IR 05000313/2008301
| ML082750586 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/05/2008 |
| From: | Operations Branch IV |
| To: | |
| References | |
| Download: ML082750586 (339) | |
Text
Page 1 of 10Appendix DScenario OutlineForm ES-D-1Facility: ANO-1 Scenario No.: 1-R2Op-Test No.: 2008-1Examiners: __________________________ Operators: __________________________ __________________________ __________________________ __________________________ __________________________Initial Conditions:80% 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.Turnover:Day shift normal working day.80% power due to dispatcher direction for loss of 500KV line as a result of maintenance onthe Mabelvale 500KV line.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.
2AI_FIC1207I (SRO, ATC)RCP total flow setpoint fails to high.
3CV016C (SRO, BOP)RCP seal failure.
4 N/AN (SRO)R (ATC)Power reductionDI_H24TC (ALL) Loss of H2 bus.
5CO_P32A N/AIf power <55%,Trip 'A' RCP(Contingency to ensure RPS trip setpoint is reached.)
6RP246,7,8,9C (SRO, ATC)M (ALL)RPS is failedManual RX trip(TS)(ATC-CT)7CV020RC006C (SRO, BOP)M (ALL)'B' RCP seal failure~200gpm RCS leak(TS) (BOP-CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 10Appendix DScenario OutlineForm ES-D-1Scenario #1-R2 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 stop a running reactor coolant pump at power.
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 a post trip reactor coolant pumpseal failure.
9) Evaluate individual ability to recognize and respond a reactor coolant system leakinside the reactor building.
10) Evaluate individual ability to recognize when conditions require the entry into technicalspecifications conditions.
11) Evaluate individual ability to recognize and respond to the need for high pressureinjection as a result of increased reactor coolant system leakag Page 3 of 10Appendix DScenario OutlineForm ES-D-1SCENARIO #1-R2 NARRATIVEThe crew will assume the watch at 80% power. The Mayflower 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.There is a severe thunderstorm warning in effect for Pope and Yell counties for the next twohours. All Natural Emergency (1203.025) actions are complete for this notification.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 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)
.When the 'B' RCP is stopped a loss of the H2 bus will occur resulting in a loss of two RCP's(B and D)(BOP-C) (SRO-C) (ATC-C). If reactor power is <55% then the 'A' RCP will be trippedby the simulator instructor to create the condition for the recognition of an RPS failure. The ATCshould recognize the reactor should have tripped and manually trip the reactor.(ATC-C)(SRO-C) (ATC-CT) (ALL-M) (TS)
.TS 3.3.1 Condition CCT criteria -The reactor should be manually tripped within 2 minutes of the loss of the H2 bus.~5 minutes post trip a ~300gpm leak will occur in the reactor building from the failed RCP seal(SRO-C) (BOP-C) (ALL-M) (TS). The crew should recognize the leak and the BOP shouldinitiate HPI per RT-2 to maintain RCS inventory pressure and subcooling margin(BOP-CT).TS 3.4.13 Condition ACT criteria -HPI should be started before the ESAS actuates on low RCS pressur Page 4 of 10Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 1-R2Event No.TimeMalf. No.Value/Ramp TimeEventDescriptionRecall ICTo be established during validationIMF RP246,7,8,9 1 0 N/A N/APerform remaining steps of 1104.005Supplement 2 RB Spray Red TrainValves Quarterly Test.
2 12IORAI_FIC1207 1.0RCP total flow setpoint fails high. Thiswill result CV-1207 Seal Injectioncontrol valve traveling full open.
3Seal Inj.8-10 gpmIMF CV016 N/ARCP seal failure requiring powerreduction and securing of the RCP.
4 Asdirectedby SRO N/A N/APower reduction to ~60%
RCPStopped Or 58%powerIMF ED184 N/ALoss of H2 bus when RCP is secured.
5If power<55%IORDI_HS1022SPTrueTrip of 'A' RCP (Contingency to ensureRPS trip setpoint is reached.)
6InitialIMFRP246,7,8,9 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.
