ML030830050

Initial Submittal of the Scenarios for the Quad Cities Examination - Dec 2002

ML030830050
Person / Time
Site:	Quad Cities
Issue date:	02/04/2003
From:	Lanksbury R NRC/RGN-III
To:	Skolds J Exelon Generation Co, Exelon Nuclear
References
50-254/02-301, 50-265/02-301
Download: ML030830050 (56)

Text

INITIAL SUBMITTAL OF THE SCENARIOS FOR THE QUAD CITIES EXAMINATION - DEC 2002

Appendix D 1

Form ES-D-1

,

4

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B) - BOP/ANSO Reviewed by:

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!j tf-tLi FACILITY: QUAD CITIES EOPERATORS:

INITIAL CONDITIONS: - 41% power, 1B Service Water Pump, 1B EHC pump, ID RHR pump and 1B Instrument Air Compressor OOS, IRM #12 bypassed. Power ascension in progress.

TURNOVER:

- 355 MWe and 41% power on the 50% FCL. Rod step 53 is partially withdrawn.

The following equipment is out of service: 1 B Service Water Pump, 1 B EHC pump, 1D RHR pump and 1B Instrument Air Compressor OOS, IRM #12 bypassed. Plant startup in progress lAW QCGP 1-1, step F.9.t. Place the A FWRV in service. QNE directions are to increase power with recircs to - 65 MLBM/hr core flow.

Event Malfunction Event Event No.

Number Type*

Description 2

1 FWO8b I-RS BFWRVlockup es.".

2 N/A N-B, S Place A FWRV in service/

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N/A R - R, S Increase power using recirc pumps 4

SW11b C-B,S TBCCW pump trip

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5 RP04b C - B, S Trip of RPS-B 6

RD04r C - R, S Rod drift out 7

TU12/RD13 M -All Turbine Trip with Hydraulic ATWS (PSA identified event) 8 TC05a C - All Trip of IA EHC Pump wt -.

Date SCENARIO NO: I OP-TEST NO: I EXAMINERS:

Appendix D 1

Form ES-D-1

.3

_CT #1 - During an 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. (BWROG RPV-6.3 PWR/LVL TERM/PREVENT)

CT #2 - 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"). (BWROG RPV-6.4 ATWS PWR/LVL RESTORE RPV LVL)

CT #3 (Contingent on water level) - With a reactor scram required, reactor not shutdown, and conditions for ADS blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion. (BWROG RPV-6.2 ATWS PWR/LVL INHIBIT ADS) r7j 77 II Ii J/Lh x,

L Facility: Quad Cities Scenario No: 1 Op-Test No: I Summary:

• The crew will take the shift at - 41% power. The B FWRV will lockup, requiring reset.

(Instrument - RO, SRO) When Feedwater flow is approximately 4.5 MLBM/hr the BOP will place the 2 nd FWRV in service. (Normal Evolution - BOP, SRO) The RO will increase reactor power using Recirc pumps. (Reactivity Manipulation - RO, SRO) The A TBCCW pump will trip, requiring manual start of the B TBCCW pump.

(Component - BOP, SRO) Next a loss of "B" RPS will occur, requiring restoration of power and resetting of isolations and equipment. (Instrument, TS - BOP, SRO) A rod will drift out of the core, requiring it to be manually inserted, scrammed and isolated. (Component, TS - RO, SRO) The turbine will trip, rods will not insert Hydraulic ATWS, requiring entry into QGA 1011. (Major - All) Approximately 2 minutes after the Turbine trips, the 1A EHC pump will trip, requiring pressure control to be transferred to the ADS valves. The scenario is complete when the crew is controlling RPV water level and pressure lAW QGA 101 Power/Level Control leg and have worked through QCOP 0300-28 to the point of attempting individual rod insertion.

Appendix D 1

Form ES-D-1 Simulator setup:

1. Reset the simulator to IC-18: rst 18

2. Take the following equipment OOS:

I B Service Water Pump in PTL 1 B Instrument Air Compressor in PTL 1D RHR Pump in PTL lB EHC Pump in PTL

3. Bypass IRM 12

4. Insert the following malfunctions:

a. Hydraulically lock the Scram Discharge Volume using malfunctions RD13a and b. imf RD13a 100, imf RD13b 100

5. Pull control rods to step 53 -

1 st 4 rods (C-11, C-5, N-11, N-5) at position 24, the others at target in.

6. Adjust recircs to - 50 MLBM/hr core flow. (This is - 45% speed demand).

7. Start the 2 "d RFP lAW QCOP 3200-03.

8. Start CAMS for Drywell sampling on the 901-56 panel.

9. Place the 1A FWRV in Sequence Manual at the left computer screen by selecting FWLC Overview screen and ensure I B FWRV is the primary. (D-1).

10. Ensure Drywell inerting in progress.

11. Ensure the RWM is setup correctly.

12. Ensure all procedures are erased.

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Appendix D 1

Form ES-D-1 Crew Turnover:

Unit 1 is at approximately 355 MWe and 41% power on the 50% FCL. Rod step 53 is partially withdrawn.

Unit 2 is operating at 97% power on the 97% Flow Control Line.

The following equipment is out of service:

1 B Service Water Pump due to a ground in the motor windings.

1 B EHC pump due to a failure of the autostart feature.

ID RHR pump due to a failure of the trip coil. Tech Spec 3.5.1, condition A.1 entered, Day 1 of 30.

1 B Instrument Air Compressor due to a seal water failure.

I RM #12 bypassed due to erratic operation Plant startup in progress lAW QCGP 1-1, step F.9.t. QNE directions are to increase power with recircs to - 65 MLBM/hr core flow.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

1 Page 1

of 10

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Description:==

1 B FWRV lockup Initiation: Shortly after the crew takes the shift and when directed by the lead examiner, lockup the 1 B FWRV using malfunction FW08b (imf fwO8b).

Time Position Applicant's Actions or Behavior RO Reports annunator1-5, H-8 is alarming and adoresses the annunciator procedure.

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Monitors Rx Water level.

Depresses 1 B VLV RESET pushbutton and holds for at least 5 seconds.

SIM OP While the RESET pushbutton is depressed, delete the locked FWRV malfunction. (dmf fwO8b)

A.

Reports 1 B FWRV reset.

Verifies Rx Water level is approximately the same as the Master Controller setting and places FWRV in auto by selecting AUTO at the FWRV controller or the Operator workstation (OWS).

Monitors Rx Water Level.

Directs Instrument Maintenance investigate FWRV lockup.

SIM OP

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As the IM sent to investigate, wait approximately 5 minutes and report n-2 that you found a loose lead on 1B FWRV and have tightened it.

BOP Monitors Balance of Plant parameters.

_Assist RO as requested by SRO/RO SRO Directs the RO to investigate the anuunciator.

P Sets scram criteria of 11 and 44 inches.

44_1 If asked, authorizes placing FWRV in Auto.

Ensures Instrument Maintenance is contacted.

Termination: The 1B FWRV lockup has been investigated and reset.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

2 Page 2

of 10

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Description:==

Place the A FWRV in service.

Initiation: Feedwater flow is approximately 4.5 MLBM/hr.

Time Position Applicant's Actions or Behavior SRO Directs A FWRV placed in service.

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BOP Verifies A FWRV is in sequence manual on the OWS screen.

Verifies B FWRV is on-line in AUTO.

• "*V*Verifies A-EWVRV is in "remote-manual" and is closed.

kIf desired, balances positions of FWRVs.

"Place A FWRV in "Auto".

U Verifies A and B FWRVs are balanced.

S",Verifies Reactor Water level being maintained.

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RO Monitors Rx Water level and 901-5 panel parameters.

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Termination: The A FWRV is in service.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

3 Page 3

of 10

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Description:==

Power ascension.

Initiation: The crew is turned over to raise reactor power with recirc pumps.

Time Position Applicant's Actions or Behavior Authorizes power increase. Gives pre-job brief. (Brief may have been done US prior to the crew assuming the shift.)

Supervises and monitors the power ascension.

RO Monitors 901-5 panel parameters.

Increases recirc pump speed using individual controllers.

BOP Monitors Balance of Plant parameters.

Provides peer-check for the RO when performing reactivity manipulations.

Termination: Feedwater flow is - 4.5 MLBM/hr.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

4 Page 4

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Description:==

1A TBCCW Pump Trip Initiation: Sim Op trips 1A TBCCW pump by inserting malfunction SW1 la (imf swlIa) when the power ascension is started or when directed by the lead examiner.

Time Position Applicant's Actions or Behavior BOP Reports annunciators 91 2-1 C-2 and D-2 are larming a d dresses the annunciator procedures. (

• 7 Determines that 1A TBCCW pump has tripped.

Starts 1B TBCCW pump.

Dispatches an operator to MCC 15-1 to check for breaker trip or thermal overload condition and sends an operator to the pump to check for an abnormal condition.

SIM OP As the operator sent to 1 5-1, wait - 3 minutes and report 1 A TBCCW pump thermal overloads are tripped. As the operator sent to investigate the pump, report 1 B TBCCW pump is running normal and 1A TBCCW pump 1*

feels warm.

SRO Directs the BOP to investigate the annunciators.

If asked, authorizes the start of 1 B TBCCW pump.

Ensures Mechanical Maintenance is contacted.

RO I Monitors plant parameters.

