ML081900145
| ML081900145 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/03/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML081900145 (110) | |
See also: IR 05000390/2008301
Text
Final Submittal
(Blue Paper)
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FINAL RO
WRITTEN EXAMINATION
AND REFERENCES
Watts Bar Nuclear Plant
NRC Initial License Written Examination - 2008
Master Examination
Please note: The following 100 pages are the Master Examination copy.
Questions 1 through 75 were administered to the RO candidates and to the
SRO candidates.
Questions 76 through 100 were administered only to the SRO candidates.
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
1
Given the following plant conditions:
A reactor trip has occurred.
Off-Site power is lost.
All other equipment has functioned as designed.
The crew is entering ES-O.1, REACTOR TRIP RESPONSE.
Upon entenng ES-O.1, Step 3 directs the operators to monitor for RCS temperature trending to
55TF.
Which temperature indication will the operators use and why?
A.
Tavg, to ensure adequate RCS heat removal is occurring.
B. Tavg, to check for natural circulation established.
C
Tcold, to ensure adequate RCS heat removal is occurring.
D. Tcold, to check for natural circulation established.
1 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
2
Given the following plant conditions:
A 200 gpm RCS leak is in progress.
Containment pressure is stable at 3 psig.
For these plant conditions, what is the MINIMUM S/G water level required in at least one S/G
and why?
A.
29%.
Ensures adequate feedwater flow or S/G inventory to ensure a secondary heat sink.
B.
39%. Ensures S/G tubes are covered in order to promote reflux cooling.
C. 29%.
Ensures S/G tubes are covered in order to promote reflux cooling.
D. 39%. Ensures adequate feedwater flow or S/G inventory to ensure a secondary heat sink.
2 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
3
Given the following:
Unit 1 at 22% reactor power.
RCP #1 trips due to a bearing failure.
Which ONE of the following identifies the immediate effect that the RCP trip will have on Loop 1
\\T AND on SG #1 level?
Loop 1 L'. T
A.
Decreases
B.
Increases
C.
Decreases
D.
Increases
SG #1 Level
Increases
Increases
Decreases
Decreases
3 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
4
Given the following plant conditions:
The Unit is at 45%.
Letdown is in service at 120 gpm per Chemistry request.
The OAC observes the following indications on 1-M-6:
VCT level is 38% and decreasing.
Annunciator Window 109-A, VCT LEVEL HIILO, is LIT.
1-LCV-62-118 indicating light is LIT for Divert to Holdup Tank.
Assuming NO operator actions, and based on these indications, actual VCT level will lower to...
A.
a level which will cause eventual loss of CCP suction.
B.
a level which will cause a swapover to the RWST.
C.
20% and cause auto makeup flow to maintain 20% level.
D.
20% and cause auto makeup flow to return level to 41%.
4 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
5
Given the following plant conditions:
!.\\-~
Unit is in fv1 od e~on RHR cooling with Train A in service in normal alignment.
RCS conditions initially are :
Temperature at 220°F.
Pressure at 330 psig .
Pressurizer level at 30% .
Loss of Shutd ow n Cooling. The crew also notes the followi ng annunciator is LIT:
- Annunciator 113E, RHR SUCT FCV- 74- 1, 2, 8, 9 OPE N & HI PRE SS .
In response to increasing RCS pressure, which ON E of the following identifies:
(1)
Why the Hot leg Loop 4 RHR suction valves, 1-FCV-74-1 and 1-FCV-74-2 , are directed
to be closed?
AND
(2)
A.
(1)
(2)
B.
(1)
(2)
C.
(1)
(2)
D.
(1)
(2)
Wh at are the imp lications of Annunciator 113E being LIT?
To protect the RHR low pressure suction piping.
At least one of the valves failed to close automatically wh en pressure reached setpoint.
To protect the RHR low pressure suction pipin g.
With the valves closed, at least one of the valves could NOT be reopened .
To ensure available ECCS makeup capacity is not exceeded if suction relief valve
opens.
At least one of the valves failed to close automatically when pressure reached setpoint.
To ensure availab le ECCS makeup capacity is not exceeded if suction relief valve
opens.
With the valves closed, at least one of the valves could NOT be reopened .
5 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
6
Given the following plant conditions:
Unit 1 is operating at 100% power.
The Component Cooling System (CCS) is in its normal full power alignment.
Which of the following indications is abnormal and requires changing plant conditions to
compensate for the con dition?
A. #4 RCP Thermal Barrier Flow - 40 gpm.
B. #4 RCP Lower Oil Coo ler Flow - 9 gpm.
C. 1A ESF Header Supply Flow - 1500 gpm .
D. 1B ESF Header Supply Flow - 5500 gpm.
6 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
7
Given the following plant conditions:
- A power escalation is in progress.
- Plant is currently holding pow er at 30% for a secondary chemistry hold.
- Pressurizer Pressure Channel Selector Switch 1-XS-68-340D is in the "PT-68-340 & 334"
position.
- Pressurizer Pressure Transmitter 1-PT-68-340 fails HIGH .
(1)
What action is required to stabilize RCS pressure at its normal value?
AND
(2)
If that action was unsuccessful, what will ensure that adequate departure from nucleate
boiling ratio (DNBR) is maintained?
A. (1) Manually increasing the master controller output.
(2) Automatic Reactor trip when Pressurizer pressure lowers to SI initiation setpoint.
B. (1) Manually increasing the master controller output.
(2) Automatic Reactor trip when Pressurizer pressure lowers to RPS trip setp oint.
C. (1) Manually decrea sing the master controller output.
(2) Automatic Reactor trip when Pressurizer pressure lowers to SI initiation setpoint.
D. (1) Manually decreasing the master controller output.
(2) Automatic Reactor trip when Pressurizer pressure lowers to RPS trip setpoint.
7 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
8
Given the following plant conditions :
- A steam generator tube rupture is in progress.
- The Chemistry Lab has just informed the crew that the activity levels in #1 SG are high, and
that sample values have been confirmed.
- The crew is implementing E-3, STEAM GENERATOR TUBE RUPTURE.
As a result of actions directed by E-3, which ONE of the following requires entry into a Technical
Specification Action statement?
A.
Adjusting the #1 SG PORV controll er setpoint to 90%.
B.
C.
Closing the TO AFW pump steam supply valve from #1 SG.
O.
Cooling down to target incore temperature of 479°F at the maximum rate.
8 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
9
Given the following plant con ditions:
Unit 1 is initially in Mode 3 preparing for a reactor startup.
A steam lea k downstream of the MSIVs requiring safety injection has occurred .
