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{{#Wiki_filter: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      R, 2        N/A                            Increase power with control rods SRO    N 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 to prevent 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      During withdrawal of control rod J-2, 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 annunciator 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 it was miscalibrated. No other nuclear instrumentation is affected. It can be recalibrated about an hour from now. You will write the IR.
EVENT TERMINATION: terminate when 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. Reports that the control rod is still uncoupled.
RO          If it is not bypassed, enables 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 hours 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 hours and disarm it within 4 hours.
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.
SRO/BOP    Refers to QCOA 0010-09 EARTHQUAKE SRO/BOP    Dispatches the field supervisor or IM to retrieve data from the seismograph.
SRO/BOP    Notifies the SM to consider classifying the event as a possible E-Plan condition.
SRO/BOP    Dispatches operators to inspect the plant for damage.
SIMOP      At the direction of the lead examiner, insert a steam leak in the RCIC steam supply line; imf rc11 10 SIMOP      When alarm 901-3 D3 comes in ensure 901-4 B15 is inserted; imf ano9014b15 on 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        Refers to TS 3.5.3 Condition A, identifies HPCI inop and enters Condition B OR TS 3.5.1 Condition F, identifies RCIC inop and enters Condition H. 12 hours to Mode 3 and 36 hours to reduce steam dome pressure to <150 psig.
SRO        If RCIC room temp exceeded 170 &deg;F enters TS 3.6.1.3 Condition B, 1 hour 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 U2 and 1B Instrument and the 1B and 2A 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/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.
BOP        Dispatches NLO to perform post start actions for the U2 and 1B instrument air compressors per QCOP 4700-09.
SIMOP      If dispatched, wait 2 minutes and report steps F.2.b-d (for 1B compressor) and steps F.4.b-e (for U2 compressor) are complete.
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 0 RWL and 2.5 psig DW pressure.
SRO SRO        Directs RO to perform QCGP 2-3, Reactor Scram.
RO          Performs QCGP 2-3 Attachment A SRO        Directs BOP to verify isolations for 0 RWL and 2.5 psig DW pressure.
BOP        Reports 0 isolations complete Verifies EDG, HPCI, Core Spray and RHR starts and reports 2.5 psig BOP DW pressure actions complete.
SRO        Directs BOP/RO to control RWL 0 to 48 with SSMP BOP/RO      Verifies SSMP suction pressure available.
BOP/RO      Opens MO 1/2-2901-7 valve.
BOP/RO      Starts the SSMP and verifies discharge pressure.
BOP/RO      Places flow controller in AUTO and increases the setpoint to 400 gpm.
BOP/RO      Opens MO 1-2902-8 valve.
BOP/RO      Closes MO 1/2-2901-7 valve When BOP/RO reports SSMP is injecting to Unit 1, insert a break SIMOP in A recirc pump suction line; imf rr11a 1 10:
SRO        Directs BOP/RO to begin a cooldown <100 deg F/hr with ADS valves BOP/RO      MAY begin a cooldown @ <100&deg;F by opening the ADS 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 &deg;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 Directs BOP to initiate Torus sprays before Torus pressure reaches 5 SRO psig.
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        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: 1a            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      R, 2        N/A                            Increase power with control rods    [ Event NOT used ]
SRO    N nm11a            RO 3                                  I      RBM 7 rod block below required power level[NOT used]
nm12a            SRO RO, 4        rd01r                    C, T  Control rod 26-23 uncoupled        [ Event NOT used ]
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 [that the startup is on hold].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. [ Events NOT used ]
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 to prevent 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.: 1a        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.: 1a        Event No.: 2            Page 2 of 10
[ Event NOT used ]
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.: 1a        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. [ Event NOT used ]
TIME    POSITION                    APPLICANTS ACTIONS OR BEHAVIORS SIMOP          Verify the RBM #7 gain failure is inserted; imf nm11a 100 SIMOP          During withdrawal of control rod J-2, 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 annunciator 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 it was miscalibrated. No other nuclear instrumentation is affected. It can be recalibrated about an hour from now. You will write the IR.
EVENT TERMINATION: terminate when RBM #7 is bypassed and TS have been addressed.
 