Termination: 1B TBCCW pump is running and the failure of 1A TBCCW pump is being investigated.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

5 Page 5

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Description:==

Trip of RPS B Initiation: When the load increase is complete or when directed by the lead examiner, trip RPS B using malfunction RP04b (imf rp04b).

Time Position Applicant's Actions or Behavior RO Reports "B" RPS 1/2/ scram and an apparent loss of RPS "B" Monitors plant parameters.

l"RO/BOP Resets the Group 2 and 3 isolations.

RO/BOP Resets the Group 1 isolation.

ROIBOP Resets the 1/2 scram SRO Directs BOP to perform QOA 7000-01, RPS Bus Failure.

Directs RPS "B" placed on alternate power.

Contacts Electrical Maintenance to investigate.

Refers to TS 3.3.8.2 and determines that he has 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to remove EPAs from service.

BOP If the RO does not report a loss of RPS "B", the BOP does.

Refers to QOA 7000-01, RPS Bus Failure.

Dispatches an operator to the Aux Electric Room to investigate.

Verifies Rx Bldg Vents auto-isolate and SBGT auto-starts.

-Verifies Group 2 and 3 valve closures.

SIM OP After - 3 minutes, report that RPS "B" EPAs are tripped and will not reset.(

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

5 Page 6

of 10

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Description:==

Trip of RPS B (Continued)

Initiation: When the load increase is complete or when directed by the lead examiner, trip RPS B using malfunction RP04b (imf rp04b).

Time Position Applicant's Actions or Behavior BOP Directs the NLO to place RPS "B" on alternate power.

Ensures Electrical Maintenance is contacted.

/SIM OP After - 1 minute, places RPS "B" on alternate power using remote

/--`714rnction RP03r (mrf rp03r alt).

\\,B P/RO R set; the Group 2 and 3 isolations.

"Rqsets the Group 1 isolation.

Fsets the 11/2 scram.

OP estores Primary Containment vent system to normal.

__ Opens AO 4720 or AO 4721..,

Reset Rx Building Floor Drain and Equipment Drain Tank Pumps.

Resets ARMs, APRMs and RBM.

Resets Rx Bldg Vents and Shutdowns SBGT.

Resets CR Vents.

Opens RWCU isolation valves and restarts RWCU.

Resets Gp 2 ISOL RESET VLV 1001-29 pushbuttons on both loops of RHR SIM OP If asked, as the EM, report to the CR and report DC solenoid cable currents are between 45 and 65 ma in the 901-3 panel.

Termination: At a minimum, the cause has been investigated, RPS B is on alternate power and the S1/2scram and 1/2 isolations have been reset.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

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Description:==

Control rod drifts out Initiation: When the minimum actions for restoring RPS B are complete and directed by the lead examiner, cause control rod 34-27 to drift out using malfunction RD04r. (imf rd04r3427).

Time Position Applicant's Actions or Behavior RO Reports alarm 901-5 A-3, Rod Drift and control rod 34-27 (J-7) drifting ou o the core.

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It Refers to the annunciator procedure and QCOA 0300-1.1 Selects control rod 34-27 (J-7),

and drives to position 00.

Reports control rod 34-27 (J-7) will not latch and drives to position 00.

BOP Refers to the annunciator procedure and QCOA 0300-11.

Places individual control rod Scram Test Switch for control rod 34-27 (J-7) to the scram position at panel 901-16.

Contacts a QNE Contacts NLO to close 1-305-105, CRD EXH VLV for control rod 34-27 (J-7).

SiM OP When directed to close 1-305-105 for control rod 34-27 (J-7), wait - 3 minutes and modify remote function RD06r (mrf rd06r3427r inop) and delete malfunction RD04r (dmf rd04r3427).

SRO Directs RO/BOP to address annunciator 901-5 A-3 and QCOA 0300-11.

Refers to Tech Spec 3.1.3.C and declares control rod 34-27 (J-7) inop.

Directs control rod 34-27 (J-7) taken OOS.-""

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e to be tae Termination: When the drifting control rod has been inserted, scrammed an~ directed to be taken COS.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

7 Page 8

of 10

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Description:==

Trip of the Main Turbine with ATWS Initiation: When the actions for the drifting control rod have been completed or when directed by the lead examiner, trip the main turbine on high bearing vibration using malfunction TU02L ramped to to 50 % over 2 minutes. (imf tu02L 50 2:).

Time Position [

Applicant's Actions or Behavior RO Notes by annunciator 901-5 A-12 that the Main Turbine has tripped and the Rx failed to scram.

Inserts a manual scram and places the Mode Switch to SHUTDOWN.

Reports rods did not insert.

__A Ilnitiates ARI Runs recirc pumps to minimum speed.

Bypa&sssthe RWM, selects the cram rods and drives them to position 00.

Directs the 1-301-25 valve closed, if necessary.

SIM OP If requested, wait - 3 minutes and close the unit 1-301-25 valve using remote function RD04r (mrf rd04r close) and report valve closed to the RO.

SRO Directs Rx scrammed on rising bearing vibration.

Enters QGA 100 due to failure to scram.

Transitions from QGA 100 to QGA 101 due to rods being out.

Directs ADS inhibited.

Directs Core Spray Pumps placed in PTL.

BOP Reports annunciator 901-7 D-2 and refers to the annunciator procedure.

Reports bearing #12 vibration is rising.

Inhibits ADS.

Places Core Spray Pumps in PTL.

Termination: Taking actions for the ATWS NOTES:

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Appendix D 1

Form ES-D-1 EVENTIPOSITION EVALUATION Event No.(s):

8 Page 9

of 10

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Description:==

Hydraulic ATWS with subsequent trip of 1A EHC pump.

Initiation: Turbine Trip Time Position Applicant's Actions or Behavior SRO Determines Main Steam Lines are open and directs the ANSO to perform QCOP 0250-02.

SIM OP If requested, wait - 2 minutes, perform QCOP 0250-02 using remote function QG09r (mrf qgO9r activate) and report completion to the ANSO.

Determines Rx power > 3% and RPV water level > -35 inches.

Directs termination and prevention of injection with exception of Boron, CRD and RCIC.

Directs RO to report when RPV water level reaches -35 inches.

Directs a level band of-35 to -166 inches.

Directs Mode Switch placed in SHUTDOWN.

Directs ARI initiated.

Directs recirc pumps run to minimum.

Directs recirc pumps tripped once minimum speed is reached.

Directs the RO to perform QCOP 0300-28.<-._

Directs pressure controlled on the bypass valves.

Sim OP When plant conditions are stable or when directed by the Lead Examiner, trip the A EHC pump using malfunction TC05A (imf tc05a).

When bypass valves close, directs reactor pressure maintained 800-1000 psig.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

8 Page 1

of 10 0

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Description:==

Hydraulic ATWS with subsequent trip of 1A EHC pump.

Initiation: Turbine Trip Time Position]

Applicant's Actions or Behavior RO Drives control rods to position 00, spiraling out from the center of the core.

Terminates and prevents feedwater injection by placing FWRVs in manual, closing and closing the FWRV isolation valves. Directs the ANSO to trip HPCI and shutdown th eSSMP if running.

Bypass SDV hig level scram and attempts scram reset.

"Directs jumpers installed to bypass reactor scram.

SIM OP If requested, wait - 2 minutes and bypass reactor scrams using remote function QG08r (mrf qg08r activate) and report completion to the RO.

Resets Rx Scram.

Directs ARI fuses removed if level < -59 inches.

SIM OP If requested, wait -2 minutes and remove ARI fuses using remote function QG14r (mrf qg14r activate) and report completion to the RO.

Directs a rod scram attempted from the individual scram panel. Tries a 2nd from a different bank.

RO/BOP Maintains Rx water level -35 to -166 inches using feedwater4 BOP Performs/directs performed QCOP 0250-02.

Trips recirc pumps.

Reports Bypass valves controlling pressure.

Trip latches HPCI.

Starts Torus Cooling Reports closure of Bypass Valves and cycles ADS valves to maintain reactor pressure 800-1000 psig.

Termination: The scenario is complete when the crew is controlling RPV water level lAW QGA 101 Power/Level Control leg and have worked through QCOP 0300-28 to the point of attempting individual rod insertion.

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Appendix D 1

Form ES-D-1 FACILITY: QUAD CITIES SCENARIO NO: 2 OP-TEST NO: 1 EXAMINERS:

OPE INITIAL CONDITIONS: IC-21,(100%

ower, The following equipment is out of service:

1B Service Water Pump, 1B E1el~ump, 1D RHR pump, 1B Stator Cooling Pump and 1B Instrument Air Compressor OOS, IRM #12 bypassed. Currently Holding Power Constant.

TURNOVER: 912 MWe. The following equipment is out of service: 1B Service Water Pump, 1 B EHC pump, 1 D RHR pump, 1B Stator Cooling Pump and 1 B Instrument Air Compressor OOS, IRM #12 bypassed. Currently Holding Power Constant. TS 3.5.1.A.1 Day 2 of 30 Event Malfunction Event Event No.

Number Type*

Description 1

N/A N -

B, S SSMP Valve Timing (QCOS 2900-03) 2 NM08!

I - R, 5 APRM failure with failure of automatic 1/2 scram.

RP02 3

SWO1 C - B, S Service Water Pump Trip.

4 RD03 C - R, S Rod drift in 1 notch.

5 ior I - B, S RHR Pump inadvertent start dihsl 10021c close 6

MC08 R - R, S Main Condenser air in leakage that requires a power reduction. (PSA identified event) 7 RR1OA M - All Recirc suction line rupture.