Operators are unable to close any MSIV from the Control Room.
The applicable EOP has directed MSIV closure.
Attempts to isol ate an MSIV from the Au xiliary Control Room have been unsuccessful.
Which ONE of the following describes:
(1) The actions requ ired by the procedure in effect,
AND
(2) When that action has been taken, how will the control room operator know it was
successful?
A.
(1) Dispatch operator to locally isol ate and bleed off the control air to the MSIVs.
(2) Requires local verification of MSIV closure.
B. (1) Dispatch operator to locally isolate and bleed off the control air to the MSI Vs.
(2) Main control room operator notes GREEN light above MSIV control sw itch es is LIT .
C. (1) Dispatch operator to attempt MSIV clo sure by pulling control power fuses.
(2) Requires local verification of MSIV closure.
D. (1) Dispatch operator to attempt MSIV closure by pull ing control power fuses .
(2) Main control room operator notes GREEN light above MSIV control swi tch es is LIT .
9 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
10
Unit 1 is in Mode 3 following a loss of offsite power and the failure of both the Unit 1 diesel
genera tors to start.
Which ONE of the following identifies how the MCR crew will monitor Core Exit Thermocouples
and the effect on the post accident monito ring (PAM) instrumentation Tech Spec LCO for Core
Exit Temperature?
A.
Plasma displays on the control board .
PAM Tech Spec LCO entry is required .
B.
Plasma displays on the control board .
PAM Tech Spec LCO entry is NOT required.
C.
Integrated Computer System (ICS) since the plasma displays on the control board will be
unavailable.
PAM Tech Spec LCO entry is required.
D.
Integrated Computer System (ICS) since the plasma displays on the control board will be
unavailable.
PAM Tech Spec LCO entry is NOT required.
10 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
11
Given the following plant conditions:
Unit 1 is at 100% power.
Alarms received indicate that an electrical board has failed .
All trip status lights are OFF on PaneI1-XX-55-5 (on 1-M-5) .
Which ONE of the following identifies (1) which electrical board failed and (2) the reason that
manipulation of controls in the Auxiliary Control Room (ACR) is required?
(1)
A.
120 VAC Vital Instrument Board 1-1.
B.
120 VAC Vital Instrument Board 1-11.
C.
120 VAC Vital Instrument Board 1-1.
D.
120 VAC Vital Instrument Board 1-11.
(2)
ACR Auxiliary Feedwater Controllers for S/G 3
and 4 have swapped to MANUAL and require
adjustment to ensure an operable heat sink is
maintained.
ACR Auxiliary Feedwater Controllers for S/G 1
and 2 have swapped to MANUAL and require
adjustment to ensure an operable heat sink is
maintained.
1-FCV-62-93 and 1-FCV-62-89 have failed
OPEN and related controls must be taken to
the AUX position to reestablish charging and
RCP seal flows.
1-FCV-62-93 and 1-FCV-62-89 have failed
OPEN and related controls must be taken to
the AUX position to reestablish charging and
RCP seal flows .
11 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
12
Given the follow ing plant cond itions:
Unit 1 is at 100% power with no Tech Spec LCO Actions in effect.
The 125 V DC Power System is normal ly aligned with the exce ption of the 6-S
Vital Battery Charger being aligned to the 125v Vital Battery Board II due to
scheduled maintenance on the 125v Vital Charger II.
Offsite power is lost.
All diesel generators start and load except for the 2B-B diesel generator which
FAILS to start.
Which ONE of the following identifies the condition of the 125V Vital DC batteries II and
IV?
(Assume NO operator action is taken.)
A. Battery II is being maintained at normal voltage.
Battery IV is discharging.
B.
Battery IV is being maintained at normal voltage.
Battery II is discharging.
C. Both batteries are being maintained at norma l voltage.
D. Both batteries are discharging.
12 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
13
Given the following plant conditions:
The Unit is at 100% power.
ERCW system is in normal alignment.
ERCW headers 1A and 2A are indicating low flow.
The following MCR alarms are LIT on 1-M-27A:
Which ONE of the following describes what has occurred in the 1A ERCW header?
A. Supply header has ruptured in the Auxiliary Building.
B. Discharge header has ruptured in the Auxiliary Building .
C. Supply heade r has ruptured upstream of the 1A strainer.
D. Supply header has ruptured between the IPS and Auxiliary Bldg.
13 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
14
Complete the following statement:
The reason a backup nitrogen supply is provided to the SG PORVs is to ensure that during
___(1)
the crew has the capability to operate them for a minimum number of cycles,
and the alignment is initiated
(2)
_
ill
11l
A.
an Appendix R Fire
automatically on low control air pressure.
B.
manually.
C.
an Appendix R Fire
manually.
D.
automatically on low control air pressure.
14 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
15
When performing ECA-1.2, LOCA OUTSIDE CONTAINMENT, why are RHR components
addressed BEFORE other ECCS components?
A.
To maintain suction to CCPs if containment sump swapover has already occurred.
B.
This allows the CCPs to maintain RCP seal injection.
C.
Isolation of RHR components requires manipulations outside the MCR.
D.
The leak is most likely to occur in the RHR system.
15 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
16
Given the following plant conditions:
- A Large Break LOCA has occurred.
Containment pressure is 10.5 psig.
RWST level is 20%.
Containment sump level is 68%.
1A RHR pump tripped due to severe damage to its motor.
1-FCV-63-73, CNTMT SUMP TO RHR PMP B SUCT failed to open automatically and
attempts to open it manually have failed.
Which ONE of the following describes the proper alignment of the Containment Spray (CS)
pumps for the existing plant conditions while the CS pumps suction is aligned to the RWST?
A. Stop both CS pumps and place the control switches in P-T-L (Pull-To- Lock) .
B. Stop both CS pumps and place the control switches in A-Auto.
C. Stop ONE CS pump and place its control switch in P-T-L (Pull-To- Lock ).
D. Stop ONE CS pump and place its control switch in A-auto .
16 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
17
Which ONE of the following is an adverse consequence of delaying bleed and feed
cooling if the conditions for initiating bleed and feed are met in FR-H.1, "Response to
Loss of Secondary Heat Sink"?
A. An over pressure challenge to the reactor vessel.
B. Inability to refill the S/Gs without damage from high thermal stresses.
C. Inability to provide sufficient injection for core cooling prior to core uncovery.
D. Steam formation in the hot legs will accelerate the degradation of natural circulation
flow.
17 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
18
Given the following conditions:
Plant is at 100% power.
All systems normally aligned.
The Transmission Operator has notified the plant that system grid voltage is high and
forecasted to go higher.
