ML082750410

Arkansas Nuclear One - 2008-09 - FINAL-OP Test

ML082750410
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/05/2008
From:	Larson B T Operations Branch IV
To:	Entergy Operations
References
50-313/08-301, 50-368/08-301, ES-301, ES-301-1 50-313/08-301, 50-368/08-301
Download: ML082750410 (335)

Text

Page 5 of 5 JPM ID:A1JPM-RO-PZR05INITIAL CONDITIONS:The Reactor is at 38% power with 3 RCP's running "D"RCP is secured.INITIATING CUE:The CRS/SM directs you to respond Annunciator K09-C1RCS Pressure HI/LO alarm

Page 1 of 19Appendix DScenario OutlineForm ES-D-1Facility: ANO-1 Scenario No.: 1-R5Op-Test No.: 2008-1Examiners: __________________________ Operators: __________________________ __________________________ __________________________ __________________________ __________________________Initial Conditions:90% power due to dispatcher direction for loss of 500KV.C2A IA compressor is out of service for overhaul.ULD is failed and will not lower power.RPS is failed and will not initiate a RX trip.Provide stop watch for surveillance.Two rods will fail to insert on the RX trip.Turnover:Day shift normal working day.90% power due to dispatcher direction for loss of 500KV line as a result of storm damage tothe Mabelvale 500KV line. No storms are currently in the area.C2A IA compressor is out of service for overhaul.1104.005 Supplement 2 RB Spray Red Train Valves Quarterly Test is in progress completethrough step 2.2.2. This is not the 18 month surveillance.Crew will continue in surveillance after turnover.

EventNo.Malf. No.EventType*EventDescription 1 N/AN (SRO, BOP)Perform 1104.005 Supplement 2 RB Spray Red TrainValves Quarterly Test 2DI_ICC0009LN (SRO)R (ATC)Dispatcher directs power reduction to 700MweULD is failed 3AI_FIC1207I (SRO, ATC)RCP total flow setpoint fails to high 4CV016C (SRO, BOP)RCP seal failure 5DI_ICC0009LN (SRO)R (ATC)Power reductionULD is failedDI_H24TM (ALL) Loss of H2 bus 6CO_P32A N/AIf power <55%,Trip 'A' RCP when H2 bus is lost(Contingency to ensure RPS trip setpoint is reached.)

7RP246,7,8,9C (SRO, ATC)RPS is failedManual RX trip(TS)(ATC-CT)CONTINUED Page 2 of 19Event No.Malf. No.EventType*EventDescription 8RD362RD363C (SRO, ATC)Stuck rod(TS)Stuck rod(ATC-CT)9CV020RC006ES259CV-1300M (ALL)C (BOP)'B' RCP seal failure~700gpm RCS leak(TS) (BOP-CT)ESAS Channel 1 fails to actuate(TS)(ATC-CT)CV1300 Fails open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 3 of 19Appendix DScenario OutlineForm ES-D-1Scenario #1-R5 Objectives

1) Evaluate individual ability to perform the valve stroke test of the EngineeredSafegaurds Reactor Building Spray Block Valve.

2) Evaluate individual ability to recognize and respond to a failed reactor coolant pumptotal seal injection flow controller setpoint.

3) Evaluate individual ability to recognize and respond a degraded reactor coolant pumpseal.4) Evaluate individual ability to perform a plant power reduction.

5) Evaluate individual ability to recognize and respond a failed unit load demand input tothe integrated control system.

6) Evaluate individual ability to recognize and respond a loss of a 6900V H bus andresulting loss of a reactor coolant pump.

7) Evaluate individual ability to recognize and respond to a reactor trip condition whereRPS fails to trip the reactor.

8) Evaluate individual ability to recognize and respond to two stuck control rods andinitiate emergency boration.

9) Evaluate individual ability to recognize and respond a post trip reactor coolant pumpseal failure.

10) Evaluate individual ability to recognize and respond a reactor coolant system leakinside the reactor building.

11) Evaluate individual ability to recognize when conditions require the entry into technicalspecifications conditions.

12) Evaluate individual ability to recognize and respond to a medium reactor coolant system leak.

13) Evaluate individual ability to recognize and respond to failure of an ES channel toactuate.14) Evaluate individual ability to recognize and respond a failed open ES component.

Page 4 of 19Appendix DScenario OutlineForm ES-D-1SCENARIO #1-R5 NARRATIVEThe crew will assume the watch at 90% power. The Mabelvale 500KV line is out of service dueto storm related damage in south east Arkansas. The down power was completed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.Reactor engineering has directed that rods can be used to account for the xenon transient.1104.005 Supplement 2 RB Spray Red Train Valves Quarterly Test is complete through step2.2.2. The crew should brief the remaining steps of the surveillance. The BOP will perform thestroke test(BOP-N) (SRO-N).The dispatcher will call and direct U1 power be reduced to ~700Mwe in the next 10 minutes.The CRS should calculate the required rate and direct power reduction per 1203.045 RapidPlant Shutdown. The ATC should recognize that the ULD is not responding and power is notlowering. The ATC should reduce power to ~700 Mwe using the SG/RX Master station in hand.(ATC-R) (SRO-N)The controlling RCP total seal injection flow setpoint will fail high.(ATC-I) (SRO-I). This willcause CV-1207 RCP Seal Injection Control Valve to fail open raising total seal injection flow tomaximum. Annunciator K08-D7 RCP Seal Cavity Press HI/LO will alarm due to the high sealinjection flow. The CRS should reference 1203.012G K08 Annunciator Corrective Action. TheACA will direct the CRS to 1203.031 Reactor Coolant Pump and Motor Emergency. The crewshould recognize high seal injection flow on C04 and take manual control of CV-1207 toestablish 8-10gpm individual seal injection flow.The RCP seal injection transient will cause the 'B' RCP lower seal to fail(BOP-C) (SRO-C). TheCRS should implement 1203.031 Reactor Coolant Pump and Motor Emergency and reducepower to ~60% in order to stop the 'B' RCP using 1103.006(ATC-R) (SRO-N) The ATC shouldreduce power to ~60% using the SG/RX Master station in hand.At ~65% power or as directed by the lead evaluator a loss of the H2 bus will occur resulting in aloss of two RCP's (B and D)(BOP-M) (SRO-M) (ATC-M). If reactor power is <55% then the 'A'RCP will be tripped along with the H2 bus by the simulator instructor to create the condition forthe recognition of an RPS failure. The ATC should recognize the reactor should have trippedand manually trip the reactor.(ATC-C)(SRO-C) (ATC-CT) (TS)

