ML051610364

Initial Submittal of the Scenarios for the Quad Cities Initial Examination - May 2005

ML051610364
Person / Time
Site:	Quad Cities
Issue date:	05/31/2005
From:	Valos N NRC/RGN-III/DRS/OLB
To:	Exelon Nuclear
References
50-254/05-301, 50-265/05-301
Download: ML051610364 (58)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No: 1 Op-Test No: 1 Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 15% power. Reactor startup is in progress. Containment inerting is in progress.

Turnover: The plant is operating at 15% reactor power with a reactor startup in progress. The 1-0640-29B, B narrow range RPV level instrument is OOS reading downscale. The 1B EHC pump and HPCI are OOS. IRM #15 is bypassed. The crew is to transfer auxiliary power per QCGP 1-1 and continue the reactor startup.

Event Malfunction Event Event No. Number Type* Description BOP 1 N/A N Transfer Auxiliary Power SRO RO 2 N/A R Increase power with control rods SRO nm11a RO 3 I RBM 7 rod block below required power level nm12a SRO RO, 4 rd01r C, T Control rod 26-23 uncoupled SRO rc11 BOP, 5 C, T Steam leak in RCIC. Group V isolation fails to actuate rc13 SRO BOP 6 ia04a C Recoverable loss of instrument air SRO 7 mc05 ALL M Circulating water rupture under the hotwell 8 rr11a ALL M Leak in the A recirc suction / TAF blowdown

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

Appendix D Scenario Outline Form ES-D-1

SUMMARY

The plant is operating at approximately 15% power with a reactor startup in progress. Drywell inerting is in progress. The 1-0640-29B, B narrow range RPV level instrument is OOS reading downscale. The B EHC pump and HPCI are OOS. IRM #15 is bypassed.

The crew will assume the shift with orders to transfer auxiliary power (BOP-N) and continue the startup by pulling control rods (RO-R). During control rod withdrawal the RBM #7 enable setpoint will drift down causing a rod out block (RO-I). After the RBM is bypassed a control rod will come uncoupled at position 48 (RO-C, SRO-T). Actions to re-couple the control rod will fail and it will be fully inserted.

An operator will report from the field that he felt vibrations in the plant and the seismograph has actuated.

A steam leak will develop in RCIC and the group V isolation will not actuate requiring the operator to isolate it manually (BOP-C, SRO-T).

A recoverable loss of instrument air will occur. The operator will start standby instrument and service air compressors (BOP-C). The NLO will be able to isolate the leak.

A rupture of the circulating water piping and subsequent flooding of the condensate pit will require the crew to scram the reactor and secure the condensate and feed pumps (M-All).

After the scram a leak in the A recirc suction header will develop. The crew will be unable to control level above the top of active fuel requiring a blowdown (M-All). RPV level will be recovered using low-pressure ECCS pumps.

The scenario will be terminated when primary containment parameters are lowering and RPV level is in a band of 0 - 48.

CRITICAL TASKS:

Critical task #1: When level approaches -59 INHIBIT ADS prevent to uncontrolled RPV depressurization. (BWROG RPV-4.2/5.2/6.2) Important PSA task/ Inhibit ADS has Risk achievement Worth RAW) of 6.06. Accomplishing this task terminates 2 of the 20 most probable Core Damage Sequences.)

Critical task #2: With the inability to maintain RPV level above -142 inches with an injection source lined-up and running INITIATE an emergency depressurization before RPV water level drops to -166" (Minimum Steam Cooling RPV Water Level) (BWROG RPV-1.1 LOSS HP INJ E/D TAF)

Critical task #3: When Torus pressure exceeds 5 psig, INITIATE drywell sprays, while in the safe region of the drywell spray initiation limit (DSIL).

Appendix D Scenario Outline Form ES-D-1 SIMULATOR SETUP:

• Reset the simulator to IC-151 from the zip disk; rst 151

• Take the simulator to run; run

• Synch to the grid and close all turbine bypass valves. QCGP 1-1 steps F.8-F.8.m

• Fill out QCGP 1-1 up to and including step F.8.m

• Run the scenario 1 CAEP file and verify the following commands in the summary o Fail the Group V isolation; imf rc13 o Increase the gain of RBM #7; imf nm11a 100 o Bind the HPCI 4 valve closed; imf hp12a 0 o Bind the HPCI 5 valve closed; imf hp12b 0 o Uncouple control rod 26-23; imf rd01r2623 o Fail the narrow range RPV level instrument 1-640-29B downscale; imf rr15b 0 o Assign TB sump alarms to come in sequentially on trigger 1; imf ano9014d20 (1 1:) on imf ano9014c20 (1 2:) on imf ano9017g5 (1 2:) on o Assign trigger 2 to its default; trg 2 e2 o Cause the condensate pumps to sequentially trip when trigger 2 goes true; imf fw17c (2 10) imf fw17d (2 15) imf fw17a (2 15) imf fw17b (2 25)

• Take the following OOS:

o 1-2301-4 valve C/S, closed o 1-2301-5 C/S, closed o HPCI trip pusbutton, trip-latched o 1B EHC pump C/S in PTL o 1-0640-29B indicator

• Bypass IRM #15 and place an equipment status tag on the joystick

• Place an EST on the 1-4723 stating instrument air backup valved in to DW pneumatics

• Place EST on the DW/Torus Purge fan in PTL stating the breaker is open

• Pump the drywell equipment sumps

• Place the zinc injection magnet above B RFP

Appendix D Scenario Outline Form ES-D-1

1. LIST OF POTENTIAL PROCEDURES:

QCGP 1-1 QCGP 2-3 QCGP 4-1 QCOP 6500-09 QCAN 901-8, D1 QCAN 901-8, B5 QCAN 901-5, A7 QCAN 901-5, C3 QCOP 0700-04 QOP 0700-05 QCAN 901-5, A2 QCAN 901-5, A3 QCAN 901-5, B3 QCOA 0300-03 QCOP 0207-01 QCOP 0207-02 QCOS 0300-14 QCOA 0010 -09 QCAN 901-3, D3 QCAN 901-3, H2 QCOA 0201-05 QCOA 4700-06 QOA 912-1 A-11 QOA 912-1 A-12 QOA 912-1 B-11 QOA 900-4 C-20 QOA 900-4 D-20 QOA 0030-01 QCAN 901-7, A5 QOA 901-7 D-10 QOA 901-7 E-10 QOA 901-7 F-10 QOA 901-7 G-5 QCOP 2900-02 QCOP 0300-16 QCOP 1100-02 QCOP 1000-30 QCOP 5750-19 QGA 100 QGA 200 QGA 500-1

Appendix D Scenario Outline Form ES-D-1 CREW TURNOVER:

Unit 1 is in a reactor startup after a weekend outage. The reactor is currently operating at approximately 15% power. QCGP 1-1 is complete through step F.8.m. Containment inerting is in progress per QCOP 1600-20. On-line Risk is YELLOW due to HPCI being OOS.

Equipment OOS:

HPCI, due to a broken turning gear. Expected back tomorrow.

LI 1-0640-29B, due to an instrument block leak. Expected back next shift.

1B EHC pump, due to a shorted motor. Expected back in 3 days.

IRM #15 is bypassed due to erratic operation.

Unit 2 is holding full load. On-line Risk is GREEN.

All Unit 1 loads are being powered from T-12.

Unit 2 is in a normal electric plant line-up.

Tech Specs:

Unit 1:

Day 1 of 14, TS 3.5.1 Condition F. HPCI OOS for turning gear repair.

Unit 2:

None Evolutions for the upcoming shift:

Transfer auxiliary power and continue the power ascension. BPO has been notified of the upcoming power transfer. Continue inerting the containment.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Page 1 of 10 Event

Description:

Transfer auxiliary power. Initiated by shift turnover.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP If the crew does not promptly begin the task, call the control room as the Shift Manager and ask them to begin.

SRO Directs BOP to transfer auxiliary power from T-12 to T-11 (QCOP 6500-09 step F.7)

RO Monitors reactor parameters during this evolution.

BOP Verifies Main Generator load greater than 75 MWe.

BOP/SRO Notifies BPO that aux power will be transferred.

BOP Turns on synchroscope for T-11 to Bus 11.

BOP Verifies T-11 and Bus 11 are in phase and voltages approximately equal.

BOP Closes T-11 to Bus 11 ACB and verifies alarm 901-8 D1, lit.

BOP Opens T-12 to Bus 11 ACB and verifies alarm 901-8 D1, off.

BOP Turns off synchroscope for T-11 to Bus 11.

BOP Turns on synchroscope for T-11 to Bus 14.

BOP Verifies T-11 and Bus 14 are in phase and voltages approximately equal.

BOP Closes T-11 to Bus 14 ACB and verifies alarm 901-8 B5, lit.

BOP Opens T-12 to Bus 14 ACB and verifies alarm 901-8 B5, off.

BOP Turns off synchroscope for T-11 to Bus 14.

BOP/SRO Notifies BPO that aux power transfer is complete.

EVENT TERMINATION: terminate when aux power has been transferred on Busses 11 and 14.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 2 of 10 Event

Description:

Increase power with control rods. Initiated by shift turnover.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP If the crew does not promptly begin the task, call the control room as the Shift Manager and ask them to begin.

SRO Directs the RO to begin the load increase RO Monitors reactor parameters BOP Monitors balance of plant parameters SRO Directly supervises control rod moves.

RO Begins load increase with control rods RO Selects an in-sequence control rod On the RWM verifies proper rod selected, its current position and RO bounds.

Communicates to the QIV Control Rod XX-YY is selected.

RO Withdrawing from position __ to position __ (continuously or by notching)

Replies, Understand Control Rod XX-YY is selected. You are moving QIV it from position __to position__. (Continuously or by notching)

RO Replies: That is correct QIV Concurs RO Verifies control rod and moves it to the desired position RO Place keeps rod moves in the rod movement book RO Repeats above steps as necessary EVENT TERMINATION: terminate at lead examiner discretion.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Page 3 of 10 Event

Description:

Rod Block Monitor (RBM) #7 enables early causing a rod block. Initiate when directed by the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP Verify the RBM #7 gain failure is inserted; imf nm11a 100 SIMOP When directed by the lead examiner, drift the RBM #7 enable setpoint by inserting malfunction; imf nm12a 10 RO Reports Rod Out Block as indicated by any or all of the following:

Alarms 901-5 A7 and C3 lit, Rod Out Permit light extinguished or selected control rod will not withdraw.

RO Holds power constant.

SRO Directs RO to refer to annuciator procedures.

RO/SRO Determines that RBM #7 is causing the rod out block and that it should be automatically bypassed at the current power level.