If the Transmission Operator requests the plant to take in the maximum value of MVARs to help
stabilize the grid, what is the maximum allowed MVAR incoming value, and how is the
adjustment made in accordance with 1-PI-OPS-1-MCR, Main Control Room?
A.
B.
C.
D.
MAX INCOMING VALUE
100 MVARs
100 MVARs
200 MVAR s
200 MVARs
METHOD OF ADJUSTMENT
Exciter Voltage Adjuster
Exciter Base Adjuster
Exciter Voltage Adjuster
Exciter Base Adjuster
18 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
19
Given the following plant conditions:
Unit 1 is at 50% power.
Rod control is in AUTO with Bank D at 176 steps.
Tavg auctioneering unit fails LOW.
Bank D group 2 step counter fails to move.
As a result, rods will __(1)__ and the Bank D control rod CERPI indications must be
matched within _(2)__.
(1)
(2)
A. Insert
+/- 12 steps of each other (highest to lowest rod).
B.
Insert
+/- 12 steps of the of the Group 1 step counter.
C
Withdraw
+/- 12 steps of each other (highest to lowest rod).
D. Withdraw
+/- 12 steps of the of the Group 1 step counter.
19 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
20
Given the following plant conditions:
- 1-XS-68-339E PRZ LVL CTRL CHAN SELECT is in the 339/335 position.
- With actual pressurizer level at 50%, 1-LT-68-339 Pressurizer Level Transmitter develops a
slow leak in the reference leg.
What IS the effect on Pressurizer level and charging flow?
A. Actual level in the Pressurizer will be increasing, causing charging flow to lower.
B. Actual level in the Pressurizer will be decreasing, causing charging flow to rise.
C. Indicated level on 1-LT-68-339 will be increasing, causing charging flow to lower.
D. Indicated level on 1-LT-68-339 will be decreasing, causing charging flow to rise.
20 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
21
Which ONE of the following describes the Reactor Protection System response to a loss of
control power versus a loss of instrument power to N-31 Source Range Monitor with the "TRIP
BYPASS SWITCH" in the "BYPASS" position ?
Control Power Loss
Instrument Power Loss
A.
No trip
B.
Reactor trip
C.
No trip
No trip
0
No trip
21 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
22
Given the following plant conditions:
Operators are responding to an unexpected annunciator, 182-B tlTB SUMP
DISCH O-RM-212 L10 RAD HI.
The station sump pumps discharge is currently aligned to the Low Volume
Waste Pond.
Which ONE of the following identifies the effect the high radiation condition has on the Station
Sump pumps and how the pumps' discharge should be aligned as a result of the alarm in
accordance with AOI-31, Abnormal Release of Radioactive Material?
Effect on
Station Sump Pump
Station Sump Pumps
Discharge Aligned to
A.
Pumps stop
Unlined Chemical Holdup Pond
automatically.
B.
Pumps stop
Lined Chemical Holdup Pond
automatically.
C.
Requires operator action
Unlined Chemical Holdup Pond
to manually stop pumps.
D.
Requires operator action
Lined Chemical Holdup Pond
to manually stop pumps.
22 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
23
If a local fire panel has a TROUBLE lit after being reset , which ONE of the following identifies
how the main control room panel (O-M-29) will indicate a subsequent trouble AND a fire alarm
on the same local panel?
Subsequent Trouble
A.
Would be indicated .
B.
Would be indicated .
C.
Would NOT be indicated.
D.
Would NOT be indicated.
Alarm
Trouble condition would clear, Alarm
would be indicated .
Trouble condition would mask alarm
cond ition.
Trouble condition would clear, Alarm
would be indicated.
Trouble cond ition would mask alarm
condition.
23 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
24
A large break LOCA is in progress. Which ONE of the following identifies conditions that require
entry into FR-Z.1 High Containment Pressure?
Containment Pressure
Containment Spray Pumps
A.
3.0 psig
No pumps running
B.
6.0 psig
1 pump running
C.
9.0 psig
1 pum p runnin g
D.
12.0 psig
2 pumps running
24 of 100
....... -~~------
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
25
Unit 1 is at 100% power. Which ONE of the following is the HIGHEST of the below listed values
for Dose Equivalent Iodine -131 (1-131) without requiring entry into the Action Statement for
LCO 3.4.16, RCS Specific Activity?
A. 0.1
~C ilgm.
B. 0.2 ~Cilgm.
C. 0.3 ~Ci/gm.
D. 0.4 ~C ilgm .
25 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
26
Given the following plant conditions:
- The Unit was at full power when a Small Break LOCA occurred.
- The crew has just stopped one of the charging pumps.
What is the reason for checking RCS pressure stable or rising at this point in ES-1.1?
A.
To determine if the residual heat removal (RHR) pumps should be secured.
B.
To confirm that a secondary heat sink is required.
C.
To confirm that flow from one charging pump is adequate to maintain pressure.
D.
To determine if the safety injection (SI) pumps should be secured.
26 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
27
Given the following plant cond itions :
A reactor trip concurrent with a loss of offsite power has occurred .
The crew has entered FR-H .2, Steam Generator Overpressure based on a YELLOW
condition on the Heat Sink CSF Status Tree.
- 2 SG pressure is 1230 psig.
- 1, #3, and #4 SG pressures are at 1210 psig.
- 2 SG level is 85% and slowly rising.
- 1, #3, and #4 SG level s are 65% and slowly rising.
Which ONE of the following actions will mitigate the SG overpressure cond ition ?
A.
Initiate blowdown flow from #2 SG.
B.
Open the condenser steam dum ps.
C.
Open the steam supply to the Turbine Driven AFW pump.
D.
Initiate minimum AFW flow to #2 SG.
27 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
28
Which ONE of the following failures associated with RCS flow transmitters causes a reactor trip
signal?
A.
A single high pressure tap fails when operating at 50% reactor power.
B.
A single low pressure tap fails when operating at 50% reactor power.
C.
Two high pressure taps fail when operating at 5% reactor power.
D.
Two low pressure taps fail when operating at 5% reactor power.
28 of 100
- .. .':'. =-
'.
0_-," __****
o* ~
._.
_
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
29
On a rising VCT level the Divert Valve is designed to ...
A.
fully open at 63% and fully close when level has lowered to 41%.
B.
begin modulating open at 63% and if level continues to rise, will be fully open at 93%.
C.
fully open at 93% and will begin modulating closed when level drops to 63%.
D.
begin modulating open at 41% and will be fully open when level reaches 63%.
29 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
30
Given the following plant conditions:
The plant is on RHR cooling following a natural circulation cooldown.
