4 Condition A for inoperable CREV system SRO Records Date and Time of Toxic Gas Monitor inoperability SIMOP ROLE PLAY: When directed to the Inhibit Switch in INHIBIT, Acknowledge the directive as necessary and then clear the control room Annunciators:

dmf ano9121g12 and dmf ano9121h12 SRO/BOP Direct EO to place SW 0-9400-122B, NH3 XMTR 125B INHIBIT SWITCH, to the INHIBIT position SIMOP ROLE PLAY: As the EO, acknowledge further directive and report completion as necessary.

BOP Direct EO to place the Control Room Isolation Reset switch at Panel 1/2-9400-105 to the RESET position, then release BOP May direct the EO to place an EST on the 0-9400-122B switch stating, Toxic Gas Monitoring channel is inoperable.

BOP May direct the EO to verify the CR4X relay is deenergized at Panel 1-9400-105 End of Event 2 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 3 Page 1 of 2 Event

Description:

CRD FCV Fails High with Rod Drift IN Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, initiate the CRD FCV Controller Upscale and Rod Drift event: ior aifc103401b 100 and imf rd03r4223 Monitor the actions of the ATC and the position of control rod L-6. Delete the rod drift malfunction: dmf rd03r4223 when:

When L-6 is at position 12 (in approximately 3 minutes)

If the ATC takes the CRC Flow Controller to manual Note:

Tripping the running CRD Pump activates Event Trigger 4 which also deletes rd03r4223 Key Parameter Response: Rod position changing on the full-core display; red DRIFT light for rod L-6; Elevated CRD Flow Controller output, Drive Pressure, and Cooling Flow.

Expected Annunciator(s): 901-5 A-3, ROD DRIFT Automatic Actions: None EVALUATOR NOTE: If the ATC focuses on QCOA 0300-04 actions for a Rod Drift, the rod will be fully inserted. If the ATC promptly diagnoses the FCV Controller failure and takes actions from QCOA 0300-06, the controller will be placed in Manual.

ATC Responds to annunciator and informs the Unit Supervisor.

Identifies one control rod, L-6, drifting IN and informs the Unit ATC Supervisor.

ATC Monitor RWM Primary Display Screen for magenta colored rods ATC Fully inserts the Control Rod to position 00.

(QCAN 901-5 A-3 Step 4 or QCOA 0300-11 Immediate Action for a rod that continues to drift without latching)

ATC/SRO Refers QCOA 0300-11, Control Rod Drift.

ATC/SRO Notifies Shift Manager and Qualified Nuclear Engineer of control rod L-6 drifting in.

ATC Demands an OD-20 ATC Verifies Blue Scram Light is NOT on for Rod L-6 ATC Checks pressure on DPI 1-340-5 CLG WTR PRESS ATC Checks pressure on DPI 1-340-4 DRIVE WTR PRESS Event 3 Continued Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 3 Page 2 of 2 Event

Description:

CRD FCV Fails High w Rod Drift IN Time Position Applicants Actions or Behavior ATC May dispatch an EO to check rod L-6 discharge line SIMOP ROLE PLAY: If dispatched to check rod L-6 discharge line, wait 2 minutes and then report that the discharge line is NOT hot.

ATC May dispatch an EO close the 113 valve on rod L-6 SIMOP ROLE PLAY: If dispatched to close the 113 valve on rod L-6, wait 2 minutes and then report that the rod L-6 113 valve is closed.

ATC Identifies a failed CRD Flow Control Valve and enters QCOA 0300-06 ATC Places FIC 1-340-1 in MANUAL and adjust flow to 60 gpm Verifies control of the FCV by adjusting flow in MANUAL between 40-ATC 60 gpm SRO May reference Tech Spec 3.1.6 for Rod Pattern Control (TS is not applicable In Mode 1 >10% RTP)

When the drifting Control Rod latches at a position 00, exit QCOA ATC/SRO 0300-11 and enter QCOA 0300-04, Mispositioned Control Rod ATC/SRO Stops all control rod movement and Recirc Flow changes ATC/SRO (When >10% RTP) Contact a QNE for guidance on returning control rod to the proper position SIMOP ROLE PLAY: As the QNE, state that a Special Maneuver Rod Move Sheet will be provided shortly.

BOP Monitors Balance of Plant parameters End of Event 3 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 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 Announces rising drywell pressure and/or alarm 901-3 A-16 at 1.55 BOP psig. if/when it alarms Directs BOP to perform actions of QCAN 901-3 A-16 and/or QCOA SRO 0201-01, Increasing Drywell Pressure SRO May set scram criteria of ~2.0 psig CREW May notify Rad Protection of high containment pressure.

IF Drywell pressure reaches 1.5 psig enters TS 3.6.1.4 Condition A.

SRO 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to reduce drywell pressure to <1.5 psig.

BOP Starts last Drywell Cooler fan IAW QCOA 0201-01 BOP Reports drywell pressure controller has failed BOP May takes manual control of the drywell pressure controller and close it BOP Close the MO 1-1601-57 valve, N2 Makeup Vlv.

BOP Contacts IMD to investigate controller failure SRO IF drywell pressure exceeded 1.5 psig considers venting the drywell.

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 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 5 Page 1 of 1 Event

Description:

Torus Level PAM Instrument Failure (Optional for Surrogate)

Time Position Applicants Actions or Behavior SIMOP: When directed by the lead examiner, contact the Unit Supervisor as the IMD Supervisor. Report that a vendor notified them that they mistakenly shipped Quad Cities an un-qualified level transmitter replacement part and that the part was recently installed in the Torus Water Level Wide Range instrument, 1-1640-10A. The indication probably reads correctly now but its performance cannot be assured during an accident.

Refers to QCOS 1600-05 and Technical Specifications 3.3.3.1 for Post SRO 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 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 6 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! 6 Verify the following commands go active:

imf ser901-7e12(6) on, ior dihs156041a(6) trip, and ior lohs156041a4(6) 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 NLO and or EMD to the tripped breaker SIMOP ROLE PLAY: As the NLO, 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 - 20 of vacuum as indicated on the 1-5140-70 BOP Closes MO 1-5405A 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 6 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 7 Page 1 of 2 Event

Description:

Emergency Power Reduction of Loss of Main Condenser Vacuum Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, initiate a loss of vacuum: imf mc08 100 25:

Key Parameter Response: Main Condenser backpressure rising on PR 1-5640-79; Generator Mwe lowering Expected Annunciator(s):

901-3 D-2 OFF GAS HI RADIATION 901-7 H-3 CONDENSER LO VACUUM 24 IN HG (in 8.5 minutes with no operator action) 901-5 F-5 CONDENSER VACUUM LO (in 9 minutes with no operator action)

Automatic Actions: (If alarms not addressed) Reactor Scram and Turbine trip BOP Respond to annunciator 901-3 D-2 and informs the Unit Supervisor SRO Directs that reactor power be held constant until the cause of the high radiation is determined EVALUATOR NOTE: QCAN 901-3 D-2 lists Condenser Air in-leakage as a probable cause for this alarm. The next 3 actions may not be performed if the crew recognizes those indications BOP Monitor SJAE and Main Steam Line radiation levels BOP Monitor Area Radiation Monitors BOP/SRO Notify Chemistry and Qualified Nuclear Engineer of abnormal Offgas activity CREW Monitors Condenser Backpressure and informs the US that backpressure is rising BOP/SRO Dispatches Equipment Operators and/or Field Supervisor to investigate SIMOP ROLE PLAY: In-plant operators as necessary to acknowledge directives.