Appendix D                              Scenario Outline                            Form ES-D-2 Op-Test No.: 1        Scenario No.: 1a          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. [ Event NOT used ]
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. Reports that the control rod is still uncoupled.
RO          If it is not bypassed, enables 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 hours 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 hours and disarm it within 4 hours.
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.: 1a        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.
SRO/BOP    Refers to QCOA 0010-09 EARTHQUAKE SRO/BOP    Dispatches the field supervisor or IM to retrieve data from the seismograph.
SRO/BOP    Notifies the SM to consider classifying the event as a possible E-Plan condition.
SRO/BOP    Dispatches operators to inspect the plant for damage.
SIMOP      At the direction of the lead examiner, insert a steam leak in the RCIC steam supply line; imf rc11 10 SIMOP      When alarm 901-3 D3 comes in ensure 901-4 B15 is inserted; imf ano9014b15 on 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        Refers to TS 3.5.3 Condition A, identifies HPCI inop and enters Condition B OR TS 3.5.1 Condition F, identifies RCIC inop and enters Condition H. 12 hours to Mode 3 and 36 hours to reduce steam dome pressure to <150 psig.
SRO        If RCIC room temp exceeded 170 &deg;F enters TS 3.6.1.3 Condition B, 1 hour 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.: 1a        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 U2 and 1B Instrument and the 1B and 2A 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/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.
BOP        Dispatches NLO to perform post start actions for the U2 and 1B instrument air compressors per QCOP 4700-09.
SIMOP      If dispatched, wait 2 minutes and report steps F.2.b-d (for 1B compressor) and steps F.4.b-e (for U2 compressor) are complete.
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.: 1a        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.: 1a        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 0 RWL and 2.5 psig DW pressure.
SRO SRO        Directs RO to perform QCGP 2-3, Reactor Scram.
RO          Performs QCGP 2-3 Attachment A SRO        Directs BOP to verify isolations for 0 RWL and 2.5 psig DW pressure.
BOP        Reports 0 isolations complete Verifies EDG, HPCI, Core Spray and RHR starts and reports 2.5 psig BOP DW pressure actions complete.
SRO        Directs BOP/RO to control RWL 0 to 48 with SSMP BOP/RO      Verifies SSMP suction pressure available.
BOP/RO      Opens MO 1/2-2901-7 valve.
BOP/RO      Starts the SSMP and verifies discharge pressure.
BOP/RO      Places flow controller in AUTO and increases the setpoint to 400 gpm.
BOP/RO      Opens MO 1-2902-8 valve.
BOP/RO      Closes MO 1/2-2901-7 valve When BOP/RO reports SSMP is injecting to Unit 1, insert a break SIMOP in A recirc pump suction line; imf rr11a 1 10:
SRO        Directs BOP/RO to begin a cooldown <100 deg F/hr with ADS valves BOP/RO      MAY begin a cooldown @ <100&deg;F by opening the ADS 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 &deg;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.: 1a        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 Directs BOP to initiate Torus sprays before Torus pressure reaches 5 SRO psig.
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        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.: 1a        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:    3a            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 is 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 [ Event NOT used ]
SRO lohs156041a4 4        ed02              SRO      T      Loss of Reserve Aux Transformer 12 RO        R, 5        N/A                                Load drop with recirc flow SRO      N 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 is 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). [ Event NOT used ]
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 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
* 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 GREEN.
OOS equipment:
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:
None 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.: 3a          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/BOP      Monitors reactor and balance of plant parameters and determines no valid Core Spray start signal exists.
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.: 3a          Event No.: 2            Page 2 of 9 Event
 