RCS temperature is 150°F.
Pressurizer pressure is 340 psig.
Pressurizer level is 25%.
Preparations for returning to Mode 4 are in progress.
In accordance with SOI-68 .02, Reactor Coolant Pumps, which ONE of the following requires an
action plan to be developed with Reactor Engineering prior to starting the first RCP?
A. Shutdown and control rods have been withdrawn 5 steps to ensure no thermal binding.
B. Pressurizer boron concentration is 45 ppm less than RCS boron .
C. Steam Generator metal temperature is 105°F.
D. An RCS boration occurred during the cooldown.
30 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
31
Given the following plant conditions:
Plant startup is in progress.
During performance of GO-1 , Unit Startup from Cold Shutdown to Hot Standby, the CLA
isolation valves were left CLOSED with power on the valves as pressurizer pressure was
raised from 900 psig to 1900 psig .
A manual safety injection (SI) is initiated.
Which ONE of the following identifies the position of the CLA isolation valves before the SI is
initiated and how the MANUAL Safety injection will affect the valves?
Before 51
A.
Valves will have
automatically opened.
B.
Valves will have
automatically opened .
C.
Valves will have
remained closed .
D.
Valves will have
remained closed .
Effect of the 51 signal
An open signal will be generated to the valves.
An open signal will NOT be generated to the valves.
An open signal will be generated to the valves.
An open signal will NOT be generated to the valves.
31 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
32
Given the following plant conditions:
- The plant is at 100% power.
- Annunciator 88C PRT PRESS HI is received.
- PRT pressure is 8.5 psig and RISING SLOWLY.
- PRT level is 67% and STABLE.
If allowed to continue, which ONE of the following describes (1) the LOWEST PRT pressure at
which the rupture disc operates, AND (2) the action required to restore PRT pressure?
A.
(1) 50 psig.
(2)
Vent the PRT to the Waste Gas Header.
B.
(1) 85 psig.
(2)
Vent the PRT to the Waste Gas Header.
C.
(1) 50 psig.
(2)
Drain the PRT to the RCDT to reduce level and pressure.
D.
(1) 85 psig.
(2)
Drain the PRT to the RCDT to reduce level and pressure.
32 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
33
Given the following plant conditions:
- The Unit is at 100% power.
- 1-M-27C. Annunciator 249A "U1 SURGE TANK LEVEL HI/LO" is in alarm.
- The CRO reports that Surge Tank level is 73% on both 1-L1-70-63A and 1-L1-70-99A and
level is rising.
- The CRO reports that 1-LCV-70-63, U1 SURGE TANK MAKEUP LCV, is closed.
-1-FCV-70-66A U1 Surg e Tank Vent is closed .
-1 -PT-70-24A, CCS HX A SUP PRESS, indicates 100 psig and stable.
- All systems are in normal operational alignment.
For the above cond itions, a leak in which ONE of the following components accounts for the
above cond itions, and what is the effect of isolating that component?
A.
RCS Sample heat exchanger.
Suspension of RCS sampling which leads to the inab ility to determine if RCS chemistry
limits are met.
B
RCP seal water return heat exchanger.
Manual isolation of RCP seal return line results in lifting of the seal return relief valve to the
PRT.
C. CVCS letdown heat exchanger.
Manual isolation of normal letdown flow results in loss of cleanup and leads to exceeding
RCS chemistry limits.
D. RCP thermal barrier.
Manual isolation of the thermal barrier heat exchangers results in lifting of the relief valve.
33 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
34
Given the following plant conditions:
Unit 1 at 100% power.
1-SI-68-901-A, Valve Full Stroke Exercising During Plant Operation: Reactor Coolant A-
Train, is in progress.
1-FCV-68-333A, Block Valve for PORV 340A, has been closed and the stroke time
recorded.
When the block valve is reopened, an increase is seen in PRT pressure and
temperature.
Which ONE of the following identifies a condition that will cause the change in PRT conditions
and the action required in accordance with 1-SI-68-901-A?
A.
A PORV opened due to the rapid pressure RISE between the PORV and the block valve
when the block valve was reopened;
Place the PORV control handswitch to CLOSE prior to opening the block valve, then return
to AUTO after the block valve has been opened.
B. A PORV opened due to the rapid pressure RISE between the PORV and the block valve
when the block valve was reopened;
Place the PORV Block Valve control handswitch to CLOSE.
C. The PORV opened due to the pressure REDUCTION which occurred between the PORV
and the block valve while the block valve was closed;
Place the PORV control handswitch to CLOSE prior to opening the block valve, then return
to AUTO after the block valve has been opened.
D. The PORV opened due to the pressure REDUCTION which occurred between the PORV
and the block valve while the block valve was closed;
Place the PORV Block Valve control handswitch to CLOSE.
34 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
35
Given the following plant conditions:
The unit is at 100% power.
Pressurizer Level Control is selected to 1-LT-68-339/335 on 1-XS-68-339E.
If 1-LT-68-335 fails low, what is the impact on the Pressurizer Pressure/Level Control System?
A.
Pressurizer Heaters de-energize and Letdown isolates.
B.
Pressurizer Heaters de-energize and Letdown does NOT isolate.
C
Pressurizer Heaters remain available and Letdown isolates.
D.
Pressurizer Heaters remain available and Letdown does NOT isolate.
35 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
36
Given the following plant conditions:
The plant is operat ing at 100% power.
Annunciator 114-A, SS~A G,t:t;JERAL WARNING is LIT.
.s
~.
Which ONE of the following (1) lists a cond ition that will cause the alarm and (2) describes what
indication the operator disp atched locally will use to determine the cause of the alarm, in
accordance with the ARI ?
(1)
A.
Reactor Trip Bypass Breaker A is
racked in.
B.
Blown Ground Return Fuse.
c.
Reactor Trip Bypass Breaker A is
racked in.
D.
Blown Ground Return Fuse.
(2)
Board-edge LED lights on the Semi-Automatic
Tester.
Board-edge LED lights on the Semi-Automatic
Tester.
Status Lights on the outside of the Local Panels.
Status Lights on the outside of the Local Panels.
36 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
37
Given the following plant conditions:
An inadvertent Safety Injection (SI) has occurred on Unit 1, and the crew is terminating
the Safety Injection.
The OAC has pressed the SI Reset pushbuttons.
Assuming no additional operator action , what is the status of the following ESF signa ls?
Low Steam Line Pressure
Automatic SI
Main Steam Isolation Signal
A.
Enabled
Disabled
B.
Disabled
Enabled
C.