7 Rx trip+5 minIMF CV020IMF RC0061000.0016120 200'B' RCP seal failure~300gpm RCS leak(TS) (BOP-CT)criteria - HPI should be startedbefore the ESAS actuates on lowRCS pressur Page 5 of 10Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R2Event 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.(BOP-N) (SRO-N)
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-1407This event is complete when Supplement 2 is complet Page 6 of 10Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R2Event No.: 2Event Description:RCP total flow setpoint fails high. This will result CV-1207 Seal Injection control valvetraveling full open.TimePositionApplicant's Actions or Behavior 12 ATCRecognize, acknowledge, and report Annunciator K08-B7 RCP BleedoffFlow HI(ATC-I) (SRO-I)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.
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.This event is complete when RCS seal injection flow is 8 to10 gp Page 7 of 10Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R2Event No.: 3 & 4Event Description:RCP seal failureTimePositionApplicant's Actions or Behavior RCP seal Inj.8-10 gpm BOPRecognize and report 'B' RCP seal failure.(BOP-C) (SRO-C)Direct 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)
ATCReduce reactor power to within the capacity of the unaffected RCPcombination, using Rapid Plant Shutdown (1203.045)
CRSDirect power reduction using ULD ATC BOPLower plant power to <60%(SRO-N) (ATC-R)This event is complete when plant power is <60%
Page 8 of 10 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R2Event No.: 5 & 6Event 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.TimePositionApplicant's Actions or Behavior CRSDirect BOP to stop the affected RCP(s) per Reactor Coolant PumpOperation (1103.006)
ANYIF time permits, THEN contact predictive maintenance to install backupindication of RCP zero speed prior to RCP stop.
BOPStart HP Oil Lift Pump (P-63B)
OREmergency HP Oil Lift Pump (P-80B)
BOPStop P-32B.
BOPVerify HP Oil Lift Pump (P-63B) remains on.
ANYMonitor affected RCP for reverse rotation ANYRecognize loss of H2 bus and two RCP's(BOP-C) (SRO-C) (ATC-C)Recognize RPS failed to complete an automatic trip. (ATC-C) (SRO-C)(TS)TS 3.3.1 Condition C CRSDirect manual trip of the reactor and performance of immediate actions.(ATC may trip the reactor before the CRS direction.)
ATCManually Trip Rx.(ATC-CT) (BOP-M) (SRO-M) (ATC-M) 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.
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).ATC Reduce Letdown by closing Orifice Bypass (CV-1223).BOP Open BWST Outlet to OP HPI pump (CV-1407 or 1408).
BOPCheck for proper electrical response ANYCheck OP HPI pump supplying normalMakeup and Seal Injection.
ATCCheck both SG levels remain 410".
ANYCheck Instrument Air Header press75 psig ANYCheck all NNI power available:
ANYCheck all ICS power available:EVENT 5 & 6 CONTINUED Page 9 of 10Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R2Event No.: 5 & 6 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.TimePositionApplicant's Actions or Behavior 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 psid acrossStartup 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)
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 to ontrolRCS 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 integrityThis event is complete when the CRS leak is starte Page 10 of 10 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 1-R2Event No.: 7Event Description:An ~200gpm RCS leak will develop in the RX building requiring HPI.TimePositionApplicant's Actions or BehaviorTrip +5 minANY Recognize and report lower PZR level and RCS pressureRecognize and report additional seal failed on 'B' RCP(BOP-C) (SRO-C)
ANYDiagnose RCS leak inside containment(BOP-M) (SRO-M) (ATC-M)(TS)TS 3.4.13 Condition AANY Determine leak rate >50 gpm (EAL consideration)CRS Direct implementation of HPI per Repetitive Tasks 1202.012 RT-2 BOPIsolate Letdown by closing either: Letdown Coolers Outlet (CV-1221)
OR Letdown Cooler Outlets (CV-1214 and 1216)
BOPOpen BWST Outlet to OP or STBY HPI pump (CV-1407 or 1408).
ANYPlace or verify RCP Seal INJ Block (CV-1206) in OVRD.
BOPOpen HPI Block valve associated with OP or STBY HPI pump (CV-1220or 1285) to maintain PZR level and RCS press(BOP-CT)CT criteria -HPI should be started before the ESAS actuates on lowRCS pressure.