8 Batfwlowlow M - All Loss of all RFPs and failure of HPCI leads to RPV Blowdown HP01 at TAF and low pressure system injection. (PSA identified I_

event)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B)- BOP/ANSO Reviewed by:

Facility Author D e/

Date

Appendix D 1

Form ES-D-1 CT #1 -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)

CT #2 - With Reactor pressure greater than shutoff head of the Low pressure system(s) before RPV water level drops to -166", INITIATE emergency depressurization. (BWROG RPV-1.1 LOSS HP INJ E/D TAF)

CT #3 - Action is taken to restore RPV water level above TAF, by OPERATING available low pressure system(s) when RPV pressure decreases below the shut off head of the low pressure system(s). (BWROG RPV-1.2 LOSS HP IND RESTORE RPV LVL).

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.'7 Facility: Quad Cities Scenario No: 2 Op-Test No: 1 Summary: The crew will take the shift at 100% power and perform QCOS 2900-03 SSMP Valve Timing Surveillance. (Normal - BOP, SRO) An APRM will fail upscale with a failure of the automatic 1/2 scram, requiring a manual 11/2 scram and bypassing of the failed APRM. (Instrument, TS - RO, SRO) A Service Water pump will trip, requiring a standby pump to be manually started. (Component - BOP, SRO) A control rod will drift in from 48 to 46, requiring it to be withdrawn back to 48.

(Component - RO, SRO) An RHR pump will inadvertently start, requiring it to be manually tripped and Tech Specs to be addressed. (Instrument, TS - ANSO, SRO)

Air in-leakage will develop in the Main Condenser Boot due to a rupture, requiring power reduction and a reactor scram. (Com ponent, Reactivity-NSO, SRO) A Recirc Suction line will rupture along with a loss of all RFPs and a failure of HPCI, which will result in level reaching TAF and RPV blowdown. (Major - ALL) The scenario ends when the crew has performed an RPV Blowdown and reestablished core cooling with low pressure systems.

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Appendix D 1

Form ES-D-1 Simulator setup:

1. Reset the simulator to IC-21: rst 21

2. Take the following equipment OOS:

I B Service Water Pump in PTL I B Instrument Air Compressor in PTL ID RHR Pump in PTL 1 B Stator Water Cooling pump in PTL 1B EHC Pump in PTL

3. Bypass IRM 12

4. Insert the following malfunctions:

a. Fail the "B" channel of RPS to scram using malfunction RP02 B and D.

(imf rp02b; imf rp02d)

b.

Fail HPCI to autostart using malfunction HP1 1. (imf HPII)

5. Ensure the RWM is setup correctly.

6. Ensure all procedures are erased.

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Appendix D 1

Form ES-D-1 Crew Turnover:

Unit 1 is at approximately 912 MWe and 97% power on the 97% FCL.

Unit 2 is at approximately 912 MWe and 97% power on the 97% FCL.

The following equipment is out of service:

1 B Service Water Pump due to a ground in the motor windings.

1B EHC pump due to a failure of the autostart feature.

1B Stator Water Cooling pump due to overheating.

1 D RHR pump due to a failure of the trip coil. Tech Spec 3.5.1, condition A. 1 entered, Day 2 of 30.

1B Instrument Air Compressor due to a seal water failure.

IRM #12 bypassed due to erratic operation.

Instructions for the shift are to hold load.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

1 Page 1

of 1 0

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Description:==

SSMP Valve Timing (QCOS 2900-03)

Initiation: Crew is directed to perform during shift turnover.

Time Position I

Applicant's Actions or Behavior SRO Directs QCOS 2900-03 performed and performs pre-job brief.

RO Monitors plant parameters.

BOP Opens and times open MO 1/2-2901-7.

Records time.

Verifies MO 1/2-2901-7 opening time meets IST ctiteria.

Closes and times close MO 1/22-2901-7.

Records time.

Verifies MO 1/2-2901-7 closing time meets IST Criteria.

Opens and times open MO 1-2901-8.

Records time.

Verifies MO 1-2901-08 opening time meets IST Ctiteria.

Closes MO 1-2901-8.

Opens and times open MO 2-2901-8.

Records time.

Verifies MO 2-2901-08 opening time meets IST Ctiteria.

Closes MO 2-2901-8.

Directs NLO to perform step H.3 of QCOS 2900-03.

SIM OP As the NLO, report that step H.3 is complete.

Verifies all Acceptance Criteria verification steps are complete.

Signs for completing the surveillance.

SRO Approves the surveillance.

Termination: QCOS 2900-03 is complete.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

2 Page 2

of 1

0

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Description:==

APRM failure with failure of automatic 1/2 scram.

Initiation: When QCOS 2900-03 is complete or when directed by the lead examiner, fail APRM #5 upscale using malfunction NM08e at 100% severity (imf nm08e 100).

Tim Position J Applicant's Actions or Behavior RO Reports annunciators 901-5 A-6, APRM UPSCALE/HIGH and 11 B-11 CHANNEL A/B NEUTRON MONITOR and refers to the procedures.

_-7' Reports APRM #5 indicates upscale.

Verifies rod block occurred.

Reports failure of 1/2 scram on RPS "B".

Inserts 1/2 scram on RPS "B".

BOP/RO Refers to QCOA 0700-03.

RO Stops all reactivity changes and holds power constant.

BOP/RO Refers to QCOP 0700-04.

RO Bypasses APRM #5 and verifies the bpass light comes on.

If desired, bypasses the associatedWRM per' COP 0700-10.

SRO Directs 1/2scram inserted on RPS I*.

Refers to QCOA 0700-03.

_____r_

Directs reactivity changes stopped and power--h-e-d constant.

Refers to QCOP 0700-04 and Tech specs 3.3.1.1 and TRM 3.3.a.

Determines minimum number of APRM channels still available.

Directs APRM #5 bypassed.

NOTE 7

The crew may or may not choose to reset the 1/ scram since this is not a

___19_

required channel.

B 0OP.

Checks for abnormally high LPRM indication.

BO____Monitors plant parameters.

Contacts QNE and Instrument Maintenance.

SIM OP If asked, as the QNE, it is not desired to bypas tPRMs 5 and 8.

Termination PRM 5 has been bypassed.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

3 Page 3

of 1

0

==

Description:==

Service Water Pump Trip.

Time ]Position IApplicant's Actions or Behavior BOP Reports 2B Service Water Pump tripped.

$iAU, YY6 Refers to annunciator procedures QOA 912-1 A-3, B-3 andC3>-._

Starts 2A Service Water Pump. Verifies adequate Service Water System pressure.

Dispatches an operator to investigate 2B Service Water Pump and breaker.

SIM OP

,,.s the NLO sent to investigate 2B Service Water pump trip, wait - 5

______minutes and report 2B Service Water tripped due to overcurrent.

Reports Fire Pumps auto-started. -

\\

_ -Dire-s 0* tcec-e he F l-e*iese -S per QCOP 4100-03.

RO Monitors plant parameters.

SRO Directs start of 2A Service Water Pump.

Refers to QCOA 3900-01 Termination: A standby Service Water pump has been started and the tripped pump is being investigated.

NOTES:

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I, Initiation: When APRM 5 has been bypassed and the 1/2/ scram is reset or when directed by the Ied examiner, trip the 2B Service Water pump using malfunction SW01e. (imf swOle).

)

'2 Si7 ji ii H flb

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

4 Page 4

of 0

==

Description:==

Control Rod drift in 1 notch.

Initiation: When a standby Service Water pump has been started and the tripped pump is being investigated or when directed by the lead examiner, cause control rod 50-15 (N-4) to drift in 1 notch by inserting malfunction RD03 (imf rd03r5015) and deleting malfunction RD03 when control rod 50-15 (N-4) reaches position 45. (dmf rd03r501 5)

Time Position Applicant's Actions or Behavior RO Reports alarm 901-5 A-3, Rod Drift and control rod 50-15 (N-4) drifted in one notch to position 46.

Refers to the annunciator procedure and QCOA 0300-04 and 11.

Stops all control rod movements and reactor recirculation flow changes.

Verifies blue scram light is not lit.

Verifies alarm 901-5 A-1 is not up.

Verifies Drive water pressure is 260-350 psid.nictcqolng water pressure is ~

15 psid.

.7..w e-e Selects control rod 50-15 (N-4,

d moves to position 48.

BOP Refers to the annunciator procedure and M-OA-0300-04 and 11.

Verifies instrument air pressure at 912-1, P1 1-340-20 is > 60 psig.

Dispatches an NLO to verify AO 1-305-127 (Scram Outlet Valve) discharge line is not hot.

SiM OP As the NLO/Field Supervisor sent to check the scram outlet valve discharge line, wait -3 minutes and report the discharge line is cool to the touch. Also report that you found the instrument air supply line to the scram inlet valve leaking at a fitting and you were able to tighten the fitting.

Contacts a QNE SRO Directs RO/BOP to address annunciator 901-5 A-3 and QCOA 0300-04/11.

Refers to Tech Spec 3.1.6 and determines 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to return control rod 50-15 (N-4) to 48 or insert and declare inop.

Directs control rod 50-15 (N-4) returned to position 48.

Termination: Control rod 50-15 (N-4) has been returned to position 48.

NOTES:

N N'

/

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION 1

Event No.(s):

5 Page 5

of 0

==

Description:==

RHR Pump inadvertent start.