SRO Refers to TS 3.3.2.1 for RBM #7 being inoperable and determines no actions are required.

RO Bypasses RBM #7 by placing its joystick to RBM 7.

RO Verifies RBM #7 bypass light lit and Rod Out Block clear.

RO Places an equipment status tag on the RBM bypass joystick.

SIMOP As IMD, report RBM #7 was calibrated yesterday and you found an error in the documentation indicating they were miscalibrated.

No other nuclear instrumentation is affected. You will write the IR.

EVENT TERMINATION: terminate when either ARPM #3 or RBM #7 is bypassed and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Page 4 of 10 Event

Description:

Uncoupled control rod. Initiated automatically when control rod 26-23 (G-6) is withdrawn to position 48.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP Ensure the uncoupled control rod malfunction is inserted; imf rd01r2623 RO Reports alarm 901-5 A2 lit and control rod 26-23 uncoupled at position 48.

SRO Directs RO to perform the actions of the QCAN and QCOA 0300-03.

RO Verifies control rod position at panel 901-5, RWM and using process computer OD-7 option 2.

NOTE The candidate may ask the QNE if the control rod has uncoupled previously during the cycle. If so, reply it has not.

RO Disables blocks to full on the RWM OR bypasses the RWM.

RO Inserts control rod to position 46 RO Withdraws control rod to position 48 and performs a coupling check.

Reports that the control rod is still uncoupled.

NOTE If the candidate asks the QNE whether attempts should be made to couple the control rod at a position other than 46, reply that it should be tried at position 44.

RO Attempts to couple the control rod by inserting it to position 44 and withdrawing it to position 48.

RO MAY enable the RWM Rod Out-of-Service option.

RO Inserts control rod to position 00 and directs an NLO to disarm the control rod per QCOP-0300-07.

SIMOP As the NLO dispatched to disarm the control rod, wait 5 minutes, insert remote function irf rd06r2623r inop and report control rod 26-23 has been disarmed.

RO Contacts the QNE for guidance on adjusting the control rod pattern.

NOTE As the QNE tell the Crew that it will take 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to develop a new rod pattern and that power should be held constant until then.

SRO Enters TS 3.1.3, Condition C. Fully insert the control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarm it within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SRO Initiates QCOS 0300-14 CRD Outage Report. (Not necessary to complete to move forward in the scenario)

RO MAY return the RWM to operation if bypassed previously.

EVENT TERMINATION: terminate when the control rod is inserted to position 00 and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 5 Page 5 of 10 Event

Description:

Steam leak in RCIC. Group V isolation fails to actuate. Initiate after the uncoupled control rod is inserted to 00 and at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner, call the SRO as the Unit NLO and report you felt a vibration in the turbine building and the seismograph has actuated.

SIMOP Verify Group V isolation failure is inserted; imf rc13.

SIMOP 2 minutes after calling as the NLO, insert a steam leak in the RCIC steam supply line; imf rc11 10 SRO/BOP MAY dispatch the field supervisor or IM to retrieve data from the seismograph.

SRO/BOP MAY notify the SM to consider classifying the event as a possible E-Plan condition.

SRO/BOP MAY dispatch operators to inspect the plant for damage.

BOP Reports alarm 901-3, H2 lit.

SRO Directs BOP to perform the actions of the QCAN.

BOP Checks Panel 901-21 and determines leak in RCIC.

SRO Enters QGA 300.

SRO Directs RO/BOP to dispatch an NLO to start the U1 DGCWP.

SIMOP When directed, wait 1 minute, start the U1DGCWP; irf sw10r run and report it complete.

NOTE Depending on how quickly the crew isolates RCIC they may not recognize the failure of the Group V isolation.

BOP Recognizes that the Group V isolation failed to occur.

SRO Directs BOP to take the actions of QCOA 0201-05.

BOP Isolates RCIC by closing the 1-1301-16 and 1-1301-17 valves.

BOP Evacuates the reactor building basement and notifies RP.

BOP Trips hydrogen water chemistry system.

BOP Verifies RCIC room temperature is lowering.

SRO Enters TS 3.5.3 Condition A, identifies HPCI inop and enters Condition B, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to be in Mode 3.

SRO If RCIC room temp exceeded 170 °F enters TS 3.6.1.3 Condition B, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to isolate the RCIC steam supply.

BOP/SRO Dispatches NLO to open the breakers for the 1-1301-16 and 17 valves.

SIMOP Wait 3 minutes, then bind the RCIC valves (imf rc10a 0, imf rc10b 0), override the green lights off (ior lohs11301161 off AND ior lohs11301171 off) and report it complete.

EVENT TERMINATION: terminate when RCIC is isolated and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Page 6 of 10 Event

Description:

Recoverable loss of instrument air.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner, insert a leak in the turbine building instrument air header using malfunction; imf ia04a 3 BOP Report alarm 912-1 A11 lit and instrument air pressure lowering.

SRO Directs the BOP to take the actions of QCAN.

BOP Starts the 1/2 and 1B Instrument and the 1B and U2 Service Air compressors SRO Sets scram criteria of 75# scram air header pressure as indicated on panel 912-1 or alarm 901-5 A1 lit.

BOP Dispatches an NLO to opens valve 1/2 3899-159 for the 1/2 Instrument Air compressor and place the compressor in NORMAL.

BOP/RO Dispatches NLO to investigate loss of instrument air.

SIMOP As the NLO, wait 3 minutes and report that the air leak is at the discharge of the 1A instrument air compressor and that if it is secured you can isolate it.

BOP Secures the 1A Instrument air compressor and notifies the NLO to isolate it SIMOP Wait 1 minute, delete the air leak, dmf ia04a and report the leak has been isolated.

EVENT TERMINATION: terminate when the instrument air leak has been isolated.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page 7 of 10 Event

Description:

Circulating water rupture under the hotwell. Initiate at the direction of the lead examiner TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner insert a rupture in the circulating water system under the hotwell; imf mc05 100 8:

BOP Reports alarm 901-7 D10 is lit.

SRO Directs BOP to perform the actions of the QCAN.

BOP/RO Dispatches an NLO to investigate the alarm.

SRO MAY set scram criteria of alarm 901-7 E10 being lit.

SRO Directs BOP to perform the actions of QOA 0030-01.

SIMOP One minute after 901-7 D10 comes in, override the TB sump alarms on by making trigger 1 true; trg! 1 SIMOP Two minutes after 901-7 D10 comes in, override 901-4 c20 and 901-7 G5 on; imf ano9014c20 on AND imf ano9017g5 on SIMOP When 901-7 E10 comes in, call in as the NLO and report there is water 1/2 way up the vent louvers of condensate pump motors.

SRO Directs RO to scram the reactor.

RO Inserts a manual scram.

BOP Secures the running condensate and feed pumps.

SIMOP Make sure trigger 2 goes true when the B RPS pushbutton is depressed.

BOP Trips the condensate transfer pumps.

NOTE The crew may trip the circ water pumps. If they do not they will trip automatically when 901-7 F10 is received.

SIMOP After the circ water pumps are tripped and if asked, report that the water level is no longer rising.

EVENT TERMINATION: terminates at the conclusion of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Page 8 of 10 Event

Description:

Leak in the Drywell / TAF blowdown TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS RO Reports all rods in, RWL and reactor pressure SRO Enters QGA 100 on low RWL SRO Directs RO to perform QCGP 2-3 RO Performs QCGP 2-3 Attachment A SRO Directs BOP to verify isolations for 0 RWL BOP Reports 0 isolations complete SRO Directs BOP/RO to control RWL 0 to 48 with SSMP BOP/RO Starts SSMP and injects to Unit 1 per the hardcard.

When BOP/RO reports SSMP is injecting to Unit 1, insert a break SIMOP in A recirc pump suction line; imf rr11a 1 10:

Directs BOP/RO to begin a cooldown <100 deg F/hr with turbine SRO bypass valves MAY begin a cooldown @ <100°F by opening the turbine bypass BOP/RO valves NOTE Depending on when the cooldown is ordered it may not be performed due to the leak and the determination of whether it can be held below 100 °F/hr.

EVENT TERMINATION: actions continue until the termination of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Page 9 of 10 Event

Description:

Leak in the Drywell / TAF blowdown TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Directs the actions of QGA 100 RPV CONTROL SRO *CT #1* Directs BOP/RO to inhibit ADS.

BOP/RO *CT #1* Places ADS Inhibit Switch in INHIBIT.

SRO Directs RO to start the second Control Rod Drive (CRD) Pump.

Places the B CRD pump control switch in close and opens the 1-0301-RO 2B. Places CRD flow controller in manual and raises flow.

SRO Directs the RO to inject Standby Liquid Control (SLC).

RO Injects SLC by placing its control switch in 1&2 or 2&1.

RO Reports RWL every 20 change.

RO Reports RWL at -142 (TAF).

SRO Enters QGA 500-1 RPV BLOWDOWN.

If dispatched to valve in the second set of CRD filters, wait 3 SIMOP minutes then report that they are valved in Directs the actions of QGA 200 PRIMARY CONTAINMENT SRO CONTROL SRO Directs BOP to initiate Torus sprays.

BOP Initiates Torus sprays.

BOP Reports Torus pressure at 5 psig.

• CT #3* Verifies Torus level <17 and inside DW Spray Initiation SRO Limit curve.

SRO *CT #3* Verifies recirc pumps and DW coolers tripped.

SRO *CT #3* Directs BOP to initiate DW sprays.

BOP *CT #3* Initiates DW sprays and verifies DW pressure lowering.

BOP Adjusts RHR flow to maintain lowering trend on DW pressure EVENT TERMINATION: actions continue until the termination of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Page 10 of 10 Event

Description:

Leak in the Drywell / TAF blowdown TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Directs the actions of QGA 500-1 RPV BLOWDOWN SRO Determines all rods in and DW pressure >2.5 psig.

Determines RHR and Core Spray (CS) are needed for core cooling per SRO the override in QGA 100 pressure leg.

SRO Determines Torus level >5 SRO *CT #2* Directs BOP to open all 5 ADS valves BOP *CT #2* Opens all 5 ADS valves BOP Verifies on acoustic monitor all 5 ADS valves open SRO Directs BOP to secure DW and Torus Sprays BOP Verifies LPCI and CS injection at 325#

RO Verifies RWL rising and reports above TAF BOP Controls RHR and CS flow to prevent flooding the RPV NOTE: SRO can only order one of the following two commands SRO MAY direct Torus and DW spray initiation SRO MAY direct RBCCW and DW coolers restarted BOP IF ordered, starts Torus and/or DW sprays BOP IF ordered, restarts RBCCW and DW coolers SCENARIO TERMINATION: terminate the scenario when RPV level is above 0 with the concurrence of the lead examiner.