BOPOpen additional HPI Block valves associated with OP HPI pump BOPIF PZR level or RCS press continues to drop, THEN place ES HPI pumpin service BOPOpen BWST Outlet to ES HPI pump (CV-1407 or 1408).BOP Verify both HPI RECIRC valves open (CV-1300 and 1301)BOP Start AUX Lube Oil pump for ES HPI pumpBOP WHEN BWST Outlet is open, THEN start ES HPI pumpBOP Stop AUX Lube Oil pump BOPOpen HPI Block valve associated with ES HPI pump (CV-1220 or 1285)to maintain PZR level and RCS press (modulating valves).BOP Open additional HPI Block valves associated with ES HPI pump:This scenario may be terminated when HPI is initiate Page 1 of 14Appendix DScenario OutlineForm ES-D-1Facility: ANO-1 Scenario No.: 2-R2Op-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 for normal pump rotation to have P33A, and P33B running. The Inside AOhas 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 pumps 2Lightning strike DI-DG2SK01A3 N/ALightning strike#2 EDG auto start#2 EDG Auto Start Command Annunciator 3CV-3807C (SRO, BOP)#2 EDG SW valve fails to open(TS).4 N/AN (SRO)R (ATC)Dispatcher directs a power reduction to 700Mwe in thenext 15 minutes.
5Lightning strikeED451I (SRO, ATC)Lightning strikeLoss of the NNI Y power supply.
6ED183M (ALL) Loss of Offsite Power/Degraded Power 7DG175DI_DG1_VR-LWC (SRO, BOP)#1 EDG will not auto start(BOP-CT)#1 EDG voltage low 8FW621 C (ATC)EFIC fails(ATC-CT) (TS)
9DG173C (ALL)M (ALL)#1 EDG will trip(TS)10A901N (SRO, BOP)Alternate AC Generator available.(BOP-CT)*(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 14Appendix DScenario OutlineForm ES-D-1Scenario #2-R2 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 condition Page 3 of 14Appendix DScenario OutlineForm ES-D-1SCENARIO #2-R2 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 crew should determine it is aspurious actuation. The #2 EDG SW valve CV-3807 will not open resulting in no cooling flow tothe EDG(BOP-C) (SRO-C). The crew should take the #1 EDG to lockout to prevent anautomatic trip of the 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.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 #1 EDG will not auto start requiring the BOP to manually start the EDG(BOP-C) (BOP-CT)
.The #1 EDG voltage will be low 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(ATC-C). The ATC shouldmanually actuate EFW from the remote switch matrix(ATC-CT) (TS)
.TS 3.3.11 Condition BCT - EFW should be manually actuated before the ERV opens in automatic.The #1 EDG will trip putting the plant into a blackout(SRO-M) (ATC-M) (BOP-M) (SRO-C)(ATC-C) (BOP-C) (TS)
.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) (BOP-N) (SRO-N)
.CT criteria - The AAC generator should be placed in service within 20 minutes of losing
- 1 ED Page 4 of 14Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 2-R2Event No.TimeMalf. No.Value/Ramp TimeEventDescriptionRecall IC 2IMF FW621, IRF CO_C2A off, IOR DO_C2ASLG 1 0 N/A N/ASwap operating ICW pumps to haveP33A and P33B running.
2 10IRF LightningIOR DI-DG2STrueTrueLightning strike will cause the auto startof #2 EDG.
3InitialIMF CV-3807 0#2 EDG SW valve will not openfollowing the EDG auto start. This willrequire the operators to shutdown #2 EDG.(TS)4 18 N/A N/ADispatcher will call and direct a powerreduction to 700 Mwe in the next 15minutes.5 28IRF LightningIMF ED451True N/AAnother lightning strike will result in theloss of the NNI Y power supply.
6 36IMF ED183 N/AA Loss of Offsite Power will occurresulting in an automatic reactor trip.
7InitialIMF 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 5 of 14Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 2-R2Event No.TimeMalf. No.Value/Ramp TimeEventDescription 8InitialIMF FW621 N/AEFIC is failed and will not automaticallyactuate EFW.(TS) (ATC-CT) criteria - EFW shouldbe manually actuated before the ERVopens in automatic.