== Description:==
Control rod 38-43 (K-11) 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 38-43; imf rd04r3843 SIMOP      When control rod 38-43 reaches position 03 delete the rod drift; dmf rd04r3843 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 38-43 is 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 38-43 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 38-43 to position 00 using a continuous insert signal.
RO          Resets the rod drift alarm with its reset switch and resets the RWM alarm by turning the rod select power to off then on.
BOP/SRO    Notifies QNE of mispositioned control rod and that it has been repositioned.
RO/BOP      Runs an OD-20.
SIMOP      If asked whether an OD-8 is required, reply that it is not needed and that you will check on thermal limits.
BOP/SRO    Notifies shift operations supervisor and ops manager.
SRO        Refers to TS 3.1.3 and determines Condition C applies. 3 hours to fully insert control rod 38-43 and 4 hours to disarm it.
BOP        Dispatches NLO to disarm control rod 38-43.
SIMOP      Wait 2 minutes and disarm the control rod; irf rd06r3843r inop.
Report control rod 38-43 has been disarmed.
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.: 3a          Event No.: 3            Page 3 of 9
[ Event NOT used ]
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. (Directions to throttle the valve are contained in QOP 5600-01.)
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.: 3a        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 hour.
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 hour to perform SR 3.8.1.1 (QCOS 0005-08), 24 hours 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.: 3a        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. Directed by QOA 6100-01 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 per QCOP 3200-05.
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.
SIMOP        If the crew decides to halt the pump swaps, call in as the Shift Manager and direct them to continue.
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.: 3a          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, HPCI and RHR running.
BOP/RO      Reports 2.5 psig isolations and autostarts complete.
SRO          Directs HPCI to be trip-latched.
BOP          Enables the HPCI trip-latch.
SRO          Directs RO/BOP to perform a RPV cooldown at <100 &deg;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
                        &deg;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 &deg;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.: 3a        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 During the scenario both loops of DW Sprays and A loop of Torus NOTE:
Cooling and Torus Sprays will be unavailable.
SRO          Directs BOP to initiate Torus sprays BOP          Initiates Torus sprays by opening the 1-1001-34B and 37B.
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          If DW temperature has not exceeded 260 &deg;F, directs BOP to restart RBCCW and DW coolers.
BOP          If directed, 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.: 3a        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, increase 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 1001-36B 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.: 3a          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 true to flash all RPV level instruments; 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        IF 2 or more ADS valves open, directs BOP to isolate the main steam lines, steam line drains, RCIC and HPCI steam lines.
BOP        If directed by the SRO, verifies MSIVs, steam line drains, RCIC and HPCI isolations closed.
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 sprays and cooling and verifying LPCI injection valves open.
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:    3b            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 is 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 [ Event NOT used ]
RO, 2        rd04r                      C      Control rod drifts out 2 notches SRO ano9017e12, BOP 3        dihs156041a                C      Gland Steam Exhauster trip [ Event NOT used ]
SRO lohs156041a4 4        ed02              SRO      T      Loss of Reserve Aux Transformer 12 RO        R, 5        N/A                                Load drop with recirc flow SRO      N 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 is 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). [ Event NOT used ]
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). [ Event NOT used ]
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 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
* 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 GREEN.
OOS equipment:
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:
None 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.: 3b          Event No.: 1            Page 1 of 9
[ Event NOT used ]
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/BOP      Monitors reactor and balance of plant parameters and determines no valid Core Spray start signal exists.
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.: 3b          Event No.: 2            Page 2 of 9 Event
 
== Description:==
Control rod 38-43 (K-11) 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 38-43; imf rd04r3843 SIMOP      When control rod 38-43 reaches position 03 delete the rod drift; dmf rd04r3843 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 38-43 is 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 38-43 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 38-43 to position 00 using a continuous insert signal.
RO          Resets the rod drift alarm with its reset switch and resets the RWM alarm by turning the rod select power to off then on.
BOP/SRO    Notifies QNE of mispositioned control rod and that it has been repositioned.
RO/BOP      Runs an OD-20.
SIMOP      If asked whether an OD-8 is required, reply that it is not needed and that you will check on thermal limits.
BOP/SRO    Notifies shift operations supervisor and ops manager.
SRO        Refers to TS 3.1.3 and determines Condition C applies. 3 hours to fully insert control rod 38-43 and 4 hours to disarm it.
BOP        Dispatches NLO to disarm control rod 38-43.
SIMOP      Wait 2 minutes and disarm the control rod; irf rd06r3843r inop.
Report control rod 38-43 has been disarmed.
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.: 3b        Event No.: 3            Page 3 of 9
[ Event NOT used ]
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. (Directions to throttle the valve are contained in QOP 5600-01.)
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.: 3b        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 hour.
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 hour to perform SR 3.8.1.1 (QCOS 0005-08), 24 hours 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.: 3b          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. Directed by QOA 6100-01 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 per QCOP 3200-05.
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.
SIMOP        If the crew decides to halt the pump swaps, call in as the Shift Manager and direct them to continue.
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.: 3b          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, HPCI and RHR running.
BOP/RO      Reports 2.5 psig isolations and autostarts complete.
SRO          Directs HPCI to be trip-latched.
BOP          Enables the HPCI trip-latch.
SRO          Directs RO/BOP to perform a RPV cooldown at <100 &deg;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
                        &deg;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 &deg;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.: 3b          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 During the scenario both loops of DW Sprays and A loop of Torus NOTE:
Cooling and Torus Sprays will be unavailable.
SRO          Directs BOP to initiate Torus sprays BOP          Initiates Torus sprays by opening the 1-1001-34B and 37B.
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          If DW temperature has not exceeded 260 &deg;F, directs BOP to restart RBCCW and DW coolers.
BOP          If directed, 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.: 3b        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, increase 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 1001-36B 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.: 3b          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 true to flash all RPV level instruments; 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        IF 2 or more ADS valves open, directs BOP to isolate the main steam lines, steam line drains, RCIC and HPCI steam lines.
BOP        If directed by the SRO, verifies MSIVs, steam line drains, RCIC and HPCI isolations closed.
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 sprays and cooling and verifying LPCI injection valves open.
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.}}