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No: 2 Op-Test No: 1 Examiners: ___________________________ Operators: ____________________________

Initial Conditions: Full power, holding load. Torus cooling on.

Turnover: The plant is holding load at rated reactor power. The 1B TBCCW pump and GCB 3-4 are OOS. Control rod M-7 is inoperable and OOS on the RWM. Torus cooling is on A loop following a planned RCIC run. The RCIC run has been completed and the crew is to secure Torus cooling first thing this shift.

Event Malfunction Event Event No. Number Type* Description BOP 1 N/A N Secure Torus cooling SRO BOP Condensate pump trip / Recirc runback, BOP reset 2 fw17b C SRO runback RO 3 rd19 I Loss of the A RWM SRO 4 rm02m SRO T Refuel Floor Rad Monitor fails upscale aoti1754012b BOP, Standby Gas Treatment starts with a failure of the 5 loil07503b1 C, T SRO heater to start loil07503b2 RO Recoverable loss of Main Condenser vacuum, load 6 mc08 R SRO drop rp04a, RO Loss of A RPS, 5 rods scram, requiring an immediate, 7 C rd05r SRO manual reactor scram rd13a and b, 8 ALL M Delayed slow scram / gross fuel failure cr01 and 2 rd14a, Pipe rupture at Scram Discharge Volume / QGA 300 9 ALL M dihs10590303 RPV Blowdown, due to 2 areas at Max Safe radiation

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

Appendix D Scenario Outline Form ES-D-1

SUMMARY

The plant will be holding load at rated conditions. The 1B Turbine Building Closed Cooling Water (TBCCW) pump and Gas Circuit Breaker (GCB) 3-4 will be OOS. Control rod M-7 will be OOS on the Rod Worth Minimizer (RWM). APRM #1 will be bypassed. Torus cooling will be on A loop.

The crew will take the shift with orders to secure Torus cooling which was running for an RCIC surveillance that has been completed (BOP-N). After Torus cooling has been secured the B condensate pump will trip causing a Reactor Recirc runback.

After the operator resets the Recirc runback signal (BOP-C) the A RWM will fail. The crew will swap to the B RWM and take the previously OOS control rod back OOS (RO-I).

One of the Refuel Floor Radiation Monitors will fail upscale causing the Reactor Building vents to isolate and Standby Gas Treatment (SGT) to auto start (SRO-T). The B SGT heater will not start (SRO-T). The operator will manually start A SGT and secure B (BOP-C).

A recoverable loss of Main Condenser vacuum will occur, causing the need for a load drop (RO-R). The NLO dispatched will refill the loop seal on the turbine vacuum breaker and vacuum will return to normal.

A loss of A RPS will occur and 5 Control Rods will scram, requiring an immediate Reactor scram (RO-C). When the scram is inserted, blockage of the Scram Discharge Volume (SDV) will cause the Control Rods to insert at a slower than normal rate, resulting in gross fuel element failure (M-All). The SDV piping will rupture, releasing Reactor coolant into the Reactor Building. Based on the Reactor coolant leak and two Reactor Building areas reaching Max Safe radiation levels, the crew will Blowdown the reactor.

The scenario will be terminated when all 5 ADS valves are open and RPV pressure is dropping.

CRITICAL TASKS:

Critical task #1: A manual reactor scram is inserted when multiple Control Rods scram in after A RPS trips.

Critical task #2: When two areas in the Reactor Building exceed MAX SAFE radiation levels, initiate emergency depressurization.

Appendix D Scenario Outline Form ES-D-1 Simulator setup:

• Reset the simulator to IC-21; rst 21

• Start Torus cooling on A loop using A RHR and B and C RHRSW pumps.

• Fill out QCOP 1000-09 through step F.1

• Fill out QCOP 1000-04 step F.1.a and b (N/A c) and F.2.a and b (N/A c).

• Take control rod M-7 (46-27) OOS on the RWM, place circular sticker on full core display and orange label above RWM

• Disarm control rod M-7 (46-27); irf rd06r4627r inop

• Place 1B TBCCW pump control switch in PTL and hang INFO CARD on control switch.

• Place 345 KV GCB 3-4 in PTL and hang HOLD / OOS card.

Run CAEP file ILT 03-1 NRC Scenario #2.cae from FLOPPY disk.

• Verify the following commands are in the Instructor Summary:

• RWM failure commands assigned to triggers 1, 2 and 3.

o trgset 1 'zdihs10207xfer .gt.0' o trg 1 'dmf rd19' o trgset 2 'zdihs10207xfer .gt.0' o trg 2 'dmf ano9015b3' o imf ano9015b3 (3 25) on o imf rd19 (3)

• FP Rad Monitor failure events assigned to trigger 4.

o imf rm02m (4) o ior loil07503b1 on (should be TRUE immediately) o ior loil07503b2 off (should be TRUE immediately) o ior aoti1754012b 0.65 (should be TRUE immediately)

• RPS A trip, 5 rods scram, and SDV blockage assigned to trigger 7.

o imf rd05r4639 (7 1) o imf rd05r2623 (7 1) o imf rd05r1847 (7) o imf rd05r3031 (7) o imf rd05r4227 (7 1) o imf rp04a (7) o imf rd13a (7 7) 60 o imf rd13b (7 7) 100

• SDV blockage modified (removed) and fuel failure assigned to trigger 8. Trigger 8 assigned to B PRS pushbutton depressed.

o trgset 8 'zloil10590301B .gt.0' o trg 8 'mmf rd13b (8 10) 60 15' o imf cr01 (8 2:) 100 3:

o imf cr02 (8 3:) 100 5:

• Scram Discharge Volume rupture, increasing Reactor Building Radiation and Reactor Building Sump alarms are assigned to trigger 9.

o ior dihs10590303 (9) norm o imf rd14a (9) 100 2:

o imf rm0106 (9 2:) 40 15:

o imf rm0108 (9 1:) 40 10:

o imf rm0109 (9 3:) 39.9 8:

o imf rm0111 (9) 40 15:

o imf rm0112 (9) 41 11:

o imf ano9014c18 (9 3:) on o imf ano9014d18 (9 5:) on

Appendix D Scenario Outline Form ES-D-1 LIST OF POTENTIAL PROCEDURES QCOP 1000-04 1000-09 1000-02 0207-01 QCOS 1700-01 QCAN 901-3 A6 901-3 A8 901-3 B8 901-3 C6 901-3 C15 901-3 G16 901-4 A5 901-4 B18 901-4 C1 901-4 C5 901-4 F7 901-5 B3 901-5 E8 901-5 F8 901-5 D8 901-6 A6 901-6 F5 912-5 A1 912-5 A4 912-5 A6 912-5 B6 901-54 B6 901-54 C7 QOA 3300-02 QCOA 3300-01 QGA 100 101 300 500-1

Appendix D Scenario Outline Form ES-D-1 CREW TURNOVER Unit 1 is holding full power. Torus cooling is on A loop due to a RCIC run last shift. On-Line Risk is YELLOW due to 345KV switchyard work.

OOS equipment:

1B TBCCW pump, due to a bad coupler. Expected back in 2 days.

GCB 3-4 is OOS for compressor replacement. Expected back next shift.

Rod M-7 is OOS at position 00, mechanically and on the RWM, due to a failed scram outlet valve. Expected back in 4 days.

Unit 2 is holding full load. On-Line Risk is YELLOW due to 345KV switchyard work.

Both units are in a normal electric plant line-up.

Tech Specs:

Unit 1:

Day 2, TS 3.1.3, Condition C. Control rod M-7 inoperable.

Unit 2:

None Evolutions for the upcoming shift:

After assuming the shift, secure Torus Cooling.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Page 1 of 8 Event

Description:

Secure Torus cooling. Initiated by turnover information.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP If the crew does not promptly begin securing Torus cooling, call as the Shift Manager and tell them to.

SRO Directs BOP to perform QCOP 1000-09 to secure Torus Cooling BOP Obtains QCOP 1000-09 and determines step F.5 is appropriate to shutdown RHR pump.

BOB Throttles Closed MO 1-1001-36A. When discharge pressure is within 25 psig of RHRSW pressure, STOPS 1A RHR pump by placing Control Switch to NAT. Continues to FULLY CLOSE 1-1001-36A.

BOP Closes MO 1-1001-34A.

BOP Opens MO 1-1001-16A.

BOP Opens MO 1-1001-18A.

NOTE The valves required to be verified by QCOP 1000-02, are NOT listed below. NO valves will require manipulation in the next step.

BOP Verifies RHR in standby line-up per QCOP 1000-02 SIMOP When asked, report that the 1-1001-42A-D are CLOSED, relays 10A-K63A and B are energized and the U1 DGCWP control switch is in AUTO.

BOP Obtains QCOP 1000-04 and uses step F.1.e to shutdown A loop and step F.2.e to shutdown B loop RHRSW.

BOP Stops 1B RHRSW pump.

BOP Closes MO 1-1001-5A. When closed, returns control switch to STOP.

BOP Stops 1C RHRSW pump.

BOP Closes MO 1-1001-5B. When closed, returns control switch to STOP.

TERMINATION: Terminate when QCOP 1000-09 and 1000-04 are complete, Torus Cooling is shutdown, RHR and RHRSW are returned to standby lineup.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Page 2 of 8 Event

Description:

B Condensate / Condensate Booster pump trip and Reactor Recirc system runback. Initiate at the direction of the Lead Examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the Lead Examiner trip the B condensate pump (CAEP file, page 3 OR imf fw17b)

RO / BOP Reports B condensate / condensate booster pump trip as indicated by annunciators 901-6 A6 and F5 or the trip light lit on the B condensate pump.

RO / BOP Verifies Condensate Pump discharge pressure > 104 psig and Reactor Feed Pump suction pressure > 145 psig.

RO Monitors Reactor Level.

RO / BOP Enters QCOA 3300-01, Loss of Condensate Pump.

RO Reports reactor power lowering and RPV level changing.

RO / BOP Reports reactor recirc pumps running back, as indicated by annunciators 901-4 A5 and F7 lit.

SRO Directs RO to insert a manual reactor scram if level cannot be maintained > 11 and < 44 (Scram Criteria)

RO / BOP Determines that reactor recirc runback is an expected condition, for the condensate pump trip from full power.

RO / BOP Dispatches NLO and/or EMD to Bus 13 to check the aux compartment and the breaker for the 1B Condensate pump for targets.

SIMOP As the NLO or EMD, call back after 3 minutes and report that the 1B Condensate pump tripped on overcurrent. Report that there were no targets on Bus 13 aux compartment and that there appears to be no damage.

