ML20210T404
| ML20210T404 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/09/1997 |
| From: | Hurley L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9709150103 | |
| Download: ML20210T404 (106) | |
Text
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September 9, 1997 NOTE T0:
NRC Document Control Desk Mail Stop 0 5.D 24 FROM:
Laura Hurley, Licensing Assistant Operations Branch, Region IV
SUBJECT:
OPERATOR LICENSING EXAMINATIONS ADMINISTERED ON JUNE 16 20, 1997, AT COOPER NUCLEAR STATION, UNIT 1 DOCKET #50 298 l
On June 16 20, 1997, Operator-Licensing Examinations were administered at the referenced facility. Attached you will find the following information for 3rocessing through NUDOCS and distribution to the NRC staff, including the NRC
'DR:
Item #1 -
a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070.
b) As given operating examination, designated for distribution under RIDS Code A070.
Item #2 -
Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42.
If you have any questions, please contact Laura Hurley, Licensing Assistant, Operations Branch, Region IV at (817) 860 8253.-
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l 9709150103 970909 PDR ADOCK 05000298 V
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4 ES-401 Site-Specific Written Examination Form ES-401-7 Cover Sheet i
U.S. Nuclear Regulatory Commission Site Specific Written Examination l
Applicant Information Name:
Reaion:
I/II/III/(I Date:
Facility / Unit:
Coom - L t..u, T License Level: @,%
Reactor Type:
W/CE/BW/kGE
-Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers.
Staple this cover
. sheet on top of the answer sheets, The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected four hours after the examination starts.
Applicant Certification l
All work done on this exainination is my own.
I have neither given nor received aid.
Applicant's Sianature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent NUREG-1021 42 of 39 Interim Rev. 8. January 1997
REACTOR Ol'l!RATOR :1XAMINATION Question 1 With the plant operating at 50% power, which one of the following Main Generator faults will cause an at.tomatic reactor scram?
a.
liigh Stator Temperature, b.
Low Ilydrogen Pressure, c.
I.oss ofIsolated Phase Ilus Duct Cooling.
d.
liigh Differential Current.
Question 2 Which one of the following is the reason that the Reactor Mode Switch should be taken out on the RUN position soon aller a Reactor Scram?
a.
Prevent loss of the Main Condenser as a heat sink.
b.
Allow movement of the SRM and IRM detectors, c.
Allow reset of the SDV High Level Scram.
d.
Reset the RWht
"*" EXAMINATION CONTINUED ON NEXT PAGE ""*
REACTOR OPliRATOR EXAMINATION Question 3 The following conditions exist:
RPS Scram Group A&D lights on panel 9-5 are ON.
l All rods are fully inserted Both Recirc Pump field bicakers have automatically tripped.
Which one of the following is the most likely cause of the scram?
a, Automatic ARIinitiation.
b.
c.
- Manual initiation of ARI.
d.
Manual Reactor Scram.
Question 4 The plant is operating at 50% power when a Reactor Scram occurs. Which one of the following describes the expected response of the RPV Level Control system to this event?
a.
Immediately afict the scram, the Feed Pump Discharge valves close and the Startup Flow Control isolation valves open.
b.
Three minutes after the scr, m, the Feed Pump Discharge valves close and one RFPT trips.
c.
ImmeGately after the Main Turbine '. rips, the Feed Pump Discharge valves close and the Startup Flow Controlisolation valves open.
d.
Three minutes after the Main Turbine trip, the Feed Pump Discharge valves close and one RFPT trips.
- "" EXAMINATION CONTINUED ON NEXT PAGE ** ***
REACIOR OPERATOR EXAMINAllON Question 5 A olant transient has cauwd a reactor scram ard prolonged SRV actuation Current conditions are as follows Reactor 1,resswe 900 psig and sining All SRVs are closed Suppression pool water level is normal.
l If Suppremim Poul ternicatwe were to nw to I 85'F, w hich one of the following is closest to the maximum RPV pressure l
allowed by the EOPs) a-1045 psig b.
940 paig c,
800 psig L
d.
600 psiB' Question 6 1hc reactar is o[nating at 70 gownt power during a power ascension when one Feedwater pumt trips Prior to the pump trip:
The reactor was operating at the 100% load line.
Two Feedwater pumps were operating.
Which org of the following desenbes the npected response of the Recite System to this event?
a.
The Recire pumps immediately runback to mmimum speed to avoid power oscillations b
if RPV level lowers to 27.5 inches the Recirc pumps wP! s anback to minimum speed to avoid power oscillations.
c.
1he Recire pumps immediately runback to 45% to minimize the rate oflevel loss.
d.
If RPV lewt lowers to 27.5 inches, the Recirc pumps will runback to 45% to minimize the rate of level loss-
"*" EXAMINATION CONTINUED ON NEXT PAGE *""
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Question 7 1 hc following cmdttions exist, i
A sinall1.OCA has occurted
]
Dovell pressure has raiwd to 3 psig.
j All four Drywelll'an Coil Units ate in RUN.
[
Which one of ;he following desenbes the expected status of ()w I'an Coil Units under these conditions?
a All four will be in operstion.
j b-Aliiour will have tnpped j
c.
All four will trip tf a Group 21 solation occurs.
d.
All four will trip if Drywell pressure reaches 3.5 psig d
Question 8 The plant is oporating at 50% power ard 50% Cue flow when power starts to slowly raise for, as yet, unexplained reasons Which one of the following is the appropriate immediate respons.e to this event?
a.
Scram the reactor.
b.
Inser* control rods.
c.
Reduce Rectro flow.
d lockout Recirc Scoop Tebe.
'"" EXAMINATION CONTINUED ON NEXT PAGE ""*
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REAClOR OPERATOR EXAMINATION Question 9 4
In the ca e of a persisting high Drywell preuure, Emergency RPV Depressuruntion will probably be required if Primary Contamment Water level exceeds 16 feet. Which one of die following desenben why depressurization is required at this
~
j point?
n.
'Ihe vacuum breaker s will become submer ged and will no longer function b
The free volurne (airspace) of the Torus will becorne im small for adequate stearn suppression
'Ihe backpttwave m the SRV dadwge path immies high enough to damage the SRV steam quenching i
c, equipment in the Torus.
- d..
Steam from the Drywell will bypass the Suppression Pwl and dacharge directly into the Totus free Volume.
Questim 10 The following conditi ns exist:
The plant is operating at 50% tower.
Drywell pressure is 1,5 psig.
Drywell tempersture is 220*F.
Suppressiw. pool pressure is.25 psig Suppression pool temperature is 90'F Steam flow is less than Feed flow.
RPV levelis 25 inchen.
Which one of the following is e possible cause of these condnims?
a.
leaking SR V, b.
leaking Main theam Safety Wlve.
c.
Inadvestent RCIC start.
d.
Closure of anMSIV.
'"" EXAMINATION CONTINUED ON NEXT PAGE *""
RiiAC10H OPliRATOR !!XAMINA1R)N Questian 1i Afica a nextaram,ifone or inre SRVs is cychnf. h0P 1 A. RPV Control, directs the o[.crstor to decrease fiV pressure to 940 psig. Which one of the following is a reawn Ibr choosing this value for the pressure limit?
To avoid actuntmg ARI a
b.
To prevent excessiv.: cycling of Non-lew Iow set SRVs I
c.
To allow reset of RPS logic, d
To emure that IU'V pressure control remains within the capability of the bypass valves a
Question 12 1henactor was operating at 100 percent power when a renctor scram occurred Only about one third of the conttul rais fully inwrted d se to an undetected hi S water level in the Scram Dischas se Volume. Reactor power as indicated on the t
APRMs is a penuit. Which one of the following acuorw, would you expect to be most effecove in inserting control rals?
Manually imtiate ARI.
a b.
De energite scram solenoids.
c.
Manually insert control nxts.
d.
Manuauy vent the CRD over piston areas.
Question 13 Following the trip ofone Rccim Pianp with the tractor at power, the operators cme the discharge vahe of the tripped pump.
Which one of the following is the rea.mn that this is dorm 7 a
Prevents or stops reverse rotation of the tripped pump h
Prevents backflow through the idle jet pumps.
c.
Preverits backflow through the idle recirc loop.
d.
lowers the probabihty of entering the instabihty region of the power / flow map.
I
'"" EXAMINATION CONTINUED ON NEXT PAGE "'"
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RI'ACIOR OPEl(AlOlt liXAMINAllON Question 14 The plant is at 35% power when condenser vacuum degrades to a point that is close to where a manual turbine trip is required Assurning no change in vacuum, a large reduction in power will result in which one of the following?
a Redacing power does not have any effect on this condition.
b.
The necessity of a turbine trip will taome more hkely The necessity of a turbine trip will becorne less likely.
c.
d.
A reactor seram is mcxe likely to occur.
Question 15 i
l'mergmey Diesel Geinatte #1 is running and is tied to its bus for load testan6 when a complete loss of onsite AC occurs, Which one of the follwuig desenbes the expected response of the Diesel Octra ator to this event?
a.
Tic Breaker li'A will trip arid the dies.cl will maintain Bus li' loads b.
The govemor will awap from Droop parallel to isochronous ante.
c.
De Diesel Output breaker will trip, the bus will load shed, then the breaker will reclose and the critical loads will acquence on.
d.
The engi.e will trip and then immediately go through a standard emergency stan and load pr(cess.
Question 16 The 480 VAC bus supplying MCC R has lost power. Which one of the following describes the ability to reenergize this MCC7 The MCC will remain deenergized; 480 Volt MCCs do not have alternste power sources a-b.
The MCC can be supplied from its alternate source only by operskir action.
The power source will transfer aner the 480 Volt bus has deenergized.
c.
r d
- The power source will fast transfer without interruption of 480 Volt power.
"*" EXAMINAT10N CONTINUED ON NEXT pAGE "'"
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Rl!AClOR OPl RATOR liXAMINATION Question 17 The Shutdown Coohng and LPCI Modes of one kop of RilR are inoperable due to the inabihty to operate the inboard injection valve. loss of which one of the following busses could cause this?
a.
A single 24 VDC bus.
b A single 125 VDC bus.
c.
loss of both 125 VDC busses.
d.
A single 250 VDC bus Question 18 Which one of the following desenbes the reason that IIPCI trips on a high RPV water level?
To pn: vent ikming icactor water through the condensing pots and reference legs, thus causing a loss of a
alllevelindications.
b.
To prevent filling the Main Stearn Lines and pushing water through the SRVa to the Torus, possibly damaging the SRVa.
To prevent filling the Main Steam Lines and losing water to the Main Condenser, possibly damaging c.
bypass valves or the Main Turbine.
d.
To prevent damage to llPCI turbine blades
""' EXAMINATION CONTINUED ON NEXT PAGE ""'
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RiiAC10lt OPI'.RATOR liXAMINAT10N Question 19 1.oss of 125 VDC panel AA2 will affect the ADS /SRV system in which one of the following ways?
a-No effect the logie power wili sap to13112.
b None of die ADS /SRV valves can be opened c
All of the ADS valves will fail open d
only valves !!, F, and O will remain fully functional b
Question 20 1he cxvitrol anun has been abarxioned and iIPCI is being operated fiom the Alternate Shutdown Facility. Which one of the following autornatic functions ofIIPCI is still active at unis time?
a.
liigh RPV levcl tnp b
low RPV level auto start.
c.
IIPCI turbine prdective trips d
IIPCI Auxiliary Oil Pump auto start and stop Question 21 An Alert has been declared due to high radioactivity relcam Part of the response to this is to verify that the Turbine lluildmg IIVAC is in senice. Which one of the ' dowing explains why this is necessary?
a.
Assures a negative pressure is maintained in the Turbine liutiding, piecluding further releases to the atmosphere.
b.
Amtes a slight positive pressure is maintained in the Turbine 13uildmg, precluding further releases to the erwironment.
c.
Assures that any releases will be fnun an elevated, monitored release point.
d As:nires that any primary system discharges in the Turbine Building are futered prior to release.
""* EXAMINATION CONTINUED ON NEXT PAGE '""
Rl! ACTOR Opl?RA10R I!XAMINATION Question 22 The followmg conditions exist.
The plant is shutdown because loth dicacts are inoperable REC pumps 'N and 1Y are runnmg with their Mode Switches in STilY.
REC pwnps 'Ir and 'C' are off with their Mode Switches in NORMAL..
All ofinite power is lost.
A few minutes later the Startup Transformer is restored and the vital busses are re-energued.
Assuming no operator action concerning the RiiC pumps, which one of the following describes the expected status of the REC pumps one minute after power is restored?
a.
None are running b.
All are running c.
'A' and TY ate running d
'lY and 'C' are running.
Question 23 Which one of the followmg explains why accumulators are installed on each MStV pneumatic supply line?
To dampen pressure transients caused by compressor cycling.
a.
b.
To ensure that su!Ticient pneumatic pressure is available to operate the MS!Vs for up to 30 minutes following a containment isolation event, To provide a surge volume large enough to assure that the pneumatic system solenoid design pressure c.
is t.ot exceeded and they do not open during a design basis main steam line break, d.
To provide suflicient pneumatic pressure to strole the valve through one half cycle after a loss of pneumatic system pressurc.
'"" EXAMINATION CONTINUED ON NEXT PAGE "*"
KliAC10lt Ol>l?RA10R liXAMINNI10N Question 24 The following events occur with the plant at 10% power:
A rnaintenance enor causes a cornplete loss of air pressure to one MSIV.
After $ minutes the enor is conected and nonnat air pressure is restored to the MSlV 4
No operator action is taken durmg this event j
Which one of the following desenbes the expected plant response to these events?
While pressure in lost the elketed MSIV will close more slowly in responw to a close signal if one a
occurs, otherwise no elTect b.
The a!Tected MSIV will close and will have to be reopened by operator action The alrected MSIV will close and then reopen when pressure is restored c.
d.
The abihty to clow the allected MSIV was lost until air pressure was restored Question 25 Dunng a plant startup RPV pressure is 600 psig bm of CRD flow at this time will have which one of the following cfTects on control nd notion? (Assume all parameters normal and unchanged tmless otherwise stated )
Normal rod and seram motion is unafTected until accumulator pressure lowers to less than (R) psig a
b.
Nonnal rod motion has been lost and scram times will exceed limits.
c.
Nonnat nd motion is unafrected but scram times will exceed limits.
d.
Normal nd motion is lost but scram times will be within hmits.