.TS 3.3.1 Condition CCT criteria -The reactor should be manually tripped within 2 minutes of the loss of the H2 bus.Two control rods will fail to fully insert on the Rx trip.(SRO-C) (ATC-C)The ATC shouldrecognize and report this condition during the immediate action report. The CRS will direct1202.012, RT-12 Emergency Boration to be performed.(ATC-CT)TS 3.1.4 Condition CCT criteria - Emergency boration should be started within 5 minutes of the RX trip.CONTINUED Page 5 of 19Appendix DScenario OutlineForm ES-D-1SCENARIO #1-R5 NARRATIVE CONTINUED~10 minutes post trip a ~700gpm leak will occur in the reactor building from the failed RCP seal(ALL-M) (TS). Subcooling margin will be lost requiring the BOP to trip all running RCP's within 2minutes.(BOP-CT) All ESAS channels will auto actuate except ES Ch.1. The crew shouldrecognize the leak and recognize ES Ch. 1 failed to actuate. The ATC should manually actuateES Ch.1 from C04(ATC-CT). CV-1300 on ES Ch.2 fails to close. The BOP should recognizethe open valve and attempt to close it manually. The CRS will direct operation per either1202.002 Loss of Subcooling Margin or 1202.010 ESAS. Either procedure is acceptable. If theCRS enters ESAS he will eventually be directed to 1202.002 Loss of Subcooling Margin.TS 3.4.13 Condition ACT-Criteria RCP' should be tripped within 2 minutes of the loss of SCM.CT criteria -ESAS Ch. 1 should be manually actuated before RT-10 is reported complete.

Page 6 of 19Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 1-R5Event No.TimeMalf. No.Value/Ramp TimeEventDescriptionRecall IC 101IMF RP246,7,8,9RPS failedIRF CO_C2A offC2A IA compressor OOSIOR DO_C2ASLGC2A IA compressor OOSIRF B5106 OPENMabelvale 500KV switchyard breaker openIRF B5110 OPENMabelvale 500KV switchyard breaker openIMF RD362 OPEN Group 2 Rod 4IMF RD363 OPEN Group 6 Rod 8IMF ES259ES Channel 1 fails to auto actuateIMF CV1300Failed open 1 0 N/A N/APerform remaining steps of 1104.005Supplement 2 RB Spray Red TrainValves Quarterly Test.

2 12 N/AIORDI_ICC0009L N/A FalseDispatcher directs power reduction to700MweULD is failed 3 22IORAI_FIC1207 1.0RCP total flow setpoint fails high. Thiswill result CV-1207 Seal Injectioncontrol valve traveling full open.

4Seal Inj.8-10 gpmIMF CV016 N/ARCP seal failure requiring powerreduction and securing of the RCP.

5 Asdirectedby SROIORDI_ICC0009L FalsePower reduction to ~60%65% or asdirectedby theLeadEvaluatorIMF ED462 N/ALoss of H2 bus when RCP is secured.

6If power<55%IORDI_HS1022SPTrueTrip of 'A' RCP (Contingency to ensureRPS trip setpoint is reached.)

7InitialIMFRP246,7,8,9 N/ARPS is failed requiring a manual RX tripon a loss of two RCP's >55% power (TS)(ATC-CT) criteria - The reactorshould be manually tripped within 2minutes of the loss of the H2 bus.

8InitialIMF RD362IMF RD363100100Two control rods will fail to insertTS 3.1.4 Condition CCT criteria - Emergency borationshould be started within 5 minutes ofthe RX trip.CONTINUED Page 7 of 19Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 1-R5Event No.TimeMalf. No.Value/Ramp TimeEventDescription 9 Rx trip+10 minIMF CV020IMF RC006IMF ES259IMF CV13001000.08 N/A 1'B' RCP seal failure~700gpm RCS leak(TS) (ATC-CT)criteria - ESAS should be actuatedbefore RT-10 reported complete.

Page 8 of 19Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 1Event

Description:

Perform remaining steps in 1104.005 Supplement 2 Red train Spray Valve Test.TimePositionApplicant's Actions or Behavior 0 BOPImplement 1104.005 Supplement 2 step 2.2.2.

BOPVerify Makeup Tank pressure > 25 psig.

BOPVerify one of the following valves closed: RB Sump Line A Outlet (CV-1405) or RB Sump Line A Outlet (CV-1414)

BOPOpen BWST T-3 Outlet (CV-1407).

BOPWhile timing stroke, open CV-2401 (modulating valve).

BOPRecord stroke time in Table 1.

BOPClose CV-2401 (modulating valve, hold control switch in CLOSE untilvalve torques closed). Verify closed indication.

BOPRecord closed stroke in Table 1.

BOPClose CV-1407.EXAMINER NOTEThis event is complete when Supplement 2 is complete ORAs directed by the Lead Evaluator Page 9 of 19Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 2Event

Description:

Dispatcher directs a power reduction to 700Mwe.ULD is failedTimePositionApplicant's Actions or BehaviorEXAMINER NOTEDispatcher will call requiring a power reduction to 700Mwe net output for unit 1 in the next 10minutes.12 CRSDirect operations per 1203.045 Rapid Plant Shutdown.

ATCCommence a plant shutdown at 0.5 to 10% per minute. Place ULD in manual. Attempt Toggle down to CRS directed megawatt setting~700 Mwe.BOPRecognize and report ULD not responding to a lowering command.

CRSDirect power reduction using SG/RX master.BOP Place SG/RX master to hand.BOP Lower plant power to <60%.

ATC BOPMonitor ICS and EHC subsystems for proper integrated response.CRS Direct chemistry or the AO to secure Zinc Injection.

CRSIf the CRS intends to stop heater drain pumps then direct AO toRemoving MSR DI From Service.

BOPAt <75% stop Heater Drain Pumps (P8A and P8B)(CRS may elect to keep the P8's running based upon P8 flow.)If Heater Drain Pumps are secured then the CRS will direct: Verify Hi Lvl Dump Isolations open:V-3041A (at B-3252)V-3037A (at B-4252)Verify Low Level Condenser Spray CV-2907 and CV-2868 (HS-2907 on C02) open.