BOP/SRO Enter QCOA 3300-02, Loss of Condenser Vacuum SRO Initiates Emergency Power Reduction (See next Page)

ATC Reduces Reactor Recirculation flow as necessary to attempt to maintain Main Condenser backpressure < 5 in Hg.

ATC (For FCL >59.4%) Does not reduce core flow to the point of entry into Instability Region 2 or below 53 Mlb/hr.

Event 7 Continued Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 7 Page 2 of 2 Event

Description:

Emergency Power Reduction of Loss of Main Condenser Vacuum Time Position Applicants Actions or Behavior ATC If MANUAL RUNBACK pushbuttons are used:

Depress buttons no more than 3 times within a 5 second period Verify MANUAL pushbutton is lit on both A and B Speed Controllers Verify speed demand on both A and B Controllers decreases by 10% for each time the pushbutton was depressed SRO May set scram criteria of 7.0 in./Hg Main Condenser backpressure SIMOP ROLE PLAY: When Emergency Power Reduction has been performed to the satisfaction of the Lead Examiner, delete the in-leakage malfunction: dmf mc08 Then report that the Loop Seals have been re-filled.

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 7 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 8 Page 1 of 2 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-16 PRIMARY CONTAINMENT HIGH PRESSURE (1.5 psig alarm In 1 minute) 901-3 G-4 DRYWELL HIGH PRESSURE (In 2.5 minutes) 901-5 D-11 PRIMARY CNMT HIGH PRESS (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)

CREW May identify rising Drywell Pressure BOP Respond to 901-3 A-16 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 Start another Drywell Cooler Fan SRO May set Scram Criteria of 2 psig 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 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 8 Continued Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 8 Page 2 of 2 Event

Description:

Drywell Pressure rising, Manual Scram/ Alternate Rod Insertion Time Position Applicants Actions or Behavior ATC Verifies all Control Rods are fully inserted ATC Makes scram report including entry into QGA 100 on RPV Water Level

< 0 inches 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 with preferred 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 Main Generator Output Breakers tripped after 30 seconds and places control switches in PTL Verifies Main Generator Field and Exciter Field Breakers (alarm 901-8 ATC 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.

End of Event 8 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 9 Page 1 of 3 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior SRO Enters QGA 100, RPV Control and QGA 200, Primary Containment Control, on 2.5 psig DW pressure SRO Directs ATC/BOP to verify 0 and 2.5 psig isolations and auto-starts ATC/BOP Stabilize RPV Pressure < 1060 psig with the Turbine Bypass Valves ATC/BOP Verifies Group 2 and 3 Isolations, RB vent isolation and SBGT start 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 Verifies Bus 18 and 19 voltage >450 volts Takes the U1 DIV I DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position Takes the U1 DIV II DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position Checks Drywell temperature is less than 260 °F Starts 1A and 1B RBCCW pump Starts drywell coolers one at a time Starts Drywell Booster Fan Event 9 Continued Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 9 Page 2 of 3 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior SRO Verifies Torus level <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 > RHR Pressure

RHR Service Water flow <3600 gpm/pump

RHR Pressure 100-250 psig BOP Prepares RHR for Operation Verifies RHR Pumps running Places LOOP A/B CONTAINMENT COOLING PERMISSIVE Switch 17 to ON Places LOOP A/B RHR SW START PERMISSIVE Switch 19 to MANUAL OVERRIDE BOP Starts RHR Service Water Opens MO 1-1001-5A/B to approximately 40%

Starts A/B RHR SW Pump Throttles MO 1-1001-5A/B as necessary Throttles MO 1-1001-16A/B as necessary BOP As directed, initiates Torus Sprays per QCOP 1000-30 Opens MO 1-1001-34A Opens MO 1-1001-37A BOP Opens/Throttles MO 1-1001-36A as necessary to maintain RHR Discharge Pressure BOP 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 Event 9 Continued Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 9 Page 3 of 3 Event

Description:

Steam leak in Drywell / QGA 100 and 200 Actions Time Position Applicants Actions or Behavior SRO If Torus water temperature cannot be held <95°F, directs start of all available Torus Cooling BOP As directed, initiates Torus Cooling per QCOP 1000-30 Opens MO 1-1001-34A/B Opens/Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure 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 >5 psig.

SRO Verifies Torus level <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 Attempts to open MO 1-1001-23B Attempts to open MO 1-1001-26B BOP Recognizes and reports that the B Loop Drywell Sprays will not open SRO/BOP Directs NLO 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.

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 End of Event 9 Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 10 Page 1 of 1 Event

Description:

Emergency Depressurization when PSP exceeded Time Position Applicants Actions or Behavior Crew Recognizes that the MSIVs have closed and may begin investigation CT2 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 > 5 feet 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 Trips RFPs due to level exceeding +48 inches ATC/BOP Monitors level instrument watching for indications of saturation and informs SRO SIMOP: When Blowdown has been performed and/or at the discretion of the Lead Examiner, Place the simulator in FREEZE.

Quad Cities 2011 NRC EXAM Scenario 3 Exelon Nuclear 2011 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 3 Revision Number: 00 Date: _________

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2011 NRC Scenario 3 Op-Test No.: ILT 09-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 100% power.

Drywell Spray Valve 23A is inoperable.

FWLC Transmitter LT 1-646A is out of service for repair.

Turnover: Perform Core Spray Monthly Test.

Event Malf. No. Event Event No. Type* Description 1 CS06 BOP Core Spray Monthly with Min Flow Valve failure TS C

2 DIHS13401A ATC Emergency Power Reductions for loss of FW DIHS13403 R Heating 3 DIHS10202320 ATC Runback Pushbutton and Master Recirc Controller AOFC102622 C Failure during downpower requires manual operation of individual Recirc Controllers 4 SER0698 SRO Target Rock Relief bellows failure TS TS 5 RR15A ATC A 2nd FWLC Transmitter fails which shifts Reg valves RR15B C to manual operation during power operation and QGA 100 and 300 actions.

6 CR01 Crew Fuel failure due to loss of FW Heating begins.

HP12 & 13 M 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.