"*" !!XAMINATION CONTINUED ON NEXT PAGII ""*
llliAC'lUR OPl:RATUR !!XAMINATION Question 26 During lower opersta n with RilR pump 'A'in Suppression Pool Coohng, a Station Oper stor mistakenly manually opens R1IR pump 'A' Shutdown Coolmg Suetmn valve (MO 13 A) This will have which one of the following consequences?
a 1here wdl be no consequences in tius mode b.
When MO 15A reaches 5% open, it will disengage the handwhcci and electrically anye back closal When MD 15A teaches full open, the RIIR Suppressmn Pool Cooling /forus Spray outtoard valve c.
(M049A) will auto close.
j d.
1he R1(R pump will inp on low suction prensurc.
Question 27 1he EOps prohibit spreying the D v all if the Drywell atmosphere is superheated. Which one of the following describes the consequences ofignoring this piohibition?
Water sprayed into the Drywell will turn to steam taising presstue even further.
a.
b.
The cold water will put excessive thennat stress on the Drywell which may lead to its failure.
The effect is unpredictable and would result in putting the plant in an unanalyzed condition.
c.
d Drywell pressure wotdd drop more rapidly than could be handled by the vacuum breakers
"*" EXAM! NATION CONTINUED ON NEXT PAGE "*"
RilACTOR OPliRAlOR liXAMINAllON Question 28 lloth !!PCI and RCIC are in o;cratum wien Supprensnu Ptol level lower s to I i feet Which one of the following describes the appropriate course of action?
a ikith IIPCI and RCic must be inppal in order to prevent overpicssuriting the Torus b.
IIPCI mue be trippal because it, ahme has the capacity to overptessurite the Torus RCIC doei not have this capacity.
c.
IIPCI must be tripped because the probability of cavitation damage to the pump increases sharply with the Suppression Pool level below 1 I fwt d
in order to minimize Toms heat load IIPCI and/or RCIC should be tripped if not required to maintain RPV level.
Question 29 Die Drywll is bemg voitilated throudi the reactor tuildmg verAlation system when the ediaust plenum todiation level rises to 110 mr/hr. Which one of the following desenbes the expected response of the ventilation systems to this event?
One train of SGT will start and the Primary Contairunent Ventilation system will be isolated a.
b one trsin of SGT will start and the Primary Containment Ventilation will be re-routed through the operating SUT Trairt c.
Both trains of SGT will start and the Primary Containment Ventilation system will be isolated.
d.
Both trains of SGT will start and the Primary Containment Ventdation will be re-routed through both SOT Trains.
"*" IIXAMINAT10N CONTINUED ON NEXT PAGE "'"
4 lil!AC10R OPl!RATOR IIXAMINATlON Question 30
~
The Offgas System 1 solation valve (OG A0 254) has automatically closed W1uch one of the following conditions could have caumithis?
a Main Steam 1ineIligh Radition 1
b.
A00 Steam Supply k w pressure.
c.
Condenser Air Removat liigh Temperature.
d.
Oligas Rad Morutor liigh liigh
?
i Questmn 31 I
The reactor had been shut down for three (3) days when RilR Shutdown Coolitig was lost. The reactor was in Cold Shutdown with an RPV temperature at the time of the loss of 130*F. Water levelis just below full scale on the Narrow I
Range indicators Which one of the following states how long the reactor will remain in Cold Shutdown a
1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> J
b.
2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> c.
2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> i
d.
3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> i-4 c
Question 32 Which one of tie following dencribes why it is important to estabhsh forced Recirc flow dunng a less of Shutdown Cooling event?
a.
Coolant stratification may mislead the operators into assuming bulk water temperature is below 212*F.
bc Coolant strstification will pnxluce high RPV stress due to temperature differential between bc.ttom and flange area c.
Prevents clad damage due to unstable transition boiling at low pressure.
d Steam buikt up RllR suction piping will lead to waterhammer when RilR flow is restored.
"*" !!XAMINATION CONTINUED ON NEXT PA0li "*"
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l ItHAC10R OPl!RATOR !!XAMINAllON 1
Question D SOT has started as a result oflow RPV 1. cycl The SOT Ddierential Presstue Control Valves are in AtTIO Under these conditiorts these valves will respond in wnich one of the following w ays?
a They will slose and cannot be contiolled until the Oroup 6 isolation is reset b
They will fully open and cannot be controlled until the Oroup 6 imtation is rewt c.
They will rnodulate to maintain Reactor fluilding negative presstue at its setpomt d
1 hey will be under the manual cetrol of the operstor who will adjust them to maintam proper negative pressure.
Question 34 Followmg a reactor scram tf e pressure in the Scrprn Discharge Volume (SDV) nses to RPV pressure Which one of the following duenbes the most hkely reason for this condition?
a SDV pressure :eturns to CRDil system pressure following a reactor scram by system design.
b.
The seram has not been reset.
c.
The SDV vent valves have failed closed.
d The CRDIi 110w control s ake has failed open l
Question 35 With Rod 26 27 selected, which one of the following RWM conditions will prevent the Emergency insertion of this rod?
None, Emergency In is never blocked a
b.
RWM Select Error.
l c.
RWM Withdraw block.
d RWM insert block.
- *** EXAMINATION CONTINUED ON NEXT PAGE *****
IMACTOR OPliRA1OR !!XAMINNilON Question %
Auunung Wth vital bum are crogual frten citta the rumal to emergency wiurces, w hich one of the followmg describes the response of the RllR pumps to an ECCS irutsation signal?
a All four pumps always start imrnedsately tegardless of power source.
l b.
With rn mal pown available all four pumps start immediately. With a loss of offute pow cr, two pumps l
start immediskb and the other two start after a 5 second time delay.
c.
Two pumps atait inunediately and the remaining two pumps stant after a $ necond time delay regardless of the power sourcc.
d.
The purnps are sequenced on at 5 wcond internis regardless of the power source.
Question 37 loss of 125 VDC Division 2 will have which one of the following elTects on tbe high pressure injection systems (llPCI &
RCIC)?
a.
Iloth IIPCI and RCIC retain their auto start function but lose their high level tnp piotection.
b.
Iloth IIPCI and RCIC lose their auto start function c.
RCIC loses its auto start fur: tion and IIPCI lose its high level inp protection d
llPCI loses its auto start function and RCIC loses its high level trip protection.
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ICACTOlt OPlillAloit liXAMINAlloN i
l Question 38 Opsaticawf the W C(ve Sprsy pump will have which one of the following c!Tect: on lorudContanunent lx cel itecorders PC lJt 1 A (Panel 9 3) and PC ljt lli(Panel 9 4)?
a lloth PC ljt l A and til will:end lower than actuallevel.
b<
!!oth PC-lJt.1 A and til will read higher than actuallevel c.
PC lJ1.l A will:end lower than actuallevel PC !Jt.lil will cad actuallevel d.
PC lJt 1 A will read higher than actuallevel PC lit ils will:end actuallevel.
1 Questmn 39 1hc following events have accurred A LOCA has occurred RPV level decreawd to.150 inches.
The Coie Spray pumps auto start.
ItPV level subsequently recovered to 450 inches.
4 The operatora took loth Core Spray Pump Switches to STOP, s
i.evel then decreased to.175 inches.
Which one c4 the following describes the expected response of the Core Spray pumps to these events?
a Afier auto-statting they remain on throughout the transient b.
They auto stop when the level signal elcars and restart w hen level lowers below the setpoint again e.
They stop when switched to STOP but restart when level decreases below their auto-start setpiint.
d.
They stop when switched to STOP and remain off.
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2
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REAC' LOR OPERN1OR EXAMINNilON e
Questmn 40 In attemptmg to inject St.C,1 rain 'N pump starts as expected, but the Tr ain 'll' pump fails to start due to a motor thermal overload Which one of the following desenbes the expected response of the Squib Valves and RWCU system inboard (RWCU MO.15) and Outboard (RWCU.MO 18) Isolation valves to these events?
a Only the 'N Sqmb valve will fire. Iloth RWCU MO 15 and RWCU MO 18 will close, b-Only the 'A' Sqmb valve will fire. Iloth RWCU.MO.15 and RWCU MO l8 will ternam open.
110th Squib valves willlite. RWCU MO.15 will remain open and RWCU MO 18 will close.
c.
d lloth Sqmb valves will fire Iloth RWCU.MO.15 and RWCU.MO 18 will close.
Question 41 A loss of all AC power will have the following effect on the ability to inject SLC during a failure to scram?
a SLC will be unaffected, all essential components are powered by DC.
b.
The squib valves will fire l'ut the pumps carmot be run.
c.
The pumps will start but the aqmb valves will not fire, d.
The sqmb valves will not fire and the pmnps will not start.
Question 42 With the reactar at full pour, which one of the following is requircd before RPS will generate a reactor scrum in response
- to a Main Turbine trip?
Any signal producing a turbine trip also provides an output to the RPS producing a reactor scram.
a b.
If tuh turbine stop valves leave fully open OR if a fast closure of the turbine control valves is detected.
c ifcitixt turbine stop valve leaves the fully open position AND a fast closure of the turbine control valves is detected d
if either turbine stop valve leaves the fully open position OR a fast chisure of any turbine control valve is detected.
'"** EXAMINATION CONTINUED ON NEXT PAGE '""
ill!AC'lOH OPERA' LOR liXAMINA'lloN Question 43 Closure of two inboard MSIVs with the plant at 20% power wdl have winch one of the followmg effects on the RPS7 a.
Always causes a Full Sciam.
b.
Always causes a llalf Sciam c.
Full scram or llalf Scram dependmg upon u hich valves close.
d.
No response or llalf Ses am depending upon which valves close Question 44 A normal plarn startup is m progress and the following conditions exist:-
The Reactor M(de Switch is in STARTUP.
All the IRM range switches are on llange 2.
NoIRMs are bypassed Which one of the following describes all the autornatic actions that will occur if IRM 'A' Drawer Function Switch is placed in the STANDilY position?
a.
None, as long as its companion APRM is not downscale.
b, Rod Withdrawallikxk only.
c.
Rod Withdrawal 111ock and RPS italf Scrant
- "** EXAMINATION CONTINUED ON NEXT PAGE ""*
I kliAC10R OPliRNiOR !!XAMINAllON l
l Question 45 -
l Which ore of the following dernics the cudtkus urder wluch the Source Range Momtors will cause a full teactor net am?
a Chantel W <r U upwale AND Clumnel 'Ir or 'D' upscale with the Reactor hkde Suitch in STARTUP.
b Any two channels upscale with the Reactor hkdc Switch tot in RUN.
c.
Any channel upscale with the Shorting 1. inks closed and the Reactor Mtde Switch in IEFUlil, d
Any channel upscale with the Signting Links open Question 46 Which one of tic following desenics an LPRM input condition to an APRM that will automatically generate a llelf Scram and Rod Ilkick a.
Less than 2 LPRM inputs per LPRM level b
Totalinputs less than 11.
e, Total inputs less than 1 i QB less than 2 LPRM inputs per LPRM level d
Total inputs less than i 1 AND less than 2 LPRM inputs per LPRM level l
Question 47 Assmung no change in actuallevel, imtiating Jct Pump flow will alTect RPV level indication in which one of the following ways?
- s.
Fuct 7xne raises, Wide Range no change, Narrow Range raises t
b.
Fuel 7ene raises, Wide Range lowers, Narrow Range no change c.
Fuel 7ene no chmige, Wide Range lowers, Narrow Range no change.
d Fuel 7ene lowers, Wide Range lowers, Narrow Range lowers.
""* liXAMINAT!ON CONTINUtID ON NiiXT PAGE ""*
i I
i REAC10R OPERA 10R EXAMINAllON l
s t
Question 52 1he plant is oluatmg at full pown when the outlet valve of Fealwater llcater 115 fails closed Wluch one of the following 4
is the rnost hiely conwquence of this event?
l a
ItFP 'N will trip on low suction p.easure b
RFP 1r will trip on low suction pressure.
c.
Iloth RFPs will mottnue to operate.
d.
One RFP will trip on low suction pa rasure. which one can't be predicted
[
Question 53 The plant is at 75% power when the Feedwater Cont of Sirnal for the 'N Feed Pump is lost Which one of the folk) wing descides the expected status of Reactor Feedwater control following this failure?
a lhe 'N RFP will runback to minimum speed, the 'Ir RFP speed will raise to max and the recite system will run back as necessary.
c b.
1he 'N RFP will trip, the ir RFP will raise to max. The operator will have to manually runback recite as necessary.
c.
Auto control of the 'N RFP is lost but the operator has full manual control.1he 'It RFP is unalTected-d Auto control of the 'N RFP is lost and the operator can only lower speed from the Manual 8/U station.
The 'Ir RFP is unaltected.
)
"*" EXAMINATION CONTINUED ON NEXT PAGE "*"
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REAC1Olt OpEltNIOlt EXAMINATION i
i j
i Question 54 The Standby Oss Treatment system has autornatically started the operstor a have subsequently placed one subsystem in STANDilY. Which one of the following umditions will cause the Standby subsystern to automatically restart?
l a
A new Group 6 Isolatum signal in receival b.
Reactor 11uilding negative pressure becomes less than. 25 inchevil,0.
c.
The running train's flow rate drops below 800 cfm d.
The running tram's carbon filter outlet temperature saises above 200'F f
3.
Question $$
1 A partial km ofoffsite power has resulted in a 4160 VAC vital bus being powered by the emergency transfinner. Which one of the following describes the expected status ofits Emergency Diesel Generator?
a Diesel has not startal b.
Diesel has rast Started and is not loaded c
Diesel has Fast Started and is loaded in parallel with the Emergency Transformer.
i d-Diesel has Slow Started and is unloaded, 2
Question 56 1
A km of all o!! site powu has nurred aid the Diesel Generator lircaker has just closed powering the vital bus. Which onc of the following describes the status of the vital bus undervoltage trips under these conditions?
a They are disabled for as kmg as the Diesel is the only source of power to the bus.
b.
They remain fully operstional during bus loading and afterward.
t c.
They are disabled during the loading pacess but become operational when the loading phase is completed d.
They are operational during the loading phase but are disabled when loadmg is completed i
4
""' EXAMINATION CONTINUED ON NEXT PAGE '""
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1 REAC1OR OPl!RA10R liXAMINA1lON Questhm 57 W1 ich one of the following desenbes the control uds rnonitored for rod drift?
a All control nds.
b Only those not i. elected for movemt nt-c.
Only those in the current RWM poup d.
Only those selected for movement.
Question $8 i
The Hod Worth Mmimizer has just generated the following:
Insert Illock Withdraw 111ock.
Select Errte, j
4 Out of Sequence Alem j
Which one of the following is the most likely cause of these conditions?
a.