RO / BOP Dispatches NLO to perform inspection of 1B Condensate Pump and to isolate Hydrogen Addition to the pump per QCOP 3300-01.

SIMOP As the NLO, call back after 3 minutes and report that there is an acrid odor in the area near 1B Condensate / Condensate Booster pump motor.

Report that you have closed 1-2799-31B and that it has been lock wired closed. (QCOP 3300-01 step D.11.(a).(1) and (2))

RO / BOP Resets Runback Control Logic as directed by QCAN 901-4 F7 SRO/BOP Notifies BPO, Chemistry and Shift Manager of reason for load drop.

TERMINATION: Event terminates after Recirc Runback has been reset.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Page 3 of 8 Event

Description:

Loss of the A Rod Worth Minimizer (RWM). Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the Lead Examiner, fail the A RWM and cause 901-5 B3 alarm by making TRIGGER 3 go true (CAEP file page 3, OR trg! 3)

RO Reports receipt of alarm 901-5 B3 Rod Worth Minimizer. Recognizes that position indication has been lost for all Control Rods on the RWM.

Determines that the A RWM has failed.

RO / SRO Notifies QNE of A RWM failure SRO Directs RO to verify that the B RWM is Ready and to swap to the B RWM RO Refers to QCOP 0207-01 to place the B RWM in service.

SIMOP When B RWM is selected in the following step, VERIFY RWM failure, dmf rd19 and annunciator 901-5 B3 are deleted.

RO Swaps RWM selector control switch from A to B.

NOTE If the crew does not promptly take rod M-7 OOS on the RWM, call as the QNE and report that you will write the IR on RWM A and remind them that rod M-7 needs to be taken back OOS on the B RWM.

RO Uses QCOP 0207-01 step F.6 to remove Control Rod M-7 from service on the B RWM.

RO Selects Secondary Functions RO Selects Rod out of Service RO Selects Control Rod M-7 and verifies it is enclosed in a blue box RO Selects Enter Request and verifies insert and withdraw blocks are applied RO Selects Exit Function TERMINATION: Event terminates after Control Rod M-7 has been removed from service on the RWM.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4,5 Page 4 of 8 Event

Description:

Refuel Floor Rad monitor fails upscale. Standby Gas Treatment Train Heater fails to start. Initiate at the direction of the Lead Examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the Lead Examiner, fail the A refuel floor Rad Monitor upscale, by making trigger 4 go true. (CAEP file, page 3 OR trg! 4 BOP Reports annunciator 901-3 G16 REFUEL FLOOR RADIATION MONITOR CHANNEL A HI RADIATION.

BOP / RO Verifies automatic isolation of RB Vents and automatic start of SBGT.

BOP / RO Reports that B 1/2 SBGT Train Heater is not energized.

BOP / RO Reports that the 1A Refuel Floor Rad Monitor has failed Upscale Reports that the 1B Refuel Floor Rad Monitor reads normal (14mr/hr)

NOTE If requested, report that UNIT 2 Refuel Floor Rad Monitors A & B read 10 and 12 mr/hr respectively.

SRO Directs RO / BOP to start 1/2 A SBGT train and secure 1/2 B train.

RO / BOP Places 1/2 A SBGT Train C/S to START RO / BOP Places 1/2 B SBGT Train C/S to OFF SRO Refers to TS 3.6.4.3 and determines Condition A is applicable. 7 days to restore 1/2 B SBGT to operable status.

SRO Refers to TS 3.3.6.2 and determines Condition A is applicable. Place channel in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (Action complete)

Refers to TS 3.3.7.1 CREVS isolation capability is maintained and the required action to place the channel in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is met.

TERMINATION: Terminate when 1/2 A SBGT train is in operation and 1/2 B train is secured and the appropriate TS have been referenced.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 5 of 8 Event

Description:

Recoverable loss of Main Condenser Vacuum. Initiate at the direction of the Lead Examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the Lead Examiner, introduce 20% air in-leakage into the Main Condenser. (CAEP file page 3 OR imf mc08 20)

RO / BOP Reports alarm 901-54 C7, NORMAL PROCESS FLOW HI/LO and that flow is >100 SCFM. Checks adsorber d/p If greater than alarm setpoint, places adsorber mode switch to bypass.

RO / BOP Checks Main Condenser Backpressure recorder. Reports backpressure increasing.

SRO Directs BOP to take actions of QOA 3300-02 SRO Directs RO to begin emergency power reduction SRO Directs RO to insert a manual Reactor scram if condenser backpressure cannot be maintained <6.5 Hg. (Scram Criteria)

RO Begins an emergency load reduction with recirc flow and then control rod insertion.

RO Monitors for indications of thermal hydraulic instabilities.

BOP Dispatches NLO / Field Supervisor check for sources of air leakage.

SIMOP At the direction of the Lead Examiner, remove air the air leak.

(CAEP file, page 3 OR dmf mc08) Call back and report that you have filled the SJAE 35 foot loop seals.

SRO/BOP Notifies Shift Manager, QNE and BPO of load drop.

TERMINATION: Terminate when an appreciable power reduction has been observed and the malfunction has been deleted.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7, 8 Page 6 of 8 Event

Description:

Loss of A RPS, 5 rods scram. Manual scram slow - delayed; gross fuel failure. Initiate at the direction of the Lead Examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the Lead Examiner, trip RPS A, cause 5 control rods to scram and initiate fuel failure by making trigger 7 go true.

(CAEP file page 3 OR trg! 7)

RO Reports receipt of annunciator alarms RO *CT #1* Reports 5 control rods have scrammed.

SRO *CT #1* Directs manual reactor scram due to multiple Control Rod Drifts RO *CT #1* Inserts Manual Reactor Scram by depressing Reactor Scram Pushbuttons and places the Reactor Mode Switch in Shutdown RO Reports that NOT ALL control rods have inserted. May report that approximately 1/2 of the Control Rods are inserting SLOWLY and the remaining 1/2 are not inserting at all.

SRO Enters QGA 100 (reactor power >3% with a scram required)

SRO Exits QGA 100 and Enters QGA 101 NOTE The SRO (RO) may direct (take) some of the actions in QGA 101 before the Control Rods automatically insert (approx 25 seconds after the manual scram.) If these actions are taken, the outcome of the scenario is unaffected.

The SRO directions may include:

Inhibiting ADS Placing Core Spray in PTL Recirc pump trip Boron injection Reactor water level reduction The RO actions may include:

Actuating and depressing the ARI pushbuttons Reduce A & B Recirc Pump speeds to Minimum RO Reports that ALL control rods have inserted into the reactor SRO Exits QGA 101 and Enters QGA 100 (directs RO to STOP injecting boron if it had been started)

RO/BOP Directs NLO to investigate A RPS trip.

SIMOP If sent to investigate the A RPS failure, wait 2 minutes and report that one of the normal EPAs is tripped for an unknown reason and place A RPS on alternate feed; mrf rp02r alt TERMINATION: Actions continue with the next event.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 9 Page 7 of 8 Event

Description:

Scram Discharge Volume Rupture causes increasing RB Radiation Level and leads to RPV Blowdown. Initiate at the direction of the Lead Examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the Lead Examiner, rupture the A SDV, cause RB Ventilation Radiation levels to begin increasing, and cause RB Sumps to alarm on level. (CAEP file page 3 OR trg! 9)

RO / BOP Reports receipt of HIGH Reactor Building Radiation Alarm RO / BOP Reports receipt of HIGH Drywell Radiation alarm.

RO / BOP Reports receipt of HIGH LEVEL in the Reactor Building Sumps SRO Directs actions of QCAN annunciator procedures RO / BOP Goes to back panels to determine which areas are experiencing high radiation.

Reports increasing Radiation in the following areas HPCI RCIC Reactor Building 1st, 2nd and 3rd floors SRO Enters QGA 300 and directs actions SRO Directs BOP / RO to run Reactor Building Vents SRO Directs BOP to report when TWO areas reach MAX SAFE values SIMOP Five minutes after the SDV rupture, call as the NLO and report that there is a large amount of steam on the first floor of the U1 Reactor Building near the Drywell Pneumatic compressor.

SRO / RO / Determines that SDV is leaking BOP SRO Directs RO/BOP to perform the actions of QCOA 0201-05.

SRO Directs RO to attempt to reset scram signal to isolate the leak.

RO Reports that he is unable to reset the reactor scram signal RO/BOP Dispatches an NLO to check basement water levels.

SIMOP As the NLO, wait 3 minutes and report 1/2 of water in the torus area. Report all other areas have no water.

TERMINATION: Actions for Event No. 9 continue on next page.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 9 Page 8 of 8 Event

Description:

Scram Discharge Volume Rupture causes increasing RB Radiation Level and leads to RPV Blowdown.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS BOP *CT #2* Reports TWO areas in the Reactor Building have exceeded MAX SAFE value SRO *CT #2* Determines RPV BLOWDOWN is required by QGA 300 due to two areas at MAX SAFE radiation levels AND a primary system discharging into the Reactor Building.

SRO Enters QGA 500-1 while continuing in QGA 300 SRO *CT #2* Directs BOP to OPEN all 5 ADS valves BOP *CT #2* Places control switch for each ADS valve to OPEN and goes to the back panels to verify that each valves has opened.

BOP Reports that ALL 5 ADS valves have opened.

RO Reports that Reactor Pressure is decreasing.

TERMINATION: Terminate the scenario when all 5 ADS valves are open and Reactor Pressure is going down with the concurrence of the lead examiner.

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No: 3 Op-Test No: 1 Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 90% power, holding load Turnover: The plant is holding load at 92% reactor power. The 1-0263-29B, B narrow range level instrument, is OOS reading downscale. The 1B TBCCW pump and HPCI are OOS.

APRM #1 is bypassed. Continue to hold load.

Event Malfunction Event Event No. Number Type* Description dihs114011a, BOP, A core spray pump autostart with a failure of the 1 C, T cs05a SRO minimum flow valve to open RO, 2 rd04r C Control rod drifts out 2 notches SRO ano9017e12, BOP 3 dihs156041a C Gland Steam Exhauster trip SRO lohs156041a4 4 ed02 SRO T Loss of Reserve Aux Transformer 12 RO 5 N/A R Load drop with recirc flow SRO BOP 6 N/A N Secure reactor feed pump and condensate pump SRO RO RPV level indicator fails upscale requiring manual level 7 rr15a I SRO control rp05a and b, Inadvertent Group I isolation and subsequent break in B 8 ALL M ms05b main steam line pc01 Unable to spray DW, DW coolers wont restart, PSP 9 dihs11001s17a ALL M blowdown dihs1100126b rr17a-d, 10 rr19a-d, ALL M Loss of all RPV level indication, RPV flooding rr20a and b

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

Appendix D Scenario Outline Form ES-D-1

SUMMARY

The plant is holding load at 90% power. The 1-0640-29B, B narrow range RPV level instrument is OOS reading downscale. The 1B TBCCW pump and HPCI are OOS. APRM #1 is bypassed.