7 CR02 Crew When the Torus Area also exceeds Max Safe M 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: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 7 BOP Normal: None Malfunction(s) after EOP (1-2): E6 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E1, 3 & 5 BOP I/C (4 per set): E1 Major Transient(s) /E-Plan entry (1-2): E6 ATC I/C (4 per set): E3 & 5 EOPs (1-2): QGA 300, QGA 100 SRO-I I/C (4 per set inc 2 as ATC): E1, 3 & 5 EOP Contingencies (0-2): E7 SRO Tech Spec (2 per set): E1 & 4 Critical Tasks (2-3): 3 ALL Major Transients (2 per set) E6 Quad Cities 2011 NRC EXAM Scenario 3

SUMMARY

Initial Conditions:

o The plant is operating at 100 power.

o Drywell Spray Valve 23A is inoperable.

Event 1: The BOP performs QCOS 1400-01, Quarterly Core Spray System Flow Rate Test (A Pump only). When the Minimum Flow valve fails to auto close, the BOP will stop the Core Spray Pump and secure the system. The SRO will address Tech Specs for one Core Spray System inoperable, 3.5.1 Condition B.

Event 2: The 1A Feedwater Heater level switch fails, resulting in the isolation of a Feedwater Heater String. The Crew responds per QCOA 3500-01, Feedwater Temperature Reduction with the Main Turbine Online. The crew performs QCOA 0400-01, Reactivity Addition, by performing an Emergency Power Reduction. When the level switch is restored, the reactivity addition is terminated after closure of the LP Heater String Bypass Valve.

Event 3: During Emergency Power Reduction, neither the Runback Pushbutton nor the Master Recirc Controller will respond. The ATC must diagnose this problem and take manual control of individual Recirc Controllers.

Event 4: 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 5: When a second FWLC transmitter fails, the reg valves shift to manual. The ATC must control level manually during power operations, a scram, and QGA 100 and 300 performance.

Event 6: Due to the loss of FW Heating, a fuel element failure begins. The crew will respond to High Offgas radiation per QCOA 1700-04. When SJAE Rad levels cannot be maintained

< 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 7: 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: Given an operating reactor plant and a loss of Feedwater heating, perform actions to control reactor power and reclose the MO 1-3403, LP HTR STRING BYP VLV, to terminate the reactivity addition.

Critical Task #2: 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 #3: 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 2011 NRC EXAM Scenario 3 EXERCISE PERFORMANCE OBJECTIVES SR-1400-P05 Given a reactor plant with a core spray loop in a standby lineup, perform the Quarterly Core Spray Pump Flow Rate Test and return the core spray loop to standby in accordance with QCOS 1400-01.

SR-3500-P02 Given an operating reactor plant when an 'A' heater high level (loss of FW heating) occurs, perform actions to control reactor power and reclose LP heater bypass valve in accordance with QCOA 3500-01 and QCOA 0400-01.

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-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-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 2011 NRC EXAM Scenario 3 Simulator Setup:

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

2. Go to RUN.

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

2011 NRC Scenario 3.cae)

3. Insert Commands for setup:

ior dihs10202320(1) default (Recirc Manual Runback Pushbutton inoperable)

ior aofc10262221 off (Recirc Master Controller LOWER overridden off)

imf cs06a (A Core Spray Min Flow MO 1-1402-38A Fails to auto close)

ior dihs1140238a norm (Min Flow MO 1-1402-38A handswitch overridden in NORM)

trgset 1 zdihs114011a(2) .eq. 1 (When the 1A Core Spray Pump is taken to STOP)

trg 1 dor dihs1140238a (Deletes Min Flow MO 1-1402-38A handswitch override)

imf rr15a 0 (FWLC Transmitter failure LT 1-646A)

imf og04 (Offgas AO 1-5406 failure to Auto Isolate)

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)

irf rh19ar open (Containment Spray 23A Breaker open)

irf rh20ar open (Containment Spray 26A Breaker open)

4. Verify the following commands for scenario performance:

imf ser1405 on (Annunciator 901-6 G-1 Heater 1A1 High Level overridden ON)

ior dihs13401a close (LP Heater Line 1 Isol Valve MO-1-3401A override closed)

ior dihs13403 open (LP Heater bypass MO-1-3403 override open)

dor dihs13401a (Deletes LP Heater Line 1 Isol Valve MO-1-3401A override)

dor dihs13403 (Deletes LP Heater bypass MO-1-3403 override)

dmf ser1405 (Deletes Annunciator 901-6 G-1 override)

imf ser1405 off (Annunciator 901-6 G-1 Heater 1A1 High Level overridden OFF)

imf ser0698 on (Annunciator 901-3 F-18 Target Rock Bellow Failure alarm)

imf rr15b 100 (2nd FWLC Transmitter failure LT 1-646B, Shifts Reg Valves to Manual)

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 >Max Safe in 15 minutes)

5. Hang Equipment Out of Service Tags on Drywell Spray valves 23A and 26A.

6. Hang Information Tag on RPV Water Level Indicator LI 1-0640-29A on Panel 901-5.

(Continued)

Quad Cities 2011 NRC EXAM Scenario 3 Simulator Setup:

7. Provide a Load Holding REMA.

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

QCOS 1400-01, Quarterly Core Spray System Flow Rate Test (A Pump only)

Short Duration Time Clock documentation for Core Spray test

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

10. Ensure procedures are erased and put away including QGAs.

11. Advance recorders.

12. Clean marked up meter/recorder faces and hard cards.

13. Remove any flags placed by the previous crew.

Quad Cities 2011 NRC EXAM Scenario 3 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. 7 o 901-3 D-2 OFFGAS HI RADIATION, Rev. 12 o 901-3 H-2 AREA HI TEMP STEAM LEAK DETECTION, Rev. 6 o 901-3 F-12 HPCI PUMP AREA HI TEMP, Rev. 7 o 901-4 F-18 TARGET ROCK VALVE 3A BELLOWS FAILURE, Rev. 7 o 901-5 A-6 APRM UPSCALE/HIGH, Rev. 8 o 901-5 D-7 LPRM HIGH, Rev. 8 o 901-5 F-8 RX VESSEL LOW LEVEL, Rev. 10 o 901-6 E-10 FW LEVEL CONT SYSTEM TROUBLE, Rev. 3 o 901-6 G-1 HEATER 1A1 HIGH LEVEL, Rev. 3 o 901-55/56 A-1, DRYWELL HIGH RAD CONC, Rev. 10 QCGP 2-3, Reactor Scram, Rev. 72 QCGP 3-1, Reactor Power Operations, Rev. 63 QGA 100, RPV Control, Rev. 9 QGA 300, Secondary Containment Control, Rev. 11 QGA 500-1, RPV Blowdown, Rev. 13 QCOA 0201-05, Primary system Leaks Outside Primary Containment, Rev. 8 QCOA 1700-04, Abnormal Offgas Radiation, Rev. 16 QCOA 1800-01, Area High Radiation, Rev. 6 QCOA 3500-01, Manual/Automatic Feedwater Heater Level Control, Rev. 10 QCOA 0400-01, Reactivity Addition, Rev. 21 QCOA 0600-12, Feedwater Level Control System Trouble, Rev. 8 QCOS 1400-01, Quarterly Core Spray System Flow Rate Test, Rev. 39 Quad Cities 2011 NRC EXAM Scenario 3 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:

1. Drywell Spray Valve MO 1-1001-23A is inoperable resulting in a 7 Day LCO per TLCO 3.6.a Condition A. On Day 2 of 7.

a. OOS due to binding that occurred during QCOS 1000-09, RHR Power Operate Valve Test.

b. As a power operated PCIV, it has been closed and deactivated per TS 3.6.1.3 Condition A.

c. 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).