ATCAs time permits after the runback refer to "Contingency Reactivity Plans"and Exhibit A (Operation of APSR Group) of Power Operation (1102.004)(This may not occur depending on operator response time and scenariotime line.)EXAMINER NOTEThis event is complete when plant power is at 700Mwe ORAs directed by the Lead Evaluator Page 10 of 19Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 3Event

Description:

RCP total flow setpoint fails high. This will result CV-1207 Seal Injection control valvetraveling full open.TimePositionApplicant's Actions or Behavior 22 ATCRecognize, acknowledge, and report Annunciator K08-B7 RCP BleedoffFlow HI.CRS Implement 1203.012G Annunciator K08 Corrective Action.

CRSGO TO "Seal Degradation" section of Reactor Coolant Pump and MotorEmergencies (1203.031).

BOPVerify the following valves are open: RCP Seal Bleed off (Normal) Return (CV-1274) RCP Seal Bleed off (Normal) from P-32D (CV-1270) RCP Seal Bleed off (Normal) from P-32C (CV-1271) RCP Seal Bleed off (Normal) from P-32B (CV-1272) RCP Seal Bleed off (Normal) from P-32A (CV-1273)

ATCVerify RCP Seal INJ Block (CV-1206) open.EXAMINER NOTEIf directed the WCO will report nothing abnormal with CV-1207.

ATCManually adjust RC Pump Seals Total INJ Flow (CV-1207) to establish32 to 40 gpm by verifying individual seal injection flow rates 8 to 10 gpm.

CRSProvide Attachment A of this procedure to a Control Board Operator toaid in monitoring seal parameters.EXAMINER NOTEThis event is complete when RCS seal injection flow is 8 to10gpm.

ORAs directed by the Lead Evaluator Page 11 of 19Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 4 & 5Event

Description:

RCP seal failurePower ReductionTimePositionApplicant's Actions or Behavior RCP seal Inj.8-10 gpmBOP Recognize and report 'B' RCP seal failure.

CRSDirect operations per 1203.012G K08 Annunciator Corrective Action and1203.031 Reactor Coolant Pump and Motor Emergency ANYDetermine Seal bleed off temp >40°F above 1st stage seal temp.

CRSImplement Rapid Plant Shutdown (1203.045). Direct power reduction using SG/RX Master ATCReduce reactor power to within the capacity of the unaffected RCPcombination, using Rapid Plant Shutdown (1203.045) .BOP Lower SG/RX master to hand.BOP Lower plant power to <60%.

ATC BOPMonitor ICS and EHC subsystems for proper integrated response.

CRSDirect chemistry or the AO to secure Zinc Injection.(If not already performed)

CRSIf the CRS intends to stop heater drain pumps then direct AO to performRemoving MSR DI From Service.(If not already performed)

BOPAt <75% stop Heater Drain Pumps (P8A and P8B)(CRS may elect to keep the P8's running based upon P8 flow.)If Heater Drain Pumps are secured then the CRS will direct: Verify Hi Lvl Dump Isolations open:V-3041A (at B-3252)V-3037A (at B-4252)Verify Low Level Condenser Spray CV-2907 and CV-2868 (HS-2907 on C02) open.(If not already performed)

ATCAs time permits after the runback refer to "Contingency Reactivity Plans"and Exhibit A (Operation of APSR Group) of Power Operation (1102.004)(This may not occur depending on operator response time and scenariotime line.)EVENT 4 & 5 CONTINUED Page 12 of 19Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 4 & 5 CONTINUEDEvent

Description:

RCP seal failureTimePositionApplicant's Actions or Behavior ATCAs time permits after the runback refer to "Contingency ReactivityPlans" and Exhibit A (Operation of APSR Group) of Power Operation(1102.004).(This may not occur depending on operator response time andscenario time line.)EXAMINER NOTEThis event is complete when plant power is <65%

ORAs directed by the Lead Evaluator Page 13 of 19 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 6 & 7 & 8Event

Description:

Loss of H2 bus when RCP is secured.RPS is failed requiring a manual RX trip on a loss of two RCP's >55% power.Two control rods fail to insert on Rx trip.TimePositionApplicant's Actions or Behavior 65%or asdirectedby theLeadEvaluator ANYRecognize loss of H2 bus and two RCP's.Recognize RPS failed to complete an automatic trip.TS 3.3.1 Condition C CRSDirect operations per 1202.001 Reactor Trip Emergency OperatingProcedure.

CRSDirect manual trip of the reactor and performance of immediate actions.(ATC may trip the reactor before the CRS direction.)

ATCManually Trip Rx. Verify all rods inserted AND Reactor power dropping.CT criteria -The reactor should be manually tripped within 2minutes of the loss of the H2 bus.

CRSDirect the performance of RT-12 Emergency Boration.TS 3.1.4 Condition CCT criteria - Emergency boration should be started within 5minutes of the RX trip.

ATCSet Batch Controller for maximum batch size as follows:a) Depress lower DISPLAYb) Depress TOTALc) Depress TOTAL RESETd) Depress BATCH SETe) Depress 9, six timesf) Depress ENTERg) Depress lower DISPLAY ATCVerify Condensate to Batch Controller (CV-1251) closed.

ATCOpen Batch Controller Outlet (CV-1250).

ATCVerify both Letdown Filters in service (F-3A and B).

ATCRecord initial BAAT (T-6) level ____________ in.

ATCStart available Boric Acid Pump(s) (P-39A or B or both).Emer.BorationActions ATCStart Batch Controller by depressing RUN key.EVENT 6 & 7 & 8 CONTINUED Page 14 of 19Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 6 & 7 & 8 CONTINUEDEvent

Description:

Loss of H2 bus when RCP is secured.RPS is failed requiring a manual RX trip on a loss of two RCP's >55% power.Two control rods fail to insert on Rx trip.TimePositionApplicant's Actions or Behavior ATCAdjust Batch Controller Flow CNTRL VLV (CV-1249) to 100% openas follows:a) Depress VALVE SETb) Depress numbers: 1, 0, 0c) Depress ENTERd) Depress lower DISPLAYe) Depress RATE ATCAdjust Pressurizer Level Control Setpoint to 220".

ATCOpen BWST Outlet to OP HPI Pump (CV-1407 or 1408).

ATCWhen PZR level is >100", Thenestablish maximum Letdown flow.