When the crew assumes the shift the A core spray pump will autostart but its minimum flow valve will fail to open. The operator will secure the pump (BOP-C, SRO-T). A control rod will drift out 2 notches and will be inserted using the QCOA (RO-C, SRO-T). The on line gland sealing steam exhauster will trip requiring the other to be placed in service (BOP-C).

A loss of Reserve Aux Transformer 12 will occur (SRO-T). A load drop to less than 2511 MWth will be performed (RO-R) and 1 RFP and 1 condensate pump will be secured (BOP-N).

The other narrow range RPV level instrument will fail upscale causing the operator to take manual control of feedwater (RO-I).

An inadvertent Group I isolation will cause a steam leak in the drywell (M-All). Drywell sprays will be unavailable and the drywell coolers will not restart. The crew will blowdown due to the inability to stay within the PSP curve or maintain DW temperature (M-All).

When saturation conditions are met all RPV level instruments will become unavailable and the crew will flood the RPV (M-All).

The scenario will be terminated when the crew identifies indications that the RPV is flooded to the main steam lines.

CRITICAL TASKS:

Critical task #1: When Torus cannot be maintained below the Pressure Suppression Pressure (PSP), INITIATE emergency depressurization.

Critical task #2: When RPV level cannot be determined, inject to establish flooding conditions.

Appendix D Scenario Outline Form ES-D-1 Simulator setup:

• Reset The simulator to IC-21; rst 21

• Take the simulator to RUN; run

• Insert rod steps 39 and 38 to target in

• Reduce power to 90% by lowering recirc flow

• Run the scenario 3 CAEP file and verify the following commands in the summary.

o Fail the A CS minimum flow valve from opening; imf cs05a o Fail the narrow range RPV level instrument 1-640-29B downscale; imf rr15b 0 o Bind the HPCI 4 valve closed; imf hp12a 0 o Bind the HPCI 5 valve closed; imf hp12b 0 o Fail switch S-17a to off; ior dihs11001s17a off o Fail the 1001-26B closed; ior dihs1100126b close o Override the DW cooler bypass switches to normal; ior dihs1loadshd1 norm ior dihs1loadshd2 norm o Tie the actions needed for the gland exhauster trip to trigger 1; imf ano9017e12 (1) on ior dihs156041a (1) trip ior lohs156041a4 (1) on o Tie a Group I isolation and steam line break to trigger 3 imf rp05a (3 5) imf rp05b (3) imf ms05b (3) 10 10:

o Cause RPV level indicators to flash when trigger 5; imf rr17a (5 15) 100 15 imf rr17b (5 15) 100 15 imf rr19a (5 15) 100 15 imf rr19c (5 15) 100 15 imf rr20a (5 15) 100 15 ior aolr10263113 (5 1:) 100 15 imf rr17c (5 1:) 100 15 imf rr17d (5 1:) 100 15 imf rr19b (5 1:) 100 15 imf rr19d (5 1:) 100 15 imf rr20b (5 1:) 100 15 ior aoli10263101 (5 45) 100 15 o Set trigger 8 to the RFP secured; trgset 8 zdihs13201rfpc1(2) .gt.0 o Cause the 640-29A to fail when trg 8 goes true; imf rr15a (8 5) 100

• Bypass APRM #1

• Take the following OOS:

o Place an info tag on the 1-0263-29B o Place the 1B TBCCW pump in PTL o Trip-latch HPCI o 1-2301-4 valve C/S, closed o 1-2301-5 C/S, closed

• Place the 13.8KV system on T-82; mrf ed54r xfrm82

Appendix D Scenario Outline Form ES-D-1 LIST OF POTENTIAL PROCEDURES QCOA 1400-01 QCAN 901-3 A4 QCAN 901-3 B16 QCAN 901-3 C15 QCAN 901-5 A3 QCAN 901-5 B3 QCOA 0300-4 QCOA 0300-11 QOA 900-7 E-12 QOA 900-8 A-2 QOA 900-8 A-3 QOA 900-8 B-2 QOA 900-8 C-2 QOA 900-8 E-2 QOA 900-8 G-2 QOA 6100-01 QCGP 3-1 QOA 912-2 B-4 QOA 912-2 C-3 QCOP 3200-05 QCOP 0600-21 QCAN 901-5 F8 QGA 100 QCGP 2-3 QGA 200 QCOP 1000-30 QCOP 5750-19 QGA 500-4 QCAP 0200-10

Appendix D Scenario Outline Form ES-D-1 CREW TURNOVER Unit 1 is holding 90% power for load following. On-line risk is YELLOW due to HPCI OOS.

OOS equipment:

HPCI, due to a broken turning gear. Expected back tomorrow.

LI 1-0640-29B, due to an instrument block leak. Expected back next shift.

1B TBCCW pump for coupling replacement APRM #1 is bypassed due to a power supply card failure Unit 2 is holding full load. On-line risk is GREEN.

Both units are in a normal electric plant line-up.

Tech Specs:

Unit 1:

Day 1 of 14, TS 3.5.1 Condition F. HPCI OOS for turning gear repair.

Unit 2:

None Evolutions for the upcoming shift:

Continue to hold load pending BPO directions.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Page 1 of 9 Event

Description:

A Core Spray pump auto start with a failure of the minimum flow valve to open. Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS NOTE In the following step the override must be deleted before the candidate places the CS to PTL. It can be done immediately after the pump starts.

SIMOP At the direction of the lead examiner cause the A CS pump to start; ior dihs114011a close then delete the override BOP Reports 1A Core Spray pump running and alarm 901-3 A4 lit.

SRO Directs BOP to perform the actions of the QCAN and/or QCOA 1400-01.

RO Monitors reactor and balance of plant parameters.

BOP Places 1A Core Spray pump to Trip or PTL.

BOP Recognizes A Core Spray minimum flow failed to open and notifies SRO.

SRO Enters TS 3.5.1 and determines Condition B is applicable. 7 days to restore A Core Spray to operable status.

BOP/RO Dispatches an NLO to the 1A Core Spray pump and/or breaker.

SIMOP Wait 3 minutes then, as the NLO, report that contractors building scaffold around Bus 13-1 bumped the Core Spray pump breaker and believe they caused it to close.

NOTE: QCOA 1400-01 assumes both Core Spray pumps autostart and directs the operator to place both pumps in PTL. Since only 1 pump received an autostart signal only that pump should be placed in PTL.

SIMOP If the crew does place both pumps in PTL role play as the Shift Manager and have B pump placed in NAT.

EVENT TERMINATION: terminate when the SIMOP has reported back from the field and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Page 2 of 9 Event

Description:

Control rod 38-55 drifts out 2 notches. Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner, insert a rod drift for control rod 38-55; imf rd04r3835 SIMOP When control rod 38-55 reaches position 19 delete the rod drift; dmf rd04r3835 RO Reports alarm 901-5 A3 lit SRO Directs the RO to take the actions of the QCAN.

BOP Monitors balance of plant parameters.

RO Identifies control rod 38-55 is the drifting out by observing the red drift light on the full core display and the rod position on the RWM.

RO Identifies that control rod 38-55 latched at a known position and enters QCOA 0300-04 and QCOA 0300-11.

BOP/SRO Notifies shift manager of mispositioned control rod.

RO Inserts control rod 38-55 to position 16 using a continuous insert signal.

BOP/SRO Notifies QNE of mispositioned control rod and that it has been repositioned.

SIMOP If asked whether an OD-20 or OD-8 is required, reply that is is not needed and that you will check on thermal limits.

BOP/SRO Notifies shift operations supervisor and ops manager.

SRO MAY refer to TS 3.1.3 and 3.1.6 and determine no actions are required.

EVENT TERMINATION: terminate when the control rod has been inserted to position 16 and all notifications have been made.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Page 3 of 9 Event

Description:

Gland steam exhauster trip. Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner, trip the gland steam exhauster by making trigger 1 go true; trg! 1 BOP Reports 1A Gland Steam Exhauster tripped as evidenced by alarm 901-7 E12 and/or the amber trip light being lit.

SRO Directs BOP to perform the actions of the QCAN.

SRO/BOP Dispatches an NLO and or EMD to the tripped breaker.

RO Monitors reactor and balance of plant parameters.

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 the 1-5405A SIMOP 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.

SIMOP 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.

EVENT TERMINATION: terminate after the 1B Gland Steam Exhauster is running with vacuum between 10 and 20 and the SIMOP has reported back.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 4,5 Page 4 of 9 Event

Description:

Loss of Transformer 12 and load drop with reactor recirc flow. Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner, trip T-12; imf ed02 BOP Reports Transformer 12 tripped as evidenced by switchyard breaker status and alarm 901-8 E2 being lit.

SRO Directs BOP to perform the actions of the QCAN and QOA 6100-01.

BOP Verifies auxiliary power transfers on Busses 12 and 13.

RO Verifies reactor power, pressure and level, steady.

BOP/SRO Notifies BPO and Shift Manager.

RO/BOP Dispatches an NLO to the switchyard and Transformer 12 SRO Briefs the crew on the actions to be taken if the reactor scrams.

SIMOP Wait 3 minutes and report as the NLO, that T-12 tripped on neutral overcurrent and that you have contacted OAD.

BOP Verifies T-11 to Bus 11 and12 is <4100 amps and that T-11 to Bus 13 and 14 is <2950 amps.

BOP Verifies stator output voltage is in green band (approximately 18kv).

SRO Directs BOP to perform QCOS 0005-08 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

NOTE QCOS 0005-08 need not be completed to move on with the scenario.

SRO Refers to TS 3.8.1 and determines Condition A applies. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to perform SR 3.8.1.1 (QCOS 0005-08), 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to declare required features with no offsite power inoperable (N/A in this case) and 7 days to restore T-12 to operable status.

SRO Notifies Unit 2 SRO to refer to TS 3.8.1.

RO Reduces power with reactor recirc flow to <2511 MWth. As directed by QOA 6100-01 SIMOP If the crew does not start dropping load in a timely manner call as the Shift Manager and tell them to do so.

RO Lower recirc flow by pressing decrease on either the master or individual controllers. If in individual one controller at a time.

SIMOP If contacted as the QNE tell the crew that the load drop may be done as rapidly as needed and should be done with recirc flow.

RO Verifies thermal power is below 2511 MWth and feed flow is less than 9.8 Mlbm/hr.

BOP Dispatches NLO to transfer MCC feeds NOTE Transferring feeds would take an hour or more so no report will be needed.