RWM deenergized b.
Drift of the selected nd Reed switch at the current rod position has failed open.
c.
d.
Steam flow has failed low with the plant at full power,
"'" EXAMINA fl0N CONTINUED ON NFXT PAGE ""*
4 1
id! ACTOR Ol'liitATUR liXAMINA110N Question 39
'the plant is operatin6 at full power when the following Recirc Pump Seal data is noted 4l Seal Cavity pressure is 10m) psig.
- 2 Seal Cavity pressure is 150 psig Which one of the following is the most hLely cause of these conditions?
a.
Normaloperation of toth nals b-Failure of toth scala c.
Partial failure of the #1 seal.
d Partial failure of the #2 scal.
Question 60 1he plant had toen operating at 60% pown wiu:n a transient ralueed RPV level to 20 inches Assuming no operator action which one of the following pumps should be in operation at this tirne?
a.
Recire.
b.
RWCU c.
RCic d.
IIPCI
"'" EXAMINATION CONTINUED ON NEXT PAGE *""
l
t 1(EAC10lt OPEl(A'l ult liXAMINNllON Question 6)
The following conditions esist 1he plant is shut down Reactor Coolant temper ature is 26PF One Shutdown Cooling loop is m service 4
A 1.PCI irutiation signal on low RPV level occurn l
%1uch one of the following describes the oper ator actions uluch must be taken m order for I.PCI to stati mjecting?
None, the system will reabgn for ugection out wnatically a
b.
Reset the Oroup 2 isolation and reset the injection valve imlation signal.
Reset the 1.PCI initiation Signal and Manually su ap the suction path for the desired pump.
c.
d Manually su ap the suction path for the desired pump, manually start the pump, and reset the injection valve imlation signal Questnin 62 In the piocess of withdrawing a control rod the operator notices that these is no pmtion displayed and the ad dnft annunciator in alann for the rod %1iich one of the following is the rnost likely cause of there symptoms?
The RPIS is ravning cata for that control rod from two positions indicating a stuck closed reed switch a.
b.
The control rat indicated in that window is at an odd need twitch position c.
The RPIS 13afTer Card or Position Indication Probe / Switch for that nd has failed d
The RPIS for that control rod is in disagreernent with the RWM pisition indication
"*" EXAMINATION CONTINUED ON NEXT PAGE "'"
I
Kl!ACIOR OPFRA10R liXAMINAllON Question 61 l
An 1.PRM assigned to a certaia RitM group fails downwale Thius the duid detector failure out of the group of eight l
detectors supplymg this RilM channel Which one of the following describes the responw of the R11M to this failure?
l a
There will be no functional c!Icct smcc the RllM still has sufficient 1.PRM inputs to function 1
b.
The tal bkwk r.etpoint will be automatically adjusted downward to compensate for the lost input e.
An Inop Rod likwk will be gener ated until the detector is bypassed d.
An inop Rod likck will te generated requiring that the rod be taken out of service.
Question 64 Dunng a 1.OCA, excessive spraymg of the Dr)well may tesult in which one of the following problerns7 a
Unnecessary damage to equipment in the Drywell.
b De inerting of the Drywell.
c.
Inabihty to vent the Primary Containment.
d Mechanical initure of the Torus to Drywell vacuum breakers-Question O in attemptmg to recover from an inadvertent Group 1 isolation, the operators find that they are unable to reset the Group 1 isolation signal Which one of the following cce.'htions,ifit existed, would cause this problem?
a.
One or more of the control switches for the MSIVs is in the OPEN position.
b.
The Reactor Male Switch not in SilUTDOWN.
c, The Main Steam 1.ine Drain isolation valv s' control switches are in the OPEN position.
d The AP across the MSIVs excccis 100 psid.
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i IEACTOlt Ophi(NiOlt liXAMINATlON Questwn 66 The following events occur; The plant is operating at 30% power.
lireaker I AN trips The Startup Transformer is deenergued The limergency Tramformer is energued The Diesel Generator is fully operational.
After 2 minutes the Startup Transformer is teenergized Which one of the following describes how the 4160 VAC electrical distribution system *csponds to maintain power to bm if7 a..
The diesel generator starts and picks up the loads on the bus b.
A fas clonare of11rvaker IFS occurs applymg power from the timergency Transformer with no UV tripp of equipment runnig on IF.
c.
Das IP kals are shak litcaker IFS closes to apply power from the Emergency Transformer. When the Startup Transfirmer is rocrvsgized the power source is fast transferred back to the Startup Transfirmer.
d 11us IF loads are eed fireaker IFS closes to apply power from the !!mergency Transformer. Any change in soume after the Startup Transformer becomes available must le done by operator action.
Question 67 Loss of the Division 1250 VDC supply to the No llreak Power Panel (NBPP) Inverter will result in which one of the following?
a The invester will auto transfer to its Div 2 DC sourcc.
b.
The inverter must be manually transferred to its Div 2 DC source, c.
The NI1PP will aute, transfer to its standby AC source.
d.
The NDPP must be manually transferred to its standby AC source.
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l l
REACTOR OPERA 10R EXAMINNiloN l
Queston M I
Ims of both divisions of 125 VDC would have which one of the following effects on the Ernergency Diese! EngttttF s
Diesels would auto start and load b
Diesels would auto start, but would not auto load c-Diesels cou'd not te started either automatically or kraPy.
d Diesels could not auto start but could be started locally.
Question 69 WWh tsnf the following desertbcs the effect of one of the three control room Intake Radiation Monitor channels failing upscale 7 Alarm only. logic requires two of three channels upscale for auto action a
l b.
The intake and Exhaust dampers close and the Recirc damper opens.
c The Control IWm Supply fans trip and the Exhaust Damper closes, pressuru.ing the Control Room i
d The Emergency Supply fan starts and the inlet filter system is placed in senice.
j l
Question 70 i
Which one of the fellowing destibes the plant response to inadequate REC cooling?
L The REC non essential header auto isolates on high REC llX outlet temperature.
a b.
ihe TEC system can be manually cross tied to the supply the REC critical loops if needed.
c.
The Service Water system will automatically cross tie to the REC critical loops on low REC pressure.
d The Service Water system can be manually cross tied to the REC entical loops if needed 1
i l
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Rl! ACTOR OPERNIOR !!XAMINATION a
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l Question 71 Which one of Oc following dex ibes the sesponse of any 11P detector not in its shield when a Contaiturent Isolation Signal n; curs 7 1
A Oroup i laclation will caux the TIP to be fully withdrawn in Auto Mode a
b=
A 0:oup i Imlation will cause the TIP to shill into Manual Reverne until it is fully withdrown 3
A Oroup 2 Islation will cause the TIP to shin into Auto Male until it is fully withdrawn e
d.
A Group 21 solation will cause the TIP to shift into Manual Reverse until it is fully withdrown Question 72 Which one of the following IIVAC systems will isolate or trip on high radiation in the Reactor fluilding thhaust Plenum?
a.
RRMO Set Ventilation b.
CSCS Pump Room FCUs c.
Control Building Ventilation d.
Main Contsof Room Ventilation Question 73 One d the Entry Cmlitims to 1%wthart S A, Secmdary Containment Control and Radioactivity Release Cmtrol, is Reactor fluilding Di!Ierential Pressure at or above 0 inches water. Which one of the following describes what two areas the differential pressme is measured between?
a.
Iletween the Reactor Building and outside.
b.
Between the Peactor Iluilding and the Drywell.
c.
Between the Reactor Duilding and the Torus.
d lictween the Reactor 1.luilding and the Turbine Buildmg
"*" EXAMINATION CONTINUED ON NEXT PAGE ""*
RI: ACTOR OPliRATOR !!XAMINATION Question 74 1hc Cmtrol Ravn has toen abandoned without havmg scrammed the reactor first Accordmg to EP 5 21 Shutdown itorn Outside the Control Room, wluch one of the following operators will scram the reactor 7 a
ASD Operator tt Control Daildmg Operator c.
Reactor Feed Pump Operstor d.
Reactor lluildmg Operator Question 75 An orange hexagonal box with ? numeral one (#1) in it appears immediately ateve Step DW/r 2 in the Drywell Temperature leg of the Primary containment Control flowchart Which one of the following descrees the steps to which this Cautmn applics?
a.
- t applies only to Step DW/r 2.
It it a; plies to Step DW/r 2 throuGh Step DW/r S where the second os ange hexagonal tmx (#5) appeara c.
It applies to all steps in the DW/r leg below me orange hexagonal tox.
d.
It a1 plies to all steps irlow the uange hexagonal box in the DW/T leg as well as to all stept in any other legs twing perfonned concunently with the DW/T leg.
Question 76 if Fuel Pool Area Radiation Monitors alarm, the refueling floor is evacuated Which one of the following requires the Reactor fluildmg to also be evacuated?
a.
Water accumulation in ti.e new fuel storage vault.
b.
The SGT system fails to start.
- c.
Reactor !!uildmg iIVAC fails to isolate,
. d Spent fuel has teen damaged.
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REACTOR OPERA 10R EXAMINATION Question 77 Inadverteiit closure of which one of the following CRD llCU vahrs will resuh in the inabihty to scram the afTected nxt?
a.
Scram Int Valve 126 L
b.
InsertllenarIsolation 101 c.
Exhatut Water llender Isolation - 105 d
Withdraw Ileader Isolation 102 Question 78 t
The plant is operatmg et 50% power vith RC)C testmg in progress. Under these conditions. Tech Specs requires an immahate reactor scram if Suppression a%A temperature reaches which one of the following temperaturn?
n.
95'F b.
10$'F c.
Il0'F s
cl 120*F L
K
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REACTOR OPERATOR EXAMINATION Question 79 A plant startup is in progress and the Reactor Male Switch is in RUN with the APRMs readmg as listed below:
Channel A 23 %
Channel H 4.0%
Channel C 5.0%
Channel D 4.7'4 Channel E 2.4%
Channel F 5.1%
Which one of the following describes the ef1'ect that this will have on further rises in reactor power?
2 The power can be raised using rods or recirc flow.
}-
n.
i b.
Power can be raised using rods only.
c.
Power can be raised using recire only.
t Power cannot be raised until the Mode Switch is returned to STARTUP/IlOT STBY.
4 i
Question 80 i
The plant is operating at full power with all parameters normal when the operators observe that RPV level slowly rises until the Feed Pumps trip causing a Reactor Scram. Which one of the following failures could have caused this behavior?
- a. -
A steam flow detector has faiicd high.
b.
Invester W has been lost.
c.
A feed flow detector has failed low, d.
Loss of NBPP.
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i
REACTOR OpF.RATOR EXAMINATION Question 81 RCIC is in operation d se to a small 1.OCA. Which one of the following desenbes the expceted response of RCIC if RPV i
level nses to 60 inches 7 The Turbine Governor valve will close stopping the turbine.
a.
b.
The Steam Supply Ukxking valve (MO 131) will close stopping the turbine.
The Minimum Flow Control valve (MO-27) will open divening flow to the Suppression Pool.
c.
d.
The Test Line Isolation valves (MO-30&33) will open diverting flow to the ECSTs Question 82 The following events occur:
A plant startup is in progress.
The Main Generator has just been synchronized to the gnd Turbine Load Controlis in Mode 3.
Load Demand is set at 100 MW, Withdrawing control rods under these conditions will result in which one of the following?
a.
Generated MWe will raise.
b The turbine bypass valves will move in the open direction.
e.
RPV pressure will raise but Turbine Governor and Turbine Stop valves do not respond.
d.
The Turbine Bypass valves will close and the Deli will switch to Mode 4,
'"" EXAMINATION CONTINUED ON NEXT PAGE **"*
. =
REACTOR OPERATOR EXAMINATION Question 83 The plaat is opaulkig at fullpowa when REC flow to the RWCU system is lost. Whiin one of the following is the expected response of the RWCU system to this event?
a.
The RWCU pump will inp, the llolding pu.nps will start The system will not isolate-b.
The mtem will isolate and the RWCU pump and lloiding pumps will inp.
c The RWCU pump and llolding pumps will trip but rn isolation will occur, d
The system will isolate and the RWCU pump will trip. T' u lloidmg pumps will start.
Question 84 The plant is oper ating at 30% power wn the following pumps running:
Two Condensate pumps.
Two Condensate Booster pumps.
One RFP, Which one of the following describes the etTect that tnpping one Condensate pump wdl have on the status of these mnmng pumps?
a.
Remaining pumps continue to run.
b.
One Condensate Ibster pump will trip on I,ow Suction Pressure after a time delay, c.
Companion Condensate Booster purap will tnp immediately.
d.
One Condensate Booster pump and the RFPT will trip on low Suction Pressure.
"*" EXAMINATION CONTINUED ON NEXT PAGE "*"
L e
REACTOR OPERATOR EXAMINATION Question 85 Mechanical Vacuum pumps ase used to assist in fonning and maintaining condenser vacuum at low power. Wluch one of the following haards makes it necessary to secure these pumps above 5% reactor power?
Hydrogen explosion in the pump.
a.
b.
Pump damage due to condensatien in the pump.
r c.
Inadequate capacity leading to loss of or insufDcient condenser vacuum.
- d. :
Motor overload due to high pump flow rate.
l-Q'xstion 86 i'
Fire Main use dunng a fac on site caused its pressure to lower to 120 psig for 30 seconds Pressure subsequently recovered to 180 psig where it has remairxxi for the past 10 minutes. Assuming no operator action concerning the Fire INmps, which one of the following identifies the Fire pumps that should be running at this time?.
.s 4
a.
Jockey Pump i
b.
Jockey Pump,1E, ID c.
IE,ID,1C 4
d.
IE, ID
""* EXAMINATION CONTINUED ON NEXT PAGE *""
l i
f 1
IEACTOR OPERATOR EXAMINATION I:
- Question 87 On a loss of air system pressure, which one of the following automatic actions will occur to protect the availabihty of.
Instrument Air?
a Auto closure of Non-Crit instrument Air Isolation valve (IA-MO.80) to isolate non critical Instrument Air loads.
b.
Auto opening of Station Air To Instrument Air Cross Tie (SA MO-81) to bypasa Instrument Air Dryers / Filters.
c.
Auto closure of Service Air Supply isolation valve (SA-PCV-609) to isolate Service Air loads.
d Auto alignment of Standby Instrument Air Dryer.
Question 88 Which one of the following REC heat loads can continue to operate indefinitely after having htst REC cooling?
a.
Rl(R Pumps b.
Cote Spray Pumps c.
Recire Pumps d.