9 48IMF DG???N/AThe #1 EDG will trip putting the plantinto a blackout.(TS)U2 will report ACC Generator is running slow. Maintenance has been dispatched.At T=52U2 will report AAC Generator has been repaired and is running normally with 2A901 closed.
10 52IRF A901ClosedThe Alternate AC Generator willbecome available.(BOP-CT) criteria - The AACgenerator should be placed inservice within 20 minutes of losing
- 1 ED Page 6 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 1Event Description:Swap operating ICW pumps to have P33A and P33B running.TimePositionApplicant's Actions or Behavior 0 BOPOpen A/B crossconnect valves:(BOP-N) (SRO-N)CW Pumps Suction Crossconnect (CV-2240)CW Pumps Discharge Crossconnect (CV-2238)
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).This event is complete when ICW flows are verified norma Page 7 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 2 & 3Event 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 CV3806 will not open.(BOP-C) (SRO-C)
CRSDirect #2 EDG be placed in lockout. (Crew may try to push stop P/B first.EDG will stop but then restart)TS 3.8.1. Condition B 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).This event is complete when #2 EDG is in lockout Page 8 of 14 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 4Event 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.(ATC-R) (SRO-N) Place ULD in manualLower 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 securedATC Stabilize power ~700 MweThis event is complete when power is stable at ~700 Mwe Page 9 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 5Event 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(ATC-I) (SRO-I)CRS Direct operations per 1203.047 Loss of NNI Power ATC BOPVerify NNI X-powered instruments selected on C03, C04, and C13.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.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.This event is complete when NNI-X instruments are selected or verified SASS selected toNNI X power and NNI Y power supply breakers are reported as not closin Page 10 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 6Event Description:A Loss of Offsite Power will occur resulting in an automatic reactor trip.TimePositionApplicant's Actions or Behavior 36 ANYRecognize and report a loss of offsite power(ATC-M) (BOP-M) (SRO-M)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 SCMThis event is complete when the immediate actions of 1202.001 are complet Page 11 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 7 & 8Event 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 BehaviorLOOP ANYRecognize #1 EDG failed to auto start.(BOP-C) (SRO-C)
BOPManually start #2 EDG.(CT-BOP)CT criteria
- The BOP should startthe #1 EDG before the 15 minute criteria for declaring an SAE for astation 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 lowBOP 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 CRSDispatch an operator to restore EDG(May not be performed as #2 EDGis known to be OOS.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 7 & 8 CONTINUED Page 12 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 7 & 8 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 Behavior BOPVerify SW to DG1 CLRs open (CV-3806).BOP Verify a Service Water pump P4A on after 15-second time delay.
ATCActuate EFW and MSLI for both SGs AND verify proper actuation andcontrol of EFW and MSLI (RT 6)(ATC-C)(CT-ATC)(TS) TS 3.3.11 Condition BCT - EFW should be manually actuated before the ERV opens inautomatic.
ATCOperate ATM Dump CNTRL valves in HAND to minimize cycling andconserve Instrument Air.
ANYCheck RCS press remains >1700 psigPZR level remains >
30".BOPIsolate Letdown by closing Letdown Cooler Outlets (CV-1214 and 1216).
ANYCheck 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)
ATCVerify RCP Seal INJ Block closed (CV-1206).BOP Close RCS Makeup Block (CV-1233 or 1234).
BOPOpen BWST Outlet to OP HPI pump CV-1407.This event is complete when CV-1407 is open Page 13 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 9Event Description:The #1 EDG will trip putting the plant into a blackout.TimePositionApplicant's Actions or Behavior 48 ANYRecognize and report #1 EDG tripped.(ATC-M) (BOP-M) (SRO-M)(ATC-C) (BOP-C) (SRO-C) (TS) TS 3.8.1 Condition E, 3.0.3CRS Direct operations per 1202.008 Blackout.
CRSDispatch an operator to restore EDG (May not be performed as #2 EDGis known to be OOS.U2 will report Maintenance is working on the ACC GeneratorCRS Request U2 start AAC Generator.