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

2.) Significant problems/abnormalities:

a.) The FWLC Transmitter LT 1-646A is out of service for repair.

3.) Evolutions/maintenance for the oncoming shift:

a.) Perform QCOS 1400-01, Quarterly Core Spray System Flow Rate Test (Group B Test for 1A Core Spray pump).

Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 1 Page 1 of 2 Event

Description:

Core Spray Monthly Time Position Applicants Actions or Behavior Key Parameter Response: A Core Spray Min Flow MO 1-1402-38A Fails to auto close Expected Annunciator(s): None Automatic Actions: None SRO Authorizes performance of QCOS 1400-01 for the 1A Core Spray Pump (Flow rate portion of test only)

EVALUATOR NOTE: The US may log entry into TS 3.5.1 prior to the start of the surveillance in lieu of the required entry at step H.1.h of the procedure.

BOP Contacts the EO to determine ESS Keep Fill pressure from PI 1-1468 located in the 1B Core Spray Room SIM OP ROLE PLAY: As the EO dispatched to the 1B Core Spray Room, call back and report the ESS Keep Fill pressure is 70 psig as indicated on PI 1-1468 BOP Announces start of 1A Core Spray Pump over the plant paging system BOP Starts the 1A Core Spray pump BOP Verifies the MO 1-1402-38A, CS PMP MIN FLOW VLV, opens BOP Records a Core Spray Pump Discharge Pressure BOP Contacts EO to inspect the 1A Core Spray pump and valves for leaks SIM OP ROLE PLAY: As EO, call back after 1 minute and report no leaks found on the 1A Core Spray pump and valves thus far. Will monitor the system during the test run.

BOP Notifies US and logs entry time of 1A Core Spray pump inoperability when the MO 1-1402-4A, CS BYP AND TEST VLV is opened SRO Enters a Short Duration Time Clock (SDTC) for T.S 3.5.1 Condition B for one Core Spray subsystem inoperable; a 7-Day LCO Event 1 Continued Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 1 Page 2 of 2 Event

Description:

Core Spray Monthly Time Position Applicants Actions or Behavior SIMOP: The Malfunction for Min Flow valve auto closure and an override for the Min Flow handswitch are inserted at Setup. When the 1A Core Spray Pump is taken to STOP, verify the handwsitch override is deleted. trg 1 dor dihs1140238a BOP Throttles open the MO 1-1402-4A valve to establish approx. 260 psig on PI 1-1450-1A, CS HEADER PRESS BOP Verifies that MO 1-1402- 38A automatically closes (May attempt to close it using the handswitch)

BOP (Per Step F.6) Closes MO 1-1402-4A BOP Stops the 1A Core Spray pump BOP Attempts to close MO 1-1402- 38A, identifies that valve closes BOP Informs the Unit Supervisor SRO Exits the SDTC and enters the 7-Day LCO for T.S 3.5.1 Condition B ATC Monitors Reactor and Reactor Pressure Vessel indications End of Event 1 Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 2 Page 1 of 2 Event

Description:

Loss of FW Heating Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, insert the following commands to simulate a failure of the 1A1 Heater level switch (1-3541-32A):

imf ser1405 on, ior dihs13401a close, and ior dihs13403 open Key Parameter Response: Reactor Power rising, Expected Annunciator(s):

901-6 G-1, HEATER 1A1 HIGH LEVEL 901-6 E-4, HEATER 1D1 EMERG DRAIN VALVE OPEN 901-6 E-5, HEATER 1D3 EMERG DRAIN VALVE OPEN 910-6 F4, HEATER 1D2 EMERG DRAIN VALVE OPEN (Possible) 901-5 A-6 APRM UPSCALE/HIGH (Possible) 901-5 D-7 LPRM HIGH Automatic Actions: Heater string isolated and bypassed; Emergency Drain valve opens ATC/BOP Acknowledges annunciator 901-6 G-1, HEATER 1A1 HIGH LEVEL and informs the Unit Supervisor BOP Verifies the Auto Actions:

Verifies FCV 1-3101A, 1A1 Emergency Drain Vlv, opens Verifies MO 1-3401A, Line 1 Htr Inlet Isol Vlv, closed Verifies MO 1-3402A, Line 1 Htr Outlt Isol Vlv, closed Verifies MO 1-3403, LP Htr String Byp Vlv, open Monitors 1A1 Flash Tank level and reports level is low and dispatches BOP an EO to investigate SIM OP ROLE PLAY: As EO dispatched to the 1A1 Flash Tank Level Controller, (LIC 1-3541-9A) wait 3 minutes and report that level is downscale and you have contacted Electrical Maintenance to assist in troubleshooting.

May report increasing Condensate Demin D/P as indicated on the DPR ATC/BOP 1-3340-1, Cond Demin DP, at the 901-6 panel Enters and directs actions of QCOA 3500-01 and QCOA 0400-01 and SRO sets scram criteria of reactor power > 105%, or any indication of Core Instabilities Event 2 Continued Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 2 Page 2 of 2 Event

Description:

Loss of FW Heating Time Position Applicants Actions or Behavior CT1 Directs power reduction continued until total Feedwater flow is < 7.6 SRO Mlb/hr.

CT1 Initiates Emergency Power Reduction by lowering individual Recirc ATC pump speeds (See Event 3)

CT1 Continues Emergency Power Reduction by inserting CRAM rods as ATC necessary to maintain Flow Control Line 100%

EVALUATOR NOTE: During rapid power reductions, annunciator 901-3 A-2, Main Stm Line Hi Radiation may alarm due to a momentary spike. The operator should verify that MSL radiation monitor readings return to normal after reactor power stabilizes or the annunciator clears.

CREW Monitors and maintains Flow Control Line (FCL) < 100%

ATC Monitors for indications of core instabilities ATC/BOP Monitors D Heater Outlet temperature and Reactor power per QCOA 3500-01, Attachment A, and scrams the reactor if operating below the curve SIMOP: When Feedwater flow is < 8.5 Mlb/hr, insert the following commands:

dor dihs13401a dor dihs13403 dmf ser1405 imf ser1405 off SIMOP ROLE PLAY: Call in as the EM Supervisor and report while removing the cover to inspect the 1A1 Heater Level Switch, the switch repositioned. It appears the switch had stuck. A work package will be prepared to clean or replace the switch.