Recire MO sets
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REACTOR OPERATOR EXAMINATION Question 89 Which one of the following configurations will maintain Fuel Pool temperature below 150'F with a full core ofnund in the Fuel Pool?
a One Fuel Pool Cooling pump and or e heat exchanger in service.
b.
11oth Fuel Pool Cooling ptunps and heat exchangers in service with maximum flow to the heat exchangers Both Fuel Pool Cooling pumps and heat excivmgers in service with a feed and bleed flowpath to the c.
Cralensate Storage Tank.
l d.
Residual liest Removal System, operating in the Fuel Pool Ar.sist made in parallel with Fuel Pool j;
cooling.
i l
Questiot.90 The Reactor Mode switch is in the REFUEL. position, and the Refueling Platform (bridge) is over the Reactor Vessel.
Which one of the following would cause a Rod Bkck under these conditions?
a.
The Fuel Grapple is loaded with fuel.
b.
The Fuel Grapple is in the FULL UP position-c.
The Frame Mounted lloist is unloaded and not FULL UP.
d.
All rois are Full-In, except for a selected rod at position 02.
""* EXAMINATION CONTINUED ON NEXT PAGE ""*
REACTOR OPi!RATOR EXAMINATION Question 91 During a system realigrunent wnh the reactor at full power a Primary Contairunent valve has been closed and independently verified. Which one of the following is required to sign ofTcompletion of this action in the Control Room log?
a.
The Operator at the Controls.
b, The Operator who closed the valve.
c.
The Operator who closed the valve and the independent Venfier.
d.
% operator who closed the valve, the Independent Verifier, and the Operator at the Controls.
Question 92 If an Operater Aid is part oia controlled pmcalure,which one of the following descriles what assures that the Operator Aid is kept updated with procedure changes?
a
- When use of the Operator Aid is complete, it is returned to the Shill Supervisor who will verify it to be current before its next use.
b.
The Posted Oper ator Aid log Index includes the procedure numbers for all active Operator Aids. This Index is checked when procedures are revised.
A' copy of the Operator Aid Request Form is kept with the applicable procedure. This form indicates the c.
part of the procedure being used and the locations of all copics of the Operator Aid d
The front of the Control Room procedure is marked that part of the procedure is being used as an Operator Aid.
""* EXAMINATION CONTINUED ON NEXT PAGE *""
REACTOR OPERATOR EXAMINATION Question 93 A loss of Shutdown Cooling has occurred. Which one of the following RWCU lineups will provide the maximum coolmg of reactor water?
a.
Suetion from the A RR loop on!y.
b.
Suction from both the A RR loop and the Reactor bottom head drain c,
Flow is b>patax! armnd the tube side of the regenerative heat exchangers directly to the non regenerative heat exchangers.
d.
1he Inboard and Outboard Isolatim Valve interkrks are bypassed to preclude RWCU pump trips should the valves not be full open, Question 94 Which one of the following explains the prtraution to not operate the CRD charging water header at a pressure greater than 1510 psig?
CRDM damage may result during a reactor scram.
a.
b.
Control rods may inadvertently msert or drin in.
The mini-purge lines to the reactor recirculation pumps may be damaged.
c.
d.
The mini purge lines to the RWCU pumps may be damaged.
"*" EXAMINATION CONTINUED ON NEXT PAGE "'"
REACTOR OPERATOR liXAMINATION Question 95 A mvveillance test is being performed that requires a manual valve to be opened The station operator has reponed that the valve canrot be opened by hand and has requested permission to use a valve wrench llaving granted this permission. you also direct the station operator to hang a tag on the valve handle. Which one of the following tags is required to be used?
a Cataion Tag b.
Danger Tag c.
Pamanent Tag d.
Test Tag Question %
Which ONE of the following is the Technical Specification safety limit for reactor pressure with fuel in the vessel 7 a.
1045 psig b.
1080 psig -
c.
1240 psig d.
1337 psig Question 97 Refueling opantions are in pmgress. One control rod is to be withdrawn and bypassed. Which one of the following describes who shall verify that all fuel has been removed from the appropriate control cell before the control rod may be withdrawli?
a.
Refueling Supervisor b.
Reactor Engineering staff member Licensed Opcator and Reactor Engineering statimember c.
d-Two Licensed Operators
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REACTOR OPERATOR EXAMINATION Question 98 A 34 year old licensed operator has a total accumulated dose (TEDE) to date this year of 1800 mrem if this operator receives the maximura dose extension, which one of the following states the maximum additional dose this operator may receive without exceeding CNS lismts?
a.
200 mrem b.
1200 mrem e,
2200 mrem d.
3200 me:r Question 99 Your accumulated lifetime dose exceeds the CNS TEDE guideline. Your TEDE for the current year is 820 mrem. Which one of the following describes the maximum amount of time you may work in a 60 mrem field during the current calendar year?
Iladng exceeckxl the lifetime TEDE guideline, you cannot work in this field until the next calendar year.
a.
b.
I taving exrmhi the lifetine HIDE guideline, you cannot wak in this field until your lifetime TEDE falls below the lifetime TEDE guideline.
c.
Three hours d.
.Utree hours unless a dose extension is granted.
Question 100 The EOPs have been enteral and you have been asked by the CRS for the current reactor water level. Actual level is about 20 inches referenced to Instrument Zero. Which one of the following instrument pairs will give you an independent evaluation oflevel?
a Fuel Zone A and Nanow Range C b.
Wide Range A and Narrow Range a c.
Wide Range B and FuelZoneIl d.
Narrow Range A and Fuel Zone C
REACTOR OPERATOR EXAMINATION
""* END OF EXAMINATION "'"
i l
m th RO ANSWER KEY 1)
D 26)
A
.51)
C 76)
D 2)
A 27)
D 52)
A 77)- D
-3)
A 28)
B 53)
D_
78)
C 4)
C 29)
C 54)
C 79)
D 5)-
C 30)
D 55) a 80)
C 6)
D 31)
A 56)
C 81)
B 7)-
-B 32)
A 57)
A 82)
B 8)
C-33)
B 58)
C 83)
D 9)
C-34)
B 59)
D 84). A 10)-
B 35)
D 60)
A 85)
A 11)
B 36)
C 61)
D 86)
D-12)
C 37)
D 62)
C 87)
C 13)
A 38)
C 63)
A 88)
A 14)
B 39)
D 64)
B 89)
D 15)
A 40)
D 65)
A 90)
A 16)
B 41)
D 66)
D 91)
C 17)
D 42)
B 67)
C 92)
D 18)
D-43)
D 68)
C 93)
C 19)
A 44)
D 69)
D 94)
A 20)-
D 45)
D 70)
D 95)
A 21)
C 46)
B 71)
D 96)
D 22)
A 47)
B 72)
A 97)
C 23)
D 48)
C 73)
A 98)-
C 24)
C-49)
B 74)
B 99)
C 25)
D
- 50) Ji 75)
C 100) B
-i RO EXAM LIST OF ATTACHMENTS 4
5,8,.Page 29, EOP Graph 7 AP 2.4.2.4.1, Attachment. 5, ppg. 15, 16, 17 i
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ES-401 Site-Specific Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applictint Information Name:
Region:
I/11/III/hb Date:
Facility / Unit: C oouv Ab %b License Level: MO Reactor Type:
d/CE/BW/
Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers.
Staple this cover sheet on top of the answer sheets.
The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected four hours after the examination starts.
Applicant Certification All work-done on-this examinat. ion is my own.
I have neither given nor received aid.
ADoh tant's Sianature Results Examination Value-Points Applicant's Score Points Applicant's Grade Percent NUREG 1021 42 of 39 Interim Rev. 8. January 1997 I
SENIOR REACTOR OPERATOR EXAMINATION Queston I With the plant operating at 50% power, which one of the following Main Generator faults will cause an automatic reactor scram?
liigh Stator Temperature.
a b.
Low !!ydrogen Pressure.
c.
Loss ofisolated Phase Bus Duct Cooling.
d.
liigh Differential Current.
Question 2 Which one of the following is the reason that the Reactor Mode Switch should be taken out of the RUN position soon after a Reactor Scram?
a Prevent loss of the Main Condenser as a heat sink.
b..
Allow movement of the SRM and IRM detectors.
c.
Allow reset of the SDV l-ligh Level Scram.
d.
Reset the RWM.
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SENIOR REACTOR OPERATOR liXAMINATION Question 3 The following conditions exist:
RPS Scram Oroup AAB lights on panel 9 5 are ON.
All rods are fully inserted.
Doth Recire Pump field breakers have automatically tripped.
Which one of the following is the most likely cause of the scram?
a.
Automatic ARIinitiation.
b.
RPS automatic seram.
c.
Manualinitiation of ARL d
Manual Reactor Scra.n.
Question 4 The plant is operating at 50% power when a Reactor Scram occurs. Which one of the following describes the expected response of the RPV Level Control system to this event?
a.
Immediately after the scram, the Feed Pump Discharge valves close and the Startup Flow Control twlation valves open b.
Three minutes aller the scram, the Feed Pump Discharge valves close and one RFPT trips.
c.
Immediately after the Main Turbine trips, the Feed Pump Discharge valves close and the Startup Flow Controlisolation valves open.
d.
Three minutes after the Main Turbine trip, the Feed Pump Discharge valves close and one RFPT trips.
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SENIOR REACTOR OPERATOR EXAMINATION Question 5 --
A plant transient has caused a reactor scram and prolonged SRV actuation. Current conditions are as follows-Reactor pressure 900 psig and rising All SRVs are closed Suppression Pool water level is normal.
If Suppression Pool tempers 're were to nse to 185'F, which one of the following is closest to the maximum RPV pressure allowed by the EOPs?
a.
1045 psig b.
940 psig j
c.
800 psig i
d.
600 psig Question 6 The reaeter is operating at 70 percent power dunng a power ascension wnen one Feedwater pump trips.' Prior to the pump.
trip:
4 The reactor was operating at the 100% load line.
Two Feedwater pumps were operating.
4
- Which one of the following describes the expected response of the Recire System to this event?
a.
The Recire pumps immediately runback to minimum speed to avoid power oscillations.
I b.
If RPV level lowers to 27.5 inches the Recirc pumps will runback to minimum speed to avoid power.
4 oscillations.
c.
The Recire pumps immediately runback to 45% to minimize the rate oflevel loss, d.
If RPV lew! lowers to 27.5 inches, the Recirc pumps will runback to 45% to minimize the rate oflevel loss.
1
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4
SliNIOR REACTOR OPERATOR liXAMINATION Question 7 The following conditions exist; A small LOCA has occurred.
Drywell pressure has raised to 3 psig.
All four Drywell Fan Coil Units are in RUN.
Which one of the following desenbes the expected status of the Fan Coil Units under these conditions?
a.
All four will be in operation.
b.
All four will have tripped c.
All four will trip if a Group 2 Isolation occurs.
d.
All four will trip if Drywell pressure reaches 3.5 psig.
Question 8 The plant is operatinc d SM'. power and 50% Core Flow when power starts to slowly raise for, as yet, unexplained reasons.
Which one of the following is the appropriate immediate response to this event?
a.
Scram the reactor, b.
Insert control rods.
c.
Reduce Recirc 11ow.
d.
Lockout Recire Scoop Tube.
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SliNIOR Rl! ACTOR OPERATOR EXAMIN ATION i
Question 9 in the case of a persisting high Drywell pressure, Emergency RPV Depressurization will probably be required if Pnmary Containment Water Level exceeds 16 feet Which one of the followmg describes why depressurization is required at this point?
The vacuum breakera will become submerged and will no longer function.
a.
b.
The free volume (airspace) of the Turus will become too small for adequate steam suppression.
The backpressure on the SRV discharge path beunes high enough to damage the SRV steam quenching e.
equipment in the Torus.
d.
Steam from the Dywell will bypass the Suppression Pool and discharge directly into the Torus free volume.
l Question 10 The following conditions exist:
The plant is operating at 50% power.
Drywell pressure is 15 psig.
Drywell temperature is 220*F, Suppression pool pressure is.25 psig..
4 Suppression pool temperature is 90*F Steam flow is less than Feed flow.
RPV levelis 25 inches.
Which one of the following is a possible cause of these conditions?
a.
Leaking SRV.
b.
Leaking Main Steam Safety Valve.
c.
Inadvertent RCIC start.
- d.
Closure of an MSIV.
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SENIOR REACTOR OPERATOR EXAMINATION Question iI After a reactor scram,ifone or more SRVs is cycling, EOP i A R' V Control, directs the operator to decrease RPV pressure to 940 psig. Which one of the following is a reason for choosing this value for the pressure hmit?
a.
To avoid actuating Aid b.
To prevent excessive cycling of Non-low low set SRVs c.
To allow reset of RPS logic.
d.
To ensure that tPV pressure control remains within the capabihty of the bypass valves.
Question 12
'ihe reactor was operating at 100 perceia power when a reactor scram occurred Only about one third of the control rods fully inserted due to an undetected high water level in the Scram Discharge Vohune, Reactor power as indicated on the APRMs is 9 percent. Which one of the following actions, would you expect to be most etTective in inserting control rods?
a.
Manually initiate ARI.
b, De-energize seram solenoids.
c.
Manuallyinsert control rods.
d.
Manually vent the CRD over piston areas.
Question 13 Following the trip of me Recirc Pump with the reactor at power, the operators close the discharge valve of the tripped pump.
Which one of the following is the reason that this is done?
Prevents or stops reverse rotation of the tripped pump.
a.
b.
Prevents backflow through the idle jet pumps.
c.
Prevents backflow through the idle recirc loop.
d.
Lowers the probability of entering the instability region of the power /Ilow map.
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Sl!NIOR RI? ACTOR OPERATOR liXAMINATION Question 14 The plant is at 35% power when condenser vacuum degrades to a point that is close to where a manual turbine trip is required Assuming no change in vacuum, a large reduction in power will nesult in which one of the following?
Reducing power does not have any effect on this condition a.
b 1he necessity of a turbine inp will become more likely c.
The necessity of a turbine trip will become less likely.
d.
A reactor scram is more likely to occur.
Question 15 Emagency Diesel Generatar #1 is runmng and is tied to its bus for load testing when a complete loss of offsite AC occurs.
Which one of the following describes the expected response of the Diesel Generator to tlus event?
a.
Tie Breaker 11% will trip and the diesel will maintain Bus 1F loads.
b.
The gove aor will swap from Droop Parallel to Isochronous mode.
c.