Initiation: When control rod 50-15 (N-4) has been returned to position 48 or when directed by the lead examiner, cause an inadvertent start of the 1C RHR pump using override dihsl 10021 c close.

(ior dihs110021c close) When 1C RHR pump is taken to PTL, delete the override.

(dor dihsl 10021c)

Time I

Position Applicant's Actions or Behavior BOP Reports 1C RHR pump auto start and refers to annunciators 901-3 A-5, A-6 and C-15.

Verifies MO 1-1001-18B (RHR Min Flow Valve) is open.

Determines a spurious pump start.

Places 1C RHR pump in PTL.

Directs NLO to 1C RHR Pump breaker.

Notify IMs, EMs, Engineering, and SOS.

SiM OP As the NLO sent to investigate 1C RHR pump breaker, wait - 3 minutes

____.__Fand report no apparent reason for the inadvertent start.

S Directs 1C RHR pump placed in PTL.

Refers to Tech Spec 3.5.1.B and determines Unit 1 has entered a 7 day time clock. Also in Tech Spec 3.6.2.3 and 3.6.2.4 and TRM 3.6a, cond A.

___ RO Monitors plant parameters.

Termination:E 1RHR pump is taken to PTL and is being investigated.

NOTES:

/ 'r-

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION 1

Event No.(s):

6 Page 6

of 0

==

Description:==

Main Condenser air in leakage that requires a power reduction.

Time Position Applicant's Actions or Behavior BOP/RO Reports annunciator 900-54 C-7, Normal Process Flow Hi/Lo.

Checks charcoal adsorber DP and bypasses if > alarm setpoint (900-54 B-6).

Reports alarm 901-7 H-3 up, notes decreasing condenser vacuum on the 901-7 panel and refers to QCOA 3300-02.

Checks for closure of off-gas or SJAE suction valves.

Verifies Steam seal pressure normal.

Verifies Circ Water system operating normal.

Verifies condenser hotwell level normal.

Verifies condenser vacuum breaker is closed and has a water seal.

Dispatches operators to look for vacuum leaks.

SIM OP As the NLO dispatched to look for vacuum leaks, wait - 10 minutes and report that the main condenser boot has an irrepairable rupture in it.

Verifies Rx pressure maintained < 1060 psig, commences a cooldown with ADS valves.

Verifies main Turbine tripped.

Verifies Group 2 and 3 isolations.

RO Reduces recirc flow as necessary to maintain condenser vacuum < 5",

maintaining core flow > 49 MLBM/hr.

Bypasses the RWM and inserts CRAM rods to position 00.

Inserts a Rx scram when vacuum cannot be maintained above 23.5".

Places Mode Switch in Shutdown.

Verifies all rods in.

Maintains RPV water level 0-48".

NOTES:

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yII Initiation: When 1C RHR pump is taken to PTL and is being investigated or when directed by the lead examiner, insert an air leak in the Main Condenser using malfunction MC08. (imf mc08 50 20:)

Appendix D 1

Form ES-D-1 Event No.(s):

6 Page 7

of 1

0

==

Description:==

Main Condenser air in leakage that requires a power reduction. (continued)

SRO Refers to QCOA 3300-02.

Sets scram criteria of 23.5" vacuum. (6.5" Backpressure)

Directs RO to perform QCGP 2-3.

If RPV water level reaches 0", enters QGA 100.

Directs BOP to verify 0" isolations.

Directs RO to maintain RPV water level 0-48".

Directs BOP to maintain RPV pressure < 1060 and commence a cooldown with ADS valves, not to exceed 100 degrees F/hr.

Termination: The reactor is scrammed due to an inability to maintain main condenser vacuum.

NOTES:

LI Initiation: When 1C RHR pump is taken to PTL and is being investigated or when directed by the lead examiner, insert an air leak in the Main Condenser using malfunction MC08. (imf mcO8,w2O:)

-irr

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

7 Page 8

of 1 0

==

Description:==

Recirc suction line rupture.

Initiation: When the reactor has been scrammed due to low Main Condenser vacuum or when directed by the lead examiner, rupture the "A" Recirc loop suction line using malfunction RR1 0a at a severity of.5% ramped over 20 minutes. (imf rrl0a.5 20:)

Time Position Applicant's Actions or Behavior BOP Reports annunciator 901-3 A-16, PRIMARY CONTAINMENT HIGH PRESSURE and refers to the annunciator procedure.

BOP/RO Reports Dywell pressure is 1.55 and rising.

BOP/RO Refers to QCOA 0201-01, INCREASING DRYWELL PRESSURE.

BOPIRO Investigates cause of rising Drywell pressure.

7 BOP/RO Announces evacuation of Rx Building.

BOP Starts 7th Drywell Cooler.

BOP/RO Reports 2.5 psig in Drywell.

SRO Refers to QCOA 0201-01, INCREASING DRYWELL PRESSURE.

Directs BOP/RO to investigate cause of rising Drywell pressure.

Directs evacuation of Rx Building.

Enters QGA 100 and 200 when Drywell pressure reaches 2.5 psig.

"Termination: The scenario ends when the crew has performed an RPV Blowdown and reestablished core cooling with low pressure systems.

NOTES:

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1reni 0FoPrm PS-fl-I EVENT/POSITION EVALUATION Event No.(s):

8 Page 9

of 1 0

==

Description:==

Loss of all RFPs and failure of HPCI leads to RPV Blowdown at TAF and low pressure system injection.

Initiation: When Drywell pressure reaches 2.5 psig, cause a loss of feedwater by inserting a loss of all feedwater pumps using batch file fwlowlow (bat fwlowlow) and reducing the capacity of the condensate pumps using malfunction FW18 at 30% over 10 minutes.

(imf fw18a 30 10:) (imf fw18b 30 10:) (imf fwl8c 30 10:) (imf fw18d 30 10:)

Time Position Applicant's Actions or Behavior RO Reports all Feedwater pumps tripped.

Reports level every 20 inch drop.

Starts 2nd CRD pump.

_ _ _ _ _ Injects SBLC.

Reports level at -142".

BOP Verifies EGDs and Low Pressure ECCS auto start, Group 2 and 3 isolations.

Reports HPCI failed to start, starts manually. After - 1 minute, HPCI trips.

Trip latches HPCI and sends an NLO to investigate.

SIM OP

- 1 minute after HPCI is started, trip HPCI using malfunction HP01.

(imf HP01)

SIM OP As the NLO sent to investigate HPCI, wait - 5 minutes and report that the HPCI Trip Throttle valve linkage is broken. Mech Maint is investigating.

BOP/RO Reports containment parameters.

Starts Torus sprays.

Reports 5 psig in Torus and reports Drywell pressure and temperature.

jj*)

Starts Drywell sprays BOP/RO Starts/verifies RCIC starts for injection.

BOP/RO Starts SSMP for injection to Unit 1.

BOP Inhibits ADS.

Reports Torus level above 5 feet.

'*N erts all ECCS flow to the cor e-Secures all containment sprays/co Opens all 5 ADS valves, and leaves switches in MAN.

I Z Verifies and reports all 5 ADS valves open.

When Rx pressure < 325 psig, verifies all LP ECCS systems inject.

S BOP/RO Maintains RPV water level 0-48 inches.

Sim OP When all injection has been attempted and with concurrence from the Lead Examiner, increase the leak size to.6 modifying malfunction rrt0a (mmfrrlOa.6 1:).

Termination: The scenario ends when the crew has performed an RPV Blowdown and reestablished core cooling with low pressure systems.

Apprendix D 1

• Nrm I::*-N-1

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

8 Page 1

of 1

0 0

==

Description:==

Loss of all RFPs and failure of HPCI leads to RPV Blowdown at TAF and low pressure system injection. (Continued)

Initiation: When Drywell pressure reaches 2.5 psig, cause a loss of feedwater by inserting aa ss of all feedwater pumps using batch file fwlowlow (bat fwlowlow) and reducing the capacity of the condensate pumps using malfunction FW18 at 30% over 10 minutes.

(imf fw18a 30 10:) (imf fw18b 30 10:) (imf fw18c 30 10:) (imf fw18d 30 10:)

Time Position Applicant's Actions or Behavior SRO Directs actions of QGA 100 and 200.

Verifies rx scrammed and all rods in.

Directs BOP to verify isolations and auto starts for 2.5 psig in Drywell.

Directs level maintained with RCIC, HPCI, SSMP, CRD>

Directs Torus sprays started and directs Torus pressure reported when 5 psig.

Directs Drywell pressure and temperature reported.

Verifies Recirc pumps and Drywell coolers off.

Directs Drywell Sprays started.

Directs use of Alternate injection systems, SBLC,.

Directs ADS inhibited.

Determines 2 or more systems available per Detail F.

When level reaches -142", determines a Detail F subsystem is lined up with a pump running.

Determines any injection source is lined up with a pump running.

Enters QGA 500-01 prior to -166".

Determines Torus level above 5 feet.

-__Directs all ECCS flow diverted to the Core.

Directs all 5 ADS valves opened and the switches left in MAN.

_Directs RPV water level restored to 0-48 inches.

Termination: T ~e scenario ends when the crew has performed an RPV Blowdown and reestablished core cooling with w pressure systems.

NOTES:

2 II IL C_!,

L bF-7F

Appendix D 1

Form ES-D-1

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B) - BOP/ANSO Reviewed by:

Facility Author Facility I~presentative t-

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L 0 P FACILITY: QUAD CITIES EOPERATORS:

INITIAL CONDITIONS: -3% Power, Reactor Start-Up In Progress, Mode Switch In Startup/Hot-Standby. The following equipment is out of service: 1 B Service Water Pump, 1B Stator Cooling Pump and 1B Instrument Air Compressor OOS, IRM #12 bypassed.