ATC Reports total Feedwater flow ATC/BOP Reports when annunciator 901-6 G-1 has cleared Directs closure of MO 1-3403, LP Htr String Byp Vlv, to terminate the SRO reactivity addition BOP Closes the MO 1-3403, LP Htr String Byp Vlv May secure one Reactor Feed pump and one Condensate/Condensate BOP Booster pump per QCOP 3200-05 End of Events 2 & 3, continue at Event 4 Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 3 Page 1 of 1 Event

Description:

Runback Pushbutton and Master Recirc Controller Failure Time Position Applicants Actions or Behavior Key Parameter Response: Recirc Pump speed and Reactor power does not lower using the Runback pushbutton or the master controller Expected Annunciator(s): None Automatic Actions: None SRO Monitors performance of Emergency Power Reduction ATC Initiates Emergency Power Reduction by lowering Recirc pump speeds ATC May attempt to reduce Recirc Pump speeds by depressing the Runback Pushbutton ATC Recognizes that Recirc Pump speed / Recirc Loop Flow is not lowering ATC May attempt to reduce Recirc Pump speeds by depressing LOWER on the Recirc Master Controller ATC Recognizes that Recirc Pump speed / Recirc Loop Flow is not lowering ATC Takes the individual Recirc Speed controllers to MANUAL and reduces Recirc Loop Flow as directed ATC Verifies that Recirc Pump speed / Recirc Loop Flow is lowering BOP Continues attempts to restore Feedwater Heating BOP Monitors Balance of Plant parameters BOP May provide peer checks as requested End of Event 3 Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 4 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 Verifies the 3A SRV indicates closed on the Acoustic Monitor Verifies Point 9 not increasing on TR 1-260-20 (Panel 901-21)

BOP Monitor for increased leakage into the Primary Containment Monitor Drywell Air Temperatures 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 4 Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.:3 Event No.: 5 Page 1 of 1 Event

Description:

Loss of 2nd FWLC Transmitter Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner Insert Malfunction: imf rr15b 100 Key Parameter Response: RPV water Level indicator 1-0640-29B reading Upscale Expected Annunciator(s):

901-5 F-8 RX VESSEL LOW LEVEL 901-6 E-10 FW LEVEL CONT SYSTEM TROUBLE Automatic Actions: Main and Low Flow Feed Reg Valves shift to Manual ATC Responds to annunciators and informs the Unit Supervisor ATC Confirms RPV water level by alternate indications ATC Recognizes all Feed Reg Valves in manual and takes manual control ATC May select SINGLE SRO May set scram criteria of <11 inches or > 44 inches ATC Recognizes and reports LI 1-0640 29B is upscale ATC Diagnoses the RPV water Level indication deviation from average at the probable cause of the FWLC transfer to MANUAL SRO Enters and directs actions of QCOA 0600-12 ATC At the FWLCS OWS review the alarm list for major and minor events ATC/SRO Contact IMD and /or System Engineering for assistance with loss of RPV Level transmitter SIMOP ROLE PLAY: Plant Support personnel as necessary to begin investigation.

ATC Controls RPV water level in manual throughout remaining events BOP Continue to monitor Balance of Plant parameters End of Event 5 Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 6 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):

(in 1.5 min) 901-3 D-2 OFFGAS HI RADIATION (in 4 min) 901-55/56 A-1, DRYWELL HIGH RAD CONC (in 5 min) 901-5 A-8 & D-8, GROUP 2 & CONTROL ROOM VENT ISOLATED (in 14 min) 901-3 C-2, OFFGAS HIGH HIGH RADIATION 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 (901-02)

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 6 Continued Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 6 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 per QCOP 2400-01 SRO/BOP Notifies Radiation Protection ATC Responds to Annunciator GROUP 2 ISOL CH TRIP 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 < 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 2 SRO Directs closing of AO 1-5406 Offgas Discharge to Stack CT 2 BOP Closes AO 1-5406 BOP As directed, verifies that AO 1-5408A and AO 1-5408B close CT 2 BOP Manually initiates a Group 1 Isolation / Closes MSIVs and MSIV Drain valves Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 6 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

< 0 inches ATC Attempts to maintain RPV level 0 to +48 with preferred 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 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 SRO Enters and directs actions of QGA 100 SRO Directs ATC/BOP to verify 0 isolations and auto-starts ATC/BOP Stabilize RPV Pressure < 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 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 Starts the Control Room AFU Booster Fan within 40 minutes ATC Dispatches EO to reset the Generator 86 Relays Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 6 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 Annunciator RX BLDG HI RADIATION and informs the Unit Supervisor BOP Monitors Area Radiation levels from the 901-2 and 901-10 panels and reports QGA 300 Entry Conditions 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 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.

BOP Reports HPCI Room Radiation levels are > Max Normal and increasing BOP/ATC Monitors Reactor Bldg Temperatures at Panel 901-21 (TR 1-1290)

SIMOP ROLE-PLAY: When requested to investigate breakers for HPCI 4 & 5, as EO report the thermals are tripped. If asked to reset them, reply that they keep tripping.

Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 6 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 Reports HPCI Room Radiation levels are > Max Safe value of 3000 mr SRO Enters and directs applicable actions of QGA 300 SRO Re-enters and directs applicable actions of QGA 100 BOP Attempts to isolated HPCI Steam Lines BOP Directs EO to investigate breakers for HPCI 4 & 5 valves 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.

SRO/BOP Announces evacuation of Unit 1 Reactor Bldg. over plant page BOP Restarts Reactor Bldg. vents if not running End of Event 6 Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7 Page 1 of 1 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 < 2.5 psig and Torus level above 5 ft.

CT 3 SRO Orders all 5 ADS valves opened and leave switches in Manual CT 3 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 SIMOP: When Blowdown has been performed and at the discretion of the Lead Examiner, Place the simulator in FREEZE.

Quad Cities 2011 NRC EXAM Scenario 4 Exelon Nuclear 2011 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 4 Revision Number: 00 Date: _________

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2011 NRC Scenario 4 Op-Test No.: ILT 09-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 75% power.

The 1A EHC Pump is out of Service.

1B Service Water Pump is out of service.

Drywell Spray Valve 23A is inoperable.