ATCPerform the following as necessary to maintain MU Tank level 55 to86":a) Close Batch Controller Outlet (CV-1250).b) Stop running Boric Acid Pump(s) (P-39A, P-39B).c) Place 3-Way valve in BLEED.d) WhenMU Tank level is lowered to desired level, Thenperform the following:(1) Return 3-Way valve to LETDOWN.(2) Start available Boric Acid Pump(s) (P-39A or B orboth).(3) Open Batch Controller Outlet (CV-1250).(These steps may not be required)

ATCAs time permits, determine actual required boration as follows:a) Obtain required boron concentration from the Plant DataBookb) Calculate batch add required using Plant Computer ORSoluble Poison Concentration Control (1103.004),Attachment A.3, "Calculation of Feed Volume For BatchBoration or Dilution".c) Use 1103.004, Attachment D, "Volume of BAAT vs. Depthof Liquid" to determine desired final BAAT level.Emer.BorationActions ATCWhen required amount of boric acid has been added per step 14) asdetermined by Reactor Engineering.(LOCA will occur prior to completing boric acid addition)

BOPManually trip Turbine.Verify Turbine throttle and governor valves closed.

ATC or BOPCheck adequate SCM.

CRSAdvise Shift Manager to implement Emergency Action LevelClassification (1903.010).EVENT 6 & 7 & 8 CONTINUED Page 15 of 19Appendix D Required Operator Actions Form ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 6 & 7 & 8CONTINUEDEvent

Description:

Loss of H2 bus when RCP is secured.RPS is failed requiring a manual RX trip on a loss of two RCP's >55% power.Two control rods fail to insert on Rx trip.TimePositionApplicant's Actions or Behavior ATCReduce Letdown by closing Orifice Bypass (CV-1223).(This is not performed due to emergency boration)BOP Open BWST Outlet to OP HPI pump (CV-1407 or 1408).

ATCPressurizer Level Control setpoint to 100".

BOPCheck for proper electrical response.

ANYCheck OP HPI pump supplying normal Makeup and Seal Injection.

ATCCheck both SG levels remain <410".

ANYCheck Instrument Air Header press >75 psig.

ANYCheck all NNI power available.

ANYCheck all ICS power available.

ATCCheck SG press >900 psig.

ANYCheck MSSV OPEN alarm clear (K07-C5).

ANYCheck MSIVs open.

ANYCheck Turb BYP valves operate to maintain SG press 970 to 1020 psig.

ANYPlace both Feedwater Demands in HAND AND verify demand at zero.

ANYCheck Main Block valves closed (CV-2625 and 2675).

ANYCheck Low Load Block valves closed (CV-2624 and 2674).

ANYCheck Startup valves maintain SG levels 20 to 40".

ANYVerify MFW pumps run back and then operate to maintain >70 psidacross Startup valves.

ANYCheck the following in service: Two Service Water pumps (P4A, B, or C). ICW pump supplying Nuclear loop (P33C or B). ICW pump supplying Non-nuclear loop (P33A or B). RB Cooling Fans (VSF1A, B, C, D, and E) Previously running Main Chiller(s) (VCH1A, B)EVENT 6 & 7 & 8 CONTINUED Page 16 of 19Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 6 & 7 & 8CONTINUEDEvent

Description:

Loss of H2 bus when RCP is secured.RPS is failed requiring a manual RX trip on a loss of two RCP's >55% power.Two control rods fail to insert on Rx trip.TimePositionApplicant's Actions or Behavior ANYCheck ESAS Actuation alarms clear on K11.

ANYCheck RCS press >1700 psig.

ATCCheck Pressurizer Level Control valve (CV-1235) maintains PZR level>55".ANYCheck PZR steam space integrity.

ATCVerify ERV, Pressurizer Spray, and Pressurizer Heaters operate tocontrol RCS press 2050 to 2250 psig.ANY Check at least one RCP running.

ATCCheck RCS T-cold remains >540F.ANYCheck adequate SCM.

ATCCheck RCS temp remains either: 580F T-hot with any RCP on OR 610F CET temp with all RCPs off.

BOPCheck SG tube integrity.

ANYCheck RCS integrity.EXAMINER NOTEThis event is complete when Emergency Boration is started ORAs directed by the Lead Evaluator Page 17 of 19 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 9Event

Description:

A ~700gpm RCS leak will develop in the RX building resulting in ESAS actuation.TimePositi onApplicant's Actions or BehaviorTrip +10 min ANYRecognize and report lower PZR level and RCS pressure.

ANYDiagnose RCS leak inside containment.TS 3.4.13 Condition A ANYRecognize and report ESAS Channels 2, 3, 4, 5, & 6 actuated.

ANYRecognize and report ES Channel 1 failed to actuate.

ATCManually actuate ES channel 1.CT criteria - ES channel 1 should be actuated before RT-10 isreported complete.

CRSDirect operations per 1202.010 ESAS, or 1202.002 Loss of SubcoolingMargin.ANYCheck adequate SCM .

ANYRecognize and report a loss of SCM.

BOPIF <2 minutes have elapsed, THEN trip all RCPs.CT-Criteria RCP' should be tripped within 2 minutes of the loss ofSCM.ATCVerify Reflux Boiling setpoint selected for EFW.

BOPVerify proper ESAS actuation (RT 10).

BOPRecognize and report CV1300 failed to close.

BOPAttempt to manually close CV1300.

ATCIF MU Tank level drops below 18", THEN close Makeup Tank Outlet(CV-1275). (MUT not expected to go below 18".

ATCIsolate Pressurizer Spray Line as follows:A. Place Pressurizer Spray Control in HAND AND verify closed(CV-1008).B. Close Pressurizer Spray Isolation (CV-1009).

ATCVerify ERV Isolation (CV-1000) closed.

ANYCheck Nuclear Loop ICW process monitor alarm clear.

ANYCheck SG tube integrity.

ANYCheck RCS press stabilizes >150 psig.(RCS pressure will stabilize >150psig)If ESAS isentered ANYCheck adequate CET SCM.EVENT 9 CONTINUED Page 18 of 19Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 9CONTINUEDEvent

Description:

A ~700gpm RCS leak will develop in the RX building resulting in ESAS actuation.TimePositi onApplicant's Actions or Behavior CRSTransition to 1202.002 Loss of Subcooling Margin.

BOPCheck elapsed time since loss of adequate SCM: IF <2 minutes have elapsed, THEN trip all RCPs.CT-Criteria RCP' should be tripped within 2 minutes of the loss ofSCM.N/AInitiate full HPI (RT 3).(ESAS will be actuated resulting in full HPI)

ATCIF MU Tank level drops below 18", THEN close Makeup Tank Outlet(CV-1275). (MUT not expected to go below 18".

