ML17213A266

2017 Fermi Initial License Exam-Administered Exam D-1 D-2 Scenarios

ML17213A266
Person / Time
Site:	Fermi
Issue date:	04/03/2017
From:	Bielby M E Operations Branch III
To:	NRC/RGN-III/DRS/OLB
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ML17061A756	List: ML17150A088 ML17150A090 ML17150A105 ML17213A257 ML17213A266 ML17213A272
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Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No.: t Op-Test No.: 2017-1 Examiners Operators:

sRol(cRs) sRo2(ATc)

Ro1(BOP)sRo3(cRs)

Ro2(ATC) RO3(BOP)SURR(CRS)

RO4(ATC) RO5(BOP)lnitial Conditions:

@Turnover:

The plant has been operatins at 100 % Reactor power. #5 Circ Water Pump is OOS for motor replacement.

Expected return to service is two weeks.Event No.Malf. No.Event Type*Event Description T c51MF0003 r(Arc)r(sRo)APRM Downscale - Bypass APRM 3 - TS 3.3.2.1 Tracking 2 NGADN302lC OO2TVSP#2ICV Unitized Actuator Failure (Oil Leak) - 4D2 R(ArC)R(SRO)Reduce Reactor Power < 93%to lock down #2 TCV c(BoP)c(sRo)Lock Down #2 TCV - 23.L09, Main Turbine 3 BADC82lN09 6ATVSP TS(SRO)Cond. Pressure lnstrument Failure CRS enters TS 3 3.6.14.1 (FUNCTION 1.d)4 c93RF0001 c97MF1087 NA Earthquake - AOP 20.000.01-AOP Actions 5 E51MF0010 EOPRFOO24 EOPRFOO25 c(BoP)c(sRo)rs(sRo)RCIC Steam Leak. Auto lsolation Fails EOP 29.100.01 Sheet 5 CRS enter TS 3.5.3, A.1 & 4.2 Manual isolation Successful 6 R11"MF3471 M(CREW)Loss of 65D - AOP 20.300.65D - Mode Switch to S/D EOP 29.100.01 Sheet 1 - RPV Control Loss of High Pressure Feed Sources E41MF0009 C(BOP or ATC)Auto Start Failure of HPCI. Manual Start Successfully

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No.t Oo-Test No.: 2017-1 Examiners:

Operators:

lnitial Condtions:

lC-20, MOL, 100% Rx. Power Event No.Malf. No.Event Type*Event Description 7 831MF0066 M(CREW)Leak in drywell - EOP 29.100.01 Sheet 2 - Primary Containment Control lnhibit ADS (CT-l, RPV-LEVEL)

Emergency Depressurization EOP 29'100.01 Sheet 3 -Open 5 SRV before -25" (C1-2, RPV-ED)Restore level 173 to 214 following ED (CT-3, RPV-TAF)E21RF0005 C(BOP or ATC)c(sRo)Auto Start Failure - Div' 1 Core Spray 8 E11MF0016 C(BOP or ATC)c(sRo)Containment Spray Valve Failure E1150-F016A/B Torus Cooling and Sprays Spray Drywell (CT 4, PC-DWS)*(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Setup: Full power lC 20, Red tag on #5 CWP, verify 23.205 HPCI SOP attachment 5 clean copy in procedure.

Scenario 2OL7 -L Overview plant has been operating at 100% power, #5 Circ Water Pump is OOS for motor replacement' Expected returntoserviceistwoweeks.

Nootherequipmentisoutofservice, Plansfortheshiftaretomaintain power.Event l-: APRM 3 fails downscale, Crew responds and bypasses APRM 3. CRS TS call.Event 2: #2 TCV Unitized actuator develops an oil leak. Alarms are manually set, so no actualtime pressure to respond. Crew should reduce reactor powerto less than9t.5%, then lock down and shutdown #2TCV, then reset lz SCtflr.Event 3: single condenser pressure transmitter failure. This will result in % isolation NSSSS.Event 4: seismic event. Only required to enter the AOP and START directing the actions.Event 5: Steam leak. Field report should clue the shift as to the location (RCIC), and the crew should isolate the steam leak per the AOP 2O.OOO.O2.

CRS evaluates TS. BOP should verify HPCI in SB.Event 6-8: Loss of 65D, results in loss of Feed. lmmediate action should place the mode switch in S/D Blown fuse on N2103-F001 will prevent use of SBFW. HPCI will fail to start, but will start manually.once level recovers to a predetermined value (L40") HPCI will isolate and a small LoCA will start on a ramp. This will force the crew to ED for level. Div 1 CSS willfail to start automatcally as well as the injection valve. Both should be identified and actions by the operator will make these work' E1150-FOL6A/8 (first selected) will fail, forcing the crew to align to the other division.

? 4? I{PCV UA FAILUREârori {É ersti rr Cto És ENT 3 COT.ID FRSS INS SÉl5MlC SETUP lng*rl l{Gl a'l I'..). 2 - tl -' ..17-1 sct{ 1 4 .., EIiENlVE.NT 5 SfEAt!l cLosE F007 ,-::::r't;i.-

,ç-l i -, -..:, -:l HFP 1rps locked rn o lrql rffiFO on*û ofo LEVEL LOWERS to 135 In3?rtû0 N UPT]RE RECIRC LOOP]R DrV 1 CS EVEIT 10 a.1' l.iv='n;i;:iCo' lí'b tt*ri oF E1150-F168

'.r..: ...i',. i:.:,_-:;l: , l'-- t r li ll b Required Operator Actions Form ES-D-2 Appendix D Page 1 of 1 Op-Test No,: 2017-1 Scenario No.: 1 Event No.: N/A Event

Description:

Overview lnitial Conditions:

The plant has been operating at 100 % Reactor power. #5 Circ Water Pump is OOS for motor replacement.

Expected return to service is two weeks.The objectives of this scenario are to: 1. Recognize, respond to, and take the required actions for an instrument

/ equipment failures requiring the use of operator and Tech Spec actions. '2. Recognize and respond to an APRM Downscale.

3. Recognize and respond to an cond. Pressure lnstrument Failure 4. Recognize and respond to a Unitized Actuator Failure.5. Recognize and respond to a Seismic Event.6. Recognize and respond to a RCIC Steam Leak 7. Recognize and respond to Loss of Bus 65D L Recognize and respond to LOCA conditions.

9. Operate RHR in all modes for Primary Containment Control.10. Execute steps in Primary Containment Controland operate the RHR System to control Drywell and Torus Temperature and Pressure.11. Execute the steps of RPV Control for level (L) and pressure (P)'1,2. Direct and supervise the Shift team during Normal, Abnormal, and Emergency operations.

The crew will be required to respond to the following order of events:. APRM Downscale - BYPass APRM 3 Failure#2TCV Unitized Actuator - Oil leak Reactor Power reduction to <91.5% Power r Cond. Pressure lnstrument Failure Earthquake o RCIC Steam Leak Loss of Bus 65D/Auto Start Failure of HPCI. Leak in Drywell b Req uired Operator Actions Form ES-D-2 Appendix D Op-Test No,: 2017-1 Scenario No.: 1 Event

Description:

APRM downscale Page 2 of 12 Event No.: I licant's Actions or Behavior App Position Time MALF: C51MF0003, APRM Downscale+2 min SRO. Respond to 3D98,3D113. Enter TS 3.3.1.1 Tracking Enter TR 3.3.2.1 Tracking. Direct APRM 3 bYPassed Per 23.605 ATC. Respond to 3D98, 3D113 r Report APRM 3 reading downscale. Dispatch operator to Relay Room to check APRM 3 ROLE PLAY: Report APRM 3 reading downscale, nothing else abnormal. Bypass APRM 3 Per 23.605 o Dispatch operator to Relay Room to check APRM 3 ROLE PLAY: Report APRM 3 Blue Bypass light is on'BOP o May direct operator to RelaY Room ROLE PLAY: RePort APRM 3 reading to Check APRM 3 downscale, nothing else abnormal.. Monitors plant conditions b Reouired Ooerator Actions Form ES-D-2 Appendix D Op-Test No.: 2017-l Scenario No': 1 Event No': 2 Event

Description:

1. 2 HPCV Unitized Actuator Failure, Lock Down #2 TCV - 23.109, Main Turbine Page 3 of 12 Position cant's Actions or Behavior Appli Time MALF: NG12N302lLSEN236BTFCLOSE

1. 2TCV UA LL Alarm+8m Respond to 4D2, Unitized Actuator Throttle Vlv Fa Briefs crew on actions for UA Failure.Briefs Power Reduction to lock-down UA.Directs power reduction to <91.5% per soP 23.109 prerequisite for closing #2HPCV.Monitors power reduction to <91.5%.Plant announcement of power reduction a a a a a a a ult.Directs lockdown of #2 HPCV SRO Monitors plant conditions.