The Diesel Output breaker will trip, the bus will load shed, then the breaker will reclose and the critical loads will sequence on.
d The engine will trip and then immediately go through a standaid emergency start and load process.
Question 16' The 480 VAC bus supplying MCC-R has luat power. Which one of the following desenbes the ability to reenergize this MCC7 a.
The MCC will remain deenergized,480 Volt MCCs do not have attemate power sources.
b.
The MCC can be supplied from its attemate source only by operator action c.
The power source will transfer after the 480 Volt bus has deenergized.
d.
The po-cr source will fast transfer without interruption of 480 Volt power.
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SliNIOR REACTOR OPliRATOR liXAMINATION Question 17 The Shutdown Cooling and LPCI Modes of onc loop of RIIR are inoperable due to the inability to operate the inteard injection valve. less of which one of the following busses could cause this?
a-A single 24 VDC bus b.
A single 125 VDC bus.
c.
Loss of both 125 VDC busses.
d.
A single 250 VDC bus Question 18 Which one of the following describes the reason that IFCI tnps on a high RPV water level?
To prevent 110 wing reactor water through the condensing pots and reference legs, thus causing a loss of a.
alllevelindications.
b.
To prevent filling the Main Steam 1.ines and pushing water through the SRVs to the Torus, possibly damaging the SRVs c.
To prevent filling the Main Steam Lines and losing water to the Main Condenser, possibly damaging bypass valves or the Main Turbine.
d.
To prevent damage to IIPCI turbine blades.
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SIIN10R REACTOR OPERATOR !!XAMINATION Questim 19 i
Loss of 125 VDC panel AA2 will afTect the ADS /SRV system in which one of the following way "
a.
No effect, the logic power will swap to BB2.
I b-None of the ADS /SRV valves can be opened.
c.
Allof the ADS valves will failopen l
d.
Only valves E, F, and G will remain fully functional-i d
- Question 20
'!he mntrol itxun has leen abarxkmed and ilPCI is being operated from the Alternate Shutdo'vn Facility. Which one of the 2
following automatic functions of1IPCIis still active at this time?
a.
liigh RPV level trip.
b.
Low RPV leul auto start.
c.
IIPCI turbine protective trips.
d.
IIPCI Auxiliary Oil Pump auto start and stop 4
Question 21 An Alert has been declared due to high radioactivity release. Part of the response to this is to verify that the Turbine Builduu; IIVAC is in service. Which one of the following explains why this is necessary?
Assures a negative pressure is maintained in the Turbine Building, precluding further releases to Oc a.
atmosphere.
b, Assures a slight positive pressure is maintained in the Turbine Building, precluding fmther releases to the envirotunent.
Assures that any releases will be from an elevated, monitored release point c.
d.
Assures that any primary system discharges in the Turbine Building are filtered prior to release.
4
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SENIOR Rl!ACTeu OPlillATOR ILXAMINATION Question 22 The following conditions exist:
The plant is shutdown tu iuse both diesels are inoperable.
REC pumps 'A' and 'D' arc running with their Mode Switches in STilY.
i REC pumps V and 'C' art off with their Mode Switches in NORMAL All offsite power is lost.
A few mimites later the Startup Transformer is restored and the vital busses are re-energized.
Assuming no operator action concerning the REC pumps, which one of the following describes the expected status of the REC pmups one minute aller power is restored?
a.
None are running.
b.
All are running.
c.
'A' and 'D' are running d.
U and 'C' are running.
Question 23 A
Which one of the following explains why accumulators are installed on each MSIV pneumatic supply line?
a.
To dampen pressure transients caused by compressor cycling.
b.
To ensure that sufheient pneumatic pressure is available to operate the MSIVs for up to 30 minutes following a containment isolation event.
c.
To provide a surge volume large enough to assure that the pneumatic system solenoid design pressure is not exceeded and they do not open during a design basis main steam line break. -
d.
To provide suflicient pneumatic pressure to stroke the valve through one half cycle aller a loss of pneumatic system pressure.
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SENIOR REAC'IOR OPERATOR liXAMINATION Question 24 The following events occur with the plant at 10% power.
A maintenance enor causes a complete loss of air pressure to one MSIV.
After 5 minutes the error is corrected and normal air pressure is restored to the MSIV.
No operetra action is talen during this event.
4 Which one of the following desenbes the expected plant response to these events?
While pressure is lost the afTected MSIV will close more slowly m response to a close signal if one a.
occurs, otherwise no effect.
b.
The affected MSIV will close and will have to be reopened by oper, tor action.
c.
The affected MSIV will close and then reopen when pressure is restored d
The ability to close the a&cted MSIV was lost until air pressure was restored.
Question 25 Dunng a plant startup RPV pressure is 600 psig. loss of CRD flow at this tim: will have which one of the following effects on control rod motion? (Assume all parameters normal and unchanged unless otherwise stated.)
Nonnal rod and scram motion is unafTected until accumulator pressure lowers to less than 600 psig.
a.
b.
Normal rod motion has been lost and scram times will exceed linuts.
c.
Nonnal rod motion is unafrected but scram times will exceed limits.
d.
Nonnal rod motion is lost but scram times will be within limits.
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(
f SENIOR RI! ACTOR OPERATOR liXAMINATION Question 26 Dunng power operation with RiIR pump 'A' m Suppression Pool Cooling, a Station Operator mistakenly manually opens RilR pump 'A' Shutdown Cochng Suction valve (MO-1 S A). This will have uhuh one of the following consequences?
1here will be no consequences in this mode.
I 3.
b.
When MO-15A reaches 5% open, it will disengage the handwheci and elect.ically drive back closed c.
When MO ISA reaches full open, the RilR Sug pression Pool Coolingfforus Spray outboard valve HO 39A)will auto close d
The RiiR pump will trip on low suction pressure.
- Question 27 The EOPs prohibit spraying the Drywell if the Drywell atmosphere is superheated. Which one of the following describes the consequences ofignoring this prohibition?
Water sprayed into the Drywell will turn to steam raising pres axe even further.
a.
b.
Tne cold water will put excessive thermal stress on the Drywell which may lead to its failure.
The c!Tect is unpre iictable and would resuh in putting the plant in an unanalyzed condition.
c.
d-Drywell pressure would drop more rapidly than could be handled by the vacumn breakers.
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SENIOR REACTOR OPERATOR EXAMINATION Question 28 ikuh I(PCI and RCIC are ir operatico wlen Sup;vession Pml level lowers to i I feet Which one of the following describes the appropriate course of acsin?
ik>th IIPCI and RCIC must be tripped in order to prevent overpressurinng the Torus.
a b.
1IPCI must be inppx! txx:ause it, akine has the capacity to overpressurize the Torus. RCIC does not have this capacity IIPCI must be tripped because the probabihty of cavitation damage to the pump increases sharply with c.
the Suppression Pool level below I I feet.
d.
In order to minimize Torus heat load 1IPCI and/or RCIC should be tnpped if not required to maintain RPV levd.
Question 29 The Drywell is being ventilated through the reactor building ventilation system when the exhaust plenum iadiation level rises to 120 mr/hr. Which one of the following describes the expected response of the ventilation systems to this event?
One train of SGT will start and the Primary Containment Ventilation system will be isolate.d a.
b.
One train of SGT will start and the Primary Containment Ventilation will be re-routed through the operating SGT Train.
13oth trains of SGT will start and ti. Primary Containment Ventilation system will be isolatd c.
d.
Both trains of SGT will start and the Primary Containment Ventilation will be re-routed through both SGT Trains.
i I
4
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SENIOR Rl! ACTOR Ol' lira IOR liXAMINA110N 1
i
. Question 30
)
i The O!Tran System liolation s alve (OO AO 254) has automaticallploacd Which one of the following conditions muld j
have eaused thit?
a Mam Steam 1.mc liigh Radithm b
ADO Steam Supply low pressure-c Condenser Air Removall bgh Temperature d
Oligns Rnd Monitor liig51tigh Questmn 31 The reactor 1, ' beca shut down for three (3) days when Rl!H Shutdown Cmling was lost The scactor was in Cold shutdown with an RPV temperature at the time of the loss of 130*F.. Water levelis just below full scale on the Narrow Range indicators. Which one of the following states how long the reactu will remam in Cold Shutdown a
1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> b
2 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> c.
2.5 innus d.
30hwra Question 32 Which one of the following dem:riben why it is imiurtant to establish forced Rwirc flow during a less of Shutdomi Coo ing i
event?
-a Cmlant stratification may mislead the operstors into assuming bulk water temimrature is below 212*F.
b.
Cmlant strstification will pnxtuce high RPV suess due to temperature dt!Terential between tottom and 11ange area.
c.
Prevents clad damage due to unstable transition boiling at low pressure, d.
Steam build up R1IR suctko piping will lead to waterhamnwr when RIIR iknu is restored 3
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. - ~. - -..
i w
f' S!!NIOR REACl OR OPl!RATOR 1(XAMINA'llON 4
?
Que.stion 33 SOT las staimi as a result of1.ow f1PV level The S01 Dificiential hrwne Control Valves are in AUTO Under these unhtions these valves will respond in which one of the following u sys?
hey wi.1 ciose and cannot be controlled until the Group 6 isolation is reset.
i t
a-b.
They will fully open and cannot be controlled until the Group 6 isolation is reset.
C-They will tuodulate to tilaititain Reactor Building negative presxule at its setpoint.
d 1hcy mil be under the manual centsol of the operstor who will adju:it them to maintain proper negative ptessure.
Question 34 Fallowing a tractor seram the pressure in the Seram Discharge Volume (SDV) rises to RPV pressure. Which one of the following describes the most hiely reason for this condition?
SDV pressure returns to CRDit system pressure following a reactor scram by system desipt s.
b.
He seram has not been leset, c.
The SDV vent valves have failed closed.
d-The CRDil flow control valve has failed open.
Question 35 With Rcd 26 27 aclected, which one of the following RWM conditions will prevent the Emergency insertion of this ind?
a.
None, Eme gency in is never bhcLed b.
RWM Select Ermr, c.
RWM Withdraw bkxk.
d RWM insert bicck.
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1 SENIOR Rl!AC~1OR Opl!RN1OR I!XAMINNilON l
QuC%IIHft M AN4Jinihjt k004 Vita l lrJs'cl are criergt/od frtgrl tidy:t tic rggmal of r;QTIgeficy IKrur(CS, %hiCh ofic of the followiftl1 dc%t des the response of the F'!R pumps to su ECCS initiation signal?
a All four purups alwayn start irnniediately regardless of power source b.
With immnal pmcr available kil four purnpa stari imrnedsatfly, With a loss of olisite power, two pumps start irrutiediately and the other t wo start aller a 5 seced time delay.
c.
Two pumps start imtnediately and the remaining two pwnps s'ntt a2cr a $ second tune delay regan' lens of the gewer merce.
d The pumps are acquenced cm at $ second intervals regardless of the gmwer source.
Question 37 loss of 125 VDC Division 2 will have which one of the following effects on the high pressure injection systems (11PCI &
RCIC)?
a floth 1(PCI and RCIC ictain their auto start furstion but lose their high level trip protection.
b.
Iloth !!PCI and RCIC lose their auto start function c,
RCIC loses its auto start furetion and !!PCI loses its high level trip protection d,
llPCI loses its auto start function and RCIC loses its lugh level trip protection.
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SIENIOR Rl!ACloit OPl:RA10R liXAMINA110N Quer.fior 3N Ogxiainsiof the W Cue S n my pump wdl have which one of the following efTects on TonWContaintnent level Rmeders i
i PC 1.R. I A (Panel 9-3) and l'C.th I11 (Panel 9 4)7 a
floth PC 1AI A and ill will read lower than actuallesel b.
Iloth PC 1.R 1 A and lit will read higher than actual level c.
PC lJO I A will read lower than actual level. PC lh til will read actuallevel d
PC-lhI A will read higher than actuallevel PC IR lil will read actuallevel Question 39 The following events have occuned A 1 OCA has occuned RPV level decreamt to.l50 inches.
The Corc Sprey purnps auto atart RPV level subsequently recovered to +50 inches The opercors took both Core Sprny Pump Sw;tches to STOP.
lxvelthen decreased to 175 inches.
Which one of the following describes the expected respom of the Core Spray pumps to these events?
After auto starting they remain on throughout the transient.
a.
b.
They auto stop when the level signal clears and iestart when level lowers bekni the setpoint again.
They sty when switched to STOP but restart when level decicases below their auto start setpoint.
c.
d.
They stop wtwn switched to STOP and remain oti.
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1 hl!NIOR Rl!AC10R OPliRATOR liXAMINATION Question 40 in attemptmg to inject St.C, Tt ain 'A' ptunp starts as expected, but the Tram 'll' ptunp fails to start due to a motor thermal overload Which one of the followmg desenties the expected response of the Squib Wlves and RWCU system Inboard (RWCU MO 15) and Outboard (RWCU MO.18) Isolation valves to these events?
a.
Only the W Squib valve will fire. Iloth RWCU MO 15 and RWCU MO 18 will clom b.
Only the W Squib valve will fue. Doth RWCU MO 15 and RWCU MO 18 will remain open Both Squib valves will fire. RWCU MO 15 will remain open and RWCU MO l8 will cime c.
d Doth Squib valves will fire. Both RWCU MO 15 and RWCU.MO 18 will cime Question 41 A loss of all AC power will have the following effect on the abihty to inject St.C during a failure to actam?
3 St C will be unalTected, all essential components are powered by DC.
a i
b.
The squib valves will fire but the pumps cannot te nut.
c.
1hc pumps will start but the squib valves will not fire.
d The squib valves will not fire and the pumps will not start.
l Question 42 With the reada at full power, which one of the followmg is required before RPS will generate a reactor neram in resimnse to a Main Turbine trip?
Any signal producing a turbine tnp also provides an output to the RPS producing a reactor scram.
a.
C b
If tuh ttabine stop valves leave fully open OR if a fast closure of the turbine control valves is detected.
l c.
If eitha ttabine stop valve lenws the fully open position AND a fast closure of the turbmc control valves is detected l
d if either turbine stop valve leaves the fully open position OR a fast closure of any turbine control valve is detated j
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SliNIOR Rl: ACTOR OPl!RNIOR !!XAMINAT10N Queston 43 l
Closure of two inboard MSIVs uith the plant at 20% power will have which one of the following c1Tects on the RPS?
a Always causes a Full Scrarn b.
Always causes a llalf Scram c.
Full $ctarn or I talf Seram depending upon which valves close.
d No tesponse or i talf Scram depending upon which valves close.
Question 44 A normal plant startup is in propess and the following conditions exist:
The Reactor Mcxic Switch is in STARTUP.