TURNOVER: Reactor Startup In Progress lAW QCGP 1-1 Step F.6. ad and ae. RWCU reject is ready to be secured and continue pulling rods for startup. The following equipment is out of service: 1 B Service Water Pump, 1 B Stator Cooling Pump and 1 B Instrument Air Compressor 0OS, IRM #12 bypassed.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A N - B, S Secure-RWCU reject 2

N/A R - R, S Pull rods to increase power

,6q NM05 I - R, S IRM failure X3 RD07 C-R, S CRD Pump trip 5

SW06/SW07 C - All Loss of RBCCW/Trip of Recirc Pumps 6

RP05 M - All Reactor Scram with inadvertent Group 1.

7 RD14/CRO2 M - All SDV Volume Rupture/Fuel Failure/QGA 300 RPV Blowdown 8

HV01 C - B, S Failure of Reactor Building Vents to isolate on DW high rads.

Date Date K

SLI 7

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///

SCENARIO NO: 3 OP-TEST NO: 1 EXAMINERS:

(

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Appendix D 1

Form ES-D-1 Facility: Quad Cities Scenario No: 3 Op-Test No: 1 Summary:

The crew will take the shift with the plant at - 3% power and secure RWCU reject blowdown. (Normal - BOP, SRO) The RO will then pull rods to increase power.

(Reactivity - RO, SRO) An IRM will fail while the NSO is pulling rods, requiring a 1/2/2 scram to be inserted. (Instrument, TS - RO, SRO) A CRD pump will trip, requiring the standby CRD pump to be started. (Component - RO, SRO) A total loss of RBCCW will occur, requiring the Recirc pumps to be tripped (Component - All) and a Rx scram to be inserted. When the scram is inserted, an inadvertent Group 1 isolation will occur. (Major - All) A fuel failure and Scram Discharge Volume rupture that cannot be isolated will occur on the Rx Scram that leads to an RPV Blowdown on 2 areas above max safe rads. (Major - All) After the Blowdown, a Drywell High High Rad alarm will come in with a failure of the RB Vents to isolate, requiring them to be manually isolated. (Instrument, TS - BOP, SRO)The scenario will be complete when the crew has completed the RPV blowdown and isolated Reactor Building Vents or at the discresion of the lead examiner.

CT #1 - The crew will recognize a failure of the Reactor Building Vents to isolate and manually isolate them using the control switch on the 912-1 Pnl.

CT #2 - The crew will recognize a trip of both recirc pumps and insert a manual reactor scram.

CT #3 - With a primary system discharging into the secondary containment and area radiation/temperature/water levels exceed maximum safe levels in more than one area of the same parameter, INITIATE an emergency depressurization. (BWROG SC-1.2 LOCA SC E/D) i1 K -q

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Appendix D 1

Form ES-D-1 Simulator setup:

1. Reset the simulator to IC-15: rst 15

2. Insert control rods until rod step 17 is at target in.

3. Take the following equipment OOS:

I B Service Water Pump in PTL 1 B Instrument Air Compressor in PTL 1 B Stator Water Cooling pump in PTL

4. Bypass IRM 12

5.

Insert the following malfunctions:

a. Fail the Reactor Building Vents to isolate using malfunction HV01.

(imf hv01)

b. Verify batch file 1oct01 02a contains the following:

imf rdl4a 100 10:

ior dihs10590303 norm imf cr02 10 8:

imf rmO106 (none 4:) 40 10:

imf rmO108 (none 4:) 40 10:

imf rm0109 (none 4:) 40 10:

imf rm0111 40 10:

imf rm0112 40 10:

imf rmO113 40 10:

c. Assign trigger 2 to its default: trg 2 E2 and then assign a Group 1 isolation to occur when RPS B is deenergized using malfunction RP05.

(imf rpO5a(2); imf rpO0b(2); imf rpO0c(2); imf rpO'd(2))

d. Bypass IRM 12.

6. Ensure the RWM is setup correctly.

7. Ensure all procedures are erased.

-, L 7 FFi

Appendix D 1

Form ES-D-1 Crew Turnover:

Unit 1 is at approximately 3% power with a Rx startup in progress. The reactor is critical, 1 Bypass valve open, Containment is deinerted. Ready to pull rod step 17. Currently in QCGP 1-1, step F.6, ad and ae Unit 2 is at approximately 912 MWe and 97% power on the 97% FCL.

The following equipment is out of service:

1B Service Water Pump due to a ground in the motor windings.

1B Stator Water Cooling pump due to overheating.

1 B Instrument Air Compressor due to a seal water failure.

IRM #12 bypassed due to erratic operation Instructions for the shift are to secure RWCU reject and continue the startup by pulling control rods in preparation for placing the Mode Switch in RUN

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Appendix D 1

Form ES-D-1 NOTES:

ti EVENT/POSITION EVALUATION Event No.(s):

1 Page 1

of 9

==

Description:==

Secure RWCU reject Initiation: The crew is directed to secure RWCU reject during shift turnover.

Time Position Applicant's Actions or Behavior SRO Directs RWCU reject secured.

RO Monitors plant parameters.

BOP Secures RWCU reject per QCOP 1200-07.

Closes FCV 1-1239, CU REJECT FCV Closes MO 1-1201-78, REJECT TO CNDSR SHUTOFF VLV.

Verifies reject flow indicates 0.

Open MO 1-1201-80, RETURN ISOL VLV as necessary to maintain RWCU pump discharge pressure 100 to 200 psig greater than reactor pressure.

Termination: RWCU reject is secured.

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

2 Page 2

of 9

==

Description:==

Increase power by pulling control rods.

Initiation: RWCU reject is secured and the US orders power ascension.

Time Position Applicant's Actions or Behavior SRO Directs rod pulls to continue startup.

Conducts pre-job brief. (May have been done prior to crew taking shift).

BOP Monitors Balance of plant parameters.

RO Refers to QCGP 4-1.

Verifies rods in step 16 are at target out.

Selects the desired control rod.

Verifies the selection of the proper control rod, its present position and bounds on the RWM.

Communicates to QIV "Ready to move rod xx-yy from position __ to QIV Rod xx-yy is selected, understanding moving xx-yy from position to RO That's correct.

Performs another self check.

Moves control rod to desired position.

When all rods in the step are at target out, verifies with the QIV that each control rod is at its desired position.

Fills out the rod sequence sheet.

Repeats for subsequent steps as necessary.

Termination: When a discernable increase has been noted or as directed by the lead examiner.

NOTES:

Appendix D Form ES-D-1 EVENT/POSITION EVALUATION(

Event No.(s):

3 Page 3

of [ 9

==

Description:==

IRM failure Initiation: When rod pulls are complete or directed by the Lead Examiner, fail irm 11do~ns S

using malfunction NM05a at 0% severity. (imf nm05a 0) 14,

5 H,4 (,L -

Time Position Applicant's Actions or Behavior

&09,0 RO Reports annunciator 901-5 C-5, IRM DOWNSCALE and refers to the annunciator procedure.

Reports IRM #11 indicates downscale.

Verifies rod block occurred.

Inserts 11/2 scram on RPS channel "A".

BOP/RO Refers to QCOA 0700-03.

RO Stops all reactivity changes and holds power constant.

BOP/RO Refers to QCOP 0700-04.

SRO Refers to QCOA 0700-03.

Directs reactivity changes stopped and power held constant.

Refers to QCOP 0700-02 and Tech specs 3.3.1.1.

Determines minimum number of IRM channels NOT available.

Directs a 1/2 scram inserted on RPS channel "A"

,4,

/2I BOP Monitors plant parameters.

Contacts QNE and Instrument Maintenance.

Termination: IRM 11 is bypassed and the 1/2 scram is inserted.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

4 Page 4

of 9

==

Description:==

CRD pump trip Initiation: When the 1/2 scram is inserted or when directed by the lead examiner, trip the "A" CRD pump using malfunction RD07a. (imf rd07a)

Time Position Applicant's Actions or Behavior RO Reports annunciators 901-5 A-2, CRD PUMP TRIP and F-2, CRD CHARGING WATER LOW PRESSURE and refers to procedures.

Verifies closed MO 1-301-2B, 1B PMP DISCH VLV for 1B CRD pump.

Starts 1B CRD pump.

Verifies Steady-state current < 34 amps on 1-302-1 B.

Throttles MO 1-301-2B discharge valve to maintain 1400-1500 psig.

Closes MO 1-301-2A, discharge valve on the tripped pump.

Dispatches an NLO to check operation of the running pump and investigate the tripped pump.

Directs an NLO to close 1-301-254A (Min flow valve) for the tripped pump and open 1-301-254B (Min flow valve) for the running pump.

SIM OP As the NLO sent to the CRD pumps, report 1 B CRD pump post start checks are sat, 1-301-254B is open, 1-301-254A is closed and 1A CRD pump tripped on overcurrent.

BOP/RO Refers to QCOA 0300-01.

BOP Monitors plant parameters.

SRO Refers to QCOA 0300-01.

1 Directs start of standby CRD pump.

Refers to TS 3.1.5 - If more than 1 accumulator alarm is received with Rx pressure > 900 psig, directs charging header pressure restored within 20 minutes.

Termination: "B" CRD pump has been started and CRD system parameters are returned to normal.