EVENT TERMINATION: terminate when reactor power <2511 MWth, feed flow <9.8 Mlbm/hr and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6,7 Page 5 of 9 Event

Description:

Secure RFP and Condensate pump. Failure of the 1-0640-29A, Narrow Range RPV Level Instrument. Initiated by the crew when feed flow is

<9.8 Mlbm/hr.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Directs BOP to secure one RFP and one condensate pump.

BOP Disables the 70% Reactor Recirc Runback logic at the digital feedwater operator workstation (OWS).

BOP Verifies the RFP selector switch is OFF.

BOP Verifies aux oil pump for RFP to be secured has a red target and an amber trip light lit.

RO/BOP Verifies reactor water level is stable.

SIMOP Immediately after the RFP is taken to STOP in the next step, verify trigger 8 goes true. Five seconds later the 640-29A will fail high.

BOP Places the control switch for the RFP to be secured in STOP.

BOP Verifies no indication of flow through the secured RFP.

BOP Verifies Aux oil pump starts.

BOP Verifies amps on running RFPs <1115 and discharge pressure stable.

RO/BOP Verifies RWL stable.

RO Reports alarm 901-5 F8 is lit, that the 1-640-29A has failed upscale and the Feed Reg Valves (FRVs) are all in Manual.

SRO Sets scram criteria of RPV water level 11 lowering or 44 rising.

RO Adjusts the FRVs to maintain water level approximately 30 as indicated on the 1-263-100A and B. (This will continue through the end of the scenario.)

RO/SRO Dispatches an NLO or IM to investigate the level instrument failure.

SIMOP Wait 5 minutes and report, as the IM or NLO, that there is no apparent cause at the transmitter and that further troubleshooting will need to be done.

BOP Selects the non-running RFP for standby.

BOP Verifies RFP suction pressure >250 psig.

BOP Places condensate pump selector switch to OFF.

BOP Places the control switch for the condensate pump to STOP.

BOP Selects the non-running condensate pump for standby.

BOP Dispatches an NLO to isolate H2 to the secured condensate pump.

EVENT TERMINATION: terminate when the condensate and feed pumps are secured

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 8 Page 6 of 9 Event

Description:

Inadvertent Group I isolation and break in the B main steam line. Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner insert a Group I isolation and main steam line break by making trigger 3 go true; trg! 3 BOP/RO Reports a Group I isolation.

RO Moves the Reactor Mode Switch to SHUTDOWN RO Reports all rods in, RWL <0 and reactor pressure >1060 psig.

SRO Enters QGA 100 on low reactor water level and high reactor pressure.

SRO Directs RO to Perform QCGP 2-3.

SRO Directs RO/BOP to verify 0 isolations and autostarts BOP/RO Verifies Group II and III isolations, RB vent isolation and SGT start.

SRO Directs RO to maintain RWL 0-48 with condensate and feedwater BOP/RO Reports Drywell pressure above 2.5 psig.

SRO Enters QGA 100 and 200 on high drywell pressure SRO Directs BOP/RO to verify 2.5 psig isolations and autostarts.

BOP Verifies Group II valves closed, EDGs Core Spray and RHR running.

BOP/RO Reports 2.5 psig isolations and autostarts complete with the exception of HPCI, which is OOS.

SRO Directs RO/BOP to perform a RPV cooldown at <100 °F/hour with relief valves.

NOTE The cooldown may not be ordered or performed if the crew determines the leak rate would cause the cooldown to exceed 100

°F/hr.

BOP/RO Starts a cooldown of the RPV by opening relief valves as needed.

BOP/RO Monitors RPV pressure to ensure cooldown will not exceed 100 °F/hr.

EVENT TERMINATION: actions continue for the remainder of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 9 Page 7 of 9 Event

Description:

Inability to spray the DW, DW coolers wont restart. Initiated through the actions of QGA 200.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS Directs the actions of QGA 200 PRIMARY CONTAINMENT SRO CONTROL SRO Directs BOP to initiate Torus sprays BOP Initiates Torus sprays by opening the 1-1001-34 and 37A or B.

BOP Reports Torus pressure at 5 psig SRO Verifies Torus level <17 and inside DW Spray Initiation Limit curve SRO Verifies recirc pumps and DW coolers tripped SRO Directs BOP to initiate DW sprays Attempts to spray the drywell by opening the 1-1001-23 and 26 on BOP both loops.

BOP Reports DW sprays will not initiate on either loop.

BOP Dispatches an NLO to manually open the DW spray valves Wait 3 minutes and open the breaker for the DW spray valves; mrf rh19ar, mrf rh19br, mrf rh20ar and mrf rh20br. Five minutes later SIMOP report you are unable to open the spray valves and MMD has been notified.

SRO Directs BOP to restart RBCCW and DW coolers.

BOP Attempts to restart DW coolers and reports failure.

SRO Directs BOP to report at 13 psig in the Torus BOP Reports Torus pressure at 13 psig.

• CT # 1* When Torus pressure exceeds the PSP curve enters QGA SRO 500-1 RPV Blowdown EVENT TERMINATION: actions continue for the remainder of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 9 Page 8 of 9 Event

Description:

Emergency Depressurization due to violation of the Pressure Suppression Pressure curve.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Directs the actions of QGA 500-1 RPV BLOWDOWN SRO Determines all rods in and DW pressure >2.5 psig Directs BOP to prevent RHR and Core Spray (CS) injection not SRO needed for core cooling.

SRO Determines Torus level >5.

SRO *CT # 1* Directs BOP to open all 5 ADS valves.

• CT # 1* Opens all 5 ADS valves by placing their control switches BOP in MAN.

When the A ADS valve is opened, increasing the main steam line SIMOP break size; mmf ms05b 100 BOP Verifies on acoustic monitor all 5 ADS valves open.

BOP MAY place one or both CS pumps in PTL.

MAY divert RHR flow to Torus cooling by throttling open the MO 1-BOP 1001-36 A and/or B or place pumps in PTL.

RO/BOP Verifies and reports reactor pressure lowering.

RO/BOP Directs a NLO to energize A and B RPS from normal power.

SIMOP Wait 3 minutes, then restore A and B RPS from normal power; mrf rp29r reset (A RPS) AND mrf rp28r reset (B RPS)

EVENT TERMINATION: actions continue for the remainder of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 10 Page 9 of 9 Event

Description:

Reference leg flashing, loss of all RPV level indication, RPV flooding.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Directs BOP and RO to watch for saturation conditions and signs of reference leg flashing.

RO Monitors reactor water level at panel 901-5.

BOP Monitors reactor water level at panels 901-3 and 901-4.

SIMOP After saturation conditions are met and at the direction of the lead examiner, make trigger 5 go true to flash RPV level instrument; trg! 5 RO *CT #2* Reports no level instruments available on panel 901-5.

BOP *CT #2* Reports no level instruments available on panel 901-3 or 901-4.

SRO *CT #2* Enters QGA 500-4 SRO Directs BOP to isolate the main steam lines, steam line drains, RCIC and HPCI steam lines.

BOP Closes all MSIVs, verifies steam line drains, RCIC and HPCI isolated.

NOTE It is critical for the crew to raise injection until indications are observed that the vessel is flooded to the main steam lines.

Which systems are used and their order is not critical.

SRO *CT #2* Directs BOP/RO to raise injection to the vessel.

BOP *CT #2* Injects with Core Spray by verifying the pumps running and discharge valves open.

BOP *CT #2* Injects with RHR by securing Torus and DW sprays and verifying LPCI injection valves open.

RO *CT #2* Injects with condensate and feedwater by opening the FRVs.

NOTE Other systems such as SLC, SSMP and CRD may be used.

NOTE Indications that the vessel is flooded to the main steam line include temperature of open ADS valve tailpipes subcooled, actuation of the acoustic monitors, actuation of high steam flow logic, rise in RPV pressure with a corresponding change in injection flow, etc.

BOP/RO Recognizes and reports indications that vessel is flooded to the main steam lines.

SCENARIO TERMINATION: terminate the scenario when the crew has recognized indications that the vessel is flooded to the main steam lines and with the concurrence of the lead examiner.

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No: 4 Op-Test No: 1 Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 80% power, 2 RFPs on.

Turnover: The plant is holding load at 80% reactor power. The 1B EHC pump and GCB 3-4 are OOS. IRM # 15 is bypassed. The crew is to start 1C RFP from Bus 12 and secure 1B RFP first thing this shift.

Event Malfunction Event Event No. Number Type* Description BOP 1 N/A N Swap reactor feed pumps SRO rd07a RO, 2 C, T A CRD pump trip rd07b SRO cu03, BOP, 3 rp10a and b C, T Leak in the RWCU room, Group III fails to actuate SRO dihs112015 BOP, 4 fw14c RO C, R Heater tube leak, load drop SRO rr06a, RO 5 C A reactor recirc pump seal failure rr07a SRO ano9017c15 6 mc01, ALL M Intake structure blockage, loss of circ water mc04 rd13b 7 ALL M 1/2 core hydraulic ATWS, SLC fails to inject sl02a and b Turbine trip and bypass valve closure due to loss of 8 N/A ALL M vacuum

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

Appendix D Scenario Outline Form ES-D-1

SUMMARY

The plant is holding load at 80% power. 2 RFPs and 3 Condensate pumps are running. 1B EHC pump and GCB 3-4 are OOS. IRM #15 is bypassed.

The crew will take the shift with orders to swap RFPs (BOP-N). After the RFP swap the A CRD pump will trip requiring the B to be started (RO-C, SRO-TS).

A leak will develop in the RWCU system and the Group III will fail to actuate on high room temperature (BOP-C). The BOP will manually isolate it. One valve will not close requiring an entry into TS (SRO-T).

A tube leak in the A3 low-pressure heater will cause the bypass to open and the number 3 string to isolate. The RO will drop load and the BOP will close the heater string bypass (RO-R, BOP-C).

The A reactor recirc pump seals will fail causing DW pressure to rise. The RO will trip and isolate the pump (RO-C).

While actions are being taken to recover from the loss of a recirc pump there will be a blockage at the intake structure tripping the circulating water pumps requiring a scram (M-All). A half core hydraulic ATWS will occur (M-All). During the ATWS condenser vacuum will be lost requiring pressure control with ADS valves.