Lower reactor power by reduction of reactor recirculation pump speed per SOP 23.138.01.

Reports power less than 91.5% when completed' a a a a May request rounds oPe rator monitor Recirc oil temperatures ATC BOP Respond lo 4D2, Unitized Actuator Throttle Vlv Fault'Direct operator to investigate

1. 2 HPCV Unitized Actuator'ROLE PLAY: Report leak inside uA enclosure.

Gannot see where leak is coming from, oilspray obscuring window' No leakage outside uA enclosure.

standing by in low dose area. lf crew shuts off pump before role play, don't report oil spray in enclosure' lf upd-ate requested, report conditions unchanged' Perform #2 HPCV lock-down per 23'109 Section 7'l ' Raise Load Demand till it stops rising with speed/Load raise push-button.

oPlaceSteamValveonLoadTestModeSelectswitchtol0%

o Depress SELECT Pushbutton for #2 HPCV'r Open N30-39-F613, HP Turb Loop B Line Drain Valve'r Depress VALVE TEST Pushbutton'. Depress TRIP SOLENOID A and TRIP SOLENOID B pushbuttons.

r Depress CANCEL TEST Pushbutton o Perform #2 HPCV UA shutdown per 23.'110.o Place UA to be shutdown in OFF.o Directs rounds operator to close TBCCW Valve for shutdown UA (P4300-F091 E).ROLE PLAY: Rounds operator reports TBCCW valve to #2 HPGV Unitized Actuator closed (P4300'F091E)

May ask for pressure, report glass still has oil on it, cannot read right now.o Depress SelecUlocked Closed pushbutton.

r Depress VALVE TEST Pushbutton.

o Depress TRIP RESET Pushbutton.

Reset Half scram bY cYcling reset a a a b Appendix D Reouired Operator Actions Form ES-D-2 Op-Test No.: 2017-1 Scenario No.: 1 Event No':-l Page 4 of 12 Event

Description:

Cond. Pressure lnstrument Failure Time Position Ap plicant's Actions or Behavior+30m MALF: BADCB2IN096ATVSP Cond Press lnst Fail SRO a a a Responds to alarms (1D39).Review 23.601 for failed instrument.

Enters TS 3 3.6.1, FUNCTION 1.d Condition A A.1 place channel in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Contact Tagging Center and/or Work Control for assistance with failed instrument.

Brief TS Action.a a BOP Responds to alarms (1D39).Monitors Condenser Pressure.Review 23.601 for failed instrument.

Dispatch operator to Testability.

ROLE PLAY: When dispatched to Testability Cabinets, wait about 3 min, and report 821-N6964 indicates upscale with RED TRIP light ON.

b Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:2017-1 Scenario No.: 1 Event No.: 4 Page 5 of 12 Event

Description:

Seismic Event Time Position Applicant's Actions or Behavior T+35m MALF: C97MF1087 6D69 - Seismic System EvenUTrouble MALF: C93RF000l Earthquake Sound SRO a a a a Responds to Seismic Event and enters 20.000.01, Acts of Nature'Briefs Crew on Seismic event.Makes Hi-Com announcement of event.Directs Monitoring the following for abnormal values: o Reactor Vessel Level.o Reactor Vessel Pressure.o Reactor Power.o Drywell Pressure.o Torus Water Level.o Drywell Unidentified Leakage.o Process Radiation Monitors.o Spent Fuel PoolWater Level.o Spent Fuel PoolTemPerature.

Directs seismic event actions for Condition AA & AC'May contact offsite agencies to confirm Earthquake.

ROLE PLAY: if contacted as offsite agency, confirm a a earthq uake at 0.02G horizontal and 0.02G vertical ATC a Monitors Power, Pressure and Level as directed by SRO for the seismic event.May dispatch operators to perform visual inspection of plant a systems.

b Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:20'17-1 Scenario No.: 1 Event No.: 4 Page 6 of 12 Event

Description:

Seismic Event Time Position Applicant's Actions or Behavior BOP Responds to alarm 6D69, Seismic Event/Trouble.

r Dispatches an operator to the relay room to check status of Seismic Panel indications (RR H11-P831) per 23.612'. ROLE PLAY: Operator reports from the relay room that seismic event has occurred with an indication of 0'02 G Horizontaland 0.02G Vertical-red ERROR LED is OFF'o Reports Relay Room indications of 0.02 G. horizontal and 0.02G verticalto CRS.NOTE: The following actions may be briefed but do not have to be completed prior to proceeding with next event.a Starts all RHRSW MDCT Fans and checks for proper running indications.

ROLE PLAY: When directed, report satisfactory operation of MDCT fans following start'Directs rounds operator to reset D1 and D2 CCHVAC Purge Compressors.

ROLE PLAY: When directed, after about 5 min, report Dl and D2 CCHVAC Purge Compressors are reset'May dispatch operators to perform visual inspection of plant systems.a a a a NOTE: Perform role play just prior to initiating next event'a ROLE PLAY: As part of seismic walk down prior to triggering steam leak, Rounds Operator report I foot steam plume from packing gland area of E5150-F045' b Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:2017-1 Scenario No.Event

Description:

RCIC Steam Leak.I Event No.: 5 PageT ot 12 Time Position Applicant's Actions or Behavior T+45m MALF: EslMF00l0, RCIC Steam Leak SRO Respond to 1D66, 1D70, 16D27, 8D46 and 17D46'Enter 29.100.01 Sheet 5.Determine rising room temperature in RCIC/Core Spray room and RB pressure High.Enter 29.100.01 Sheet 5, Secondary Containment Control.May direct RCIC isolation.

Validate isolation of leak by monitoring for lowering room temperatures.

Enter TS 3.5.3 RCIC, 1. 3.5.3 4.1 Verify HPCI Operable, lmmediately

2. 3.5.3 4.2 ) Restore RCIC, 14 daYs 3. Orders Tech Spec actions for TS 3.5'3 RCIC a a a a a a a ATC Monitors plant conditions.

BOP Respond to 1D6, 1D70,16D27, 8D46 and 17D46.Monitor RClc system and determine RClc Automatic isolation did NOT occur lF room temperature exceeds 154'.(IPCS ARM Screen)Manually isolate RCIC System by closing E5150-F007 and E51 50-F008.Validate isolation of leak by monitoring for lowering room temperatures.

Perform Tech Spec actions for TS 3.5.3 RCIC (verify HPCI oPERABLE)a a a a b Appendix D Reouired Operator Actions Form ES-D-2 8of12 Op-Test No.:2017-1 Scenario No.: 1 Event No,: 6 Event Description Applicant's Actions or Behavior Time Position MALF: E41 MF0009, HPCI autostart Failure T+55m SRO Directs Mode Switch to Shutdown per AOP 20.300.65D.

Directs Scram reports from ATC and BOP.Enters EOP 29.100.01, Sheet 1 , RPV Control.Establishes Level band of 1731o 214 inches and pressure band of 900 to 1050 psig.May direct ATC to perform Scram Procedure AOP 20.000.21.

Expands Level band to 0 to 214 inches.Briefs crew on options and intended course of action May order attempt to restart Center HFP.Directs start of SLC PumP.Directs start of HPCI.a a a a a a a a ATC a a a a a a Places Reactor Mode Switch in Shutdown due to loss of all high pressure Feed or CRS direction from AOP Provides Scram report.Verifies all control rods are fully inserted.May report HPClAuto Start Failure.Starts A or B SLC PumP.May attempt to restart Center HFP.Manually Starts HPCI to raise level.a BOP Provides scram rePort.May dispatch operator to 65D Bus in BOP Swgr Room to investigate.