All the IRM range switches arc <m Range 2.
N2 IRMs are bypassed.
Which ore of the following describes all the automatic actions that will occur if IRM 'N Drawer Function Switch is placed in the STANDDY position?
None, as long as its companion APRM is not downscale.
a.
i b.
Rod Withdrawal filock only.
c.
RPSllalf Scram only, d.
Rod Witixirawal111ock and RPS Italf Scrant
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Sl!NIOR REACTOR OPERATOR liXAMINAllON Question 45 W:h one of tic folkswmg deuilo the embtknw under which the Sour ce Range hkinitors will cause a full teactor scram 7 Chanrel W (t 'C' upule AW Channel 'Ir or *!Y upscale with the Reactor hkde Switch in STARTUP.
a b
Any two channels upscale with the Reackx Mode Switch not in RilN.
c.
Any channel upscale with the Shorting 1. inks closed and the Reactor Male Switch in REFUEL.
l d
Any channel upscale with the Shorting 1. inks open.
Question 46 Whichone of the fiillowing descrites an IJ'RM input condition to an APRM that will automatically generate a llalf Scrain and Rod likwk.
less than 21.PRM inputs per ifRM level.
a b,
Totalinputs less than 11.
Total inputs less than 1 I Qll iess than 21.PRM inputs per ISRM level c-d.
Total inputs less than 1 i AW less than 21.PRM inputs per I.PRM level.
Question 47 Asmitrung in change in actuallevel, initiating Jet Pump flow will afTect RPV level indication in which one of the following ways?
Fuel Zone raises, Wide Range no change, Narrow Range raises a.
b.
Fuel Zone raises, Wide Range lowers, Narrow Range no change.
Fuel Zone no change, Wide Range lowers, Narrow li ange no change.
e d.
Fuel Zone lowers, Wide Range lowers, Narrow Range lowers,
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4 SF.NIOR Rl!ACT011 Opil.it A10lt liX AMIN A IlON Question 48 l
l An Aukniats Dquessurvation Syston ( ADS)initiatite hannurted, and blowdown is in progress The initiation signals are still present Pressmg and releasmg the Div i and DIV 11 Riis!!T pushbuttons will have which one of the followmg eficcts on the ADS Valves?
a.
ADS Valves will close and remam closed b
ADS Valves will close, then reopen when the RES!!T pushbuttons are releaned.
ADS Valves will close for 120 seconds, and then will reopen c.
d ADS Valves will remain open. Once initiated the reset pushbuttons have no effect.
Question 49 The following events occurred The plant was at 100% power when a small steam leak developed Drywell pt essure has risen to 3 0 psig.
The eactor serammed.
RPV water level iowered to +2 inches before bems testored to rxamal.
Which one of the following lists the PCis group isolations that should have occuned?
a.
Groups 1,2,6.
b.
Groups 2,3,6.
c.
Groups 1,6.
d 0:oups2,3.
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l l
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SENIOR REACTOR OPERA 10R liXAMINATION Question 50 Wluch one of the following conditions will result in the automatic closme of the MSIVs?
a RPV Level is.150 inches b.
!)rywell pressure is 3 psig.
c.
Main Steam 1.ine adiation is 100 mthir.
d.
Reactor iluddmg Ventilation exhaust plenum radiation in 50 mr/hr.
Question $1 1hc following events occur:
A pressure transient results in the opening of SRVs D and F. at their setpoint of 1080 psig.
. The pressure switch in the tailpipe of SRV D has failed such that it does not sense that the valve is open.
RPV pressure lowers and the SRVs close.
If presswe riws once again, which one of the following describes when SRVs D and F will reopen?
lloth will reopen at 1080 psig.
a b.
SRV D at 1015 psig, SRV F at 1080 psig.
SRV D at 1015 psig SRV F at 1025 psig.
c.
d.
SRV D at 1080 psig, SRV F at 1025 psig.
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SENIOR ltHAC IOR OPERATOR F.XAMINN!!ON Question 52
'lhe plant in operating at full pow.it whai the outlet valve of Feedwater 1leater 115 fails clomi Wriich one of the following l
is the most hLely consequence of this event?
a RilN willinp on low suction pressure b
HFP 'll' will trip on knv suction pressure l
c.
Iloth RI'Ps will continue to operate.
d, One RFP will trip on low suction presstue which one can't be predicted Question $3 The plant is at 75% power when the Feedwater Control Signal for the 'A' Feed l' ump is lost. Which one of the following desenben the expected status of Reactor Feedwater control following this failure?
The 'A' 101' will runback to minimum speed, the 'll' RFP speed will raise to max and the recirc system a.
will run back as necessary.
b.
1he'N RFI' will trip, the 'll' RFP will raise to max. The operator will have to manually tunbact: recirc as necessary.
Auto contr01 of the 'N RFP is lost but the operator has full manual contiol. The 11' RFP is unafrected.
c.
d Auto controf of the 'N RFP is lost and the operator can only lower speed from the Manual S/U station.
The1r RFP is unafTected.
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Sl;Niolt Rl!ACTOlt OPl:JtA10lt i!XAMINATION Question 54 The Standby Oas Treatment system has autornatically started The operators have subsequendy placed one subsystem in STANDilY. Which one of the following conditions will cause the Standby subsystem to automatically restart?
a A new Group 6 Isolation signal is received l
b.
1(cacu fluilding negative picsmure becomes less than 25 inches /il,0, l
c.
The turming tram's flow rate drops bekiw 800 cfm.
d.
The running train's carixm filter outlet tempersture aises above 200*F Question $$
A partial kun of offsite power has resuhed in a 4160 VAC vital bus bemg imwered by the emergency transformer. Which one of the following desenbes the expected status ofits !!mergency Diesel Ocner stor?
a Diesel has not started.
b.
Diesel has Fast Started and is not loaded.
c.
Diesel has Fast Started and is loaded in par allel with the limergency Transfonner.
d Diesel has Slow StLted and is unloaded.
Question 56 A kas of all offsite power has occunut and the Diesel Generator llreaker has just closed powering the vital bus. Which one of the followmg describes the status of the vital bus undervoltage trips under these conditions?
a They are disabled fix as long as the Diesel is th only source of power to the bus.
b.
They remain fully operational during bus loading and allerward.
c.
They are disabled during the loading process but become operational when the loading phase is completed.
d
%ey are operational during the loading phase but are disabled when loading is completed
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S!!NIOR RiiACTOR Ol'l::RATOR liXAMINATION i
Question 57 Which one of the following dewnles the control rods tinirutoicd for nd dnft?
a.
All c<mtrol rods b
Only those not Selected for movement c.
Only those in the cunent RWM group.
d.
Only those selected for novement.
Question 58 The Ittd Worth Mmimiter han just genciated the ibliowing:
Insettlilak Withdraw likxk.
Select Ernt Out of Sequence Alann.
Which one of the following is the most hkely cause of these conditions?
a.
ItWM deenerr,ized.
b.
Dnn of the selected ud c.
Reed switch r.t the current rod position has failed open.
d.
Steam flow has failed low with the plant at full power.
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i i
a SliN!OR IEACTOR OPERATOR INAMINAT10N E
Question 59 The plant is operating at full power when the following Recirc Pump Seal data is notal
- 1 Seal Cavity pressure is 1(XX)psig 4
l
- 2 Seal Cavity pressureis 150 psig r
j Which one of the following is the most likely cause of these conditions?
a Normal operation of tuth seals i
tt Failure of txith scals.
1 c.
Partial failure of the #1 scal.
d.
Partial failure of the #2 seal.
Omston 60 r
. he plant had tren operatmg at 60% power when a transient reduced RPV level to.20 inches. Assuming no operator action which one of the following pumps should be in operation at this time?
n.
Recire.
4
]
b.
RWCU c.
RCIC d.
IIPCI I
h
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Sl!NIOR Rl!AC 1OR OPliRATOR liXAMINAllON Question 61 The follow mg conditions exist.
1he plant is shut down Reactor Coolant temperature is 265'F One Shutdown Coohng Imp is m hervice.
4 l
A 1.PCI imtiation signal on low RPV level occurs Which one of the following describes the operator actions which must be taken in order fut LPCI to start injecting?
a None, the system wdl realign for injection automatically, b
Reset the Group 2 isolation and reset the injection valve isolation signst Reset the l#Cl Initiation Signal and Manually swap the suction path for the des'aed purup I_
c.
d-Manually swap the suction path for the desired pump, manually start the pump, and reset the Injection valve isolation signal.
Question 62 In the process of withdrawing a courol rod the operator notices that there is no position displayed and the rod drift annunciator in alarm for the rod Which one of the following is the most likely cause of these symptoms?
a lhe RPIS is rtwiving data for that control rod from two positions indicating a stuck closed reed switch.
b.
The control itst indicated in that window is at an odd reed switch position.
c.
The RPIS lhlTer Card or Position Indication Probc/ Switch for that rod has failed d
Tim RPIS for that control rod is in disagreement with the RWM position indication.
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l SENIOR RiiAC' LOR OPERNIOR EXAMINATION 1
Question 63 An LPRM assigned to a certain RitM gxup fails downscale. uis is the third detector failure out of the group of eight i
detectors supplying this RllM channel Wluch one of the following desenbes the response of the RilM to this failure?
There will be no functional effect smce the RBM still han sumcient i.PRM inputs to function.
a i
b.
The rod bkwk setpoint will be automatically adjusted downward to compensate for the lost input c.
An inop Rod likick will be generated until the detector is bypassed q
d An Irm thd lilock will be generated requiring that the rod be taken out of aesvice t
i Question 64 s
Durmg a LOCA, excessive spraying of the Drywell may result in w hich one of the followmg problems?
s.
Unnecessary damage to equipment in the Drywell.
4 b.
De inesting of the Daywell.
c.
Inabihty to ver.1 the Primary Containment.
d.
Mechanical failure of the Toms to Drywell vacuum breakers 4
i Questica 65 i
in attemptmg to recover from an inadvertent Group I isolation, the operators fmd that they are unable to reset the Group i isolation signal. Which one of the following conditions,if at existed, would cause this problem?
a.
One or more of the control switches for the MSIVa is in the OPEN position.
b.
De Reactor Mode Switch ;.,t in SIIUTDOWN c.
The Main Steam Line Drsin isolation vakes' contr01 switches are in the OPEN position d
The AP across the MSIVs exces 100 ps;d
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4 t
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SliN!OR IEAC1 Olt OPliRATOlt liXAMINATlON j
Question 66 1he followmg events occm; 1hc plant is operatmg at 30% power litcaker I AN trips 4
1hc Startup Transfo mer is deenergimi 1he timergency Transformer is energized i
The Diesel Generstor is fully oper ational i
After 2 minutes the Startup Transfonner is teenergued.
Which me of the following desenbes how the 4160 VAC electrical distnbution system responds to maintain power to his 1E7 a
lhe diesel generator starts and picks up the loads on the bus-1 b
A fast chenire ofIlreaker IFS man applying power from the Emergency Tramformer with no UV trips 4
of equipment running on 1F.
c.
Ilus IF loaJs are rJni Dreaker IFS closes to apply power from the Emergency Transfonner When the Startup Transfmna is raragired the power sowcc is fast transfened back to the Startup Transformer.
d.
lius IF loads are shed llreaker IFS closes to apply power from the Emergency Transformer. Any change in nource after the Startup Transfonner becomes available must be done by operator action i
j Question 67 1,oss of the Division 1250 VDC supply to the No Dreak Power Panel (NilPP) Inverter will result in which one of the followmg?
a.
The inverter will auto transfer to its Div 2 DC source-1 b.
The invester must be manually transferred to its Div 2 DC source.
c.
The N!!PP will auto transfer to its standby AC wurce.
d.
The NBPP must be manually transfened to its standby AC source.
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SENIOR RiiAC'l OR OPERAT OR llX AMIN ATioN Question 6h loss oflxith dmstons of 12$ VDC would have which one of the followmg efic<ts on the timergency Diesel !!Driuta?
a Diesels would auto start and load b.
Dict.els would auto start, but would not auto load c.
Diesels could not be started cather automatically or locally.
d Diesels could not auto start but could be started kcally.
Question 69 Which one of the following describes the effect of one of the lluce control rann intale Radiation Monitor charmels failing upscale?
Alarm only, logic requires two of three channels upscale, for auto action.
a b.
De intale and lidaust dampers close and the Recirc damper ojens.
The Control Room Supply fans trip and the Exhaust Damper closes, pressurizing the Control Room.
c.
d The Emergency Supply fan starts and the inlet filter system is placed in senice.
Question 70 Which one of the following describes the plant response to inadequate REC cooling?
ne REC non<ssential header auto isolates on high REC llX outlet temperature.
a b.
The TEC system can be manually cross tied to the supply the REC critical loops if needed The Senice Water system will automatically cross tie to the REC cnticalloops on low REC pressure, c,
d.
The Senice Water system can be manually cross tied to the REC cnticallocys if reded
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P SliNIOR REACTOR OPl(RATOR liXAMINATION Question 71 Whh ur of Llw folkming (L xrdies the sesT'onse of any TIP detector tot in its stueld when a containment tsolation Signal occurs?
a A Group i Imlation will cauw the Til' to be fully withdrawn in Auto Male.
l l
tt A Oroup i isolation will cause the TIP to shdi into Manual Reverne until it is fully withdr own c.
A Group 2 Isolation will cause the TIP to ahift into Auto Male until it is fully withdrawn d.
A Group 2 Isolation will cause the TIP to shift into Manual Reverne until it is fully withdrawn Question 72
%hh one of the folkming IIVAC systems will isolate or trip on high radiation in the Reactor lluilding thhaust Plenum?
a RRMO Set Ventilation b
CSCS Pump RoomI/CUs c.
Controllluildmg Ventilation d.
Main Control Room Ventilation Question 73 One tithe Entry Ccudiums to Flowchart $A, Sectalary Containment Control and Radioactivity Release Control, is Reactor liuilding DdTerential Pressure at or above 0 inches water. Which one of the following describes what two areas the ddTerential pressure is measured between?
a Detween the Reactor lluildmg and outside.
b.
Between the Reactor Buildmg and the Drywell.
c.
Iletween the Resetor Building and the Torus.
d lletween the Reactor Building and the Turbine Duildmg 4
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SliNIOR Rl!AC10R OPl:RA10R !!XAMINATR)N Questmn 74 I
1hc Control Ravn has tan abandoned without having act anuned the reactor first. According to I:P $ 2.1, Shutdown from Outside the Control Roorn, which one of the followmg operators will scram the reactor?
a ASD Operstor b.