Turnover: Swap Condensate pumps Event Malf. No. Event Event No. Type* Description 1 None BOP Start the 1A Condensate pump and secure the 1B N Condensate pump 2 ED01C BOP Switchyard Breaker 4-6 Trip and restoration C

3 SW02A BOP Service Water Pump degradation C

4 SER0382 ATC 1A Recirc High Vibration Alarm, Seal Leak, RR06A C Shutdown and isolate Recirc Pump TS RR07A 5 None ATC Insert Cram Rods for loss of 1A Recirc Pump R

6 RR03A Crew 1B Recirc Pump trips /Manual scram. After RPS has RD13A M been tripped, approximately 1/2 of the control rods remain withdrawn. (Hydraulic ATWS) 7 TC05B Crew QGA 101 Level/Power Control. Turbine Bypass M valves become unavailable, requiring manual RPV Pressure control with Relief Valves 8 DIHS11130301 ATC Malfunction after Major: Failure of 1st SBLC Pump to C start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal: E1 Malfunction(s) after EOP (1-2): E7&8 ATC Reactivity (1 per set): E5 Abnormal Events (2-4): E2, 3, & 4 BOP I/C (4 per set): E2 & 3 Major Transient(s) /E-Plan entry (1-2): E6 ATC I/C (4 per set): E4 & 8 EOPs (1-2): QGA 100 SRO-I I/C (4 per set inc 2 as ATC): E2,3,4,&8 EOP Contingencies (0-2): E7 SRO Tech Spec (2 per set): E4 Critical Tasks (2-3): 3 ALL Major Transients (2 per set) E6 Quad Cities 2011 NRC EXAM Scenario 4

SUMMARY

Initial Conditions:

o The plant is operating at 75% power.

o The 1A EHC Pump is out of service.

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

o Drywell Spray Valve 23A is inoperable.

Event 1: The BOP starts the 1A Condensate pump and secures the 1B Condensate pump.

Event 2: GCB 4-6 is inadvertently tripped open during a Switchyard breaker inspection. The problem is resolved and the US directs the BOP to reclose GCB 4-6 per QCOP 6400-08.

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 should start the 1/2 or the 2A Service Water Pump and secure the 1A pump.

Event 4: 1A Recirc Pump Seals fail due to pump vibration. Drywell pressure begins to rise.

The ATC must shutdown the Pump and isolate it. The SRO must address Technical Specifications for Single Loop Operation.

Event 5: ATC inserts control rods (CRAM rods) to exit exclusion region.

Event 6: The 1B Recirc Pump trips. When the second Recirc pump trips, the ATC must manually scram the reactor. Only 1/2 of the withdrawn control rods insert. The crew performs the actions of QGA 100 and 101 for a 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.

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).

Quad Cities 2011 NRC EXAM Scenario 4 EXERCISE PERFORMANCE OBJECTIVES SR-3300-P01 Given a reactor plant during a startup, start the condensate system in accordance with QCOP 3300-02.

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.

SN-6400-P40 Given an open 345kv circuit breaker, locally remove the circuit breaker from service and / or return the circuit breaker to service in accordance with QOP 6400-03 or QOP 6400-06.

SR-0202-P03 Given an operating reactor plant with reactor recirculation pump vibrations resulting in a recirc pump seal leak, trip the recirc pump and isolate the leak in accordance with QCOA 0202-06, and QCOA 0202-04.

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-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-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-P17 Given a reactor plant with an ATWS where emergency depressurization is required using QGA 500-1 or QGA 500-4, terminate and prevent RPV injection except for boron, CRD and RCIC, prior to initiating depressurization in accordance with QGA 101 and QGA 500-1 or QGA 500-4.

SR-0001-P19 Given a reactor plant with an ATWS following an emergency depressurization, slowly raise and control RPV injection with Preferred ATWS Systems.

Quad Cities 2011 NRC EXAM Scenario 4 Simulator Setup:

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

2. Go to RUN.

3.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 the 1B Service Water Pump to PTL hang an OOS INFO card.

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

2011 NRC Scenario 4.cae)

4. Insert Commands for setup:

imf rd13a 100 (SDV North Hydraulic lock)

trgset 8 zdihs10590300(1) .eq. 1 (When Mode Switch is taken to Shutdown)

imf tc05b(8 5:) (5 minutes after Trigger 8, 1B EHC pump trips)

ior dihs11130301 off (SBLC selector switch off 1st pump failure)

irf rh19ar open (Containment Spray 23A Breaker open)

irf rh20ar open (Containment Spray 26A Breaker open)

ior dihs13901b ptl (Override B Service Water Pump in PTL)

5. Verify the following commands for scenario performance:

imf ed01c (Swyd Breaker 4-6 trip)

dmf ed01c (Delete Swyd Breaker 4-6 trip)

imf sw02a 34 1: (1A SWP capacity degrades to 34% severity on a 1 min ramp)

imf rr06a 100 10: (1A Recirc Inboard Seal Leak)

imf rr07a 100 20:1ARecirc Outboard Seal Leak)

imf ser0382 on (1A Recirc Pump High Vibration annunciator)

imf rr03b (1B Recirc Pump Seizure/Trip)

dor dihs11130301 (Deletes SBLC switch override, allows 2nd pump to start)

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)bat toruslevelfail

6. Provide a Holding Load REMA.

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

QOP 3300-11 signed off up to Step F.12, with steps marked N/A for steps other than those necessary to start 1A and secure 1B condensate pumps.

8. Provide the Lead Examiner with:

Switching Orders to re-close Switchyard Breaker 4-6

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

10. Ensure procedures are erased and put away including QGAs.

11. Advance recorders.

12. Clean marked up meter/recorder faces and hard cards.

13. Remove any flags placed by the previous crew.

Quad Cities 2011 NRC EXAM Scenario 4 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-16 PRI CNMT HIGH PRESSURE, Rev. 12 o 901-4 C-3 RECIRC PUMP A HIGH VIBRATION, Rev. 6 o 901-4 B-6 RECIRC DRIVE B TRIP, Rev. 6 o 901-5 A-1 SCRAM VALVE AIR SUPPLY LOW PRESSURE, Rev. 7 o 901-5 A-10(15) CHANNEL A(B) MANUAL SCRAM. Rev. 6 o 901-5 A-14 CHANNEL A/B DISCH VOLUME HIGH LEVEL, Rev. 9 o 912-1 B-3 SERVICE WATER LOW PRESSURE, Rev. 6 o 912-2 C-3 345KV CKT BKR TRIP, Rev. 7 QCGP 2-3, Reactor Scram, Rev. 72 QCGP 3-1, Reactor Power Operations, Rev. 63 QGA 100, RPV Control, Rev. 9 QGA 101, RPV Control (ATWS) Rev. 13 QGA 200, Primary Containment Control, Rev. 9 QCOA 0201-01, Increasing Drywell Pressure, Rev. 23 QCOA 0202-04, Reactor Recirc Pump Trip - Single Pump, Rev. 33 QCOA 0202-05, Reactor Recirc Pump Trip - Both Pumps, Rev. 17 QCOA 0202-06, Recirculation Pump Seal Failure, Rev. 22 QCOP 0201-16, Terminate and Prevent RPV Injection, Rev. 5 QCOP 0300-28, Alternate Control Rod Insertion, Rev. 29 QCOP 0203-01, Reactor Pressure Control Using Manual Relief Valve Actuation, Rev. 13 QCOP 1100-02, Injection of Standby Liquid Control, Rev. 12 QCOP 6400-08, Operating 345KV Circuit Breakers, Rev. 16 QOP 3300-11, Condensate/Condensate Booster Pump Change Over. Rev. 23 Quad Cities 2011 NRC EXAM Scenario 4 CREW TURNOVER

1. Plant Conditions:

a.) Unit 1 is at 73% Power.

b.) Unit 2 is at 100% Power.

c.) Technical Specification limitations:

(1) Unit 1:

1. Drywell Spray Valve MO 1-1001-23A is inoperable resulting in a 7 Day LCO per TLCO 3.6.a Condition A. On Day 2 of 7.

a. OOS due to binding that occurred during QCOS 1000-09, RHR Power Operate Valve Test.

b. As a power operated PCIV, it has been closed and deactivated per TS 3.6.1.3 Condition A.