ROLE PLAY: lf dispatched to 65D Bus, after about 5 min, report 64 Ground Fault Relay has actuated.Reports SBFW unavailable due to F001 failure.Reports HPCI Auto Start failure.Manually Starts HPClto raise level.May attempt to restart Center HFP.May dispatch operator to N2103-F001 valve.May dispatch operator to N2103-F001 power supply (2PC-1-54) to turn it off, to allow manual operation of SBFW.ROLE PLAY: lf dispatched to SBFW injection N2103 F00l valve, after about 5 min, report unable to manually open valve ROLE PLAY: lf dispatched to 2PC'1'5A, after about 5 min, turn off 2PC-l -5A, and report it is off'ROLE PLAY: tf ordered to manually open SBFW injection N2103-F001 report itwill not open and request mechanical maintenance assistance.

a a a a a a b Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:2017-1 Scenario No.: 1 Event No.: 7 Event

Description:

Recireulation Loop Rupture, ED, Level recoverv.

Core Sprav Auto Start Failure.Page 9 of 12 Time Position Applicant's Actions or Behavior T+65m MALF: 831MF0066, Recirc Loop Rupture A MALF: E2lRFOOOS, Auto Start Failure - Div. I CS SRO Enters EOP 29.100.01 Sheet 2, Primary Containment Control.Establishes Level band of 173 to 214 inches, expands band to 0 to 214 inches.May order attempt to restart Center HFP.Conduct EOP Brief.Directs ADS inhibited (CT-í, RPV-LEVEL).

Orders second CRD PumP started.Orders SLC injection.

Conduct Brief for Emergency Depressurization' May order DW Pneumatics bypassed and restored.Enter 29.100.01, Sheet 3, Emergency Depressurization.

At TAF and before -25", Direct 5 ADS SRVs opened. (CT-2' RPV-ED)Directs placing RHR in Torus Cooling and Torus Spray.Directs level band of fi3 b 214 following ED. (CT-3, RPV'TAF)a ATC Reports rising Drywell Pressure.May attempt to restart Center HFP.May start second CRD PumP started.May perform SLC injection.

Coordinate with BOP to shutdown/operate LP Pumps to restore and maintain RPVwater level 173 to214 inches. (CT'3' RPV'TAF)Places RHR in Torus Cooling and Torus Spray as directed.May bypass and restore DW pneumatics.

ROLE PLAY lf dispatched, after 5 min report, report D 1(D2)Radiation Monitor Sample Pump in service'a a a a BOP Reports rising Drywell Pressure.May attempt to restart Center HFP.Reports unable to maintain RPV levelwith available high pressure sources.May start second CRD PumP started.May perform SLC injection.

Reports Division 1 Core Spray Pumps failed to start, manually starts/align Division 1 Core Spray Pumps.lnhibits ADS. (CT-l, RPV-LEVEL)

Opens 5 SRVs as directed. (CT'2, RPV-ED)Coordinate with ATC to shutdown/operate LP Pumps to restore and maintain RPVwater level 173 to214 inches' (CT'3' RPV-TAF)May bypass and restore DW pneumatics.

ROLE PLAY lf dispatched, after 5 min report, report D f (D2)Radiation Monitor Sample Pump in service.a a a a a a a a a a a b Required Operator Actions Form ES-D-2 Appendix D Event

Description:

Containment Coolinq and Failures Page 10 of 1 Op-Test No.:2017-1 Scenario No.: 1 Event No.: 12 Applicant's Actions or Behavior Position Time MALF: E1 lMFOO16/17' Gontainment Spray Valve Failure E1150'F16A/8 T+75m Directs placing RHR in Torus Cooling and Torus Spray order E1 1 50-F010 closed)When Torus Pressure reached 9 psig directs Drywell Spray after Rácirc Pumps verified OFF and stopping all Drywell Cooling Fans Directs securing Drywelland Torus Sprays before Drywelland Torus Pressure reach 0 Psig.Monitors DWSIL curve prior to spraying drywell'on Division 1 or 2 RHR. (CT 4, PC'DWS)a a a a (Mav Directs DrywellSPraY SRO Verify or Shutdown the Reactor Recirc pumps'Shuts down all drywell cooling fans.Places RHR Div 1or 2 in Torus Cooling and Torus Sprays'o Place Containment Spray Mode Select Switch in MANUAL'o Unlock and OPen E1150-F0284 or B'o Start I RHR PumP'o Open 81150-F024 A or B.o Open 81150-F027 A or B'o Partially oPen E1150-F068 A or B'o Start both RHRSW PumPs.o Fully oPen E1150-F068 A or B.Places RHR Div 1or 2in Drywell Spray' (CT 4, PC-DWS)o Place or verify Containment Spray Mode Select Switch in MANUAL.o lnitiate Drywell Spray when directed'o Open E1150-F021 A or B.o Start second RHR PumP.o Unlock and OPen E1150-F016 A or B'Reports Failure of E1150-F016 A or B Secures Torus and Drywell Sprays before Drywell and Torus pressure reach 0 Psig.ROLE PLAY lf dispatched to Ell50'Fl6A breaker, after 3 min report, acrid burned insulation smell near MCC (72C'34'5D)'

lf Opatched to Ell50-Fl68 breaker, after 3 min report' acrid uuined insulation smell near MCC (72F'4A-3AR)'

ROLE PLAY lf dispatched, after 3 min report, report D 1(D2)a a a a a Radiation Monitor SamPle Pump in service ATC b Appendix D Reo uired Ooerator Actions Form ES-D-2 Op-Test No.:2017-1 Scenario No.: 1 Event No.: 7 Page11of12 Event

Description:

Recirculation Loop Rupture, ED, Level recoverv.

Core Sprav Auto Start Failure.BOP a a a Verify or Shutdown the Reactor Recirc pumps.Shuts down all drywell cooling fans.Places RHR Div 1or 2 in Torus Cooling and Torus Sprays.o Place Containment Spray Mode Select Switch in MANUAL.o Unlock and Open E1 150-F0284 or B.o Start 1 RHR PumP.o Open 81150-F024 A or B.o Open 81150-F027 A or B.o Partially open E1150-F068 A or B.o Start both RHRSW PumPs.o Fully open E1 150-F068 A or B.Places RHR Div 1or 2in Drywell Spray. (CT 4, PC-DWS)o Place or verify Containment Spray Mode Select Switch in MANUAL.o lnitiate Drywell Spray when directed.o Open 81150-F0214 or B.o Start second RHR PumP.o Unlock and OPen E1150-F016 A or B.Reports Failure of E1 150-F016 A or B Secures Torus and Drywell Sprays before Drywell and Torus pressure reach 0 psig.ROLE PLAY lf dispatched to E1150-Fl6A breaker, after 3 min report, acrid burned insulation smell near MCC (72C'34-5D)'

lf dispatched to Ell50-F168 breaker, after 3 min report, acrid burned insulation smell near MCC l72F4A'3AR).

ROLE PLAY lf dispatched, after 3 min report, report D 1(D2)a a a Radiation Monitor Sample Pump in service.

CRITICAL TASKS Title llhen RPV Level cannot be maintained 0-214" with available injection an uncontrolled RPV ssurization ADS to sources, RPV-LEVEL l4tith RPV level below TAF, restore with all available low pressure system(s), when RPV maintain RPV water level above and TAF, bY INJECTING head the low ssure decreases below the RPV-TAF When RPV Level cqnnot be maintained greater Emergency Depressurízatíon, bere level reaches Minimum steam cooling RPV Water Level inches 5 than TAF",INITUTE RPV-ED DWSIL, Torus regton iti tn ation chamber the snn exceeds spray sure When suppres pres ln Ie the hi and w safe o.f sprays Drywell (e INITIATE pressure ps is), containment lower actions to take or limit the I initiation WSIL)(D spray Drywel side out he and he coolers to fans if ure ,ss Drywell cooling restoring by pre PC-DI,YS Scenario Outline Form ES-D-1 Appendix D I Oo-Test No.: 2017-1 sRo2(cRs) sRo3(ATC)

RO4(BOP)SROl(CRS)

RO5(ATC) RO2(BOP)SURR(CRSI ROI(ATC) RO3(BOP)Turnover:

TheplanthasbeenoperatinsatL00%Reactorpowerforthelastl85davs' CenterRecircMG Coolin fan is OOS for motor replacement.