The scenario will be terminated when the actions of QCOP 0300-28 have been taken, Torus cooling is on and reactor pressure is under control with ADS valves CRITICAL TASKS:

Critical task #1: With a reactor scram required and the 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. (BWR RPV-6.2 ATWS PWR/LVL INHIBIT ADS)

Critical task #2: 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 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). (BWROG RPV-6.4 ATWS PWR/LVL RESTORE RPV LVL)

Appendix D Scenario Outline Form ES-D-1 Simulator setup:

• Reset the simulator to IC-20; rst 20

• Take the simulator to run; run

• Raise power to 80% with recirc flow (77.7% demand on the master controller)

• Verify zinc injection is indicated to the A RFP

• Verify main condenser flow is SOUTH

• Run the CAEP file for scenario #4

• Verify the following in the summary.

o Trip the 1B CRD pump; imf rd07b o Fail the Group III isolation; imf rp10a AND imf rp10b o Override the 1-1201-5 to open; ior dihs112015 open o Assign an A recirc pump seal failure to trigger 1 imf rr06a (1) 100 4:

imf rr07a (1) 100 10:

o Assign intake structure blockage to trigger 3 imf ano9017c15 (3) on imf mc04a (3) 25 2:

o Assign the sequential tripping of the circ pumps to trigger 5 imf mc01a (5 5) imf mc01c (5 1:)

imf mc01b (5 2:)

o Fail the SLC relief valves; imf sl02a 450 AND imf sl02b 450 o Insert a hydraulic lock on the south SDV; imf rd13b 100

• Take the following OOS; o 1B EHC pump control switch in PTL o GCB 3-4 control switch in PTL

• Bypass IRM #15

• Supply the crew with a copy of QOP 3200-04 signed off to step F.6

Appendix D Scenario Outline Form ES-D-1 LIST OF POTENTIAL PROCEDURES QOP 3200-04 QCAN 901-6 F7 QOA 900-6 H-7 QCOP 0202-13 QCAN 901-5 B2 QCOA 0300-01 QCOA 0201-05 QOA 900-3 H-2 QCAN 901-4 A11 QCAN 901-4 A12 QCAN 901-4 A13 QCAN 901-4 B10 QCAN 901-4 D10 QCAN 901-6 C6 QCAN 901-6 D9 QCAN 901-6 F3 QCAN 901-6 G3 QCAN 901-6 H12 QCOA 3500-01 QCGP 3-1 QCGP 4-1 QCOA 0400-02 QCOA 0201-01 QCOA 0202-06 QCOA 0202-04 QCOA 4400-01 QCOA 4400-04 QCOP 0300-28 QGA 100 QGA 200 QGA 101 QCOP 0250-02 QCOP 0201-16 QCOP 1000-30

Appendix D Scenario Outline Form ES-D-1 CREW TURNOVER Unit 1 is holding 80% power for heater tuning and an upcoming RFP clearance. On-line risk is YELLOW due to 345 KV switchyard work.

OOS equipment:

1B EHC pump, due to a shorted motor. Expected back in 3 days.

GCB 3-4 is OOS for compressor replacement. Expected back next shift.

IRM #15 is bypassed due to erratic operation.

Unit 2 is holding full load. On-line risk is YELLOW due to 345 KV switchyard work.

Both units are in a normal electric plant line-up.

Tech Specs:

Unit 1:

None Unit 2:

None Evolutions for the upcoming shift:

The BOP is to start the 1C RFP from Bus 12 and secure B RFP for a clearance scheduled to be placed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from now. Pre-start checks on 1C RFP and 1D Condensate pump are complete; an Equipment Operator is standing by to monitor pump starts.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Page 1 of 11 Event

Description:

Changeover reactor feed pumps. Initiated by turnover information.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP If the crew does not promptly begin the RFP swap, call in as the Shift Manager and tell them to.

RO Monitors reactor parameters.

SRO Directs BOP to swap reactor feed pumps.

BOP Places the condensate pump selector switch to OFF.

BOP Places the D condensate pump control switch to close.

BOP Verifies condensate pump discharge140 psig.

BOP Verifies condensate booster pump suction 110 psig and discharge 220 psig.

BOP Verifies RFP suction 200 psig.

SIMOP As an NLO if asked, report 1D Condensate pump is running normally.

BOP Verifies 1C RFP aux oil pump control switch has a red target and an amber trip light.

BOP Dispatches NLO to perform pre-start checks on 1C RFP per step F.14.

SIMOP As the NLO, wait 2 minutes and report step F.14 complete.

BOP Closes the MO 1-3201C C RFP discharge valve.

BOP Opens the AO 1-3201C C RFP recirc valve.

BOP Places the 1C RFP control switch to close.

BOP Opens the MO 1-3201C RFP discharge valve.

BOP Verifies flow stabilizes then places the AO 1-3201C to AUTO and verifies it closes.

BOP Directs the NLO to perform post start checks per step F.24 SIMOP Wait 3 minutes then, as the NLO, report step F.24 of QOP 3200-04 is complete.

EVENT TERMINATION: actions continue on next page.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Page 2 of 11 Event

Description:

Changeover reactor feed pumps (cont.).

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS BOP Closes the MO 1-3201B B RFP discharge valve.

BOP Verifies the AO 1-3201B B RFP recirc valve opens.

BOP Places the 1B RFP control switch to TRIP.

BOP Opens the MO 1-3201B B RFP discharge valve.

BOP Verifies the AO 1-3201B B RFP recirc valve closes.

BOP Verifies 1B RFP aux oil pump running.

BOP Places the RFP selector switch to 1B BOP Directs the NLO to verify the warming valves are open.

SIMOP Wait one minute then, as the NLO, report that valves 1-3299-40 and 1-3299-116 are open.

BOP Places the 1D condensate pump control switch to TRIP.

BOP Places the condensate pumps selector switch to 1D BOP Verifies flow control line per QCOP 0202-13.

EVENT TERMINATION: terminate when C RFP running with B in standby and D condensate pump off and selected for standby.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Page 3 of 11 Event

Description:

A CRD pump trip. Initiated at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP Verify trip for B CRD pump is in; imf rd07b SIMOP At the direction of the lead examiner trip the A CRD pump; imf rd07a.

RO Reports 1A CRD pump tripped and alarm 901-5 B2 lit.

SRO Directs RO to perform the actions of the QCAN and QCOA 0300-01.

BOP Monitors balance of plant parameters.

RO Verifies the MO 1-0301-2B closed.

RO Places the 1B CRD pump control switch to CLOSE.

RO Reports 1B CRD pump failed to start.

RO Dispatches an NLO to the 1B CRD pump and breaker.

SIMOP Wait 2 minutes then, as the NLO, report that it appears the breaker is not fully racked in.

SRO/RO Directs the NLO to rack the breaker out then back in.

SIMOP When the RO places the c/s to PTL, delete the B CRD pump trip; dmf rd07b RO Places the 1B CRD pump control switch in PTL.

SIMOP When the second accumulator alarm comes in, report as the NLO that the breaker has been racked out and back in.

SRO Refers to TS 3.1.5 and determines Condition B applies. 20 minutes from discovery time concurrent with charging water pressure <940 psig, restore charging water pressure to >940 psig AND declare the associated rods scram time slow or declare the rods inoperable.

RO Verifies the MO 1-0301-2B closed.

RO Places the 1B CRD pump control switch to CLOSE.

RO Verifies CRD pump current <34 amps.

RO Opens the 1-0301-2B to establish a discharge pressure of 1400-1500 psig.

RO Closes the 1-0301-2A.

RO Directs the NLO to verify proper operation, close the 1-0301-254A and open the 1-0301-254B.

SIMOP Wait 3 minutes then, as the NLO, report that the 1-0301-254A is closed, the 1-0301-254B is open and the post start checks are satisfactory.

EVENT TERMINATION: terminate when the B CRD pump is on line with discharge pressure between 1400 and 1500 psig and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page 4 of 11 Event

Description:

Leak in the RWCU system, Group III fails to actuate. Initiated at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP Verify Group III isolation failure inserted; imf rp10a and imf rp10b SIMOP At the direction of the lead examiner, insert a leak in the RWCU system; imf cu03 10 BOP Reports alarms 901-4 A12 and A13 and 901-3 H2 are lit.

SRO Directs BOP to perform the actions of the QCAN and QCOA 0201-05.

RO Monitors reactor parameters.

BOP/SRO Dispatches an NLO to panel 2201-77A and B.

BOP Checks recorder 1-1290-27 and verifies indications of a leak in the RWCU heat exchanger room.

SRO Enters QGA 300.

SRO Directs RO/BOP to dispatch an NLO to start the U1 DGCWP.

SIMOP When directed, wait 1 minute, start the U1DGCWP; irf sw10r run and report it complete.

BOP Isolates the leak by closing 1-1201-2, 1-1201-5 and 1-1201-80 valves.

BOP Reports that the 1-1201-5 valve failed to close.

BOP/SRO Recognize that the Group III isolation failed to actuate when required.

SIMOP If directed to the RWCU area, wait 2 minutes and report steam in the heat exchanger room (from camera) and, if the crew has isolated the RWCU system, that the steam is subsiding.

RO/BOP Evacuates the Reactor Building.

BOP Notifies Radiation Protection BOP Trips hydrogen water chemistry system.

BOP Monitors RB stack gas activity recorder 1/2-1740-203 and sees no change.

BOP/SRO Notifies Shift Manager.

BOP Dispatches an NLO to acknowledge the RWCU local panel annunciator.

SIMOP Wait 2 minutes; acknowledge RWCU panel alarm (mrf cu17r ackn) and report back that the alarms have been acknowledged.

RO Monitors reactor water level and feedwater flow.

SRO Refers to TS 3.6.1.3 and determines Condition A is applicable. 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to isolate the affected flowpath with at least 1 closed deactivated valve.

SRO/BOP Dispatches an NLO to open the breaker for the 1-1201-2 valve.

SIMOP Wait 2 minutes then override the green lights off for the 1-1201-2; ior lohs10595551 off SRO Exits QGA 300.

EVENT TERMINATION: terminate when the RWCU system is isolated and TS have been addressed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Page 5 of 11 Event

Description:

LP feedwater heater tube leak, load drop.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner, insert a tube leak in the 1A3 heater; imf fw14c 100 10:

BOP/RO Reports A3 flash tank level rising or alarm 901-6 F3 lit.

SRO Directs BOP to take actions of QCAN and/or QCOA 3500-01 BOP/RO Verifies high level in 1A3 flash tank.

NOTE It is OK for the crew to begin a load drop before the low-pressure heater string isolates. If they dont they MUST begin one after the low-pressure heater string bypass valve opens.

SRO Directs the RO to begin an emergency power reduction.

RO Begins an Emergency load reduction with recirc flow and then control rod insertion.

RO/BOP Dispatches NLO and/or Field Supervisor to investigate the high level.

SIMOP As the NLO, wait 3 minutes and report that the heater controllers appear to be operating correctly but level in the 1A3 flash tank level is high. Report that the 1A3 drain cooler LCV is full open.