Controlliuilding Operstor e
Reactor Fcal Pump Operstor d-Henctor fluildmg Operator Question 75 An orange hexagonal tox with a numeral one (#1) in it appears immediately alove Step DW/r.2 in the Drywell Temperature leg of the Pnmary Containment Control flowchart Which one of the following describes the steps to which this Cauticm applies?
a.
It applies only to Step DW/f.2.
h.
It applies to Step DW/r 2 through Step DW/f R where the accorul orange hexagonal tox (#5) appears.
c.
It applies to all steps in the DW/T leg below the orange hexagonal tox d.
h a;phes to all steps Iclow the mange hexagonal box in the DW/T leg as well as to all ateps in any other legs being performed concunently with the DW/r leg
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Sl!NIOlt Rif AC 1Olt OPhitA10lt i XAMINAllON Que; tion 70 1he reactor in operatmg at full power wben the following events occur The Tsubine Control Valves close The Turbine 13ypass Valves fully open 1he Reactor Seramn The SRVs open bric0y-Which one of the following could have cauwd thin chain of events?
a Turbine 1,oad Reference signal has failed downncale-b.
1hc MSIVe have closed c.
1he Standby (11) Pressure Controller has failed low.
d The Flow 1.imiter has failed downncale.
Question 77 1he plant is operating at full power with all pas ameters normal when the operators obwrve that RPV level slowly low era by about 12 inches and testabilizes at this new lower level Which one of the following instrument faihires could have caused this behavior?
a A steam flow detector has failed fully downscale.
b.
All stearn Dow input to RVLCS has been lost c.
A feed now detector han failed fully dowmcale-d All feed 110w input to RV1.CS has been lost
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i
SIINIOR Rl! ACTOR OPERATOR liXAMINAllON Queston 78 The scaetor has simaly scianuned and the MSIVs are closed I(PCI is maintaming RPV level and premue Suppression Pool Coolmg is not available and Prirnary Containment Pressure is rising Which one of the following der.csibes the appropriate considerations if Primary Containment venting becomes necessary?
Venting via the Torus will not keep up with decay heat production but will mmimite the rate of a
radioactisity release.
b Venting via the Tma will Lcep up with decay heat production and will minimize the rate of:adioactinty release.
Venting via the Drywcl! will not keep up with drxay heat but will mimmue the rate of radioactivity c.
release.
d Venting via the Drywell will keep up with decay heat production and will minimite the rate of radioactivity relene Question 79 The following events occur; Le scactor hasjust acranuned from full power.
4 Power cannot be deterinined using the APRMs.
4 All other coinhtions are as expected kr these conditions 4
No post actam operator actions have been taken 4
At this time which one of the following can prmide the power level infonnation necessary if entry into the EOPs is to be avoided?
None, Entry into Failure to Scram is always required if power cannot be detemuned using APRMs a
b.
IRMs c.
SRMs d
Steam now.
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SENIOR REACTOR OPliRATOR EXAMINAllON l
Questnin 80 Followmg a LOCA you may have to decide between 1.PCI irhection ir3to the RPV and spraying the Primary Contairunent Wluch one of the following dewrilves the proper priority of these evolutums?
l.PCI iryection always takes precedence over containment spray.
a.
b.
Containment spray always takes precedence over iJ'Cl injection Containment aprny takes precedence as king as the 2/3 core height interlock is not m forcc-c.
d Containment spray takes precedence if Containment presmre is above PCPL (l'rimary Containtnent Pressure !.imit)
Question HI 1he qiesakir luive exited that llPCI has tnp[ul and then estarted with no operstor action Which one of the following was the cauw of theinp?
a.
Iow steam supply pressure.
b.
liigh steam flow rate c.
liigh RPV level d
liigh IIPCI area temperature.
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S!!NIOR Rl! ACTOR OPERATOR !!X AMINAllON Questuin 82 A LOCA has occurred and the following conditions exist.
Drywellll, concentsatioriis 7%
4 Torus 11, concentsation is 4%
Dr>well 0, concentration is 4%
Torus 0, concentiation is 6%
~
Which one of the following denctibes the contairunent atmosphere?
l a
IWh the Torus and the Drywell are below the flamable hmit.
b.
The Torus is above the flamable limit and the Drywell is below the flamable limit.
c.
Se Drywc!) is above the flamable limit and the Torus is below the llamable limit d Both the Torus and the Drywell are above the flamable imut.
Question 83 A loss of Drywell Cooling fans is causing a rise in Drywell temperature and pressure. Drywell pressure is 1.8 psig and slo 41y increasing Which one of the following is required by AP 2.4.8 4.2, loss of Drywell Coolers, to maintain Drywell pressure below 2 psig7 a.
Seram the reactor.
b.
Run both recirculation purrps back to minimum speed to reduce reactor power.
c.
Vent the Drywell through the Standby Oas Treatment System.
d.
Vent the Drywell through the Reactor 13uildmg Exhaust Plenunt
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SliNIOR RRACTOR OPERA IOR !!XAMIN ATION Question H4 A fire on site has caused an Emergency Diesel Generator to start inadvertently. Wluch one of the following is the major conectn regarding t}us event?
a The engme will have lost fire protection b.
The engine will have no trip protection c.
The engine may be numing v.ithout SW cooling.
d.
The engine may be rurming witinnut tube oil circulation.
Question 85 You are the Refueling Supenima when a Refuel Ibir Area liigh Radiation alann occurs. You have inunediately detemuned that the alarm is due to the fact that a spent fuel assembly has been moved too close to the surface. Which one of the following specifies the course of action you should takei n.
Direct the Refueling Machine Operator to terminate all fuel movement and order the inunediate evacuation of the refueling floor, b.
Contact the Shift Supervisor and recmunend an Alen be declared end order the immediate evacuation of the Reactor 13uilding.
c.
Contact Radiation Protection and follow their instructions.
d Dired the Refuchng Machine Operator to lower the spent fuel assembly and order the evacuation of the refuel floor.
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4 SENIOR REACTOR OPliRATOR ILXAMINA110N i
Question 86 i
J EOP 5 8, Scusidary Contamnv;nt Control, has been entered due to hir.h area temperatures Other Secondary Containment parametas alsa have lan uweang No primary system in currently dischargmg into the Secondary Containtnent and Step SC.12 has been reached Which one of the followir.g combinations of parameter indications would require a reactor a
r.hutdown in accordance with OP 21.57 a
SW Quad temperature alarm Iligh and iIPCI Room radiation level of 1600 nu/hr.
b.
RCIC Room tadiation level of 800mr/hr and SW Quad water level of 1 I feet.
s c.
SW Quad temperature of 205'F and SW Quad water level of 10 fect, i
d SW Quad temperature of 202*F and NE Quad temperature of 210'F.
Question 87 t
Durms full pawa operation, which one of the following is the minimum Operations Departrnent complement required for the Fire 13rigade?
a.
Two b.
Three c.
Four d.
Five 1
i Question 88 Reackr thermal power may unintentionally execed 2381 M Wt for brief periods. Which one of the followmg is maximum thermal power level that may exist without requiring a Notification of Abnormal Condition eport?
a 2386 MWt b
2398 MWt c.
2404 MWt d
2428 MWt
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S!!NIOR REACTOR OPERAlOR liXAMINATION
- Question 89 1hc following conditions exist The plant is operating at 100% power.
1IpCl is out of service with the turbine torn down RCIC hasjust failed its quarterly full Dow surveillance test and been declared inoperable.
l It has teen 89 days since the previous full Dow surveillance t st was successfully completed I
Which one of the followmg actions is required as a result of these conditions?
f rutiste an orderly shutdown and reduce teactor pressure to less than i 13 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a b.
Imtiate an orderly shutdown and redt.cc reactor pressure to less than 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
(
Return either iIPCI or RCIC to oguable status within the next seven days, or complete an orderly reactor c.
shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> d
Provided that ADS is operable, continus reactor operation and reuirn either !IPCl or RCIC to operable status within the next seven days, or cornplete an orderly reactor shutdown and depressurbation to less than 150 psig within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Question 90 Reacta power has lxxm kwered to $% to allow a Drywell entry. Which one of the folio.ing describes the requirement for closure of the inner and outer aishick doors after each entry and exit by persormel?
ikith doors may remain open to facilitate equipment stagmg a
b.
Only the inner dmr may remain open if necessary tc facilitate staging of equipment, Ibther the irma or the outa dow may remain open to facilitate staging of equipment, but at least one door c.
must remain closed at all times
' d.
At least one door must remain ekved at all times, and loth doors must be closed after equipment and personnel have entered or exited.
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l SliNIOR RF. ACTOR OPERATOR EXAMINATION Question 91 A reactor cooldown is in propess Reactor pressure is 500 psig, and RWCU inlet temperatwe is 470 'F. Refer to. RWCU Aceptable 0;uating Range Curve, from S0p 2.2 66. RWCU. Which one of the following explains the results of operating RWCU under these conditions?
The resultmg high depressurization rate > 20 psig/ min will cause a liigh NRilX outlet ternperature a
isolation b
RWCU pmnp cavitation will cause a Group 3 isolation c.
RWCU may cause an excessive reactor cooldown rate.
d it will be diflicult to maintain regenerative heat exchanger pressure penter than 200 psig to prevent RWCU pwnp runout.
Question 92 Which one of the following conditions requiring a procedure change can you complete as a Pen-And Ink change?
A valve, referred to in the procedure, has been removed You want to cross this step out of the procedure a.
to complete the evolution b.
A new instrunrnt has replaced the instrument referred to in the procedure and the tolerance has changed The new tolerance is actually more conservative than the original value and you wish to change the procedure to reflect the new tolerance.
Due to the imtallation of a new pressure gare, the sequence of steps to valve the page into service should c.
have been changed Two steps are now irrelevant and you wish to remove them.
d.
Two tables were alled to the pmcedur e. A reference to one of these hbles is made by its correct title but an incorrect table number. You wish to correct the reference to the table number.
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SliNIOR REACTOR OPERATOR !!XAMINATION Questite 93 A pump previour tagged out of unice is required to complete a system imeup You have deternuned that the work on the pump has been completed, and that the person signed onto the Tagging Order has len the site and cannot be kcated Amadmg to AP O.9, Tagging Orders, which one of the following may authonze teleasing the tags aner ensuring that it is i
safe to hn the tags?
a.
WorLet's Supenisor b.
Contr01 Room Supenisor c.
Shin Supervisor d.
- Duty Station Operator Question 94 The Shin Supenisor has determired that an Emerpary MWR is needed. Which one of the folkming must ermeur with this decision tdre the action plan can be completed?
a.
Any other SRO b.
Operations Sugnisor c.
Plant Manager d
Radiation Protection Manager
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SENIOR REACTOR OPERATOR EXAMINATION Question 95 Accordmg to the Technical Specification 13ases, which one of the following deacnbes how public safety is assured when Pnmary Containment Integnty is not required dunng open vessel physics tests performed at low power?
a.
The Control Rod Velocity Limiter prevents fuel damage at these low power levels.
b.
The Reactor Building and Standby Gas Treatment Systems provide sumcient barricts to keep off site doses well below 10CTR100 hmits.
c.
Since reactor pressure is low dunng these operations, a pipe break cannot occur, d.
The pressure suppressim pool water provides sumcient scrubbing of fission products at these low power levels to preclude off-site releases.
Question %
A core scload is in progress Which one of the following activities is specifically your responsibility as the Refueling Floor Supervisor?
a Authonze personnel access to the Refuel Floor.
b.
Review and approve Refueling Floor SWPs.
c.
Maintain the omeial copy of the SNM transfer form.
d.
Review and approve the Si J transfer form sequence of steps.
Question 97 A certain radiation worker has an accumulated TEDE of 800 mrem for the year. Which one of the following lists the.
individuals who must approve increasing this dose by an additional 1400 mrem?
a.
Department Supervisor and AIARA Supervisor
. b.
- Department Manager and Radiological Manager
- c..
Department Supervisor, Radiological Manager, and ALARA Supervisor d.
- Department Manager, Radiological Manager, and ALARA Supervisor
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4 SENIOR REACTOR OPERATOR EXAMINATlON Question 98 De reactor has tum taken to hot shutdown for replacement of an instrument in Containment. The task has been completed and 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> aner shutdown, a restait and Primary Containment nitrogen purge is ordered Which one of the following actionsis required?
I Reactor iluilding Exhaust System is to be used for the purge.
a.
b.
Standby Oss Treatment is to be used for the purge.
I c.
The Drywellis to be incited first.
d.
The purge must be delayed for at least six hours after the reactor becomes critical Question 99 Which one of the following describes the prescribed method for marking the EOP flowcharts?
Each CRS shall mark the flowcharts with a single color perman:nt marker (in the phnt control room) a.
assigned for his use only, b.
The CRS is the only one who shall enter infonnation on the EOP flowcharts, c,
The SS and CRS should use different colored markers to enter informauon on the EOP flowcharts.
d.
. The CRS should use a different color erasable marker each time he enters or re-enters a flowchart.
Question 100 The reactor has serammed due to high pressure in the Drywell. All rods are in. De Scram Discharge Volume vent and drain valws have failed to close. Which one of the following subsequent aW.onal conditions would require you to escalate this event to the General Emergency level?
,1 Drywell leak rate is confirmed to a > 50 gpm.
a.
b.
Fire in switchyard causes total loss of ofTsite power.
Drywell leak rate is confirmed to be > 50 gpm concurrent w3h loss of all offsite power due to fire in c.
t d.
SJAE monitor indicates 2400 mrem /hr.
u......
t SENIOR REACTOR OPERATOR EXAMINATION
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l l
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D' 26)
A 51)
C 76)
A 2)
A 27)- D 52)
A 77)
A 3)
A 28)
B 53)
-D 78)
B 4)-
C 29)
C 54)
C' 79)
D I
5)-
C-30)
D 55)
B 80)
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SRO EXAM-LIST OF ATTACHMENTS.
5.8, Page 29, EOP Graph 7 AP.2.4.2.4.1, Attachment 5,-ppg. 15, 16, 17 EAL Matrix SOP 2.2.66, Attachment 1, RWCU Acceptable Operating Range-Curve Tech-Spec-3.5 i
I i
i J
uurtosTAits NUCLE AR REGULATORY COMMISSION at mon iv
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,a u s, u zA on wr. sone 400 4
c.a w.aTaN T E x As 16011 sesa qpy 6 July 2,
1997 S
[
OAp G. R, Horn, Senior Vice President 0gg7/60[
of Energy Supply Nebraska Public Power District g
141415th Street q'JO7I Columbus, Nebraska 68601
SUBJECT:
NRC INSPECTION REPORT 50-298/97-01
Dear Mr. Horn:
An NRC inspection was conducted June 16 20,1997, at your Cooper Nuclear Station reactor facility. The inspection included an evaluation of one applicant for a senior reactor operator license and six applicarts for reactor operator licenses. We determined that the seven applicants satisfied the requirements and the appropriate licenses were issued.