Expected return to service is one week'Scenario No.: Fermi 2 lnitial Conditions:

lC-20, MOL. 100% Rx' Power.2 Operators Examiners:

Facility Event Descrpton Malf, No.Event Type*Event No.N(BOP)N(SRO)Shift RBCCW PumPs 7 r(sRo)rs(sRo)Drywell Pressure Transmitter Failure TS 3.3.1.1 A.tlA.2,3.3.6.1 A A.1, 3.3.6.2 A 4.1, 3.3.7'1 A 4.1 B 82(Drywell Pressure lnstrumentation) 821MF004 cR 58-39 lndividual scRAM from half scram during Drywell Pressure Transmitter Failure and blown fuse. Disarm cR due to badly damaged fuse clip c11MF1106 c(sRo)2 c(BoP)c(sRo)flashing amps.frip llrth Recirculation MG Cooling Fan (Manual or Automatic) with on MG Co ng Fan (Field High Vi n North R TAXMP817-A096NOlSE TACET4lCOl 2TVSP 3 c(cREW)Pump (or automatic if temP Direct manual TriP North Rx Recirculation AOP Entry 20.138.01 Recirculation Pump Trip AOP 20.107.02 Loss feed water H h rau tc on m fo itor t r e h yd CRA th M and Red uce array power to OW fl of exit ln lities.nsta b I limit reached)R(ATC)R(SRO)4 M(CREW)ra a d fro m collate ue to rcu Reci ation u P maSe Tri South of Rx mp p ual n Fa RPS to ils h S t u n dow a M Switch Mode to cool fa fan lu re).ing h n CT I bit ADS(re n AI d Rod Stuck Fa Scram u il a Cause m Scra)(Total 5 831MF0057 c71MF0006 cl1MF0001 c(ATC)c(sRo)SRO directs sLC injection.

ATC lnjects sLc. sLc Squib valve fails to fire crew lnjects sLc (cT 2, ATWS-SLC)6.c41RF0008 c41RF0009 sRo directs 29.ESP.03.

ATC manually inserts control Rods per 29.ESP.03 (CT 3,ATWS-RODS)

SRO directs 29.ESP.10.

ATC resets ARI to perform scram-reset-scram per 29.ESP.03.

All rods insert when ARI is re-initiated twice CREW 7 CREW SRO directs Terminate and Prevent. BOP performs Terminate and Prevent for Level to lower RPV level <114 inches. (CT 4, ATWS-T&P)Maintain RPV level 50 to 100 inches. (CT 5, ATWS-INJ)8 c(BoP)c(sRo)RCIC isolates on high exhaust diaphragm pressure.

BOP utilizes alternate systems to maintain level 9 E51MF0002 (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (N)ormal, setup: Full Power lC 20. Center RR Mg Set Fan RT off, Once the crew takes the shift' prompt the CRS to complete the task to shift RBCCW pumps'Scenario 2Ot7 -2 Overview Plant has been operating at 100% power Event 1: Normal shift of RBCCW Pumps Event 2: Single Drywell Pressure Transmitter failure, resulting in single control Rod Drift (blown fuse for one rod). cRS enters TS for instrument failure, directs actions per AOP for cR Drift' The % scram and this rod will not be recoverable during the remainder of the scenario.

Directing closure of C11-F112 for CR 58-39 from SOP will stop the input to the SDV'Event 3-4: High vibration report on North RR MG fan, crew should shutdown fan (amps are oscillating)'

brief single loop and trp the North RR Mg Set. Crew should enter RR Pump Trip AOP 20'138'01" ATC should recognize in the EXIT region and insert the red cram rods, Additional groups of rods will be required to completely clear the EXIT region, cRS should direct the BoP to complete the s/D of the N RR Pump per AOP 20.138.01.

Event 5-9: Trip of south RR Pump. ATC should place MS in S/D and report Failure to scram (high power ATWS) SLC will fail on the first pump selected, T&P for level will result in level band 50-100"' RCIC will isolate at level 2,forcingthe crew to use other systems (SBFW &/ FW). Actions in 29'ESP'03 (re-initiate ARI) will be successful inserting all control. scenario may be terminated at evaluators discretion once level is controlled in the band and power is lowering' t: :l:r: STIUP. tn$rfln5sn E 1O.O rilrPqi a 0 CTTVE EleYr165 rrtlP*o qn=o tto CLAR Â.'IPS OI'] TRIPJOFF-r - . :: l-;: CLEÂR 5DV:r... ' _r t::;l SLC Sl'\tAP PULIP 29 SP tl r$nFn on.ûotlCt:ii'.'r::--r-;

VENT 5 sfAfu'l LOSE FO 1;-1 5C{ 1::L!1r" '!'- -SETUP I :li I -: - ':ven1 E 5D CLOSE FO o T{0 rtnp0 onco oüeo HPCI lsoltlonT 2 42 HPCV UA RE EVE{RUPIUR RECIRC PI FAIL RDtVlcs EVÉNT cor.o ss rNsT EV*I{T 10-- ,l :l:ll Eiüdú60.¿ojt*'itii,rf+Úti An"o itt=o-'o sEtSM 6A OF 811 FAIL:-,.., l,--i::: 811 168 h Appendix D Reouired Actions Form ES-D-2 Op-Test No.:2017-1 Event

Description:

Scenario No.: 2 Event No.: N/A Overview Page 1 of 12 lnitial Conditions:

The plant has been operating at 100 % Reactor power for the last 185 days. Center Recirc MG Cooling fan is OO for mótor replacement.

Expected return to service is one weeks. Plans for the shift are to maintain full Power.The objectives of úhis scenario are to: r Recognize, respond to, and take the required actions for an instrument

/ equipment failures requiring the use of operator and Tech Spec actions. Shift RBCCW Pumps.r Recognize and respond Scram of one control rod. Recognize and respond to a Drywell Pressure lnstument Failure. Recognize and respond to imminent equipment failure.r Recognize and respond trip of Reactor Recirculation Pump Execute steps of RPV Control - ATWS Sheet 14.e Execute steps of PC Control- 29.100.01 Sheet 2.e Recognize and respond to failures in SLC system.o Manually insert Control Rods per 29.ESP.03' Recognize and respond to isolation of RCIC.The crew wifl be required to respond to the following order of events: o Shift RBCCW PumPs. Drywell pressure lnstrument Failure (TS 3.3.1.1,3.3.6.1,3.3.6.2, 3.3.7 '1) with Scram of one Rod r High Vibration North Recirculation MG Cooling Fan Manualtrip of North Reactor Recirculation pump.. Spurious trip of South Reactor Recirculation pump'r Mode Switch to SHUTDOWN, (ATWS)o SLC Squib valve fails to fire. RCIC isolates on start at L2 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.'. 2017-2 Scenario No.: 2 Event

Description:

Shift RBCCW Pumps Page 2 of 12 Event No.:--!-Position icant's Actions or Behavior Time Directs BoP to shifi RBCCW Pumps for scheduled maintenance on the a center pump.SRO+0 min. Shifts RBCCW Pumps in accordance with 23.127, Section 6'1: 1. Directs Rounds Operator to place T4100-8033, Battery Rooms AC Unit, switch in OFF.ROLE PLAY: After -1 minute, RB Rounds reports T4'100-8033 switch is in OFF.2. Closes P44OO-F613, Div 1 EECW To Batt Rm's A/C lso Vlv NOTE: 2119, RBCCW PUMPS DIFF PRESS H IGH/LOW, may alarm du um shift 3. Crew Update: starting south RBCCW Pump, shutting down center RBCCW Pump.4. Announces starting South RBCCW Pump, shutting down Center RBCCW PumP over Hi-Com.5. Starts the South RBCCW PumP'6. Stops the Center RBCCW PumP'7. lf necessarY reviews ARP 2D119'8. Verifies P42-F403, RBCCW DP ControlVlv, is maintaining proper differentialpressure by verifying annunciators 2D100 and2D1O4 are clear.9. Opens P44OO-F613, Div 1 EECW To Batt Rm's A/C lso Vlv (H11-P808).