ATC BOPVerify proper EFW actuation and control (RT 5).(The BOP may perform RT-5 as part of RT-10)

ATCTrip both MFW pumps.

ANYCheck ESAS Actuation alarms clear on K11.IF RCS press is >150 psig, THEN verify proper ESAS actuation (RT 10).(RCS pressure will be >150 psig)

ATCIsolate Pressurizer Spray Line as follows:A. Place Pressurizer Spray Control in HAND AND verify closed(CV-1008).B. Close Pressurizer Spray Isolation (CV-1009).

ATCVerify ERV Isolation (CV-1000) closed.

ANYCheck Nuclear Loop ICW process monitor alarm clear.

ANYCheck SG tube integrity.

ANYCET SCM is adequate, THEN control RCS press low within limits ofFigure 3 (RT 14).(SCM will not be adequate)

ANYCheck RCS press remains >150 psig.ANYCheck SG levels at or approaching 370 to 410".

ANYCheck primary to secondary heat transfer in progress.(Primary to secondary heat transfer will not be in progress)

ATCRaise primary to secondary T to 40 to 60°F by adjusting TURB BYP orATM Dump Control System to establish SG press within limits of Figure 5.Actions for LOSM EOP BOPIF SG press drops below 720 psig, THEN bypass MSLI.a) On Initiate module in each EFIC cabinet, place each SGbypass toggle switch in BYPASS and release.EVENT 9 CONTINUED Page 19 of 19Op-Test No.: 2008-1Scenario No.: 1-R5Event No.: 9CONTINUEDEvent

Description:

A ~700gpm RCS leak will develop in the RX building resulting in ESAS actuation.TimePositionApplicant's Actions or Behavior ANYCheck primary to secondary heat transfer in progress.(Primary to secondary heat transfer will not be in progress)

N/AIF RCPs cannot be run due to either inability to maintain adequate CETSCM OR H1 and H2 bus degraded voltage (<6900V), THEN bump RCPsto establish primary to secondary heat. Establish PZR level >180".(Pressurizer level can not be established >180" therefore RCP's will notbe bumped)

ATCVerify SG levels at or approaching 370 to 410".Action s for LOSM EOP CRSIF an uncontrolled RCS cooldown is occurring due to HPI/break flow,regardless of SG status, THEN GO TO Small Break LOCA Cooldown(1203.041).EXAMINER NOTEThis scenario may be terminated when the CRS transitions to 1203.041 ORAs directed by the Lead Evaluator Page 1 of 15Appendix DScenario OutlineForm ES-D-1Facility: ANO-1 Scenario No.: 2-R5Op-Test No.: 2008-1Examiners: __________________________ Operators: __________________________ __________________________ __________________________ __________________________ __________________________Initial Conditions:100% PowerEFIC is failed and will not auto actuate.C2A IA compressor is out of service for overhaul.Provide picture of RS-4Turnover:Day shift normal working day.C2A IA compressor is out of service for overhaul.Currently under a severe thunderstorm warning for the next hour. All actions of 1203.025Natural Emergencies are complete.Swap ICW pumps to have P33A and P33B running to allow visual inspection of P33C. TheInside AO has been briefed and is standing by the ICW pumps. P33B had not been drained.

EventNo.Malf. No.EventType*EventDescription 1 N/AN (SRO, BOP)Swap operating ICW pumpsLightning strike DI-DG2SK01A3 N/ALightning strike#2 EDG auto start#2 EDG Auto Start Alarm 2CV-3807C (SRO, BOP)#2 EDG SW valve fails to open(TS).#2 EDG Shutdown 3 N/AN (SRO)R (ATC)Dispatcher directs a power reduction to 700Mwe in thenext 15 minutes.

4Lightning strikeED451I (SRO, ATC)Lightning strikeLoss of the NNI Y power supply.

5ED183M (ALL) Loss of Offsite Power/Degraded Power 6DG175DI_DG1_VR-LWC (SRO, BOP)#1 EDG will not auto start(BOP-CT)#1 EDG voltage low (<4100V) 7FW621C (SRO, ATC)EFIC fails(ATC-CT) (TS)DG173M (ALL)#1 EDG will trip(TS)8A901 N/AAlternate AC Generator available.(BOP-CT)*(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 15Appendix DScenario OutlineForm ES-D-1Scenario #2-R5 Objectives

1) Evaluate individual ability to perform the swapping of the operating ICW pumps.

2) Evaluate individual ability to recognize and respond to the false auto start ofemergence diesel generator.

3) Evaluate individual ability to recognize and respond to the failure to open of the servicewater supply valve on an operating emergence diesel generator.

4) Evaluate individual ability to reduce plant power.

5) Evaluate individual ability to recognize and respond to the loss of the 'Y' Non-NuclearInstrumentation system.

6) Evaluate individual ability to recognize and respond to a loss of offsite power.

7) Evaluate individual ability to recognize and respond to failure of the emergence dieselgenerator to auto start.

8) Evaluate individual ability to recognize and respond to the failure of the EmergencyFeedwater Initiation and Control system to automatically actuate emergencyfeedwater.

9) Evaluate individual ability to recognize and respond to the tripping of the remainingemergence diesel generator putting the plant in a blackout condition.

10) Evaluate individual ability to perform the energizing of a vital bus from the alternate ACgenerator.

11) Evaluate individual ability to recognize when conditions require the entry into technicalspecifications conditions.

Page 3 of 15Appendix DScenario OutlineForm ES-D-1SCENARIO #2-R5 NARRATIVEThe crew will assume the watch at 100% power. C2A IA compressor is out of service foroverhaul. It is a day shift normal working day. ANO is currently under a severe thunderstormwarning for the next hour. All actions of 1203.025 Natural Emergencies are complete.The crew will start P33B and secure P33C per1104.028 ICW Operating Procedure step10.2(BOP-N) (SRO-N). This is being performed in order to visually inspect the motor rotor. P33Bhad not been drained.A lightning strike will cause the auto start of the #2 EDG. The CRS should direct operations per1203.012A Annunciator K01 Corrective Actions. The crew should determine it is a spuriousactuation. The #2 EDG SW valve CV-3807 will not open resulting in no cooling flow to the EDG(BOP-C) (SRO-C). The crew should take the #2 EDG to lockout to prevent an automatic trip ofthe EDG(TS).TS 3.8.1. Condition BThe dispatcher will call and direct U1 to reduce net generator output to 700Mwe(SRO-N)(ATC-R).A second lightning strike will result in the loss on NNI-Y power supply(ATC-I) SRO-I). The crewshould recognize the loss of NNI-Y power. The CRS should implement 1203.047 Loss of NNIPower. The power supply breakers on RS-4 bkr 9 and Y01 bkr 39 will not reset. Breakers S-1and S-2 on the NNI-Y power supply will not be tripped.Letdown flow and pressure indication will be lost on C04. The letdown orifice bypass valve willfail to 50% reducing letdown flow. CFT pressure instrumentation will be lost along with NaOHtank temperature. All NNI-Y inputs to PMS/PDS will be lost or fail to mid scale.A loss of offsite power will occur due to storm related grid instabilities(SRO-M) (ATC-M)(BOP-M). The reactor will trip automatically. The CRS will direct operations per 1202.001 RxTrip. After the immediate actions are complete the CRS will transition to either 1202.008Blackout or 1202.007 Degraded Power depending on when the BOP manually starts the #1 EDG.The #1 EDG will not auto start requiring the BOP to manually start the EDG(BOP-C) (BOP-CT)