Disabled
Disabled
D.
Enabled
Enabled
37 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
38
Given the following plant conditions:
A main steam line rupture has occurred inside containment.
Con tainm ent pressure peaked at 3.6 psig .
All engineered safety features have actuated per design.
What is the expected status of the containment Upper Compartment Cooling Fans (UCCF) and
Lower Compartment Cooling Fans (LCCF) 10 minutes after the event?
UCCF
LCCF
A.
Running
Tripped
B.
Tripped
Runnin g
C.
Running
Running
D.
Tripped
Tripped
38 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
40
While performing ES-1.3 Transfer to Containment Sump, the Containment Spray Pump
handswitches are required to be placed in Stop-PULL-TO-LOCK at which ONE of the
following setpoints?
A.
Containment Sump level rises to 83%.
B.
Containme nt Sump level rises to 34%.
C.
Refue ling Water Storage Tank level drops to 16.1 %.
D.
Refueling Water Storage Tank level drops to 8%.
40 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
41
Given the following plant conditions:
- At EOL, a reactor startup is in progress following a 6-day outage.
- The Reactor Engineer has provided an ECP which predicts the reactor going critical at 120
steps on Control Bank D.
Which ONE of the following conditions will result in the critical rod height being HIGHER than
the value predicted by the ECP?
A. A dilution of 500 gallon s is performed.
B. Feedwater flow is increased to all SGs due to a controller malfunction .
C. Steam Dump Controller 1-PIC-1-33 fails, resulting in a pressure decrease of 50 psig.
D. An improperly performed step in the Post Maintenance Test procedure results in the closure
of all MSIVs.
41 of 100
[
.- ....
.
.
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
42
Given the following plant conditions:
The unit is at 100% power.
Unidentified leakage is 0.03 gpm .
Steam Generator #3 has a 17 gpd tube leak.
AOI-33, Steam Generator Tube Leakage, Appendix A for Steam Generator Tub e Leak
Monitoring, is in prog ress.
Subsequ ently, the activity in the RCS increased significantly due to fuel failure s.
NOTE: Radiation Monitor Identification Numbers:
1-RM-90-106 - Lower Containment Radiation Monitor
1-RM-90-119 - Condenser Vacuum Pump Exhaust
1-RM-90-423 - #3 Steam Line Radiation Mon itor
Which ONE of the following describes how 1-RM-90-1 06 and 1-RM-90-423 will respond as a
result of the failed fuel without a change in the amount of steam generator tube leakage and the
action directed in AOI-33, Appendix A, for using radiation monitors to quantify tube leakage ?
RAD Monitor Response
A.
1-RM-90-106 and 1-RM-90-423
increase.
B
1-RM-90-106 and 1-RM-90-423
increase.
C.
1-RM-90-106 rema ins constant.
1-RM-90-423 increases.
D. 1-RM-90-106 remains constant.
1-RM-90-423 increases.
Action to Quantify
Recalculate values for correlating 1-RM-90-11 9 to
SG tube leakage.
Stop using 1-RM-90-119 as the preferred indication
for SG tube leak rate monitoring.
Recalculate values for correlating 1-RM-90-119
to SG tube leakage.
Stop using 1-RM-90-119 as the preferred indication
for SG tube leak rate monitoring.
42 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
43
Given the following plant conditions:
The Unit is at 50% load , steady state.
All Feedwater valves/pumps are in automatic.
Both Main Feedwater Pumps are running.
Standby Feed Pump is off with its control handswitch in "auto".
The controlling steam flow (SF) transm itter on #1 S/G fails LOW .
Which ONE of the following describes the response of the Feedwater Control System to the
given conditions?
A.
MFP speed RISES ; #1 S/G Feedwater regulating valve closes initially to match feedwater
flow to the failed SF input.
B.
MFP speed RISES ; #1 S/G Feedwater regulating valve closes initially due to the level error
signal present.
C.
MFP speed LOWERS; #1 S/G Feedwater regulating valve closes initially to match
feedwater flow to the failed SF input.
D.
MFP speed LOWERS; #1 S/G Feedwater regulating valve close s initially due to the level
error signal present.
43 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
44
Given the following plant conditions:
- The unit is at 100% power.
- The TO AFW pump is out of service to repair the Trip-an d-Thrott le valve
linkage.
- 6.9 KV Shutdown Board 1B trips due to a differential relay actuation.
- An inadvertent Safety Injection occurs.
Which ONE of the following describ es the SG s that are receiving AFW flow and wh ich
SG blowdown isolation valves are closed, as a resu lt of the above conditions? (Assume
no ope rator action .)
A.
B.
c.
O.
On ly SG 1 and 2
Only SG 1 and 2
Onl y SG 1 and 3
On ly SG 1 and 3
SG SLOWDOWN Isolated
Only SG 1 and 3
Only SG 1 and 2
44 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
45
Given the following plant conditions:
The unit is at 100% power.
All secondary condensate and feedwater pumps are in service.
The 1D Unit Board develops a fault and trips due to relay operation.
Which ONE of the following pumps is lost as a result of this failure ?
A.
1B Hotwell Pump.
B.
1A Condensate Booster Pump .
C.
1B #3 Heater Drain Tank Pump .
D.
Standby Main Feed Pump .
45 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
46
Given the following plant cond itions :
1A-A and 1B-B SI Pump breakers are "Racked Up" .
A fuse blows in the NORMAL DC Trip circuit for the 1A-A SI Pump.
A safety injection (SI) actuation occurs.
Which ONE of the following describes the response of the SI Pumps to the SI signal?
A.
1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start until the control power
supply is transferred.
B.
1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start and must be
started from the MCR handswitch .
C.
Both SI Pumps will auto start, but 1A-A SI Pump cannot be stopped from the
D.
Both SI Pum ps will auto start, but 1A-A SI Pump will immediately trip due to the blown fuse.
46 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
47
Which ONE of the following is the power supply for the 2A-A Diesel Generator Fuel Oil Priming
pump?
A.
480v AC from Diesel Generator Auxiliary Board 2A1-A.
B.
480v AC from Diesel Generator Auxiliary Board 2A2-A.
C.
125v DC from the 125v DC Vital Battery Board 2-1.
D.
125v DC from the 125v DC 2A-A Diesel Battery Distribution Panel.
47 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
48
After a reactor trip and safety injection on Unit 1, the following conditions are observed for 1A-A
Diesel Generator (DG):
1-M-26A, Window 198A, "DG START/RUN FAILURE" alarm - LIT.
Green "DG Run" light - ON.
Red "DG Run" light - OFF.