ATCCheck adequate SCM is maintained.ATC Place P7B handswitch in PULL-TO-LOCK BOPCheck 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).This event is complete when the WCO is dispatched or T=52 Page 14 of 14Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 2-R2Event No.: 10Event Description:The Alternate AC Generator will become available.TimePositionApplicant's Actions or BehaviorReport as U2 that the AAC generator is running properly and 2A901 is closed.
52CRS Transition to step 2 CRSDirect BOP to energize A3 using ES Electrical System Operation(1107.002), Alternate AC Generator Operation" section.(BOP-N)(SRO-N)(CT-BOP) CT criteria - The AAC generator shouldbe placed in service within 20 minutes of losing #1 EDG.
BOPPlace DG1 Output Breaker (A-308) in PULL-TO-LOCK.
BOPVerify A1 to A3 Supply Breaker (A-309) open.BOP 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-310and 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.This scenario is complete when A3 is powered from the AAC Generator Page 1 of 12Appendix DScenario OutlineForm ES-D-1Facility: ANO-1 Scenario No.: 3-R2Op-Test No.: 2008-1Examiners: __________________________ Operators: __________________________ __________________________ __________________________ __________________________ __________________________Initial Conditions:100% powerC2A IA compressor is out of service for overhaul.RPS is failedRX trip P/B on C03 is failedTurnover:C2A IA compressor is out of service for overhaul.Swap operating EH oil pumps for following maintenance on the standby pump.
EventNo.Malf. No.EventType*EventDescription 1 N/AN (BOP, SRO)Swap the operating EH oil pumps 2AO_PI2418K10B5DO_HS2420RDO_HS2420GCV2420I (BOP, SRO)'B' core flood tank pressure transmitter line breaks (TS)3FW086C (SRO, BOP)P8A heater drain pump winding failure and trip.
4 N/AN (SRO)R (ATC)Power reduction 5CO_P14BCO_P14ADI_PB9201C (BOP)Operating EH pump will tripTurbine trip >43%
6RP246,7,8,9DI_ICC0020 C (ATC)C (ATC)M (ALL)RPS is failed(TS)C03 manual trip P/B failed(TS)Manual reactor trip(ATC-CT)7RC001M (ALL)~150 GPM tube leak in the 'A" SG(TS)(BOP-CT)8 N/AN (ATC) Plant cooldown and depressurization
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 12Appendix DScenario OutlineForm ES-D-1Scenario #3-R2 Objectives 1)Evaluate individual ability to swap running EH oil pumps.
2)Evaluate individual ability to recognize and respond to the failure of a core flood tankpressure indication.
3)Evaluate individual ability to recognize and respond to a heater drain pump trip.
4)Evaluate individual ability to perform a rapid plant power reduction.
5)Evaluate individual ability to recognize and respond to the loss of the operating EH oilpump and resultant turbine trip.
6)Evaluate individual ability to recognize and respond to a reactor protection systemfailure to complete an automatic trip.
7)Evaluate individual ability to recognize and respond to a steam generator tube leak.