.The #1 EDG voltage will be <4100V requiring the BOP to raise EDG voltage.CT criteria - The BOP should start the #1 EDG before the 15 minute criteria for declaringan SAE for a station blackout.The EFIC system is failed and will not automatically actuate EFW on the Loss of Offsite Power(ATC-C) (SRO-C). The ATC should manually actuate EFW from the remote switch matrix(ATC-CT) (TS). The ATC will perform 1202.012 Repetitive Tasks RT-5 Verify proper EFWactuation and control. EFW may be manually actuated before the step in the EOP that directsverifying EFW actuated.TS 3.3.11 Condition BCT - EFW should be manually actuated before the ERV opens in automatic.

CONTINUED Page 4 of 15Appendix DScenario OutlineForm ES-D-1SCENARIO #2-R5 NARRATIVE CONTINUEDThe #1 EDG will trip putting the plant into a blackout(SRO-M) (ATC-M) (BOP-M) (TS). TheCRS will direct operations per 1202.008 Blackout.TS 3.8.1 Condition E, 3.0.3The alternate AC generator will become available. The BOP should energize the A3 bus fromthe AAC generator(BOP-CT).CT criteria - The AAC generator should be placed in service within 20 minutes ofregaining the AAC Generator.

Page 5 of 15Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 2-R5Event No.TimeMalf. No.Value/Ramp TimeEventDescriptionRecall IC 102IMF FW621EFIC failureIRF CO_C2A offC2A IA compressor OOSIOR DO_C2ASLGC2A IA compressor OOSIMF DG175#1 EDG fails to auto startIMF CV3807 Off#2 EDG SW valve fails closedIRF K01E7 OffD01 Trouble offIOR DI_DG1_VR_LW 15sec#1 EDG voltage low 1 0 N/A N/ASwap operating ICW pumps to haveP33A and P33B running.

10 T1IRF LightningIOR DI-DG2SIOR DI_DG2SPIRF K01A3DRF LightningTrueTrue False OnLightning strike will cause the auto startof #2 EDG.

2InitialIMF CV-3807 0#2 EDG SW valve will not openfollowing the EDG auto start. This willrequire the operators to shutdown #2 EDG.(TS)3 18 N/A N/ADispatcher will call and direct a powerreduction to 700 Mwe in the next 15minutes.4 28 T2IRF LightningIMF ED451True N/AAnother lightning strike will result in theloss of the NNI Y power supply.

5 36IMF ED183 N/AA Loss of Offsite Power will occurresulting in an automatic reactor trip.

6InitialIMF DG175 N/AThe #1 EDG will not auto start requiringthe operators to manually start the EDG.(BOP-CT) criteria - The BOP shouldstart the #1 EDG before 15 minutecriteria for declaring an SAE for astation blackout.CONTINUED Page 6 of 15Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 2-R5Event No.TimeMalf. No.Value/Ramp TimeEventDescription 7InitialIMF FW621 N/AEFIC is failed and will not automaticallyactuate EFW.(TS) (ATC-CT) criteria - EFW shouldbe manually actuated before the ERVopens in automatic.U2 will report ACC Generator is running slow. Maintenance has been dispatched.

48IMF DG173 N/AThe #1 EDG will trip putting the plantinto a blackout.(TS)At T=52U2 will report AAC Generator has been repaired and is running normally with 2A901closed.8 52IRF A901ClosedThe Alternate AC Generator willbecome available.(BOP-CT) CT criteria - The AACgenerator should be placed inservice within 20 minutes ofregaining the AAC Generator.

Page 7 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 1Event

Description:

Swap operating ICW pumps to have P33A and P33B running.TimePositionApplicant's Actions or Behavior CRSDirect performance of 1104.028 ICW Operating Procedure step 10.2.

0 BOPOpen A/B crossconnect valves:CW Pumps Suction Crossconnect (CV-2241)CW Pumps Discharge Crossconnect (CV-2239)

BOPDirect AO to vent P-33B as necessary by opening ICW Pump P-33BVent (ICW-1191).

BOPStart P-33B.

BOPWhen P-33B has run at least 3 minutes, Then stop P-33C.

BOPVerify flow is normal (~2000 gpm) on ICW Coolers Inlet Flow Non-Nuc(FI-2218) (CO9).EXAMINERS NOTE:This event is complete when ICW flows are verified normal ORAs directed by the Lead Evaluator Page 8 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 2Event

Description:

Lightning strike will cause the auto start of #2 EDG.#2 EDG SW valve will not open following the EDG auto start. This will require theoperators to shutdown #2 EDG.TimePositionApplicant's Actions or Behavior 10 CRSAcknowledge and report Annunciator K01A3 EDG 2 AUTO STARTCOMMAND.CRSDirect plant operation per K01A3 EDG 2 AUTO START COMMAND.

BOPVerify that DG2 auto start.

BOPCheck bus A4 energized from bus A1.BOP Check bus B6 energized.

ANYVerify SERV WTR to DG2 CLRS (CV-3807) opens.Recognize and report CV3807 will not open.EXAMINEERS NOTEIf called the AO will report CV-3807 cannot be opened locally.

CRSDirect #2 EDG be placed in lockout. (BOP may try to push stop P/B first.EDG will stop but then restart)TS 3.8.1. Condition BEXAMINEERS NOTEIf called U2 will report Alternate AC Generator is available.

CRSContact work management to investigate cause of EDG start.

CRSRefer to TS 3.8.1 Condition B for operability requirements.