2. 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).

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

2.) Significant problems/abnormalities:

a.) 1A EHC pump is OOS for motor bearing replacement.

b.) The 1B Condensate Pump has an inboard seal leak. Scheduled to be removed from service late this shift.

c.) The 1B Service water Pump is out of service for repair of cracked terminal leads.

3.) Evolutions/maintenance for the oncoming shift:

Unit 1 is operating at approximately 720 Mwe on the 100% FCL.

Currently holding load for upcoming 1B Condensate Pump repairs.

Start the 1A Condensate Pump and secure the 1B Condensate pump per QOP 3300-11.

o Local actions have been completed in preparation, up to Step F.12.

Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 1 Page 1 of 1 Event

Description:

Start the 1A Condensate pump and secure the 1B Condensate pump.

Time Position Applicants Actions or Behavior SRO Directs and supervises the Condensate Pump changeover SIMOP ROLE PLAY: As the EO, support the Condensate Pump changeover as necessary.

Places the selector switch for Condensate/Condensate Booster Pumps BOP to OFF BOP Starts the 1A Condensate/Condensate Booster Pump BOP Verifies Reactor Feed Pump suction pressure >200 psig BOP Verifies Condensate/Condensate Booster Pump Motor Currents < 245 Amps BOP Directs the EO to verify the 1A Condensate/Condensate Booster Pump bearings are at the proper oil level SIMOP ROLE PLAY: As the EO, report that the 1A Condensate/Condensate Booster Pump bearings are at the proper oil level.

BOP Directs the EO to verify the 1A Condensate/Condensate Booster Pump bearings has no major seal leaks SIMOP ROLE PLAY: As the EO, report that the 1A Condensate/Condensate Booster Pump has no major seal leaks.

BOP Stops the 1B Condensate/Condensate Booster Pump BOP Verifies RPV water level is stable Verifies the 1A Condensate/Condensate Booster Pump Motor Currents BOP are between 160 and 245 Amps BOP May place the selector switch to select the 1B Condensate/Condensate Booster Pump for standby operation BOP Directs the EO to close and lock the Hydrogen addition valve (1-2799-31B) on the 1B Pump and Open and lock Hydrogen addition valve (1-2799-31A) on the 1A Pump ATC Monitors RPV water level and Panel 901-5 indications SIMOP ROLE PLAY: As the EO, report that 1-2799-31B is CLOSED and locked and 1-2799-31A is OPEN and locked.

End of Event 1 Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 2 Page 1 of 1 Event

Description:

Switchyard Breaker 4-6 Trip and restoration Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, trip Swyd Bkr 4-6 using the command imf ed01c, then delete the Swyd Bkr 4-6 trip to allow re-close using dmf ed01c Key Parameter Response: At Panel 912-2, CKT BKR 4-6 Red Iight off, Green/Open Light on Expected Annunciator(s): 912-2 C-3, 345KV CKT BKR TRIP Automatic Actions: None BOP Responds to annunciator and informs the Unit Supervisor Determines which breaker tripped, 4-6, and informs the US Places CKT BKR 4-6 in Pull-To-Lock Dispatches an operator to the Relay House Notifies the Shift Manager and Transmission Dispatcher SIM OP ROLE PLAY: As OAD, call into the Control Room and report you inadvertently bumped the control cabinet for GCB 4-6 while staging equipment for an upcoming modification. You have inspected the cabinet and found no damage. You suggest contacting Transmission and re-closing CB 4-6.

Contacts Transmission Operations for permission and Switching SRO Orders to re-close GCB 4-6 LEAD EVALUATOR NOTE: Provide a copy of the Switching Orders after the SRO requests them from Transmission.

SRO Directs re-closure of GCB 4-6 per QCOP 6400-08 Directs EO in the Relay House to inspect GCB 4-6 and surrounding BOP area prior to closure of the circuit breaker SIMOP ROLE PLAY: As EO, call back after approximately 2 minutes, and report area is cleared of all personnel and no safety hazards exist. If directed or asked to complete QCOP 6400-08 steps F.2a.-c., wait 1 minute and report those steps as complete.

Turns on the 345KV Synchronization Switch with the key and verifies BOP synchroscope is at 12 oclock and incoming and running voltages are equal Closes GCB 4-6 with the control switch at the 912-2 panel and verifies BOP both RED lights are energized BOP Turns off 345KV breaker synchronization switch and removes key BOP Verifies re-closure cutout toggle switch is in the UP (ON) position ATC Monitors Panel 901-5 parameters End of Event 2 Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 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 Identifies and reports that Service Water pressure is at the alarm point BOP but steady SRO Supervises actions of the QCAN BOP Dispatches an EO to investigate SIMOP ROLE PLAY: As the EO dispatched to the Crib House: Report that that the 1A Service Water Pump is very noisy and feels warmer than normal.

BOP Monitors Service Water pressure on PI 1-3940-18 Recognizes that the 1B pump will not start at 75 psig as header BOP pressure lowers SRO May direct starting the 1/2 or 2A SWP BOP Verifies closed the FIRE PROT SW SPLY VLV, MO-1-3906 Starts standby Service Water Pumps to restore normal system BOP pressure BOP Secures the 1A SWP ATC Monitors Panel 901-5 indications End of Event 3 Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 4 Page 1 of 2 Event

Description:

1A Recirc Pump High Vibration, Seal Leak, Shutdown and isolate Recirc Pump Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, begin the loss of the 1A Recirc Pump by inserting the following commands: imf rr06a 100 10: imf rr07a 100 20: imf ser0382 on Key Parameter Response: Pressures equalizing on A Recirc Pump Inboard and Outboard seals, PI 1-262-17A & C Expected Annunciator(s):

901-4 C-3 RECIRC PUMP A HIGH VIBRATION 901-3 A-16 PRI CNMT HIGH PRESSURE (Possible in approximately 3 minutes)