10. Direct the Rounds operator to place T4100-8033, Battery Rooms AC unit, switch in AUTo, and to verify RPS MG Set doors are closed.ROLE PLAY: After -1 minute, RB Rounds reports T4100-8033 switch is in AUTO.Periodically monitors RBCCW system temperatures and pressures to a (H11-P808) ensure proper sYstem oPeration h Required Operator Actions Form ES-D-2 Appendix D Op-Test No.: 2017-2 Scenario No.: 2 Event No': 2 Event

Description:

Drvwell Pressure lnstrumentation Failure, CR 58-39 scram Page 3 of 12 Time Position cant's Actions or Behavior+15 min MALF: B2lMFOOO4 Drywell Pressure Transmitter Failure SRO Respond to Half Scram (High Drywell Pressure)

(3D73'3D80, 3D81, 3D85)Brief actions for individual rod scram.Enter AOP 20.106.07 Rod Drift.Contact SNE about individual rod scram.Direct CR 58-39 disarmed after fuse clip damage reported.May direct closing C1l-F112 Review 23.601 for failed instrument.

EnterTS 3.3.1.1, FUNCTION 7 Condition A,4.1 ) Place channel in trip, 12 hr ORndition A, A.2 ) Place associated trip system in trip, 12 hr Enter TS 3.3.6.1 FUNCTION 2.c Condition AA.1 Place channel in trip, 12 hr Enter TS 3.3.6.2 FUNCTION 2 Condition A A.1 ) Place channel in trip 12, hr Enter 3.3.7.1 FUNCTION 2 Condition A 4.1 Enter condition B, immediately Condition B, 8.2 ) Place channel in trip, 24, hr Contract Tagging Center and/or Work Control for assistance with failed instrument.

Brief crew on TS im a a a a ATC r Respond to Half Scram (High Drywell Pressure)

(3D73' 3D80'3D81,3D85) o Reports half scram, rod drift alarm and individual rod scram cR 58-39 (3De).o Dispatch operator to check HCU 58-39. ROLE PLAY: Rounds operator reports both scram Valves open at HCU 58-39. Nothing else is abnormal'. Dispatch operator to check fuses for CR 58-39.o ROLE PLAY: Report blown fuse and severely damaged and charred fuse clips on B side for 58'39'. Directs rounds operator to disarm CR 58-39 per 23.106.o May direct closing C11-F112 o Monitors Power, Pressure and Level. May dispatch operator to Testability Cabinets to check drywell pressure instrumentation.

ROLE PLAY: When disPatch C71-N6504 reading uPsc ed to Testability, after about 3 min, report ale, al! other channels reading normal.BOP Respond to Half Scram (High Drywell Pressure)(3D73' 3D80'3D81,3D85)

Monitor drywell pressure Review 23.601 for failed instrument.

will dispatch operator to Testability cabinets to check drywell pressure instrumentation.

ROLE PLAY: When dispatched to Testabi C7l-N6504 reading upscale, all other lity, after about 3 min, rePort cJiannels reading normal.

Form ES-D-2 ApPendix D Required Operator s EventDescription:HiohVibrationNorthRecirculationMGCoolinqFan Page 4 of 12 Op-Test No.: 2017-2 Scenario No.: 2 Event No.:-9-Actions or Behavior Position Time MALF 7_A096NOls ACET41 noise meter am fan p Genter E 1 P8 T AXM Fan Genter Trip 2TVSP c01 T T+30m a a F an Cooli MG lation ng rcu Reci North of rects Di Trip 38.I 0 2 P 0 A (AO lation Pump Recircu Reactor of Brief Trip SRO a IGH H P TEM AIR SET DRIVE A S MG SY RC ECI R D1 3 42 to Respond ATC PLAY: Building Rounds rePorts neirc Ño set cooling F severe ts"There radio via Reactor ROLE n.the N n o vibration 7D49 I nd 72 a 7 I D nu an nciators, to res pond automaticallY fan tf trips Fan Cool MG ng ation Recircul North Trip BOP Appendix D Reouired Ooerator Actions Form ES-D-2 Op-Test No: 2017-2 Scenario No.: 2 Event No.; 4 Event

Description:

Trip North Rx Recirculation Pump Page 5 of 12 Time Position A icant's Actions or Behavior T+32m SRO o Direct manualTrip of North Rx Recirculation Pump.. Enter AOP 20.138.01. Hi-Com announcements of events.. Conducts AOP brief (if not already done).r Directs ATC to perform 20.138.01 , Condition A Actions.o Directs BOP to verify feedwater heating change,s are due to the power change IAW ARP 5D85, "Loss of Heater Drains",. Directs the notification or notifies Station Nuclear Engineer (SNE) of the unplanned power change and requests his assistance.

ROLE PLAY: SNE states he will come to the control room as soon as possible.

until he gets there, increase monitoring for thermal-hydraulic instabilities.. Notifies RP and Chemistry of power change >15o/o. (Condition E)o Reviews TS 3.4.1, requirements for SLO. (NOTE Application of the required limitations for single loop operation may be delayed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after transition from two recirculation loop operations to single recirculation looP oPeration.

)a p rotected D ay for ATC. When directed Trips RRMG "A".o Monitors reactor power and flow conditions, on the power/flow map.o 20.138.01 lmmediate Action (lc) lnsert the cram Array when in the exit a regron.Monitors for THI when in exit region BOP a Responds to annunciator 5D85, LOSS OF HEATER DRAI NS a Reports loss of Heater Drains due to Recirc Pump Trip.Reviews AOP 20.107.02, "Loss of Feedwater Heating", Enclosure A'Reports Feedwater temperature change is consistent with power change.Peer checks closure of 83,105-F0314.

Peer checks re-opening of 831 05-F0314.When directed, performs AOP 20.'138.01 , Condition A Actions: (May peer check or perform actions). Place Recirc A & B Flow Limiter 213 Deleat Switch in DEFEAT' lncrease core monitoring for instability (24.000.01 Attachment 34b).. Close B3105-F0314 (B) for tripped RR Pump.o After 5 minutes fully open 83105-F0314 (B). Maintain RR MG Set speed as per 23.138'01 a a a a a o lnform SNE of unplanned power change h Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 2017-2 Scenario No.: 2 Event No.: 5 Event

Description:

Trip of south Rx Recirculation Pump, with ATWS Page 6 of 12 Time Position icant's Actions or Behavior T+45m MALF: B3lMF0057 I sRo Acknowledge Mode Switch in Shutdown. Directs Scram Reports. Enters EOP 29.100.01 Sheet 1, records scram reports.. Transitions to EOP 29.100.01 Sheet 1A, RPV Control-ATWS'. Directs ATC to perform FSQ 1 thru 8.. Directs BOP to confirm isolations and actuations for levelas they occur.. Directs BOP to lnhibit ADS (CT'1, ATWS'ADS) Directs BoP to bypass and restore drywell pneumatics and order 29.ESP.11.. Directs BOP to maintain pressure 900 to 1050 psig. May expand lower end of band due to leak in drYwell.. SRO acknowledges FSQ-1 thru 8 complete. SRO acknowledges ADS inhibited.

o SRO acknowledges report on Drywell Pneumatics and 29'ESP 11'. SRO acknowledges report on FSQ 1 thru 8 complete and Reactor Power ATC. Recognizes trip of South Reactor Recirculation pump.. Performs lmmediate action (20.138.01 lA), places Mode Switch in Shutdown. Reports Failure to Scram to CRS.o Provides Scram rePort to CRS. Peforms FSQ 1 thru I using Hard Card: (Verifiable)