NOTES:

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

5 Page 5

of 9

==

Description:==

Loss of RBCCW Initiation: When "B" CRD pump has been started and CRD system parameters are returned/being returned to normal or when directed by the lead examiner, simulate a leak in the RBCCW system by reducing the capacity of the 1 B RBCCW pump using malfunction SW07a to 85% reduced capacity over 5 minutes. (imf sw07b 85 5:) After 1 minute, override annunciator 912-1, F-1 on to simulate RBCCW expansion tank low level. (imf ano9121fl on) After 2 minutes, override annunciator 9014c18 on to simulate Rx Building Floor Drain Sump High Level. (imf ano9014c18 on)

After 3 minutes, trip the "A" RBCCW pump using malfunction SW06a. (imf sw06a)

Time Position Applicant's Actions or Behavior BOP Reports annunciator 912-1 D-1 RBCCW Low Pressure and refers to the proc.

Checks PI 1-3740-4, DISCH HDR PRESS and determines Unit 1 RBCCW discharge press is 40 psig and dropping.

Directs-ar NLO to line up the /2 RBCCW pump to Unit 1 and investigate RBCCW low pressure on unit 1.

SIM OP As the NLO sent to RBCCW, wait - 4 minutes,,an on the suction piping for the RBCCW pump askedvou can isolate it.

,/

""f JP Refers to QCOA 3700-01.

BOP/RO Monitors Recirc pump seal cooling temp and flow.

SIM OP When the crew is monitoring recirc seal temps, trip the "B" RBCCW pump using malfunction SW06. (imf sw06b)

Reports annunciators 901-4 G-3 and G-7, Recirc pump A and B Seal Cooling Water low flow and refers to the procedure.

Directs NLO to remove RWCU Filter Demins from service and stops the RWCU pumps.

BOP Closes MO 1-3701, U-1 RBCCW HDR ISOL.

Reports annunciator 912-1 C-1, RBCCW pump trip and reports a trip of 1A RBCCW pump trip and RBCCW discharge pressure - 20 psig and dropping.

RO Monitors plant parameters.

Inserts a Rx Scram.

RO/BOP Trips the recirc pumps and refers to QCOA 0202-05.

SIM OP When actions for low RBCCW flow are completed, trip 1B RBCCW pump I using malfunction sw06b (imf sw06b).

NOTES:

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Appendix 0 1

Form ES-D-1 NOTES:

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i Li /L LI Event No.(s):

5 Page 6

of 9

==

Description:==

Loss of RBCCW (continued)

Initiation: When "B" CRD pump has been started and CRD system parameters are returned/being returned to normal or when directed by the lead examiner, simulate a leak in the RBCCW system by reducing the capacity of the 1 B RBCCW pump using malfunction SW07a to 85% reduced capacity over 5 minutes. (imf sw07b 85 5:) After 1 minute, override annunciator 912-1, F-1 on to simulate RBCCW expansion tank low level. (imf ano9121fl on) After 2 minutes, override annunciator 9014c18 on to simulate Rx Building Floor Drain Sump High Level. (imf ano9014c18 on)

After 3 minutes, trip the "A" RBCCW pump using malfunction SW06a. (imf sw06a)

SRO Refers to QCOA 3700-01.

Direc*s seal temps and flow monitored.

Directs RWCU stopped and MO 1-3701 closed.

Directs Rx scrammed.

Directs Recirc pumps tripped and refers to QCOA 0202-05.

Termination: Reactor Recirc pumps are tripped.

Appendix D I

Form ES-D-1 V.i-\\

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

6 Page 7

of 9

==

Description:==

Reactor Scram with Inadvertent Group 1 Isolation Initiation: Failure of RBCCW/Trip of Recirc Pumps Time Position Applicant's Actions or Behavior RO Depresses Scram pushbuttons.

Places Mode Switch in Shutdown.

Verifies and reports all rods in.

Maintains RPV water level 0-48".

BOP/RO Maintains RPV pressure < 1060 psig.

RO Verifies SRMs/IRMs insert.

Verifies Main Turbine tripped.

Verifies alarm 901-8 H-9, EXCITER FIELD BRKR OPEN is lit.

SRO Directs Rx scrammed and QCGP 2-3 entered.

Directs RPV water level maintained 0-48".

Directs RPV pressure maintained < 1060 psig and RPV cooldown < 100 degrees F/hr.

Directs QCOA 0202-05, Trip of Both Recirc Pumps performed.

BOP/RO Reports all MSIVs closed.

BOP Performs RPV cooldown at < 100 degrees F/hr.

BOP/RO Refers to QCOA 0202-05.

Termination: Mode Switch in SHUTDOWN and RPV water level being controlled.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

7 Page 8

of 9

==

Description:==

SDV Rupture/Fuel Failure/QGA 300 RPV Blowdown Initiation: When the reactor scram is inserted, insert batch file 1oct01 02a to simulate a SDV rupture, a fuel failure and a failure of the scram reset switch. (bat Ioct0102a)

Time Position Applicant's Actions or Behavior BOP Reports annunciator 901-3 A-1 Rx BDG Hi Rad and refers to the ann. Proc.

Reports alarming area in the Rx BLDG to the SRO.

Evacuates affected areas.

Dispatches an operator and Rad Protection to investigate.

Directs RP to set up access control.

SIM OP As the operator sent to investigate hi rads, wait - 3 minutes and report a lot of steam and water in the vicinity of the North SDV.

Refers to QCOA 0201-05 and 1800-01 Monitors and reports rad levels.

Reports torus level > 5 feet.

Opens all 5 ADS valves and leaves switches in MAN.

Verifies and reports all 5 ADS valves open.

RO Attempts to isolate the leak by resetting the Rx scram lAW QCOP 0500-02.

Reports the scram will not reset.

SRO Enters QGA 300.

Directs Unit 1 DGCWP started.

SiM OP As the NLO directed to start the U-1 DGCWP, wait - 3 minutes and start the pump using remote function SW 10. (mrf swi0r RUN)

Directs Rx BLDG Basement water levels checked.

SiM OP As the NLO sent to check Rx Bldg water levels, wait - 5 minutes and report that access is not allowed to the Rx Bldg Basement.

Directs scram reset if not attempted.

When it has been determined that a system is discharging into the RX BLDG, cannot be isolated and one-area > Max Safe, enters QGA 100 When 2 areas > Max Safe, enters QGA 500-1 Determines Torus level above 5 feet.

Directs all ECCS flow diverted to the Core.

Directs all 5 ADS valves opened and the switches left in MAN.

Termination: The scenario will be complete when the crew has completed the RPV blowdown.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION NOTES:

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Event No.(s):

8 Page 9

of 9

==

Description:==

Reactor Building Vents fail to isolate when Drywell High High Radiation alarms.

Initiation: Drywell High High Radiation alarms after the Reactor Blowdown.

Time Position Applicant's Actions or Behavior BOP Reports annunciators 901-55 and 56 A-1, DRYWELL HIGH HIGH RAD CONC and refers to the annunciator procedure.

Verifies Group 2 isolation.

Notes failure of Unit 1 Reactor Building Vents to isolate and manually isolates.

Reports failure of Reactor Building Vent isolation to the US.

Contacts maintenance to investigate the failure of Reactor Building Vents to isolate.

US Directs Unit 1 Reactor Building Vents isolated.

RO Monitors plant parameters.

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1 1-1 1-Termination: Reactor Building Vents are isolated.

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Appendix D 1

Form ES-D-1

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B) - BOP/ANSO Reviewed by:..

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Facilit., 'Representative ate Date Date I

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Facility: Quad Cities Scenario No: 4 OD-Test No: I Examiners:

Initial Conditions: - 700 MWe, 75% power, 1A RHR Loop and 11B Service Water Pump OOS. B SBGT running for monthly surveillance.

Turnover: The following equipment is out of service: 1A RHR loop and 1 B Service Water Pump.

B SBGT is running for the monthly surveillance per QCOS 7500-05 and is ready to be shutdown per step H.2.p.

Event Malfunction Event Event No.

Number Type*

Description I

N/A N - B, S Shutdown SBGT 2

RR01 R-R, S Insert Control Rods to exit the instability region due to recirc drive motor breaker trip.

3 RD02 C - R, S Stuck control rod.

4 EG05 C - B, S Stator Cooling Pump Trip with failure of the Standby to auto start.

5 AD01 I - B, S ADS valve fails open due to setpoint drift - Rx scram 6

RP02/RP03 I - R, S Control rods fail to insert on manual scram - initiate ARI.

(PSA identified event) 7 MS05/RP05 M - All Steamline break in Drywell with a Group I.

8 Ior M - All Failure of Drywell Sprays and Cooling leads to RPV zdishl 1001S blowdown and flooding. (PSA identified event) 17(B)1 Bat DWCLRTRIP Failt: Quad Cities Scenario No: 4 Op-Test No: 1 Operators:

Appendix D 1

Form ES-D-1 The crew will take the shift with SBGT running. The surveillance is complete and needs to be shutdown. (Normal - BOP, SRO) After this, a Recirc Pump drive motor breaker will trip, requiring the RO to insert cram rods. (Reactivity manipulation, TS RO, SRO) While inserting cram rods, one of the rods will stick, requiring drive water pressure to be raised in order to drive it. (Component, - RO, SRO) When they have inserted cram rods/exited the instability region, the running Stator Water Cooling Pump will trip and the standby will fail to auto start, requiring it to be manually started. (Component - BOP, SRO). An ADS valve will fail open and will not close when attempted manually, (Instrument, TS - BOP, SRO) requiring a manual scram to be inserted. When the manual scram pushbuttons are depressed, no rod movement will occur, requiring initiation of ARI to insert the rods. (Instrument - RO, SRO) After the rods are inserted, a steamline break will occur in the Drywell with an inadvertent Group 1 isolation. Coupled with a failure of Drywell Sprays and Cooling, this will lead to an RPV Blowdown and RPV Flooding. (Major - All) The scenario will be completed when the crew has identified the requirements to determine the Main Steam Lines are flooded.