Red "DG Above 40 rpm" light - ON.
Diesel Generator 6.9 KV breaker - OPEN .
Diesel Generator voltage - ZERO.
From the above indications, the operating crew knows that 1A-A Diesel Generator started and
A.
shutdown after 10 seconds.
B.
engine speed did not rise above 550 rpm.
C.
engine speed exceeded 550 rpm but did not rise above 850 rpm.
D.
shutdown due to insufficient air in the receiver.
48 of 100
-
.0*":'
-
- ..
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
49
The Turbin e Building NAUO has placed 1-HS-15-44 , SG Blowdown Disch to CTBD , (Cooling
Tower Blowdown), in OPEN per SOI-15.01, in order to direct SGBD flow to CTBD .
Which ONE of the following will occur if radiation monitor 1-RM-90-120 loses flow through the
monitor?
A.
Blowdown will be isolated to the CTBD resulting in loss of blowdown flow .
B.
Blowdown will be isolated to the CTBD and automatically be redirected to the condensate
C.
Blowdown will continue to the CTBD but will isolate if 1-RM-90-121 reached the HI RAD
setpoint.
D.
Blowdown will continue to the CTBD and will NOT isolate if 1-RM-90-121 reached the HI
RAD setpoint.
49 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
50
Given the following plant conditions:
Unit 1 experienced a Reactor Trip/Safety Injection due to a LOCA inside containment.
When checking annunciators following the trip and SI, the CRO notes that the follow ing
annunciators are in alarm:
o
173B, LWR CNTMT AIR 1-RM-106 RAD HI.
o
173E, LWR CNTMT AIR 1-RM-106 INSTR MALF.
Assum ing all components respond as designed, which ONE of the following actions will the
NAUO take due to the above conditions?
A. Reopen the radiat ion monitor isolation valve which restores flow through the monitor to
restore Tech Spec operability.
B. Restart the radiation monitor pump which restores flow through the monitor to restore Tech
Spec operability.
C. Stop the radiation monitor pump to prevent damage to the pump due to the monitor being
isolated as a result of the safety injection.
D. Close the radiation monitor isolation valves to isolate monitor due to the pump being tripped
as a result of the safety injection.
50 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
51
Reactor trip and safety injectio n signals have been manually initiated. Which ONE of the
following describes the required positions for the listed ERCW valves in accordance with E-O,
App endi x A. Equipment Verification?
O-FCV-67-144,
O-FCV-67-152,
"CCS Heat Exchanger 'C'
"CCS Heat Exchanger 'C'
Disch to Hdr A"
Alt Disch to Hdr S"
A.
CLOSED
OPEN to Pos ition A
8
THR OTTLED
CLOSED
C.
THROTTLED
OPEN to Pos ition A
D.
OPEN
CLOSED
51 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
52
Given the following plant conditions:
The plant is operating at 100% power with 1B CCP in service.
The Control Room Operator shutdowns down the C-A ERCW pump in preparation for a
test on the 2A 6.9 KV Shutdown Board.
Which ONE of the following describes the impact of shutting down the pump on the listed
parameters?
(Assume no other operator action. )
18 CCP Oil
Seal Water Return Heat
Temperature
Exchanger Temperature
A.
Rises
Rises
B.
Rises
Remains constant
C.
Remains constant
Rises
D.
Remains constant
Remains constant
52 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Ques tion Number:
53
Which ONE of the following identifies both of the following?
(1) The lowest of the listed containment pressures that results in 1-FCV-32-80, Aux Air to
Rx Bldg Train B, being automatically isolated , and
(2) The lowest of the listed air pressures sensed downstream of the valve tha t allows the
valve to REMAIN OPEN after the valve was opened and the control switch on 1-M-15
placed to A-Auto after the isolation signal was reset.
ill
ill
A.
2.0 psid
68 psig
B.
2.0 psid
78 psig
C
3.0 psid
68 psig
D.
3.0 psid
78 psig
53 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
54
Given the following plant conditions :
Plant is in Mode 4.
Lower containment air lock is broken and inner door is jammed and will not open.
If conditions were to require an emergency entry into lower containment by opening the sub-
hatch, which ONE of the following is REQUIRED to be contacted prior to opening the sub-hatch,
and what action is required as a result of the sub-hatch being open ed?
A. Shift Manager;
Perform 1-SI-88-24, Containment Divider Barrier Personnel Acce ss Hatches & Equipment
Hatches. within one (1) hour.
B. Shift Manag er;
Perfo rm 1-SI-88-24 , Containment Divider Barrier Personnel Acce ss Hatches & Equipment
Hatches . prior to Mode 3 entry .
C. Work Week Manager;
Perform 1-SI-88-24 , Containment Divider Barrier Personnel Access Hatches & Equipment
Hatches. within one (1) hour.
D. Work Week Manager;
Perform 1-SI-88-24, Containment Divider Barrier Personnel Access Hatches & Equipment
Hatches, prior to Mode 3 entry.
54 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
55
Which ONE of the following identifies the NORMAL pressure band controlled by the
Containment Annulus Vacuum System and the required method of controlling pressure if 1-M-
27B Window 232-B, ANNULUS l1P LOIDAMPER SWAPOVER is LIT?
Annulus Pressure Band
A.
-6.0 to -6.2" WC
B.
-6.0 to -6.2" WC
C.
-4.3 to -4.5" WC
D.
-4.3 to -4.5" WC
Method of Controlling Pressure
Dispatch a NAUO to RESE T the dampers locally.
Swap the dampers using handswiches on 1-M-27B.
Dispatch a NAUO to RESET the dampers locally.
Swap the dampers using handswiches on 1-M-27B.
55 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
56
Given the following plant conditions:
The unit is at 100% power.
1-M-1B, Window 17-D, 120 AC VITAL PWR BD 1-1 UV/CKT TRIP, is LIT.
Which ONE of the following describes the impact on the Computer Enhanced Rod Position
Indication (CERPI) System and what is required to ensure that Tech Spec Rod Group Alignm ent
Limits are met?
Rod position indication
A.
Availa ble
B.
NOT Available
C.
Available
D.
NOT Available
Actions Reguired for Rod Group alignment
Use the "ALL RODS" function on the operating display.
Flux map is required to confirm rod position.
Flux map is required to confirm rod position.
Use the "ALL RODS" function on the operating display .
56 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
57
Which ONE identifies BOTH of the following for Hydrogen Recombiner operations?
(1) The MAXIMUM Hydrogen Recombiner temperature allowed when operating?
AND
(2) The HIGHEST of the listed containment hydrogen concentrations allowed when placing the
recombiner in service?