Revision as of 21:49, 22 December 2019

Final As-Administed Scenarios for the Quad Cities Initial Examination - May 2005
ML051610320
Person / Time
Site: Quad Cities  Constellation icon.png
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: ML051610320 (58)
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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 R, 2 N/A Increase power with control rods SRO N 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 to prevent 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
  • 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 During withdrawal of control rod J-2, 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 annunciator 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 it was miscalibrated. No other nuclear instrumentation is affected. It can be recalibrated about an hour from now. You will write the IR.

EVENT TERMINATION: terminate when 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. Reports that the control rod is still uncoupled.

RO If it is not bypassed, enables 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.

SRO/BOP Refers to QCOA 0010-09 EARTHQUAKE SRO/BOP Dispatches the field supervisor or IM to retrieve data from the seismograph.

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

SRO/BOP Dispatches operators to inspect the plant for damage.

SIMOP At the direction of the lead examiner, insert a steam leak in the RCIC steam supply line; imf rc11 10 SIMOP When alarm 901-3 D3 comes in ensure 901-4 B15 is inserted; imf ano9014b15 on 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 Refers to TS 3.5.3 Condition A, identifies HPCI inop and enters Condition B OR TS 3.5.1 Condition F, identifies RCIC inop and enters Condition H. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to Mode 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reduce steam dome pressure to <150 psig.

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 U2 and 1B Instrument and the 1B and 2A 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/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.

BOP Dispatches NLO to perform post start actions for the U2 and 1B instrument air compressors per QCOP 4700-09.

SIMOP If dispatched, wait 2 minutes and report steps F.2.b-d (for 1B compressor) and steps F.4.b-e (for U2 compressor) are complete.

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 0 RWL and 2.5 psig DW pressure.

SRO SRO Directs RO to perform QCGP 2-3, Reactor Scram.

RO Performs QCGP 2-3 Attachment A SRO Directs BOP to verify isolations for 0 RWL and 2.5 psig DW pressure.

BOP Reports 0 isolations complete Verifies EDG, HPCI, Core Spray and RHR starts and reports 2.5 psig BOP DW pressure actions complete.

SRO Directs BOP/RO to control RWL 0 to 48 with SSMP BOP/RO Verifies SSMP suction pressure available.

BOP/RO Opens MO 1/2-2901-7 valve.

BOP/RO Starts the SSMP and verifies discharge pressure.

BOP/RO Places flow controller in AUTO and increases the setpoint to 400 gpm.

BOP/RO Opens MO 1-2902-8 valve.

BOP/RO Closes MO 1/2-2901-7 valve When BOP/RO reports SSMP is injecting to Unit 1, insert a break SIMOP in A recirc pump suction line; imf rr11a 1 10:

SRO Directs BOP/RO to begin a cooldown <100 deg F/hr with ADS valves BOP/RO MAY begin a cooldown @ <100°F by opening the ADS 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 Directs BOP to initiate Torus sprays before Torus pressure reaches 5 SRO psig.

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 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: 1a 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 R, 2 N/A Increase power with control rods [ Event NOT used ]

SRO N nm11a RO 3 I RBM 7 rod block below required power level[NOT used]

nm12a SRO RO, 4 rd01r C, T Control rod 26-23 uncoupled [ Event NOT used ]

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 [that the startup is on hold].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. [ Events NOT used ]

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 to prevent 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
  • 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.: 1a 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.: 1a Event No.: 2 Page 2 of 10

[ Event NOT used ]

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.: 1a 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. [ Event NOT used ]

TIME POSITION APPLICANTS ACTIONS OR BEHAVIORS SIMOP Verify the RBM #7 gain failure is inserted; imf nm11a 100 SIMOP During withdrawal of control rod J-2, 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 annunciator 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 it was miscalibrated. No other nuclear instrumentation is affected. It can be recalibrated about an hour from now. You will write the IR.