BOP Reports high level in 1A3 heater as evidenced by alarm 901-6 G3 lit.

SRO Directs BOP to perform the actions of the QCAN BOP Verifies the A3 heater string isolated.

BOP Verifies the low-pressure heater string bypass valve opens.

RO Monitors for indications of thermal hydraulic instabilities.

BOP Reports 1A3 heater high-level alarm clear.

RO Reports feedwater flow <7.6 Mlbm/hr.

BOP Closes the low-pressure heater bypass valve.

BOP/SRO Contacts QNE to determine thermal limits and Chemistry to perform sampling.

EVENT TERMINATION: terminate when the low-pressure heater bypass valve is closed.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 6 of 12 Event

Description:

Failure of the A Reactor Recirc pump seals. Initiated at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner insert a recirc pump seal failure by making trigger 1 go true; trg! 1 BOP/RO Reports A recirc pump seals failing OR DW pressure rising.

SIMOP After the seal leak is identified, trip the 1A TBCCW pump; imf sw11a BOP Reports trip of the A TBCCW pump SRO Directs BOP to perform the actions for the trip of the TBCCW pump and the RO to perform the actions of QCOA 0201-1 and/or QCOA 0202-06.

BOP Starts the 1B TBCCW pump and dispatches an NLO to investigate.

RO Places the A recirc drive motor breaker control switch to TRIP.

RO Closes the 1-0202-4A, A recirc suction valve.

RO Closes the 1-0202-5A, A recirc discharge valve.

NOTE Depending on how many control rods were inserted previously additional rods may not need be inserted.

RO Verifies/inserts control rods to got less than 59.4% flow control line.

RO Monitors for indications of thermal hydraulic instabilities.

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore DW pressure to

<1.5 psig.

SIMOP Wait 3 minutes and report no apparent cause for the TBCCW pump trip.

SRO Refers to TS 3.4.1 and determines Condition C is appropriate. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to satisfy the requirements of the LCO.

EVENT TERMINATION: terminate when the 1B TBCCW pump is running, 1A recirc pump is tripped and isolated and flow control line is <59.4%.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Page 7 of 11 Event

Description:

Intake structure blockage, loss of circulating water. Initiate at the direction of the lead examiner.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP At the direction of the lead examiner insert the intake structure blockage by making trigger 3 go true; trg! 3 BOP Reports alarm 901-7 C15 lit.

SRO Directs BOP to perform the actions of the QCAN.

BOP Dispatches an NLO to the cribhouse to verify proper operation of the traveling screens.

SIMOP Wait 3 minutes then report as the NLO that there is a large quantity of fish and debris clogging the screens and several have broken shear pins.

SIMOP At the completion of the call sequentially trip the circ water pumps by making trigger 5 go true; trg! 5 BOP/RO Reports A Circ water pump trip and alarm 901-7 A15 lit.

NOTE Procedure allows operation with only 1 circ water pump but the SRO may order a reactor scram any time after the first circ water pump trips. With no circ water pump running an immediate scram is required.

SRO Directs BOP to perform the actions of the QCAN.

BOP Verifies a radwaste discharge is not in progress by calling the radwaste operator or by checking flow.

SRO/BOP Directs RO to drop load as necessary to maintain vacuum.

RO Drops load with recirc flow and rods to maintain backpressure <6.5.

BOP Reports C Circ water pump trip.

BOP Monitors B Circ water pump current and trips it if >325 amps.

BOP Reports B Circ water pump trip.

SRO Directs RO to insert a manual scram RO Inserts a manual scram EVENT TERMINATION: actions continue through the end of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 7,8 Page 8 of 11 Event

Description:

1/2 core ATWS with a failure of SBLC to inject. Turbine trip and bypass valve closure due to loss of vacuum. Initiated by the order to manually scram the reactor.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS NOTE The actions for the remainder of the scenario are split into power leg actions (pages 8 and 9), level leg actions (page 10) and pressure leg actions (page 11).

RO Reports failure to scram.

RO Moves the reactor mode switch to SHUTDOWN.

RO Actuates Alternate Rod Insertion by arming and depressing both pushbuttons on the right then left OR left then right.

RO Runs B recirc pump to minimum speed of 32%.

RO Verifies cram rods already inserted to position 00.

SRO Enters QGA 100 on reactor power above 3% with a scram required then transitions to QGA 101.

SRO *CT #1* Directs BOP to inhibit ADS and place Core Spray in PTL.

BOP *CT #1* Places ADS in INHIBIT and both Core Spray pumps in PTL.

SRO Directs RO to report ATWS actions.

RO Reports Rx Mode Switch in S/D, ARI actuated, B recirc at minimum and current reactor power.

SRO Directs RO to trip B recirc pump.

RO Trips the B recirc pump by closing the 1-0202-5 valve SRO Directs RO to insert control rods per QCOP 0300-28.

NOTE The actions directed by QCOP 0300-28 are on the following page.

SRO Directs RO to inject SLC.

RO Attempts to inject SLC by taking the control switch to 1&2 or 2&1.

Reports SLC relief valves appear to be lifting and SLC is not injecting.

RO Dispatches an NLO or MMD to investigate SLC relief valve operation.

SRO Determines SLC cannot be injected through the RWCU system due to the leak.

EVENT TERMINATION: actions continue until the end of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 7,8 Page 9 of 11 Event

Description:

1/2 core ATWS with a failure of SBLC to inject. Turbine trip and bypass valve closure due to loss of vacuum. Initiated by the order to manually scram the reactor.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS RO ACTIONS DIRECTED BY QCOP 0300-28 RO Inserts control rods per QCOP 0300-28.

RO Individually drives centrally located control rods, spiraling out RO Places the scram discharge volume bypass switch in BYPASS.

RO Resets the reactor scram by placing the reset switch in 2&3 then 1&4.

RO Notes the blue scram light lit on the full core display.

RO Directs Unit 2 (lead examiner) to bypass all scram signals per QCOP 0300-28.

LE When requested, direct the Simop to bypass the reactor scrams.

SIMOP Wait 2 minutes, bypass the reactor scrams; mrf qg08r activate then tell the lead examiner it is complete.

LE Report to the RO that the scram signals have been jumpered out per QCOP 0300-28.

RO Checks the status of the blue scram lights. If they are lit, dispatches an NLO to remove ARI fuses.

SIMOP Wait 2 minutes and remove the ARI fuses; mrf qg14r activate then call and report it complete.

RO Observes reactor pressure >700 psig and inserts a manual scram.

RO Observes no rod movement during the scram.

RO Resets the scram and directs Unit 2 to individually scram control rods.

NOTE Lead Examiner, the candidate will tell you which rods should be individually scrammed and you will relay that information to the Simop. It is expected that the candidate will order 3 or more rods attempted before determining that they are unsuccessful.

SIMOP At the direction of the lead examiner Individually scram control rods relayed to you using malfunction imf rd05rXXXX EVENT TERMINATION: actions will continue until the end of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 7,8 Page 10 of 11 Event

Description:

1/2 core ATWS with a failure of SBLC to inject. Turbine trip and bypass valve closure due to loss of vacuum. Initiated by the order to manually scram the reactor.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Observes MSIVs open and directs Unit 2 (lead examiner) to bypass isolations per QCOP 0250-02.

LE When requested, direct the Simop to bypass the MSIV isolation signals.

SIMOP Wait 1 minutes, bypass the MSIV isolation signals; mrf qg09r activate then tell the lead examiner it is complete.

LE Report to the SRO that the MSIV isolation signals have been jumpered out per QCOP 0250-02.

SRO *CT #2* Directs BOP and RO to terminate and prevent injection.

RO *CT #2* Terminates feedwater by placing all 3 FRVs in MAN and closing them and closing the MO 1-3206A and B.

NOTE The MO 1-3206A and B need not be full closed to report that terminate and prevent is complete.

RO Reports terminate and prevent complete at the 901-5 panel.

BOP *CT #2* Terminates ECCS systems by trip-latching HPCI and verifying SSMP not running.

BOP Reports terminate and prevent complete.

SRO Directs RO to report at -35 RPV level.

RO Reports -35RPV level.

SRO *CT #3* Directs RO to report when RPV level is at -142 (TAF) OR reactor power is <3% OR all ADS valves closed and DW pressure

<2.5 psig.

RO *CT #3* Reports when RPV level is at -142 (TAF) OR reactor power is <3% OR all ADS valves closed and DW pressure <2.5 psig SRO *CT #3* Directs RO to report RPV level.

RO *CT #3* Reports current RPV level corrected for the current RPV pressure.

SRO *CT #3* Directs RO to inject with feedwater to maintain level between -166 and the level it was lowered to.

RO *CT #3* Injects with feedwater by manually opening the low flow FRV and adjusts as necessary to maintain the given level band.

EVENT TERMINATION: actions continue until the end of the scenario.

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 7,8 Page 11 of 11 Event

Description:

1/2 core ATWS with a failure of SBLC to inject. Turbine trip and bypass valve closure due to loss of vacuum. Initiated by the order to manually scram the reactor.

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SRO Directs BOP to maintain RPV pressure 800-1000 psig using the turbine until it trips, then the turbine bypass valves and then the ADS valves.

BOP Monitors main condenser backpressure and transitions from turbine bypass valves to ADS valves as backpressure approaches 23 hg.

BOP Opens ADS valves by placing their control switches to MAN. If valves need to be cycled, alternates between the 1-0203-3B and 1-0203-3C BOP Starts torus cooling on at least one loop of RHR.

BOP Places Containment Cooling permissive switch to ON for the desired loop(s).

BOP Places RHRSW Start Permissive switch to MANUAL OVERRIDE for the desired loop(s).

BOP Opens the 1-1001-34 for the desired loop.

BOP Starts/verifies running 2 RHR pumps.

BOP Throttles open the 1-1001-36 for the desired loop. Establishes RHR pump discharge pressure between 100 and 250 psig.

BOP Opens 1-1001-5 approximately 40% on the desired loop(s).

BOP Starts and RHRSW pump on the desired loop(s).

BOP Closes 1-1001-16 on the desired loop(s).

BOP Throttles the 1-1001-5 to maintain RHRSW pressure at least 15-20 psig higher than RHR pressure and RHRSW flow <3600 gpm.

NOTE A line-up maximizing torus cooling would include the following; 2 RHR pumps and 1 RHRSW pump running on each loop, the 1-1001-16A and B valves would be full closed and the 1-1001-36A and B would be full open or open to a position that maintains RHR discharge pressure near 100 psig. There should also be no RPV injection flow.

SCENARIO TERMINATION: terminate when the RO is injecting and maintaining level within the given band, RPV pressure is being controlled with ADS valves, torus cooling is on and with the concurrence of the lead examiner.