1. Confirm Rx mode switch in S/D (should have already done this)2. Confirm ARl.o Reports FSQ 1 thru 8 complete and Reactor Power to CRS BOP LAY Reactor B uildin Rou nd reports vta radio S mall leak from ROL E P g s coolin s coils of North Recirculation MG Cooling Fan R MG Sets." (50"No d rops per m inute)De bris from th e 1a n imbedded n both R obvious problems with the RR MG Sets.". Verifies isolations and actuations for level as they occur using Hard Card.r lnhibits ADS (CT-1, ATWS'ADS). Reports ADS inhibited.. Defeats Drywell Pneumatic lsolation with Keylock Switches on H11-P808 and P817.o contacts Tagging center (operator outside cR) to perform 29.ESP.11.. Reports DrywellPneumatics bypassed and restored a ordered.ROLE PLAY: About 10 min. after request, installdefeats report to Control Room that 29.ESP.11 is complete.nd 29.ESP.1'1 for 29.ESP.1 I and h Required Operator Actions Form ES-D-2 Appendix D Op-Test No: 2017-2 Scenario No.: 2 Event No.: 6 Event

Description:

SLC Squib valve fails to fire Page7 of 12 Time Position icant's Actions or Behavior T+48 MALF c41RF0008 c4tRF0009 SRO Directs SLC injection. (CT 2, ATWS-SLC). Receives report of SLC injection, noting time for injection and SLC Tank level ATC a a a a a a Place key lock for selected SLC pump to run'After diagnosis, determines Squib did not fire.Selects other SLC pump. (CT 2, ATWS'SLC)Verifies proper pump operation and isolation of RWCU Marks time of SLC initiation and SLC Tank level Reports failure of squib valve to CRS.

h perator Actions Fo rm ES-D-2 A dix D Required O 2017-2 Scenario No.: 2 Event No':-L Page B of 12 Event DescriPtion Op-Test No.icant's Acti ons or Behavior Position Time o Directs ATC to Defeat ARI using 29'ESP'10' o Directs ATC to insert Control Rods using 29'ESP'03' (CT 3' ATWS'RODS) After all rods in, SRO directs SLC shutdown' After all rods in, SRO transitions back to 29' 100'01 Sheet 1 'SRO+49 min ContactsTaggingCenter(operatoroutsideCR)anddirectsperformance of 29,ESP.10.

ROLE PLAY: Tagging Center acknowtedges peÉorm 29'ESP'10' ROLE PLAY: About 10 min. after request;trigger E.SP10 Defeats and"- ,lport to Cotntrot Room that 29'ESP'10 is complete'oUsing2g.EsP.O3,utilizesoneormoreofthefollowingtoattemptto insert Control Rods:. Raise CRD Hydraulic D/P' (section 2'0). ManualControlRod lnsertion' (section 3'0), Scram-Reset-Scram. (section4'0) o Attempts to drift rods using section 2'0: ' Place CRD Flow Controller in MANUAL Open Flow ControlValve using CRD Flow controller'

' Open C1 152-F003 to maximize cooling water flow'. Manually inserts ControlRods (CT 3, ATWS-RODS). Place CRD Flow Controller in MANUAL'Adjust Flow Controller and C1152-F003 to maintain sufficient D/P for rod motion.Place the RWM in BYPass.Close C11-F034 if needed to maintain drive D/P'lnsert the Cram ArraY.lnsert rods in checkerboard pattern spiraling out from center Cntnue inserting remaining rods spiraling out from center'I I t ATC perator Actions Form 2 A dix D Required O Page 9 of 12 Event No.: 7 Op-Test No: 2017-2 Scenario No': 2 Event DescriPtion:

icant's Action s or Behavior Position Time Scram Reset and Scram Re-initiation:

o VerifY 4 Blue Scram lights are on'o May re-open C1 100-F034 to re-charge accumulators' o After 29.ESP.1O is complete, reset ARI'o Verify SDV vent and drain valves are open'o Allow the SDV to drain (3D94 clear)'o lnitiate a manual scram by performing one or both of the following:

' Depress four manual scram pushbuttons'

' Arm and dePress ARI Pushbuttons' o lf Rods move inward, rePeat'observesinwardrodmovement,resetsARlandwaitsfor3D94toclear lnitiates ARI and again observes inward rod movement (2nd time)'Verifies all rods in with RWM and fullcore display'Crew UPdate: "Allrods in" Shuts down running SLC PumP'a a a a a ATC (continue)

Appendix D Requi red Operator Actions Form ES-D-2 Op-Test No.: 2017-2 Scenario No.: 2 Event No.: I Event

Description:

Terminate and Prevent/Maintain RPV Water Level Page 10 of 12 Time Position ica nt's Actions or Behavior+50 min SRO Determines that Terminate and Prevent is required.

Crew Update "We have met the conditions to Terminate and Prevent for Level" Directs BoP to Terminate and Prevent all injection into the RPV with the exception of Boron, CRD and RCIC. (CT 4' ATWS'T&P)Directs level lowered less than 114" Wide Range. Directs BOP to maintain RPV level 50 to 100 inches.After all rods in, directs BoP to restore and maintain RPV water level 173to 214 inches. (CT 5, ATWS-INJ)a a a a BOP. Acknowledges order to Terminate and Prevent.r Acknowledges lower RPV level less than 114 inches. Maintain level 50 to 100 inches on Wide Range. Performs Terminate and Prevent (Hard Card): (CT 4, ATWS'T&P)1. CS Division I PumPs to OFF.2. RHR Division 1 PumPs to OFF'3. SBFW PumPs to OFF.4. CS Division 2 PumPs to OFF.5. RHR Division 2 PumPs to OFF.6. HPClAux Oil Pump oFF if HPCI not running or Lower HPCI Setpoint to Minimum if running.7. Crew Update "Lowering RPV Level." 8. lf RFP Running, lower speed on both RFP in Manualto close FW Check Valves.9. When RPV Level is less than 114 inches, commence feeding with available sources.o Uses FW or SBFW to maintain RPV level 50 to 100 inches.. After rods are all in, restores and maintains RPV level 173 to214 inches using available systems. (CT 5, ATWS{NJ) h Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 9 Event

Description:

RCIC isolates on start at L2 Page11of12 Time Position Applicant's Actions or Behavior MALF: - E51MF0002+60 min SRO Acknowledges RCIC lsolation.

May inquire if available sources are adequate to maintain level BOP ldentifies RCIC has isolated.Utilizes SBFW or Feedwater to Maintain RPV Level 50 to 100 inches.May direct investigation by Rounds Operator for cause of RCIC isolation at Testability Cabinets.

CRITICAL TASKS Title Task Description ATI'YS.SLC lüith a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting sLC or Boron using the alternate means, to the containment des limits ATWS-RODS With a reactor scram required and the reactor not:;hutdown.

TAKE ACTION TO REDUCE POWER by inserting control rods, to prevent exceeding the containment limits.ATWS-ADS With a reactor scram required, reactor not shutdown,IW.to pyevent an uncontrolled RPV depressurization, and to prevent causing a s excurslon.

ATWS.T&P During an A TWS wit h conditions met to perform power/level control TERMINATE AND PREVENT INJECTION.

with exception of boron CRD and RCIC into the RP V unt il conditions are met to re-est abl ish ATWS-INJ LVhen conditions are met to re-establish iniection use avai lable injection systems to MAINTAIN RP V water leve I above the Min lm um Steam Cool tng RP V Water Level the need surizatíon Scenario Outline Form ES-D-I Appendix D lnitial Conditions' lC-10 MOL 5.6% Rx Power 650 psie Reactor Pressure.

N RFP is feedinq via the SULCV'Turnover:

Reactor startup is in prosress.

GOP 22.00.02 Up to step 6.2.24 is comlete.