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

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 1a 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. [ Event NOT used ]

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. Reports that the control rod is still uncoupled.

RO If it is not bypassed, enables 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.: 1a 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.

SRO/BOP Refers to QCOA 0010-09 EARTHQUAKE SRO/BOP Dispatches the field supervisor or IM to retrieve data from the seismograph.

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

SRO/BOP Dispatches operators to inspect the plant for damage.

SIMOP At the direction of the lead examiner, insert a steam leak in the RCIC steam supply line; imf rc11 10 SIMOP When alarm 901-3 D3 comes in ensure 901-4 B15 is inserted; imf ano9014b15 on 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 Refers to TS 3.5.3 Condition A, identifies HPCI inop and enters Condition B OR TS 3.5.1 Condition F, identifies RCIC inop and enters Condition H. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to Mode 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reduce steam dome pressure to <150 psig.

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.: 1a 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 U2 and 1B Instrument and the 1B and 2A 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/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.

BOP Dispatches NLO to perform post start actions for the U2 and 1B instrument air compressors per QCOP 4700-09.

SIMOP If dispatched, wait 2 minutes and report steps F.2.b-d (for 1B compressor) and steps F.4.b-e (for U2 compressor) are complete.

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.: 1a 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.: 1a 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 0 RWL and 2.5 psig DW pressure.

SRO SRO Directs RO to perform QCGP 2-3, Reactor Scram.

RO Performs QCGP 2-3 Attachment A SRO Directs BOP to verify isolations for 0 RWL and 2.5 psig DW pressure.

BOP Reports 0 isolations complete Verifies EDG, HPCI, Core Spray and RHR starts and reports 2.5 psig BOP DW pressure actions complete.

SRO Directs BOP/RO to control RWL 0 to 48 with SSMP BOP/RO Verifies SSMP suction pressure available.

BOP/RO Opens MO 1/2-2901-7 valve.

BOP/RO Starts the SSMP and verifies discharge pressure.

BOP/RO Places flow controller in AUTO and increases the setpoint to 400 gpm.

BOP/RO Opens MO 1-2902-8 valve.

BOP/RO Closes MO 1/2-2901-7 valve When BOP/RO reports SSMP is injecting to Unit 1, insert a break SIMOP in A recirc pump suction line; imf rr11a 1 10:

SRO Directs BOP/RO to begin a cooldown <100 deg F/hr with ADS valves BOP/RO MAY begin a cooldown @ <100°F by opening the ADS 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.: 1a 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 Directs BOP to initiate Torus sprays before Torus pressure reaches 5 SRO psig.

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 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.: 1a 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: 3a 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 is 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 [ Event NOT used ]

SRO lohs156041a4 4 ed02 SRO T Loss of Reserve Aux Transformer 12 RO R, 5 N/A Load drop with recirc flow SRO N 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 is 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). [ Event NOT used ]

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 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

  • Take the following OOS:

o Place an info tag on the 1-0263-29B o Place the 1B TBCCW pump in PTL

  • 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 GREEN.

OOS equipment:

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:

None 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.: 3a 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/BOP Monitors reactor and balance of plant parameters and determines no valid Core Spray start signal exists.

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.: 3a Event No.: 2 Page 2 of 9 Event

Description:

Control rod 38-43 (K-11) 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 38-43; imf rd04r3843 SIMOP When control rod 38-43 reaches position 03 delete the rod drift; dmf rd04r3843 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 38-43 is 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 38-43 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 38-43 to position 00 using a continuous insert signal.

RO Resets the rod drift alarm with its reset switch and resets the RWM alarm by turning the rod select power to off then on.

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

RO/BOP Runs an OD-20.

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

BOP/SRO Notifies shift operations supervisor and ops manager.

SRO Refers to TS 3.1.3 and determines Condition C applies. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to fully insert control rod 38-43 and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to disarm it.

BOP Dispatches NLO to disarm control rod 38-43.

SIMOP Wait 2 minutes and disarm the control rod; irf rd06r3843r inop.

Report control rod 38-43 has been disarmed.

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.: 3a Event No.: 3 Page 3 of 9

[ Event NOT used ]

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. (Directions to throttle the valve are contained in QOP 5600-01.)