However, the applicants' written examination performance was marginal. In contrast, we observed good performance in all aspects of the operating examination.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, h Arthur T. Howell Ill, Director Division of Reactor Safety
\\
Docket No.: 50 298 License No.: DPR 46 l
Enclosure:
NRC Inspection Report 50 298/97-01 yll
/
ge n
/
e
- Nebraska Public Power District 2-'
cc w/ enclosure (w/o Attachment 21:
' John R. McPhail, General Counsel Nebraska Public Power District P.O. Box 499 Columbus, Nebraska 68602-0499 P. D. Graham, Vice President of L
' Nuclear Energy Nebraska Public Power District
- P.O. Box 98 Brownville,- Nebraska 68321 B. L. Houston, Nuclear Licensing and Safety Manager
- Nebraska Public Power District P.O. Box 98 Brownville, Nebrassa 68321
- St Jobe, Technical Training Supervisor Nebraska Public Power District P.O. Box 98 Brownv'le, Nebraska 68321 Dr. William D. Leech MidAmerican Energy -
907 Walnut Street
- P.O. Box 657 Des Moines, Iowa 50303-0657 Mr. Ron Stoddard Lincoln Electric System 11th and O Streets 1 Lincoln, Nebraska 68508
- Randolph Wood, Director Nebraska Department of Environmental Quality P.O. Box 08922 Lincoln, Nebraska 68509-8922 1
J
Nebraska Public Power District Chairman
- Nemaha County Board of Commissioners
.Nemaha County Courthouse 1824 N Street Auburn, Nebraska 68305 Cheryl Rogers, LLFQ Program Manager Environmental Protection Section Nebraska Department of Health 301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 68509 5007 Dr. Mark B. Horton, M.S.P.H.
Director -
Nebraska Department of Health P.O. Box 950070 Lincoln, Nebraska 68509-5007 R. A. Kucera, Department Director of Intergovernmental Cooperation Department of Natural Resources P.O. Box 176
. Jefferson City, Missouri 65102 Kansas Radiation Control Program Director u
Nebraska Public Power District bec w/o Attachment 2:
E-Mail report to T. Boyce (THB)
E Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK) bec to DCD (IE01) bec distrib. by RIV:
Regional Administrator Resident inspector DRP Director DRS-PSB Branch ChirI (DRP/C)
MIS System Branch Chief (DRP/TSS)
RIV File Project Engineer (DRP/C)
I bec w/ Attachment 2:
Laura Hurley (DRS/ OPS)
Stuart Richards (NRR/HOLB)
DOCUMENT NAME: R:\\_CNS\\CN701 RP.TRM To receive copy of document, Indicate in box: "C" = Copy wthout enclosures "E" = Copy wth enclosures "N" = No copy RIV:RE:OB E
RE:OB C
RE:OB C C:OB - lC D:DRP C
D:DRS TRMeadows/imb MEMurphy RElantz JLPellet TPGwynn ATHowell til 06/27/97 06/27/97 06/27/97 06/27/97 07/02/97 07/02/97 OFFICIAL RECORD COPY l
l
ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket No.:
50 298-License No.:
DPR-46 Report No.:
50 298/97 01 Licensee:
Nebraska Public Power District Facility:
Cooper Nuclear Station Location:
P.O. Box 98 Brownville, Nebraska Dates::
June 16 20,1997 Inspectors:--
Thomas R. Meadows, Chief Examiner, Operations Branch Mike E. Murphy, Reactor Engineer (Examiner), Operations Branch Ryan E. Lantz, Reactor Engineer (Examiner), Operations Branch Approved By:
John L. Pellet, Chief, Operations Branch Division of Reactor Safety ATTACHMENTS: :
. Supplemental Information - :
Final Written Examinations and_ Answer Keys
2-EXECUTIVE
SUMMARY
Cooper Nuclear Station NRC Inspection Report 50-298/97-01 NRC examiners evaluated the competency of one senior reactor operator and six reactor operator licerise applicants for issuance of operating licenses at the Cooper Nuclear Station. The licensee developed the initiallicense examinations using the pilot process program guidance contained in Generic Letter 95-06 end NUREG-1021, Supplement 1, " Operating Licensing Examiners Standards." NRC examiners reviewed, approved, and administered the examinations. The initial written examinations were administered to all seven applicants on June 13,1997, by facility proctors in accordance with instructions provided by the chief examiner. The NRC examiners administered the operating tests on June 17-19,1997. All of the applicants displayed the requisite knowledge and skills to satisfy the requirements of 10 CFR Part 55 and were issued the appropriate licenses. Four applicants passed with marginal scores on their written examinations.
I f
-Operations The control room operators exhibited professional demeanor and good communications (Section 01).
-i All seven applicants _ passed the written examinations. Four applicants demonstrated marginal knowledge on the written examinations, with final scores of 80 or 81 percent. Overall, applicant scores on the written examination were marginal (Section 04.1).
All seven applicants passed the operating test. The applicants appeared well prepared for their tests, with only minor performance deficiencies identified (Section 04.2).
The licensee submitted an examination outline of adequate quality, but it was --
revised to enhance the examination (Section 05.1.1).
-The licensee submitted mination package was adequate for administration,' but was enhanced to impros discrimination quality. The licensee staff was responsive in providing enhancements identified during the review process (Section 05.1.2).
4
_ _ _. _ _. _ _ _ _. _. _ - _ _._._ _.__. _ _..~
I 4
l --
3-Report Dptails Summary of Plant Status j
The plant operated at essentially 100 percent power for the duration of this inspection, l
L Operations 01 Conduct of Operations a.
Insoection Scooe During the in-plant main control room portion of the operating test walkthroughs, the examiners observed the on-shift operators during routine operations of the
- facility, b.
Observations and Findinos The demeanor of the operators was professional and crew communications were effective. The inspectors observed several spurious alarms that were acknowledged -
promptly by the operators.
c.
Conclusions The control room operators exhibited professional demeanor. Communications was effective.
04' Operator Knowledge and Performance
- 04.1 initial Written Examination a.
insoection Scoce On June 13,1997, the facility licensee proctored the administration of the written examinations approved by the NRC to six individuals who had applied for initial reactor operator licenses, and one individual who had applie'd for initial upgrade senior operator license. The licensee graded the written examinations and tlie.
-examiners reviewed its results, The licensee also performed a post examination -
_ question analysis which was reviewed by the examiners.
b.
- Observations and Rndinas.
The score for the senior reactor operator upgrade and two reactor operator applicants was the minimum passing score of 80 percent. The scores for the other four reactor operator applicants ranged from 81 to 87 percent, with the average score for all applicants at 83 percent. Overall, the applicants demonstrated a
4 2.
marginal level of knowledge on the written examination. More than half of all applicants missed the following questions which had the same number on both examinations: 11,14, 22, 26, 35, 58, 64, 89, 92, 07, and 99. Also, none of the applicants got question 77 right. All of the above questions were determined by the licensee to be valid and the chief examiner concurred with this determination. These i
questions break down in the following areas:
4 AREA Number of Questions Missed by Over 50%
a I'
EOPs/EOP Bases two j
Procedure / Equipment Basis one System Interlocks one j
Electrical System one System design and Operation four 1
Administration two j
Rt.diological Protection one Reasons for missing these questions appeared to be related to question difficulty I
and isolated training weaknesses. The licensee initiated appropriate actions to upgrade candidate specific knowledge and correct specific training weaknesses, i
t
[
c, Conclusions 4
l All seven applicants passed their applicable written examinations. Overall, some applicants demonstrated a marginal knowledge level on the written examinations.
However, no broad knowledge or training weaknesses were identified as a result of 1
evaluation of the graded examinations.
04.2 -Initial Operatino Test a.-
Insoection Scoce i
The examination team administered the various portions of the operating examination to the seven applicants on June 17-19,1997. Each applicant
[
' participated in two dynamic simulator scenarios. Each reactor operator applicant
- also received a walkthrough test which consisted of ten system tasks and four administrative areas. The upgrade senior reactor operator applicant was tested in i
- five system tasks and four administrative areas.
b.
Observations and Findinos All applicants passed all portions of the operating test. The applicants performed wellin the dynamic simulator scenarios. However, three isolated performance
]
deficiencies were observed: (1) emergency operating procedure entry conditions were not always communicated to the control room supervisor by the reactor i
operators, although critical parameters were effectively monitored by the crews,
.s.
(2) annunciators were not always acknowledged immediately, which tended to delay addressing reemerging or degrading conditions to some extent, and (3) only one crew of three recognized that a containment vacuum breaker had stuck open in one of the scenarios. None of these deficiencies affected the overall effective performance of the three crews, but were communicated to the licensee's staff for incorporation into future training.
Overall, the apphcants performed well on the walkthrough portion of the test.
However, two of the seven applicants failed to start a service water booster pump when initiating drywell sprays. Although this oversight would not hinder drywell spray function, the inspectors found that it was a management expectation and procedural requirement to start the booster pump for this task, c.
Conclusions All seven applicants passed the operating test. The applicants were well prepared.
05 Operator Training and Qualification 05.1 initial Licensina Examination Development The facility licensee developed the initiallicensing examination in accordance with guidance provided in Generic Letter 95-06, " Changes in the Operator Licensing Program."
05.1.1 Examination Outline a.
Insnoction Scoce The f acility licensee submitted the initial examination outline on April 22,1997.
The chief examiner reviewed the submittal against the requirements of NUREG-1021, " Licensed Operator Examiner Standards" Revision 7, Supplement 1, and NUREG/BR-0122, " Examiner's Handbook for Developing Operator Licensing Written Examinations," Revision 5.
b.
Observations and Findinos The chief examiner determined that the initial examination outline satisfied NRC requirements. The chief examiner advised the licensee to enhance the simulator scenarios by adding additional component and instrument f ailures.
i i
6-c.
Conclusions The licensee submitted an adequate examination outline on April 22,1997.
1 05.1.2 Examination Packaae a.
Inspection Scope The facility licensee submitted the completed examination package on June 2, 1997. The chief examiner reviewed the submittal against the requirements of NUREG 1021, " Licensed Operator Examiner Standards" Revision 7, Supplement 1, and NUREG/BR-0122, " Examiner's Handbook for Developing Operator Licensing Written Examinations," Revision 5.
l b.
Observations and Findinas The draft written examination was transmitted by the licensee to the NRC on May 7,1997. The draft written examination contained 125 questions, 75 of which were designated to be included on both reactor operator and senior reactor operator examinations. All of the questions were developed for this examination. The draft examination vas considered technically valid, to discriminate at the proper level, and responsiv i to the sample plan submitted by the licensee on April 22,1997.
However, the chief examiner provided enhancement suggestions for about a third of the questions. The suggestions generally related to clarity of the question stem, inadvertent cues, distractor plausibility, or level of knowledge required. After extensive discussion of the chief examiner's suggestions, the licensee modified the examinations as agreed. The chief examiner concurred with the resolution of his suggestions and the final product. The licensee performed a post examination analysis and recommended that no further changes be made to the written examinations. The examiners concurred with this analysis and recommendation.
The licensee submitted two dynamic scenarios and one backup scenario, which was not used during the examination. The chief examiner made suggestions to enhance the examination quahty by replacing some component and instrument failures to better discriminate applicant performance. Other comments, which the licensee incorporated, included editorial and enhancements to f acilitate administration. The licensee initiated nonor editorial enhancements to the scenarios to f acilitate administration during the chief examiner's preparation week onsite.
To support the systems portion of the operating test, the facility licensee provided job performance measures developed to evaluate selected operator tasks that contained well written task elements, performance standards, and comprehensive evaluator cues. Fifteen job performance measure tasks with two followup questions' each were submitted. _ The chief examiner provided comments concerning enhancement of the walkthrough test, which were incorporated. The chief examiner challenged the critical step assignments for it ee job performance measures and the licensee revised these critical step assignments. Also, the licensee revised three job performance measure questions in response to the chief
- examiner's enhancement suggestions.
The licensee submitted two sets c lob performance measures to cover the administrative section of the walkth.ough test. One set was submitted for reactor
-operator applicants and another for the senior operator upgrade applicant. Thejob j
_ performance meesures submitted were acceptable. However, to facilitate
~
administration, some minor changes were made to some administrative job
-performance measures during preparation week.
1 c.
_Q.onclusions Overall, the final written examination and operating test materials submitted were of high quality, discriminated at the appropriate license level, and were adequate for administration. Further, licensee staff were highly responsive in responding to enhancement suggestions developed during the review process. ' No significant char ges to examination materials were required as a result of administration.
05.2 Simulation Facility Performance a.
Insoection Scoog The examiners observed simulator performance with regard to fidelity 'during the examination validation and administration.
b.
Observations and Findinas The simulator performance was good. No fidelity problems were noted. The
' licensee's simulator support staff were very efficient and greatly enhanced the examination schedule. Turn around times between scenarios'and job performance measures _were very f ast.- This eliminated dead time and helped ease applicant stress levels.
c.
Conclusions The simulator and simulator staff supported the examinations well.
8-V. Manaaement Meetinas X1 Exit Meeting Summary The examiners presented the inspection results to members of tbs licensee management at the conclusion of the inspection on February 28,1997. The licensee acknowledged the findings presented.
The licensee did not identify as proprietary any information or materials examined during the inspection.
i
ATTACHMENT 1 SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee William Green, Lead Licensed instructor Tim Florence, Simulator Supervisor Phil Graham, Vice President, Nuclear Steve Jobe, Technical Training Supervisor Mike Peckham, Plant Manager Le a Croteau, Training Manager Duane Shallenberger, Lead Licensed instructor Dave VanDerKamp, Operations Supervisor Dave Robinson, Quality Assurance Assessment Manager Brad Houston, Licensing Manager l
Bob Creason, Senior Operator Training Specialist UBC.
None i
INSPECTION PROCEDURES USED NUREG 1021 Supplement 1, " Operator Licensing Examiner Standards," Revision 7 NUREG/BR 0122
" Examiners' Handbook for Developing Operator Licensing Written Examinations," Revision 5