CT #1 - Crew will recognize instabilities region has been entered and insert control rods to exit instabilities.

CT #2 - When Torus Pressure cannot be maintained below PSP curve and/or drywell temperature cannot be restored or held below 280'F, INITIATE emergency depressurization. below 2800F, INITIATE emergency depressurization.

CT #3 - When RPV level cannot be determined, INJECT into the RPV to maintain RPV flooded to the Main Steam Lines. (BWROG RPV-2.2 LOSS LVL INST MRPVFP)

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Scenario No: 4 Op-Test No: 1

Appendix D 1

Form ES-D-1 Simulator setup:

1. Reset the simulator to IC-20: rst 20

2. Take the following equipment OOS: 11B Service Water Pump in PTL 1A RHR Loop 1A RHR Pump in PTL 1B RHR Pump in PTL Verify the following valves CLOSED and THEN override their lights off MO-1-1001-43A (ior lohsl 100143al off)

MO-1-1001-43B (ior lohsl 100143bl off)

MO-I-1001-7A (ior lohsl 10017al off)

MO-1-1001-7B (ior lohsl 10017bl off)

MO-1-1001-19B (ior lohsl 100119al off)

Verify the following valves CLOSED, leave the hand switches in NEUTRAL and THEN open the valve breakers:

MO-1-1001-18A (mrf rhl7ar open)

MO-1-1001-19A (mrf rh18ar open)

MO-1-1001-23A (mrf rh19ar open)

MO-1-1001-26A (mrf rh20ar open)

MO-1-1001-28A (mrf rh21ar open)

MO-1 -1001 -29A (mrf rh22ar open)

MO-1 -1001 -34A (mrf rh23ar open)

3. Insert the following malfunctions:

a. Fail both channels of RPS and ATWS to scram using malfunction RP02 A - D and RP03 A,B.

(imf rp02a; imf rp02b; imf rp02c; imf rp02d; imf rp03a; imf rp03b)

b.

Fail the "B" Stator Water Cooling pump to autostart by overriding it off.

(ior dihsl5300scpb trip)

c.

Fail the "B" RHR Loop S-17 switch by overriding it off. (ior dihs11001s17b off)

d. Assign trigger 15 to DWCLRATRP. (trg 15 DWCLRATRP)

e. Cause the DW Coolers to trip when trigger 15 goes true by inserting batch file DWCLRTRP. (bat DWCLRTRP)

f.

Override the "A" RHR Pump discharge pressure gauge downscale.

(ior aopi110402a 0)

g. Override the RHR DISCH HDR PRESS HI/LO alarm on the 901-3 panel ON.

(imf an9013c8 on)

4. Start the "B" train of SBGT lAW QCOS 7500-05 step H.2.c - e.

5. Ensure the RWM is setup correctly

6. Ensure all procedures are erased.

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Appendix D 1

Form ES-D-1 Crew Turnover:

Unit 1 is at approximately 700 MWe and 76% power on the 92% FCL.

Unit 2 is at approximately 912 MWe and 97% power on the 97% FCL.

The following equipment is OOS:

1 B Service Water Pump due to a ground in the motor windings. Electrical Maintenance is investigating.

1A RHR Loop is OOS for packing replacement on the 1-1001-66A valve.

Day 1 of 7, TS 3.5.1, Condition B, LPCI Subsystem A Inop.

Day 2 of 3, TS 3.5.1, Condition D, Both LPCI Subsystems Inop.

Day 2 of 30, TS 3.5.1, Condition A, RHR Pump Inop.

Day 1 of 7, TS 3.6.2.3, Condition A, A Loop RH R Suppression Pool Cooling Inop.

Day 1 of 7, TS 3.6.2.4, Condition A, A Loop RH R Suppression Pool Sprays Inop.

Day 1 of 7, TRM 3.6.a, Condition A, A Loop RHR Drywell Sprays Inop.

Instructions for the shift are to hold load.

QCOS 7500-05, SBGTS MONTHLY OPERABILITY TEST is complete through step H.2.o, has been running for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and is to be shutdown when you take the shift.

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

1 Page 1

of 10

==

Description:==

Shutdown SBGT Initiation: The crew is directed during the shift turnover to shutdown SBGT.

Time Position Applicant's Actions or Behavior SRO Directs "B" SBGT Train secured.

Approves the surveillance.

RO Monitors plant parameters.

BOP Refers to QCOS 7500-05.

Places the "B" train 1/2 SBGTS TRAIN MODE SELECTOR SWITCH in B OFF.

Announces alarm 912-5 B-6 SBGT trouble.

Places '/2 B SBGTS TRAIN MODE SELECTOR SWITCH to B PRIM.

Records SBGT B run time and verifies > 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Verifies X2 - 7505B INLET DAMPER closed.

Verifies _' - 7504B TURB BLDG CLG AIR DMPR open.

Verifies '/ - 7503B SBGTS AIR HTR off.

Verifies X2 - 7506B 1/ SBGTS FAN off.

Verifies _2 - 7507B SBGTS FAN DISCH DMPR closed.

Verifies all applicable SBGTS annunciators are cleared.

Verifies '/2 B SBGTS TRAIN MODE SELECTOR SWITCH in B PRIM.

Verifies 'A A SBGTS TRAIN MODE SELECTOR SWITCH is in A STBY.

Signs off surveillance performance.

Termination: SBGT shutdown per QCOS 7500-05.

NOTES:

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Appendix D I

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

2 Page 2

of 10

==

Description:==

Insert Control Rods to exit the instability region due to recirc drive motor breaker trip.

Initiation: When SBGT shutdown is complete per QCOS 7500-05 or when directed by the lead examiner, trip the "A" Recirc Pump Motor breaker using malfunction RR01a. (imf rr01a)

Time Position Applicant's Actions or Behavior LL

• l BOP/RO Reports annunciator 901-4 A-9, RECIRC SETS DRIVE MOTOR AUTO TRIP BOP Refers to the annunciator procedure.

Reports 1A Recirc MG tripped.

Verifies "B" Recirc pump speed < 78% and motor current < 724 amps.

BOP/RO Refers to QCOA 0202-04.

Refers to QCOA 0400-02.

Closes MO 1-202-5A and reopens after at least 5 minutes.

Monitors loop delta-T and RPV bottom head temperature.

Contacts QNE.

Monitors Off-Gas rad levels and refers to QCOA 1700-04.

Performs QCOS 0202-09 for single loop ops.

RO Monitors for power oscillations.

Bypasses the RWM.

//______Continuously inserts all CRAM rods to position 00.

Continues to insert control rods to target in until power has stopped increasing and FCL < 59.4%.

Continues to monitor for power oscillations.

Completes QCOP 0207-02 to document bypassing the RWM.

SRO Directs the RO to monitor for power oscillations.

Refers to QCOA 0202-04.

Directs CRAM rods driven to position 00.

Directs control rods inserted to target in until power has stopped increasing and FCL < 59.4%.

Refers to QCOA 0400-02.

Directs QCOS 0202-09 performed.

Refer to TS 3.4.1. and declares A Recirc Loop not in operation within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Termination: Instability region is exited.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

3 Page 3

of 10

==

Description:==

Stuck Control Rod Initiation: When the last cram rod is being driven, stick it at position2'Wusing malfunction RD02.

(imf rd02rxxyy 50)

Time Position Applicant's Actions or Behavior RO Repopts that rod xx-yy is stuck at position 24 Refers to QCOA 0300-02.

Verifies no Control Rod Block or RWM Select Block exist and Control Rod xx-yy is selected.

Throttles MO 1-302-8, U-1 CRD DRIVE WTR PCV to increase drive water pressure in 50 psid increments to a maximum of 400 psid.

Drives the Control Rod to position 00 after Drive Water pressure is > 350 psid.

Returns Drive Water pressure to 260 - 350 psid.

BOP Monitors plant parameters and continues actions for a tripped Recirc pump.

Contacts QNE.

SRO Refers to QCOA 0300-02.

Directs RO to investigate cause of stuck Control Rod.

May refer to TS 3.1.3. - Control Rod is not considered stuck for Bases 3.1.3-3.

SIM OP If asked as Ops Management, direct I B RFP secured.

Termination: The stuck control rod is driven to 00.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

4 Page 4

of 10

==

Description:==

Stator Cooling Pump Trip with failure of the Standby to auto start.

Initiation: When the stuck control rod is driven to 00 or when directed by the lead examiner, trip the "A" Stator Cooling Water Pump using malfunction EG05a. (imf egO5a)

Time Position Applicant's Actions or Behavior BOP/RO Reports annunciator 901-7 B-10, STATOR COOLING PUMPS AUTO TRIP.

Starts the 1 B Stator Cooling Water pump.

SiM OP When the 1 B Stator Cooling Water Pump is given a start signal, delete override DIHS15300scpb. (dor dihs15300scpb)

Refers to annunciator procedure.