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.: 3a 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.: 3a 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. Directed by QOA 6100-01 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 per QCOP 3200-05.

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.

SIMOP If the crew decides to halt the pump swaps, call in as the Shift Manager and direct them to continue.

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.: 3a 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, HPCI and RHR running.

BOP/RO Reports 2.5 psig isolations and autostarts complete.

SRO Directs HPCI to be trip-latched.

BOP Enables the HPCI trip-latch.

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.: 3a 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 During the scenario both loops of DW Sprays and A loop of Torus NOTE:

Cooling and Torus Sprays will be unavailable.

SRO Directs BOP to initiate Torus sprays BOP Initiates Torus sprays by opening the 1-1001-34B and 37B.

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 If DW temperature has not exceeded 260 °F, directs BOP to restart RBCCW and DW coolers.

BOP If directed, 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.: 3a 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, increase 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 1001-36B 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.: 3a 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 true to flash all RPV level instruments; 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 IF 2 or more ADS valves open, directs BOP to isolate the main steam lines, steam line drains, RCIC and HPCI steam lines.

BOP If directed by the SRO, verifies MSIVs, steam line drains, RCIC and HPCI isolations closed.

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 sprays and cooling and verifying LPCI injection valves open.

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: 3b 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 is 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 [ Event NOT used ]

RO, 2 rd04r C Control rod drifts out 2 notches SRO ano9017e12, BOP 3 dihs156041a C Gland Steam Exhauster trip [ Event NOT used ]

SRO lohs156041a4 4 ed02 SRO T Loss of Reserve Aux Transformer 12 RO R, 5 N/A Load drop with recirc flow SRO N 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 is 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). [ Event NOT used ]

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). [ Event NOT used ]

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 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

  • Take the following OOS:

o Place an info tag on the 1-0263-29B o Place the 1B TBCCW pump in PTL

  • 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 GREEN.

OOS equipment:

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:

None 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.: 3b Event No.: 1 Page 1 of 9

[ Event NOT used ]

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/BOP Monitors reactor and balance of plant parameters and determines no valid Core Spray start signal exists.

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.: 3b Event No.: 2 Page 2 of 9 Event

Description:

Control rod 38-43 (K-11) 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 38-43; imf rd04r3843 SIMOP When control rod 38-43 reaches position 03 delete the rod drift; dmf rd04r3843 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 38-43 is 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 38-43 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 38-43 to position 00 using a continuous insert signal.

RO Resets the rod drift alarm with its reset switch and resets the RWM alarm by turning the rod select power to off then on.

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

RO/BOP Runs an OD-20.

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

BOP/SRO Notifies shift operations supervisor and ops manager.

SRO Refers to TS 3.1.3 and determines Condition C applies. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to fully insert control rod 38-43 and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to disarm it.

BOP Dispatches NLO to disarm control rod 38-43.

SIMOP Wait 2 minutes and disarm the control rod; irf rd06r3843r inop.

Report control rod 38-43 has been disarmed.

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.: 3b Event No.: 3 Page 3 of 9

[ Event NOT used ]

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. (Directions to throttle the valve are contained in QOP 5600-01.)

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.: 3b 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.: 3b 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. Directed by QOA 6100-01 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 per QCOP 3200-05.

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.

SIMOP If the crew decides to halt the pump swaps, call in as the Shift Manager and direct them to continue.

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.: 3b 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, HPCI and RHR running.

BOP/RO Reports 2.5 psig isolations and autostarts complete.

SRO Directs HPCI to be trip-latched.

BOP Enables the HPCI trip-latch.

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.: 3b 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 During the scenario both loops of DW Sprays and A loop of Torus NOTE:

Cooling and Torus Sprays will be unavailable.

SRO Directs BOP to initiate Torus sprays BOP Initiates Torus sprays by opening the 1-1001-34B and 37B.

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 If DW temperature has not exceeded 260 °F, directs BOP to restart RBCCW and DW coolers.

BOP If directed, 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.: 3b 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, increase 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 1001-36B 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.: 3b 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 true to flash all RPV level instruments; 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 IF 2 or more ADS valves open, directs BOP to isolate the main steam lines, steam line drains, RCIC and HPCI steam lines.

BOP If directed by the SRO, verifies MSIVs, steam line drains, RCIC and HPCI isolations closed.

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 sprays and cooling and verifying LPCI injection valves open.

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.

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