A.
B.
c.
D.
(1) Maximum Temperature
(2) H2 Concentration
6%
4%
6%
4%
57 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
58
Following a refueling outage, the following cond itions exist:
Unit 1 is in Mode 3 prepa ring for Mode 2 entry .
Fuel shuffles are being conducted in the Spent Fuel Pit.
Spent Fuel Pool Cooling pump A is the only Spent Fuel Pool Coolin g pump in service.
The 2A-A Shutdown Board normal feeder breake r is inadvertently opened during testing.
The DG starts and reenergizes the shutdown board.
Which ONE of the following describes the initial effect on the Spent Fuel Pool Cooling system ,
and the required action, if any , per Spent Fuel Pool Tech Specs?
A. The Spent Fuel Cooling Pump strips from the board, and then sequences back on to the
shutdown board .
Spent Fuel Pool Tech Specs requires that movement of irradiated fuel assemblies in the fuel
storage pool be immediately suspended.
B. The Spent Fuel Cooling Pump strips from the board , and then sequences back on to the
shutdown board .
Spent Fuel Pool Tech Specs does NOT require that movement of irradiated fuel assembli es
in the fuel storage pool be suspended.
C. The Spent Fuel Cooling Pump strips from the board , and remains off.
Spent Fuel Pool Tech Specs requires that movement of irradiated fuel assemblies in the fuel
storage pool be immediately suspended.
D. The Spent Fuel Cooling Pump strips from the board , and remains off.
Spent Fuel Pool Tech Specs does NOT require that movement of irradiated fuel assembli es
in the fuel storage pool be suspended.
58 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
59
Which ONE of the following identifies (a) how main steam header pressure responds as turbine
load is raised from 25% to 65%, and (b) which method of mainta ining Tavg matched with Tref
results in the value for MTC being the MOST negative as turbine load is raised ?
A
(a)
Main steam header pressure lowers
(b)
Rods are withdrawn to maintain Tavg on program, with Boron concent ration held
const ant.
B.
(a)
Main steam header pressure rises.
(b)
Rods are withdrawn to mainta in Tavg on program, with Boron concentration held
cons tant.
C.
(a) Main steam header pressure lowers.
(b)
Rod position is held constant, while Boron concentration is lowered to maintain Tavg
on program .
D.
(a) Main steam header pressure rises.
(b) Rod position is held constant, while Boron concentration is lowered to maintain Tavg
on program.
59 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
60
Which ONE of the following identifies monitors associated with Condenser Vacu um Pump
discharge which are Post Accident Monitors (PAM), in accordance with SOI-90.05, Post
Accident Radiation Monitors?
A. Both 1-RM-90-119 and 1-RM-90-404.
B. Neither 1-RM-90-11 9 nor 1-RM-90-404.
C.
1-RM-90-119 is a PAM, but 1-RM-90-404 is NOT.
D. 1-RM-90-404 is a PAM, but 1-RM-90-119 is NOT.
60 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
61
Which ONE of the following occurs automatically if the "8" MFP trips due to thrust bearing wear
with the plant initially at 100% power? (Assume no other equipment failures .)
A.
The motor driven AFW Pumps start.
8.
The Condensate 01 pumps trip if feedwater flow drops to <80%.
C.
The "8" MFPT condenser condensate inlet and outlet valves go closed.
O.
The short cycle valve , 1-FCV-2-35, modulates open to dump excessive condensate flow.
61 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
62
Which ONE of the following identifies a condition that causes an instrument malfunction alarm on O-RM-90-1 22, WDS Liquid release radiation monitor, and the effect the instrument
malfunction alarm has on valve O-RCV-77-43, CT BLDN LN RAD RELEASE CNTL?
A.
B.
C.
D.
Cause of the alarm
Loss of signal from detector
Loss of signal from detector
Loss of flow through the mon itor
Loss of flow through the monitor
Effect on O-RCV-77-43
Auto closes O-RCV-77-43 if the valve was open.
Prevents O-RCV-77-43 from opening if the valve 's
local control handswitch was placed to OPEN .
Auto closes O-RCV-77-43 if the valve was open .
Prevents O-RCV-77-43 from opening if the valve 's
local control handswitch was placed to OPEN .
62 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
63
A release of the Monitor Tank is in progress through the Liquid Radwaste System. Which ONE
of the following conditions directly results in automatic closure of 0-FCV-77-43, Liquid Radwaste
Release Flow Control Valve?
A.
High radiation signal on 0-RM-90-225, Condensate Demineralizer Release Liquid Radiation
Monitor.
B.
River flow drops to less than 3500 cfs after a 1 minute time delay.
C.
Cooling Tower Blowdown flow drops below 25,000 gpm .
D.
SG Blowdown flow exceeds 150 gpm.
63 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
64
Given the follow ing plant cond itions:
Unit 1 is operating at power when control air pressu re starts to drop.
Annunciator 42-F , SERVICE AIR PCV-33-4 CLOSED, alarms.
The CRO responds in accordance with the Annunciator Response Instruction (ARI).
Which ONE of the following identifies the decreasing Control Air system pressure that causes
this alarm to occur and whether the Auxiliary Air compressors would have started if the air
pressure dropped low enough to cause the alarm, but then recovered without dropping any
lower?
Pressure to Cause Alarm
Aux Air Compressors
A.
83 psig
Will have started
B.
83 psig
Will NOT have started
C.
80 psig
Will have started
D.
80 psig
Will NOT have started
64 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
65
Given the following plant conditions:
Unit 1 is currently at 100%.
A fire occurs in the Cable Spreading Room.
The crew was unable to start the HPFP pumps .
The incident Commander also reports that due to multiple fire damper failures the fire is
spread ing quickly.
The crew has entered AOI-30.2, Fire Safe Shutdown.
In accordance with AOI-30.2, which ONE of the following failures results in a loss of a Control
Function required to place the Plant in Hot Standby?
REFERENCE PROVIDED
A. Motor Driven AFW Pumps will not start.
B. RCS Thermal Barrier Boost er Pumps trip.
C. One Main Steam Isolation Valve fails to close.
D
Letdown Isolation Valve 1-FCV-62-69 fails closed.
65 of 100
'::'. '"
..,
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
66
For Mode 1 operation, which ONE of the follow ing describes the MINIMUM number of Licensed
Operator positions to man a shift, AND the MAXIMUM time requirement to restore if the
minimum shift manning for Licensed Operators is not met per OPDP-1, Conduct of Operations
and Tech Spec 5.2.2, Unit Staff?
Minimum Shift Manning
Time Requirement
A.