CRSVerify proper MOD alignment for Service Water Pump (P-4B) andMakeup Pump (P-36B) per Makeup & Purification System Operation(1104.002) AND Service Water and Auxiliary Cooling System(1104.029).EXAMINERS NOTE:This event is complete when #2 EDG is in lockout ORAs directed by the Lead Evaluator Page 9 of 15 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 3Event

Description:

Dispatcher will call and direct a power reduction to 700MWe in the next 15 minutes.TimePositionApplicant's Actions or Behavior 18 CRSDirect operations per 1203.045 Rapid Plant Shutdown.

ATCCommence a plant shutdown at 0.5 to 10% per minute. Place ULD in manual Lower ULD setpoint to ~730 MWe ATC BOPMonitor ICS and EHC subsystems for proper integrated response.ATC Refer to "Contingency Reactivity Plans.

CRSAt <90%, direct Zinc Injection be secured.ATC Stabilize power ~700 Mwe.EXAMINERS NOTE:This event is complete when power is stable at ~700 Mwe ORAs directed by the Lead Evaluator Page 10 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 4Event

Description:

Another lightning strike will result in the loss of the NNI Y power supply.TimePositionApplicant's Actions or Behavior 28 ANYRecognize the loss of NNI-Y power.Recognize and report loss of letdown flow and pressure indication on C04.Recognize and report CV-1223 at 50%.CRS Direct operations per 1203.047 Loss of NNI Power.

ATC BOPVerify NNI X-powered instruments selected on C03, C04, and C13.(Green light on for each SASS parameter)(CRS may direct placing SASS selector switch to the X position)ATC Check NNI Y AC power available.EVALUATOR NOTE:The BOP will go to back of control room to a picture of RS-4 to simulate resettingBreaker RS-4 bkr 9.The evaluator will tell the BOP that bkr 9 will not reset.

BOPReset AND close Normal supply breaker RS-4 bkr 9.

CRSDispatch an operator to reset ANDclose Alternate supply breaker Y01bkr 39, while continuing with this procedure.EXAMINERS NOTE:Report as AO that Y01 bkr 39 will not reset.

CRSDispatch an operator to reset NNI Y power supply using Reactor CoolantSystem NNI (1105.006), "Resetting NNI Power Supplies" section, whilecontinuing with this procedure.The S-1 and S-2 switches are on the NNI power supply and will not betripped. Time will not permit any operator actions to be accomplished bythe outside control room operator.EXAMINERS NOTE:This event is complete when instruments are verified selected to NNI-X power and powersupply breakers Y01 bkr 39 and RS-4 bkr 9 are reported as not closing ORAs directed by the Lead Evaluator Page 11 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 5Event

Description:

A Loss of Offsite Power will occur resulting in an automatic reactor trip.TimePositionApplicant's Actions or Behavior 36ANY Recognize and report a loss of offsite power.CRS Direct operations per 1202.001 RX trip.

ATCManually Trip Rx, Verify all rods inserted and Reactor power dropping.BOP Manually trip Turbine, Verify Turbine throttle and governor valves closed.

ANYCheck adequate SCM.EXAMINERS NOTE:This event is complete when the immediate actions of 1202.001 are complete ORAs directed by the Lead Evaluator Page 12 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 6 & 7Event

Description:

The #1 EDG will not auto start requiring the operators to manually start the EDG.EFIC is failed and will not automatically actuate EFW.TimePositionApplicant's Actions or BehaviorLOOPANY Recognize #1 EDG failed to auto start.

BOPManually start #1 EDG.(BOP-CT) CT criteria - The BOP should start the #1 EDG before the15 minute criteria for declaring an SAE for a station blackout.CRS Direct operations per 1202.007 Degraded Power.

BOPVerify both EDGs supplying associated ES buses with proper voltage,frequency and loading:100 to 4200V.5 to 60.5 Hz2750 kwBOP Recognize #1 EDG voltage is low.BOP Adjust #1 EDG voltage to ~4160V.

BOPVerify 480V MCC B55 and 56 power supply is selected to B5.

BOPClose ACW Isolation (CV-3643).

BOPClose CV-3640BOP Close CV-3820 ANYRecognize and report Service Water Pump discharge pressure highalarm.(CRS may elect to place additional SW loads in service)

CRSDispatch an operator to restore EDG.(May not be performed as #2 EDGis known to be OOS.)EXAMINERS NOTE:U2 will report ACC Generator is running slow. Maintenance has been dispatched.CRS Request U2 start AAC Generator.BOP Verify P36B Bus Select MOD Control selected to A3.BOP Verify P4B Bus Select MOD Control selected to bus A3.EVENT 6 & 7 CONTINUED Page 13 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 6 & 7 CONTINUEDEvent

Description:

The #1 EDG will not auto start requiring the operators to manually start the EDG.EFIC is failed and will not automatically actuate EFW.TimePositionApplicant's Actions or BehaviorBOP Verify SW to DG1 CLRs open (CV-3806).BOP Verify a Service Water pump P4A on after 15-second time delay.

ATCActuate MSLI for both SGs AND verify proper actuation and control ofEFW and MSLI (RT 6).TS 3.3.11 Condition B(ATC-CT) CT - EFW should be manually actuated before theElectromatic Relief Valve (ERV) opens in automatic.

ATCOperate ATM Dump CNTRL valves in HAND to minimize cycling andconserve Instrument Air.(Crew may determine ADV's not cycling and leave in auto)ANY Check RCS press remains >1700 psig PZR level remains >

30".BOP Isolate Letdown by closing Letdown Cooler Outlets (CV-1214 and 1216).ANY Check OP and STBY HPI pumps off.

BOPPlace RCP Seals Bleedoff (Alternate Path to Quench Tank) controls inCLOSE (SV-1270, 1271, 1272 and 1273).

BOPIsolate RCP Seal Bleedoff (Normal) by closing CV-1270, 1271, 1272,and 1273.ATCIF PZR level is >55", THEN verify Proportional Control PressurizerHeaters operating in AUTO.

ATC BOPPlace the following breakers in handswitches in PULL-TO-LOCK. A1, A2, H1, H2 Condensate pumps (P2A, B and C) ICW pumps (P33A, B and C)ATC Verify RCP Seal INJ Block closed (CV-1206).BOP Close RCS Makeup Block (CV-1233 or 1234).BOP Open BWST Outlet to OP HPI pump CV-1407.EXAMINERS NOTE:This event is complete when CV-1407 is open ORAs directed by the Lead Evaluator Page 14 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 8Event

Description:

The #1 EDG will trip putting the plant into a blackout.The Alternate AC Generator will become available.TimePositionApplicant's Actions or Behavior 48 ANYRecognize and report #1 EDG tripped.TS 3.8.1 Condition E, 3.0.3CRS Direct operations per 1202.008 Blackout.