8)Evaluate individual ability to commence a reactor coolant system cool down anddepressurizatio Page 3 of 12Appendix DScenario OutlineForm ES-D-1SCENARIO #3-R2 NARRATIVEThe crew will assume the watch with the plant at 100% power. C2A IA compressor is out ofservice for overhaul.The turn over sheet will direct the crew to swap operating turbine electro-hydraulic pumps per1106.012 Electro-Hydraulic Oil System OperationSection 14 (SRO-N) (BOP-N).The 'B' Core Flood Tank pressure instrument PT-2418 tube will fail resulting in a low pressurealarm and the slow venting of the 'B' CFT. The CRS should implement 1203.012I AnnunciatorK10 Corrective Action(BOP-I) (SRO-I) (TS)TS 3.5.1 Condition BP8A heater drain pump will experience a winding failure causing a high temperature alarm andP8A trip (SRO-C)(BOP-C). The CRS should reference 1203.012E Annunciator CorrectiveAction P8A/P8B FLOW LO and CONDENSATE PUMP AUTOSTART.A plant power reduction is required to maintain suction pressure. The CRS should direct thepower reduction per 1203.045 Rapid Plant Shutdown(ATC-R) (SRO-N)
.After the power reduction the operating EH oil will trip. The standby pump will not start(BOP-C).The loss of both EH pumps will result in a turbine trip. (Crew may complete a manual RX tripprior to the turbine trip) The reactor will fail to trip do to a failure of RPS(ATC-C) (TS). Themanual RX trip pushbutton is failed(ATC-C). The ATC should manually trip the reactor usingthe shunt trip breakers(ATC-CT) (ATC-M) (BOP-M) (SRO-M)
.TS 3.3.1 Condition CTS 3.3.2 Condition ACT criteria - The reactor should be manually tripped before the pressurizer goes solid.A ~150gpm tube leak will occur in the 'A' SG(ATC-M) (BOP-M) (SRO-M) (TS). The CRS shoulddirect operation per 1202.006 Tube Rupture. The leak will be large enough to require HPI beinitiated(BOP-CT). An RCS depressurization and cooldown should be started(ATC-N).TS 3.1.13 Condition BCT criteria - HPI should be initiated before SCM is lost.The scenario may be terminated when a controlled cooldown and depressurization is started orat the direction of the lead evaluato Page 4 of 12Appendix DScenario OutlineForm ES-D-1Simulator Instructions for Scenario 3-R2Event No.TimeMalf. No.Value/Ramp TimeEventDescriptionRecall ICIMF RP246,7,8,9 IOR DI_ICC0020IRF CO_C2A off IOR DO_C2ASLG 1 0 N/A N/ASwap the operating EH oil pumps 2 8IOR AO_PI2418IRF K10B5IOR DO_HS2420RIOR DO_HS2420GIMF CV2420 0 ON OFF ON 1The 'B' core flood tank pressureindication will fail to zero and the 'B'CFT actual pressure will slowly vent tothe RB atmosphere.(TS)3 & 419 IMF FW086 N/AP8A heater drain pump will experiencea winding failure causing it to heat upand eventually trip requiring a powerreduction to ~60%.
32IRF CO_P14AIRF CO_P14B OFF OFFThe operating EH pump will trip causinga loss of EH fluid.
532.5 IOR DI_PB9201TrueMain turbine trip >43% power. (Crewmay complete a manual RX trip prior tothe turbine trip)
6InitialIMF RP246,7,8,9IOR DI_ICC0020 N/A FalseRPS is failed and will not cause anautomatic trip.(TS) Manual trip P/B isfailed requiring the operators tomanually trip the reactor using theshunt trip P/B.(TS) (ATC-CT) criteria -The reactor should be manuallytripped before the pressurizer goessolid.740 IMF RC001
.2A ~150 GPM tube leak will develop inthe 'A" SG requiring initiation of HPI.(TS) (BOP-CT) criteria - HPI shouldbe initiated before SCM is lost.
8N/A N/A N/AA plant cooldown is required to allow forisolation of the bad S Page 5 of 12Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 1Event Description:Swap the operating EH oil pumpsTimePositionApplicant's Actions or Behavior 0 CRS, BOPDispatch operator to EH oil pumps to monitor for proper operation.
BOPStart P-14A by placing HS-9201 in START.AO at the EH pumps will report EH pressure on PI-8534 is reading ~1850psi ANYRecognize P-14A Pressure is normal.
BOPStop P-14BThis event is complete when P-14B is secured Page 6 of 12 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 2Event Description:The 'B' core flood tank pressure indication will fail to zero and the 'B' CFT actual pressurewill slowly vent to the RB atmosphere.(TS)CFT Pressure transmitter failureANY Recognize and report CFT Low pressure alarmCRS Direct operations per 1203.012I ANYDetermine PI-2418 is failed causing CFT (T-2B) pressure to be low ANYRecognize that actual CFT pressure is lowering.
CRSDetermine CFT inoperable, write a Condition Report and enterTS 3.5.1 Condition B.