Current direction is to continue the GOp bv raising pressure, and complete step 6.2.25. Additional crew is bein briefed to perform GOp 7.2.1throuqh 7.2.3 (Preparine Main Turbine for Rolll. thev wll be comins to the control room in about an hour. Diesel Fire Pump is taeeed out, due to spurious start erlier todav'An Emergent lssuesTeam (MWC L8l has been formed and istroubleshootinthe Diesel Fire Pump'Scenario No.Fermi 2 Operators 3 Examiners:

Facility: Oo-Test No.: 2017-1 sRo2(cRsl sRoI(ATC)

ROs(BOP)sRo3(cRS)

RO3(ATC) RO1(BOPI Event Type*Event Descrpton Malf. No.Event No.Raise reactor pressure with pressure regulator' Maintain Bypass valve 15-30% open my withdrawing control rod to increase Reactor Power.cr.1RF0398 R(ArC)R(SRO)t Control Rod 22-19 Drift out of the core.c(A sRo 2 c11MF0363 Trip #2 System GSW Pump. Enter AOP 2O.L3I'0L Loss Of General Service Water. Direct start of standby GSW pump using hard card'P41MF0006 shutdown Electric Fire Pump Per SOP 23.501.01 Fire water suppression System EnterTR 3.12'2 COND B24hr N(BOP)TS(SRO)3 Hpcl steam Leak (field report). Manual isolation unsuccessful, E4150-F600 BreakerTriPs.

AOP 20.000.02 Abnormal Release Of Radioactive Material c(BoP)c(sRo)4 E4r.MF0007 E41RF0033 r)M EOP 29.100.01 Sheet 5, Secondary Containment - >MSO Temperature

-HPCI exceeds Max Safe -> Mode Switch to Shutdown (CT-l, SC-SCRAM)5 Mode SW failure EOP 29.100.01 Sheet 1 RPV Control P603_A048_1 P603_A048_2 P603_A048_3 P603_4048_4 c(sRo)6 Two Areas > MSO Temperature due to HPCI watertight door not closed -EOP 29.100,01 Sheet 3 - Emergency Depressurization (CT 2, SC-ED)M(Ail)7 TA2OTEN2O6 ZOUT SRV H Failure during ED - Open One other SRV 821MF0030 BOP)8 (l)nstrument, (C)omponent. (M)ajor (N)ormal, (R)eactivity, Setup: Low power tC 10 - 4 %, 650# RPV pressure.

GOP marked up to step 6.2.24 complete' N RFPT feeding via the SULCV. Diesel Fire Pump OOS for repairs. Protected Equipment placard placed per ODE20'Scenario 2017 -2 Overview plant startup in progress.

Crew is directed to raise power / pressure in preparation for commencing Startup of MTG that will be performed by other shift personnel.

Target is near 30% open on BPVs and 700# RPV pressure.Event 1-2: Commence withdrawing control rods and raising pressure regulator setpoint.

Control rod drift Rod 22-i.9 drifting OUT. ATC will use Emergency Rod ln to fully insert and hold the rod inserted until it is defeated per AOP 20.706.07.

Event 3: GSW pump #2trip, causing Electric Fire Pump to Auto Start. Enter AOP and direct starting any additional GSW Pump. This will recover pressure.

Follow up actions should use the SOP to return the Electric Fire purnp to Auto. TS call for Both Fire Pumps INOP by the CRS during the evolution.

Event 4: HpCl steam leak, initiated with a radio call from Operator, indicating water tight door not closed on his way out of the area. Attempts to isolate HPCI will fail, temperature indications are driven by ramps in the lesson, so lowering RPV pressure will not be successful, Event 5-6: Mode SW to SD for MSO in HPCI area. MS will fail, manual PB willfunction.

Event 7-8: 2 areas >MSO, ED SRV H failure during ED.

rLo 2017-1 SCH NO 3-',r : :'. ; ,-'rlF;";r_-. i ,- 1:,:. 'EVENT 1:,' -r.,:- -:,, , l_.:.,, -.,:..,:)'t' DISARt\,1 l.,lCU 22-1S r- i,r :l.r: i:f',i'r:.

EVENT 2 4CVE a o z_81'l EVERT 4 R¿mp down Room Temp t rtnP3'6O LOCAL SHUDOUJN EFP FVEMT 3-..ri t-rr:.' -:i .-.i ,-.' --'rff, :a',:1,--"r't. i, ; r:.:;:-rl : ::::i' ;E"il '"-.: :.': ll.l. lil rmpl3ot on! offs0 rirmp3360 onq off.o I coN nSert o il 017.1 sCr. 2 EVH1 4 I.i !trtt i!::: I r", l;l:ia:. t;EVEXT G 10.0 ramr{5 a clrvEtt"Et05tp* o: o1*0 CLE.A.R AI,'IPS OII TRIP,OFF SLC IÑJECi FAIL 2'_.: _--..1 i".,.L-TLÉÂR sDV PU.tP.,::1.,-;,_1

{ i . :, l _il 29. E Sp.11 rrnr4omoilro VEI 2 2 I{PCV UA FAILURSETUP. ln3art rlsT EVENvENi 4 SEtSMtC 1 20 1 7-1--: i .- :: tt ti: - - ;:.- .-_ .:rt :,r ! ;:.,: ,.: i:,:, : -r I i.:, i'EV_:]i ::)i;a-: -:._r ',_-L : ,.:.fEM LE,4K cLosE F007. ..  :, t_ -:t.- -::;cLos F008 HP lrrps locked rn o f $srt t0 rnFo on!û ottao lnsrt HPCI lsollronVENT; RUPTURE RECIRC LOOPI FAILURE OR DIV 1 CS EV.!T 1Ol -'r'r '; ,:': , -t:ll.: engol1!o FAI l l'l :'1.:1. r J:'-j'.=:::, ,-.- . :: :: OF E11 1't- : r - i: ::.i lrr.'-r -- .. -;

Req ured Operator Actions Form ES-D-2 Appendix D Op-Test No.:2017-1 Event

Description:

Scenario No.: 3 Event No.: N/A Overview Page 1 of lnitial Conditions:

lC-10 4% Rx power 650 psig Reactor Pressure.

N RFP is feeding via the SULCV. Reactor startup is in progress.

GOp 22.00.2 Úp to step 6.2.24 is complete.

Current direction is to continue the GOP by ráirn pressure, and compleie step A.Z.ZS. Additional crew is being briefed to perform GOP 7.2.1 throujh T.2.3 (p:reparing Main Turbine for Roll), they will be coming to the control room in about an hour. Diesel Fire pump-is tagged out, due to spurious start earlier today. An Emergent.lssues Team tlVlWC 1B) has been formed nO s trouOteshooting the Diesel Fire Pump. TRM 312:2 14 day LCO entered to restore the inoperable pump to oPERABLE status. currently on step ?¿! ol rod pull' sTA is logging temperature an'd presrre as required.

Direction after taking the shift will be to increase rector pressure by 50 Psig.The objectives of úfiís scenario are to:. Recognize, respond to, and take the required actions for an instrument

/ equipment failures requirng the use of operator and Tech Spec actions.o Raise reactor power using the RMC system.r Recognize, respond to, and take the required actions for Control Rod Drift'o Recognize, respond to, and take the required actions for Trip GSW pump. Shutdown Electric Fire Pump.r Recognize, respond to, and take the required actions for steam leak in Secondary Containment. Recognize, respond to, and take the required actions for SRV failure to operate'The crew wilt be required to respond to the following order of evenÚs;. Raise power -3%r Respond to Control Rod Drift. Trip GSW pump - start standby GSW pump - shutdown Electric Fire Pump HPCI Steam Leak o One Area Exceeds Max Safe - Mode Switch to Shutdown'. Two Areas Exceeds Max Safe - Emergency Depressurize' SRV H Failure to OPEN for ED.