Automatic Actions: None ATC Responds to annunciator and informs the Unit Supervisor ATC Attempt to reset the vibration monitor by depressing PMP VIB MONITOR RESET pushbutton ATC Verify both Recirc Pumps running at less than 78% speed ATC Review the performance of both Recirc Pumps and note any abnormalities ATC Instruct the Vibration Engineer to immediately begin evaluating Recirc pump vibration data SIMOP ROLE PLAY: Vibration Engineer as necessary when directed to evaluate vibration data ATC Identify and reports that the pressures are equalizing on A Recirc Pump Inboard and Outboard seals BOP Reports the Primary Containment pressure trend to the Unit Supervisor BOP If necessary, responds to Annunciator 901-3 A-16 BOP Monitors Balance of Plant parameters and peer checks as necessary SRO May enter and direct actions from QCOA 0201-1 including actions to isolate the leak Event 4 Continued Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 4 Page 2 of 2 Event

Description:

1A Recirc Pump High Vibration, Seal Leak, Shutdown and isolate Recirc Pump Time Position Applicants Actions or Behavior SRO Enters and directs actions of QCOA 0202-06 ATC May insert in-sequence control rods SRO Directs ATC to trip and isolate the A Recirc Pump ATC Trips the A Recirc Pump using either the ASD INPUT breaker control switch or the EMERGENCY STOP pushbutton ATC Closes the 1-0202-4A, A Recirc suction valve ATC Closes the 1-0202-5A, A Recirc discharge valve ATC Directs an EO to isolate seal injection to A Recirc Pump SIMOP ROLE PLAY: EO as necessary when directed to isolate seal injection to A Recirc pump. Wait 5 minutes and then report that seal injection to A Recirc pump is isolated.

ATC/BOP Verify A Recirc Pump seals depressurize SRO Enters and directs actions of QCOA 0202-04 for single Loop Operations SRO Refers to TS 3.4.1 and determines Condition C is appropriate. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy the requirements of the LCO SRO IF DW pressure rises above 1.5 psig, SRO refers to TS 3.6.1.4 and determines Condition A applies. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to restore DW pressure to <1.5 psig.

End of Event 4 Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 5 Page 1 of 1 Event

Description:

Insert Control Rods for loss of 1A Recirc Pump Time Position Applicants Actions or Behavior EVALUATOR NOTE: Depending on how many control rods were inserted previously additional rods may not need be inserted.

ATC Monitors for indications of thermal hydraulic instabilities on SRM period or LPRM levels SRO Enters and directs actions of QCOA 0202-04 for single Loop Operations SRO Directs actions to lower the Flow Control Line as necessary to avoid Instability Regions 1 or 2 ATC If necessary, bypasses RWM IAW QCOA 0400-02 ATC Continuously inserts control rods until Reactor operation is outside of Instability Region II SRO Supervises control rod insertion BOP Monitors Balance of Plant parameters End of Event 5 Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 6 Page 1 of 2 Event

Description:

1B Recirc Pump Trip /Manual Scram/Hydraulic ATWS Time Position Applicants Actions or Behavior SIMOP: Focus the Simulator Camera on the SBLC control switch in preparation for Event 8 SIMOP: When directed by the Lead Examiner trip the B Recirc Pump: imf rr03b Key Parameter Response: On B Recirc Loop, lowering flows on Pump, Jet Pumps, and Loop Expected Annunciator(s):

901-4 B-6 RECIRC DRIVE B TRIP 901-4 A-1 RRCS MAJOR FAILURE 901-4 A-7 RECIRC PUMP B LOW DP Automatic Actions: Reactor power lowers ATC/BOP Responds to annunciators and informs the Unit Supervisor ATC Recognizes the loss of both Recirc Pumps ATC Depresses the Manual Scram Pushbuttons per QCOA 0202-05 Immediate Operator Actions SRO Enters and directs actions of QCOA 0202-05 ATC/BOP Closes the B Recirc Pump Discharge Valve, MO 1-0202-5B and reopens after five minutes Key Parameter Response: All 8 RPS Scram Solenoid Lights are off; On Full Core Display, North Control Rods do not indicate Full-In; reactor power remains > 5%

Expected Annunciator(s):

901-5 A-1 SCRAM VALVE AIR SUPPLY LOW PRESSURE 901-5 A-10(15) CHANNEL A(B) MANUAL SCRAM 901-5 A-14 CHANNEL A/B DISCH VOLUME HIGH LEVEL Automatic Actions: None ATC Reports control rods did NOT insert SRO Enters QGA 100, transitions to QGA 101 ATC Arms and depresses ARI Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 6 Page 2 of 2 Event

Description:

1B Recirc Pump Trip /Manual Scram/Hydraulic ATWS Time Position Applicants Actions or Behavior 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 Dispatches EO to close the 1-301-25 valve SIM OP 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 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 ATC Directs operator to bypass all reactor scrams per QCOP 0300-28 SIM OP ROLE PLAY: If requested, wait approx. 2 minutes and bypass all reactor scrams using: irf qg08r 1 Then report completion.

Event 6 Continued Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 7 Page 1 of 2 Event

Description:

QGA 101 Level/Power Control Time Position Applicants Actions or Behavior ATC Resets reactor scram.

ATC Dispatches EO to de-energize ARI by removing fuses in 2201-70A and 2201-70B panels per QCOP 0300-28 SIM OP 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 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 SIM OP 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.

SRO Verifies reactor power >5% and RPV water level > -35 SRO Directs all injection except boron, CRD, and RCIC terminated and RPV water level lowered to at least -35. (Terminate and prevent from 901-3 and 901-5)

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

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

Closes A and B Feed Reg Valve isolations, MO-1-3206-A/B SRO Determines further level reduction needed at -35 RPV water level ATC/BOP Reports level when Rx power < 5%, RPV water level at TAF or ADS valves are closed with DW pressure < 2.5 psig.

Event 7 Continued Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 7 Page 2 of 2 Event

Description:

QGA 101 Level/Power Control Time Position Applicants Actions or Behavior SRO Directs RPV water level maintained between -166 and the level to which it was lowered ATC/BOP (CONTINUOUS) Maintains level between -166 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) Opens ADS valves 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 BOP Places RHR in the Torus Cooling Mode as directed End of Event 7 Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 4 Event No.: 8 Page 1 of 1 Event

Description:

Failure 1st SBLC Pump to start Time Position Applicants Actions or Behavior SIMOP: Delete the override for the SBLC switch when the ATC operator selects the 2nd SBLC pump for injection. dor dihs11130301 SRO Directs SBLC Injection prior to exceeding 95°F Torus Water Temperature ATC Reports SBLC tank level and selects a SBLC pump for injection by placing the control switch to SYS 1 or SYS 2 ATC Reports the SBLC pump has failed to inject, and selects the other SBLC pump ATC Verifies and reports the 2nd SBLC pump is injecting Squib B light is off Flow Light is on RWCU System isolated SBLC Tank level lowering Pump discharge pressure slightly high than reactor pressure Annunciator 901-5 H-6 SBLC Squib valve circuit failure is on Neutron flux is decreasing ATC Monitors SBLC Tank level for 16% decrease (in 21 minutes)

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

ML12271A166

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