CRSCrew may begin 1104.001 Core Flood System Operating Procedure toraise 'B' CFT pressure or determine a leak has occurred and CFTpressure cannot be recovered.This event is complete when the 'B' CFT determined to be inoperabl Page 7 of 12 Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 3 & 4Event Description: P8A heater drain pump will experience a winding failure causing it to heat up andeventually trip.A power reduction is required to maintain feedwater suction pressure.TimePositionApplicant's Actions or Behavior ANYRecognize and report P8A winding temperature is going up. (Crew mayelect to stop P8A prior to the pump tripping.)CRS Direct operations per 1203.012E Annunciator K06 Corrective action.CRS Initiate steps to determine cause of high temperature alarm ATCCommence reducing power at ~ 10%/minute per Rapid Plant Shutdown(1203.045) to within the capacity of T-40 high level dump (~ 630 MW or~70% power) and secure affected pump. (The pump may trip before apower reduction can be started.)
ATC, BOPMonitor ICS and EHC subsystems for proper integrated response.
CRSDirect securing Zinc Injection.
CRSAs time permits instruct ATC to refer to "Contingency Reactivity Plans"AND Exhibit A (Operation of APSR Group) of Power Operation(1102.004)
ANYContact AO to verify Htr Drn Tk T-40A Hi Lvl Dump Isol (CV-3041A) isopen at breaker (B-3252).Report as AO that P8A is not rotating ANYDirect AO to check the tripped Heater Drain Pump for reverse rotation.
ATC, BOPPlace Low Level Condenser Spray CV-2907 AND CV-2868 in service byplacing HS-2907 on C02 in OPEN.This event is complete when plant power is stabilized at ~70%
Page 8 of 12Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 5 & 6Event Description: The operating EH pump breaker will trip causing a loss of EH fluid and a main turbinetrip >43% power.RPS is failed and will not cause an automatic trip.(TS) The operators are required themanually trip the reactor.TimePositionApplicant's Actions or BehaviorANY Recognize and report P14A tripped and P14B failed to start.
CRSDispatch operator to reset P-14A breaker (B-3225). (Crew may not havetime to dispatch this operator before the turbine trips)ANY Recognize turbine valves closing ANYRecognize turbine tripped >43% power.
ANYRecognize RPS failed to automatically trip the reactor.TS 3.3.1 Condition C ATCRecognize manual reactor trip push button is failedTS 3.3.2 Condition A ATCTrip the reactor using the shunt trip push buttons.CT criteria - The reactor should be manually tripped before thepressurizer goes solid.CRS Direct operations per 1202.001 Reactor TripANY Recognize and report a loss of offsite powerCRS 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 CRSAdvise Shift Manager to implement Emergency Action LevelClassification ATCReduce Letdown by closing Orifice BypassBOP Open BWST Outlet to OP HPI pump CV-1407EVENT 5 & 6 CONTINUED Page 9 of 12Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 5 & 6 ContinuedEvent Description: The operating EH pump breaker will trip causing a loss of EH fluid and a main turbinetrip >43% power.RPS is failed and will not cause an automatic trip. Manual trip P/B is failed requiringthe operators to manually trip the reactor using the shunt trip P/B.TimePositionApplicant's Actions or BehaviorATC Adjust Pressurizer 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 psi.ATCCheck all NNI power available ATCCheck all ICS power available ATCCheck SG press >900 psig.ATCCheck MSSV OPEN alarm clear (K07-C5).
ATCCheck MSIVs open.
ATCCheck Turb BYP valves operate to maintain SG press 950 to 1020 psig.
ATCPlace both Feedwater Demands in HANDAND verify demand at zero.
ATCCheck Main Block valves closed (CV-2625 and 2675)
ATCCheck Low Load Block valves closed (CV-2624 and 2674).
ATCCheck Startup valves maintain SG levels 20 to 40".
ATCVerify MFW pumps run back and then operate to maintain >70 psidacross Startup Valves.
BOPCheck Two Service Water pumps (P4A, B, or C).EVENT 5 & 6 CONTINUED Page 10 of 12Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 5 & 6 ContinuedEvent Description: The operating EH pump breaker will trip causing a loss of EH fluid and a main turbinetrip >43% power.RPS is failed and will not cause an automatic trip. Manual trip P/B is failed requiringthe operators to manually trip the reactor using the shunt trip P/B.TimePositionApplicant's Actions or Behavior ANYCheck ICW pump supplying Nuclear loop (P33C or B).