Appendix D u ired Ooerator Actions Form ES-D-2 Op-Test No.: 2017-1 Scenario No.: 3 Event No.:J!-Event

Description:

Raise reactor pressure with pressure reoulator

/ Control Rods Page 2 of I Time Position A icant's Actions or Behavior Malf - Cl1MF0398 - Re-initialize NUMAG RWM+0 min SRO. Direct increase Reactor Pressure Per the GOP using Pressure Regulator and ControlRods.. Provide oversite of reactivity change.ATC. Maintain Bypass valve 15-30% open my witfr{rgying control rod to increase Reactor Pdwer. Control Rod Withdrawal (23.623). May increase Pressure using Pressure Regulator per GOP 22.000'02 BOP. Peer checks reactivity manipulations.

h Req uired Operator Actions Form ES-D-2 Appendix D Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 2 Event

Description:

Control Rod 22-19 Drift out of the core Page 3 of 8 Time Position cant's Actions or Behavior+15 min Malf - Cl I MF0363 - Control Rod 22-19 Drift out of the core ATC a a a Observes Alarm 3D80, Control Rod Drift Alarm.Announces alarm for CRS.ldentifies rod 22-19 drifting, places the Rod Select Power to ON, and selects rod22-19.Reports rod 22-19 drifting out of the core to CRS.Fully insert using EMER ROD lN - lmmediate action'Place RWM to bypass (required because below LPSP) (NOTE 1 in AOP)Monitors critical parameter, second drifting rod.Coordinate with Rounds Operator to disarm the control rod'ROLE PLAY: Close C11'F103 and Cll-F105 for HGU 22'19'Delete Malf - Cl 1 MF0363.BOP Act as peer checker for ATC actions.SRO o Acknowledges Alarm 3D80, Control Rod Drift Alarm report'. Announces and enters 20j06.07 Control Rod Drift AOP' Announces the 20.106.07 control Rod Drift event over the Hi-com.o AOP Brief for 20.106.07 Control Rod Drift. Directs ATC to perform subsequent actions for condition B of 20.106.07' o Reviews 3.1.3, Control Rod operability, section 3.1.6, Rod Pattern Control, and Section 3.3.2.1, Control Rod Block lnstrumentation'. Conducts a crew brief.. Notifies Work Control personnelof rod 58-39 disarmed, reqye-sls a CARD b writien, órotection iags be hung for C-1 1-F103 and C1 1-F105, and a revw of 'OO for activies that mght affect current plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2017-'1 Scenario No.: 3 Event

Description:

TriP #2 GSW PumP Page 4 of I Event No.: 3 Position icant's Actions or Behavior Time MALFUNCTION - P41MF0006'Trip of #2 GSW Pump+20 min Crew Update "Entering AOP for Loss of GSW".Enters AOP 20.13'1.01, "Loss of GSW".Conducts AOP Brief.Directs BOP to start available GSW Pump using hard card (may do before brief), Acknowledges indicated cause of pump trip'May request follow-up by Tagging CenterMWM.

May direct clearing of 7D72 per the ARP Directs shutdown of Electric Fire Pump to standby Enters TRM Section TR3.12,2, Fire Suppression Water System Condition B, for INOP of both Electric and Diesel Fire pumps, 24 hr Acknowledges report of #2 GSW PumP Trip.e backu to restore or SRO. Announces Alarms 7D11,7D14 and7D72.. Announces Trip of #2 GSW PumP.. Directs Outside Rounds to investigate trip of #2 GSW Pump at pump and breaker.ROLE PLAY: Outside Rounds operator acknowtedges investigate Trip of Number 2 GSW PumP.o Starts available GSW Pump.o Makes plant announcement for start of GSW Pump.. contacts outside Rounds operator to inform that GSW Pump has been started.o Directs Outside Rounds Operator verifies local lake level and strainer operation.

ROLE tnV: Outside Rounds repofts, "Normal strainer operation and no change in lake level".o Monitors GSW pressure to ensure correct system response to pump start.ROLE PLAY: Outside Rounds reports, "Good start on Number? GSW Pump".. Acknowledges good start on GSW start.o Checks indicated GSW intake levelindication.

ROLE PLAY: Outside Rounds reports, "64 Device tripped on Number 2 GSW Pump Breaker.o Reports indicated cause of #2 GSW Pump trip to SRO.. Clears 7D72 per ARP with permission for CRS Directs rounds operator to GSW pump house for placing Electric Fire Pump in standby Place Electric Fire Pump in standby per 23.501'01 o Place PSOOO-CO02, Electric Fire Pump, CMC switch in OFF/RESET.

o Direct field operator to Push STOP button on Electric Fire Pump Local Panel P80-P415, Electric Fire Pump P'B' Station'o Verify 7D11, ELECTRIC FIRE PUMP LOCAL START, clear'o Verify P4l-R809, Fire Protection Header Pressure lndicator (red n o Place than 5 3 eed ig ps le)greater switch MC n T AU o c F Pu re Electric BOP Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2017-1 Scenario No.: 3 Event

Description:

HPCI Steam Leak Event No.: 4 Time Position licant's Actions or Behavior+30 min MALF: E41MF0007, HPCI Steam Leak MALF: E41MF0008, Failure E41-F002 MALF: E4lRF0033 E41-F600 Breaker Tri SRO ROLE PLAY: Operator was entering area from South East Subbasement.

l-o-ulUag nO'â cloud of steam. Was unable to close watertight door in to HPCI area. Leaving RB'. Respond to 1D66, 1D70,16D27. Enter AOP 20.000.02 Abnormal Release of Radioactive material.. Enter 29.100.01 Sheet 5, Secondary Containment Control. Directs lsolation of HPCI o Brief Actions for Steam Leak/Scram.. May direct RB evacuated BOP Respond to 1D70, 1D66,16D27 Attempt isolation of HPCI o Attempt Closure of 84150-F002 r Attempt Closure of E4150-F600 Reports failure of HPClto isolate -F41-F002 and E41-F600 failed to close Dispatch operato rto check MCC for E41-F600.

(2P81-1C)a a a a h Appendix D Reouired Operator Actions Form ES-D-2 Op-Test No.: 2017-1 Scenario No.: 3 Event

Description:

HPCI exceeds Max Safe Event No.:--.'.-

Page 6 of I Time Position A icant's Actions or Behavior MALF: P603-4048-1 Mode SW forced P603-A048 2 Mode SW forced P603-A048-3 Mode SW forced P603-A048-4 Mode SW forced+35 min SRO. Acknowledged Report of HPCI area exceed MSO.. Direct Mode Switch to Shutdown prior to MSO Temperature. (CT-' SC-scRAM). Directs Scram report from ATC and BOP Enter 29.100.01 Sheet 1 , RPV Control. Direct 173 to 214 inches level band and 500 to 700 psig pressure band. May direct lowering pressure by 90"F or less.. May direct ATC to perform AOP 20.000.21 BOP r Report HPCI area exceed MSO r Provides scram report.. Maintains level and pressure as directed ATC. Places Reactor Mode Switch in Shutdown when directed (CT-1' SC'scRAM). Reports failure of Reactor Mode Switch and depresses SCRAM pushbutton causing SCRAM. Provides Scram report.o Verifies all control rods are fully inserted.. Perform actions in AOP 20.000.21 Reouired Ooerator Actions Form ES-D-2 Appendix D Op-Test No.: 2017-1 Scenario No.: 3 Event

Description:

Two Areas > MSO: Emeroencv Deoressurize Page 7 of I Event No.: 6,7,8 Position Actions or Behavior cant's Time MALF: 821MF0030 H SRV FAILURE. Conduct Brief for Emergency Depressurization' Acknowledge report of South East Subbasement

> MSO o Enter 29.100.01, Sheet 3, Emergency Depressurization'. Direct 5 ADS SRVs opened. (CT-2' SC'ED) Directs levelband of 173to214 following ED'SRO+45 min ATC coordinate with BoP to shutdown/operate LP Pumps to restore maintain RPV water level 173 lo 214 inches.disoatched and RB is accessible, after 5 min report'Raaton Monitor Sample Pump in service'a and ROLE PLAY If report D f (D2)r Reports South East Subbasement

> MSO o Opens 5 ADS SRVs as directed. (C1'2, SC-ED)o Recognizes failure of H SRV, selects non ADS SRV and opens it'o coordinate with ATC to shutdown/operate LP Pumps to restore and maintain RFV water level 173 lo 214 inches'disoatched and RB is accessible, after 5 min report'Raiaton Monitor Sample Pump in service.a ROLE PLAY If report D 1(D2)BOP CRITICAL TASKS andwith a primary system discharging secondary exceed the MANUALLY SCRAM the reactor, bere any area containment levels.into the With reactor at power Maximum Safe Operating SC-SCRAM r adi at ion/t e mp er atur e/w øter more than one area and containment the into a with secondary discharging system primary tn levels exceed levels maxlmum operating safe SC-ED