ATCVerify proper EFW actuation and control (RT 5).(CRS may direct ATC to re-perform RT5. RT 5 was performed during theDegraded Power event.)

CRSDispatch an operator to restore EDG (May not be performed as #2 EDGis known to be OOS.)EXAMINERS NOTE:U2 will report Maintenance is working on the ACC GeneratorCRS Request U2 start AAC Generator.ATC Check adequate SCM is maintained.ATC Place P7B handswitch in PULL-TO-LOCK.BOP Check off-site power available.

CRSDirect dispatcher to take emergency actions to restore power, includingsystem load shed if necessary.CRS Transition to step 33.

CRSDispatch an operator to take manual control of EFW pump (P7A) usingEmergency Feedwater pump Operation (1106.006).EXAMINEERS NOTECall as U2 and report AAC Generator is running normally and 2A-901 is closed.

52CRS Transition to step 2 of 1202.008 Blackout.

CRSDirect BOP to energize A3 using ES Electrical System Operation(1107.002), Alternate AC Generator Operation" section.(BOP-CT) CT criteria - The AAC generator should be placed inservice within 20 minutes of regaining the AAC Generator.BOP Place DG1 Output Breaker (A-308) in PULL-TO-LOCK.BOP Verify A1 to A3 Supply Breaker (A-309) open.EVENT 8 CONTINUED Page 15 of 15Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R5Event No.: 8CONTINUEDEvent

Description:

The #1 EDG will trip putting the plant into a blackout.The Alternate AC Generator will become available.TimePositionApplicant's Actions or BehaviorBOP Verify A3-A4 Tie Breakers open (A-310 and A-410).BOP Verify no bus A3 Lockout.

BOPTurn Synchronize switch on for A3-A4 Tie Breakers (A-310 and A-410).

BOPClose A3-A4 Crosstie (A-310).

BOPTurn Synchronize switch off.

BOPCoordinate with Unit 2 to ensure 2K9 is NOT overloaded when startingloads on bus A3.

BOPIf desired, Then start Service Water Pump P-4A or B per Service Waterand Auxiliary Cooling System (1104.029).

CRSGO TO 1202.007, "DEGRADED POWER" procedure.EXAMINERS NOTE:This scenario is complete when A3 is powered from the AAC Generator ORCRS transitions back to 1202.007 Degraded Power ORAs directed by the Lead Evaluator ES-301Transient and Event Checklist Rev 1Form ES-301-5Facility: ANO-1Date of Exam: 9-8-2008Operating Test No.: 2008-1Scenarios 1 23 (Spare)CREW POSITIONCREW POSITIONCREW POSITION M I N I M U M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 2, 5 3 2 1 1 0NOR 1 1, 3 7 1 1 1 1 1 I/C3, 7, 8 2, 62, 4, 6, 94, 6, 92, 4, 5, 6, 9 5 4 4 2 MAJ 6, 9 5, 8 6, 7 7, 6 6, 7 4 2 2 1 RO1, 2, 3 TS6, 6, 7 0 0 2 2 RX 3 0 1 1 0NOR1, 2, 5 3 1 1 1 I/C3, 4, 7, 8, 9 4, 7 5 4 4 2 MAJ 6, 9 5, 8 2 2 2 1SRO-U2, 3, 5 TS7, 8, 9, 9 4 0 2 2 RX 0 1 1 0NOR 1 1, 3 2 1 1 1 I/C 4, 92, 4, 6, 7 4 4 4 2 MAJ 6, 9 5, 8 2 2 2 1SRO-U1, 4, 6 TS2, 7, 8 3 0 2 2Instructions:

1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type;TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant(BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument orcomponent (I/C) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in theBOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.Reactivity manipulations may be conducted under normal orcontrolled abnormal conditions (refer to Section D.5.d)but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced withadditional instrument or component malfunctions on a 1-for-1 basis.3. Whenever practical, both instrument and component malfunctions should be included; only those that requireverifiable actions that provide insight to the applicant's competence count toward the minimum requirements specifiedfor the applicant's license level in the right-hand columns.

ES-301Competencies Checklist Rev 1Form ES-301-6Facility:ANO-1Date of Examination: 09/08/2008 Operating Test No.: 2008-1APPLICANTS ROSRO-USCENARIOSCENARIOCompetencies 1 23 (Spare)1 23 (Spare)Interpret/DiagnoseEvents and Conditions2, 3, 6, 7, 8, 92, 4, 5, 6, 82, 4, 5, 6, 7, 92, 3, 4, 6, 7, 8, 92, 4, 5, 6, 7, 82, 4, 5, 6, 7, 9Comply With andUse Procedures (1)2, 3, 5, 6,7, 8, 91, 2, 4, 5, 6, 81, 2, 3, 4,5, 6, 7, 8, 91, 2, 3, 4, 5,6, 7, 8, 91, 2, 3, 4,5, 6, 7, 81, 2, 3, 4,5, 6, 7, 8, 9Operate ControlBoards (2)2, 3, 5, 6,7, 8, 91, 2, 4, 5, 6, 81, 3, 4, 6,7, 8, 9 N/A N/A N/ACommunicateand Interact2, 3, 5, 6,7, 8, 91, 2, 3, 4, 5, 6, 81, 2, 3, 4,5, 6, 7, 8, 91, 2, 3, 4, 5,6, 7, 8, 91, 2, 3, 4,5, 6, 7, 8, 91, 2, 3, 4,5, 6, 7, 8, 9DemonstrateSupervisory Ability (3)

N/A N/A N/A1, 2, 3, 4, 5,6, 7, 8, 91, 2, 3, 4,5, 6, 7, 81, 2, 3, 4,5, 6, 7, 8, 9Comply With andUse Tech. Specs. (3)

N/A N/A N/A7, 8, 9, 92, 7, 86, 6, 7Notes: (1)Includes Technical Specification compliance for an RO.

(2)Optional for an SRO-U.

(3)Only applicable to SROs.Instructions:Check the applicants' license type and enter one or more event numbers that will allowthe examiners to evaluate every applicable competency for every applicant.