ANYCheck ICW pump supplying Non-nuclear loop (P33A or B).
BOPCheck RB Cooling Fans (VSF1A, B, C, D, and E)
BOPCheck Previously running Main Chiller(s) (VCH1A, B)
ANYCheck ESAS Actuation alarms clear on K11.
ANYCheck RCS press > 1700 psig.
ATCCheck Pressurizer Level Control valve (CV-1235) maintains PZR level >
55" BOPCheck PZR steam space integrity.
ATCVerify ERV, Pressurizer Spray, and Pressurizer Heaters operate tocontrol RCS press 2050 to 2250 psig.
ANYCheck at least one RCP running.
ATCCheck RCS T-cold remains >540°F.ANYCheck adequate SCM.
BOPCheck SG tube integrityThis event is complete when the operators recognize the SG tube lea Page 11 of 12Appendix DRequired Operator ActionsForm ES-D-2Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 7 & 8Event Description:A ~150 GPM tube leak will develop in the 'A" SG requiring initiation of HPI.TimePositionApplicant's Actions or Behavior ANYRecognize SG tube leak on the 'A' SGTS 3.1.13 Condition B CRSTransition to 1202.006 Tube RuptureCRS Direct operations per 1202.006 Tube Rupture step 25 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 CRSAdvise Shift Manager to Notify Nuclear Chemistry to beginoff-site dose projections andImplement Emergency Action LevelClassification (1903.010).BOP Open BWST Outlet to OP HPI pump CV-1407 ATCReduce Letdown by closing Orifice Bypass BOPAdjust Header Pressure Controller setpointATC Check TURB BYP valves controlling SG press 950 to 990 psig.
ATCOperate Pressurizer Heaters AND Pressurizer Spray valve (CV-1008) tomaintain RCS press low within limits of Figure 3.
ATC, BOPWHEN RCS press is <1700 psig, THEN bypass ESAS.
BOPVerify OTSG N-16 monitors selected to Gross.ANY Recognize Lowering PZR level BOPInitiate RT2 HPICT criteria - HPI should be initiated before SCM is lost.
ANYDetermine 'A' as bad SG CRSDirect AO to perform Control of Secondary System Contamination(1203.014) in conjunction with this procedure.EVENT 7 & 8 CONTINUED Page 12 of 12Op-Test No.: 2008-1Scenario No.: 3-R2Event No.: 7 & 8ContinuedEvent Description:A ~150 GPM tube leak will develop in the 'A" SG requiring initiation of HPI.TimePositionApplicant's Actions or Behavior ATCSelect 'A' SG to indicate on Header press recorder.
ATCVerify EFW pump Turbine (K3) Steam Supply CV-2667 from 'A' SG inMANUAL closed.ANY Check adequate SCM ANYCheck ESAS Actuation alarms clear on K11.
ANYCheck at least one RCP per loop running.
BOPTrip P-32DATC Establish RCS cooldown rate of <100°F/hr on 'B' SG, ATCControl RCS press low within limits of Figure 3 (RT 14).This scenario is complete when an RCS cooldown and depressurization have been started ES-301Transient and Event Checklist Rev 2Form ES-301-5Facility: ANO-1Date of Exam: 9-8-2008Operating Test No.: 2008-1Scenarios 1 2 3CREW 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 4 1 1 1 0NOR1, 10 2 1 1 1 I/C2, 5, 63, 7, 9 6 4 4 2 MAJ 6,7 6, 9 4 2 2 1 RO1, 2, 3 TS 0 0 2 2 RX 4 0 1 1 0NOR 1, 4 2 1 1 1 I/C2, 3, 5,6,75, 8, 9 5 4 4 2 MAJ 6,7 6, 9 2 2 2 1SRO-U2, 3, 5 TS 6,7 2 0 2 2 RX 0 1 1 0NOR 11, 4, 10 3 1 1 1 I/C3, 5, 73, 5, 7, 9 4 4 4 2 MAJ 6,7 6, 9 2 2 2 1SRO-U1, 4, 6 TS3, 8, 9 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 applicant 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 positio 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 (*) Reactivity and normal evolutions may be replaced withadditional instrument or component malfunctions on a 1-for-1 basi 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.