Dispatches an operator to check Stator Cooling Water parameters and the tripped Stator Cooling Water pump.

Directs Electrical Maintenance to investigate failure of 1 B Stator Cooling Water pump to auto start.

RO Monitors plant parameters.

SRO Refers to QCOA 5300-01.

Directs 1 B Stator Cooling Water pump started.

Termination: The "B" Stator Water Cooling pump has been manually started and the trip of the "A" Stator Water Cooling pump is being investigated.

NOTES:

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Appendix D 1

Form ES-D-1 EVENTIPOSITION EVALUATION Event No.(s):

5 Page 5

of 10

==

Description:==

ADS valve fails open due to setpoint drift - Rx scram Initiation: When the "B" Stator Cooling Water pump has been manually started and the trip of the "A" Stator Water Cooling pump is being investigated or when directed by the lead examiner, cause the "E" relief valve to spuriously open using malfunction AD01 e at 0% severity and stick open using malfunction ad07e at 100% severity. (imf adOle 0) (imf ad07e 100)

Time Position Applicant's Actions or Behavior BOPIRO Reports annunciators 901-3 E-13, E-14 and E-16 and refers to the annunciator procedures.

Determines "E" Relief Valve open by use of the Acoustic monitor.

Places the Key Switch for "E" Relief Valve in OFF.

Reports "E" Relief Valve did not close, attempts to close by cycling the Key Switch between MAN and AUTO.

Scrams the reactor and enters QCOA 0203-01 at SUBSEQUENT OPERATOR ACTIONS.

Determines "E" Relief Valve solenoid can be deenergized with the keylock switch.

Starts Torus cooling.

Monitors torus temperature.

Monitors Recirc loop temps, Reactor shell and flange temps and continues to attempt to close "E" Relief Valve.

RO Monitors plant parameters.

SRO Refers to QCOA 0203-01.

Directs the BOP to attempt to close "E" Relief Valve.

Directs the RO to insert a Manual Reactor Scram.

Refers to TS 3.5.1 and directs plant shutdown.

Termination: The crew has attempted to close "E" relief valve.

NOTES:

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

6 Page 6

of 10

==

Description:==

Control rods fail to insert on manual scram - initiate ARI.

Initiation: RO attempts manual Rx scram due to "E" relief valve sticking open.

Time Position Applicant's Actions or Behavior RO Inserts a manual reactor scram.

Places the Mode Switch in SHUTDOWN.

Reports no rod motion.

Manually initiates ARI.

Runs Recirc pumps to minimum.

Reports control rods are inserting.

Reports all Control Rods are inserted.

BOP Monitors plant parameters.

Inhibits ADS.

Places Core Spray Pumps in PTL.

SRO Enters QGA 100 on failure to scram.

Determines rods are > 04 and the reactor will not stay shutdown per QNE.

Enters QGA 101.

Directs ADS inhibited.

Directs Core Spray pumps placed in PTL.

Returns to QGA 100 when all control rods are inserted.

Termination: The RO has manually initiated ARI and all control rods are inserted.

NOTES:

Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

7 Page 7

of 10

==

Description:==

Steamline break in Drywell with a Group I.

Initiation: When the control rods are inserted tor'whohn *"di.....by.

~u4wmi, insert a steam line break in the Drywell using malfunction MS04c at 2% severity over 20 minutes (imf ms04c 2 20:)

and insert an inadvertent Group 1 isolation using malfunction RP05.

(imf rp05a; imf rp05b; imf rpO5c; imf rp05d)

Time Position Applicant's Actions or Behavior BOP/RO Reports closure of MSIVs BOP/RO Controls RPV pressure as directed by SRO BOP/RO Reports annunciator 901-3 A-16, PRIMARY CONTAINMENT HIGH PRESSURE and refers to the annunciator procedure.

BOP/RO Reports Dywell pressure is 1.55 and rising.

BOP/RO Refers to QCOA 0201-01, INCREASING DRYWELL PRESSURE.

BOP/RO Investigates cause of rising Drywell pressure.

BOP/RO Announces evacuation of Rx Building.

BOP Starts 7th Drywell Cooler.

BOP/RO Reports 2.5 psig in Drywell.

BOP Reports containment parameters.

Attempts to start Torus sprays, reports Torus Sprays will not start and directs NLO to manually open the MO 1-1001-34B valve.

SIM OP As the NLO sent to open the MO 1-1001-34B valve, wait 5 minutes and deenergize the MO 1-1001-34B valve breaker using remote function RH23br. (mrf rh23br open) Wait 10 more minutes and open the MO 1-1001-34B valve using remote function RH33br. (mrf rh33rb open)

Termination: The crew is taking actions in QGA 200 to address rising containment pressure and temperature.

NOTES:

Appendix D Form ES-D-1 Time Position Applicant's Actions or Behavior SRO Refers to QCOA 0201-01, INCREASING DRYWELL PRESSURE.

Directs BOP/RO to investigate cause of rising Drywell pressure.

Directs evacuation of Rx Building.

Enters QGA 200 and re-enters QGA 100 when Drywell pressure reaches 2.5 psig.

Directs BOP to verify isolations and auto starts for 2.5 psig in Drywell.

Directs level maintained 0-48 inches.

Directs Torus sprays started and directs Torus pressure reported when 5 psig.

Directs Torus sprays started locally.

Directs Drywell pressure and temperature reported.

Verifies Recirc pumps and Drywell coolers off.

Directs Drywell Sprays started.

Directs Drywell sprays started locally.

Establishes blowdown criteria for torus pressure and drywell temperature.

Termination: The crew is taking actions in QGA 200 to address rising containment pressure and temperature.

NOTES:

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EVENT/POSITION EVALUATION Event No.(s):

7 Page 8

of 10

==

Description:==

Steamline break in Drywell with a Group I. (Continued)

Initiation: When the control rods are inserted

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insert a steam line break in the Drywell using malfunction MS04c at 2% severity over 20 minutes (imf ms04c 2 20:)

and insert an inadvertent Group 1 isolation using malfunction RP05.

(imf rp05a; imf rp05b; imf rp05c; imf rp05d)

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Appendix D 1

Form ES-D-1 EVENT/POSITION EVALUATION Event No.(s):

8 Page 9

of 10

==

Description:==

Failure of Drywell Sprays and Cooling leads to RPV blowdown and flooding.

Initiation: Verify that trg 15 goes active when the crew trips the "A" DW Cooler and that batch file DWCLRTRP has gone active, preventing the DW Coolers from being restarted.

Time Position Applicant's Actions or Behavior BOP Reports 5 psig in Torus and reports Drywell pressure and temperature.

Attempts to start Drywell sprays, reports Drywell Sprays will not start and directs NLO to manually open the MO 1-1001-23B valve.

SIM OP As the NLO sent to open the MO 1-1001-23B valve, wait 5 minutes and deenergize the MO 1-1001-23B valve breaker using remote function RH20br. (murf rh20br open) Wait 3 more minutes and report back that you cannot get the MO 1-1001-23b valve open due to the limitorque operator failing to engage.

Attempts to restart Drywell coolers, reports that Drywell coolers will not start.

Reports Torus pressure rise and drywell temp every 20 degree F rise.

Reports when blowdown criteria is met.

Reports Torus level above 5 feet.

Opens all 5 ADS valves and leaves switches in MAN.

SIM OP When all 5 ADS valves are open, modify malfunction ms04c to a 12%

steam leak over 1 minute. (mmf ms04c 12 1:)

Verifies and reports all 5 ADS valves open.

When Rx pressure < 325 psig, verifies RHR and CS injection valves open.

BOP/RO Diverts ECCS flow as necessary to maintain RPV water level 0-48 inches.

RO Monitors for saturation conditions.

Reports saturation conditions met.

SIM OP When saturation conditions are met, insert batch file seqflash (batseqflash5then6) to cause level instruments to fail upscale.

Reports all level instruments read upscale.

Reports Torus level >5 feet.

Reports 0 ADS valves open.

Reports Feed Pump is available.

Verifies MSIVs, Main Steam Line Drains, RCIC and HPCI isolated.

Injects to flood the RPV.

Monitors for flooding conditions met.

Termination: The crew has identified the requirements to determine the Main Steam Lines are flooded.

-- NOTES:

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m Fi Frm Fi -fl-i EVENT/POSITION EVALUATION Event No.(s):

8 Page of 10 0

==

Description:==

Failure of Drywell Sprays and Cooling leads to RPV blowdown and flooding.

(Continued)

Initiation: Verify that trg 15 goes active when the crew trips the "A" DW Cooler and that batch file DWCLRTRP has gone active, preventing the DW Coolers from being restarted.

Time Position Applicant's Actions or Behavior SRO Enters QGA 500-01.

Determines Torus level above 5 feet.

Directs all ECCS flow diverted to the Core.

Directs all 5 ADS valves opened and the switches left in MAN.

Directs RPV water level restored to 0-48 inches.

Directs RO to monitor for saturation conditions.

Declares RPV water level unknown.

Enters QGA 500-4.

Determines all rods in.

Directs all 5 ADS valves opened.

Determines 0 ADS valves open.

Determines Feed Pump is available.

Directs MSIVs, Main Steam Line Drains, RCIC and HPCI isolated.

Directs injection to flood the RPV.

Directs conditions monitored to meet flooding conditions.

Termination: The crew has identified the requirements to determine the Main Steam Lines are flooded.

NOTES:

Appenuix U I

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