Restore within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
B.
Restore within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
C
Restore within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
D.
Restore within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
66 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
67
With the Steam Dump Mode switch in the Tavg mode, what determines whether the load
rejection controller or the Rx trip controller will be in service?
A.
Loss of Load (C-7) Interlock.
B.
LO-LO Tavg Interlo ck (550°F).
C
"A" Train Reactor Trip breaker position.
D.
"B" Train Reactor Trip breaker position.
67 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
68
Given the following plant conditions:
Unit is in Mode 6.
15 fuel assemblies have been reloade d after a complete core off-load .
Source Range N-13 1 indicates 10 cps and is selected for audible count rate indication.
Source Range N-132 indicates 5 cps.
In accordance with FHI-7, "Fuel Handling and Movement", which ONE of the follow ing
unanticipated changes in count rate requires suspension of core alterations?
A
N131 indica tes 25 cps and N132 indicates 8 cps.
B.
N131 indicates 15 cps and N132 indicates 20 cps.
C.
N131 indicates 40 cps and N132 indicates 8 cps.
D.
N131 indicates 20 cps and N132 indicates 15 cps.
68 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
69
A Power Range chann el has failed requiring the crew to implement AOI-4, NIS Malfunctions.
The US has entered the appro priate Technical Specifi cations and states that a flux map will be
required per Surveillance Requirement 3.2.4.2.
SR 3.2.4.2 directs the operators to verify OPTR is within limits using moveable incore detectors
once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
What is the maximum time for the initial performance of the flux map and the maximum time for
subsequent performances?
A.
B.
c.
D.
Initial Performance
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
15 hours
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
15 hours
Subsequent Performances
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
12 hours
15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />
15 hours
69 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
70
Given the following conditions:
Unit 1 shutdown is in progress.
Reactor power is 14% and decreasing.
Intermediate Rang e NI-36 fails HIGH.
Which ONE of the following identifies how the failure of the NI will affec t the reactor trip system
and the effect the failure will have on the Source Rang e Nls?
Reactor Trip System
A.
Reactor trip will occur at the time of
failure .
B.
Reactor trip will occur at the time of
failure.
C.
Reactor trip will occur if power
reduction is continued .
D
Reactor trip will occur if power
reduction is continued .
Effect on Source Range Nls
Source Ran ge Nls will have to be
MANUALLY reinstated.
Sou rce Range Nls will
AUTOMATICALLY reinstate.
Source Range Nls will have to be
MANUALLY reinstated.
Source Range Nls will
AUTOMATICALLY reinstate .
70 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
71
An individual enters a Radiological Controlled Area (RCA) covered by a General RWP to
perform equipment inspections.
Which ONE of the following identifies an area within the RCA where a Job Specific RWP is
required before ent ry is allowed, in accordance with RCI -153, Radiation Work Permits?
A.
Area wh ere whole body dose rates excee ds 100 mrem/hr.
B.
Are a posted as Hot Parti cle Area .
C. Area with general contamination levels great er than 200 dprn/f Oucrn".
D. Area where total expected dose is greater than 5 mrem.
71 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
72
Given the following plant conditions:
Following an accident, both Trains of Control Room Isolation have been initiated.
Several Auxiliary Building Area Radiation Monitors rise to the alarm setpoint.
Which ONE of the following MCR air intake radiation monitors will detect and alert the crew of a
radiation hazard entering the control room and what actions will the ARI direct the crew to
perform?
A.
O-RM-90-125,
B.
O-RM-90-125,
C.
O-RM-90-205,
D.
O-RM-90-205,
Stop MCR Emergency Pressurization Fans .
Align Emergen cy Pressurization Fan suction to alternate source.
Stop MCR Emergency Pressurization Fans.
Align Emergency Pressurization Fan suction to alternate source.
72 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
73
The Operator-at-the-Controls (OAC) is responding to an accident. He recognizes that he must
take actions which are NOT contained in the emergency operating procedure in effect and are
NOT covered by prudent operator actions . Which ONE of the following describes the proper
action to be taken?
A.
The OAC shall take no action until a procedure is developed or revised.
B.
The OAC shall obtain approval from a licens ed SRO prior to taking action .
C.
The OAC should obtain concurrence from another licensed RO prior to taking action.
D.
The OAC should immediately take appropriate actions necessary and inform the SRO when
time permits.
73 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
74
Given the following:
A Site Area Emergency (SAE) has been declared on Unit 1.
Two hours after the SAE declaration, an individual is to be authorized to receive an
Emergency Exposure radiation dose above the TVA who le body dose limit during the
mitigation of the emergency situation.
In acco rdance with EPIP-15 , Emergency Exposure Guidelines, whose app roval is requ ired for
the individual to rece ive the dose?
A.
TSC Radcon Manager.
B. Onshift Shift Manager.
C. Site Emergency Director.
D. Site Vice President.
74 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
75
Which ONE of the following identifies where a Portable Satellite Telephone, available for use
during an emergency, is located?
A.
Main Control Room
D. Operations Support Center
75 of 100
AOI-30.2
FIRESAFESHUTDOWN
Rev. 27
Paqe 17 of 1291
4.5
Safe Shutdown Logic Diagram
NOTES
(1) INITIATING EVENT IS AN APPENDIX R FIRE
(2) REFER TO SECTION 4.3 FOR A COMPLETE
DESCRIPTION OF THE SHUTDOW N KEYS , THEIR
FUNCTIONS AND COMPONENTS.
(3) LEGEND FOR DIAGRAM SYMBOLS AS FOLLOWS '
DESCR IPTION OF KEY
KEY NUMBER
I,.~ "oo~""w,m'",,,
<
~ SAFETY FUNCTlON OR E.ND
STATE TO BE AnAINED
(4) OFFSITE POWER NOT CREDITED FOR ALTERNATIVE SHUTDOW N.
(5) RCP THERMAL BARRIER COOLING REQUIRES SUPPORT OF
~
'
.,........
- l
i.J
i.J:J
~
!\\J
I'~
~()
~
'6!
{\\j
C;
IV(t\\
~I
~
<t:\\
Final Submittal
(Blue Paper)
FINAL SRO
WRITTEN EXAMINATION
AND REFERENCES
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
76
Given the following conditions:
Unit 1 is at 100% power. Solid State Protection System (SSPS) Train 'B' Actuation Logic testing
is being performed using 1-SI-99-1 OB with :
Train 'B' SSPS Mode Selector switch in the 'TEST' position .
Train 'B' SSPS Input Error Inhibit switch in the "INHIBIT" pos ition .
A unit trip occurs due to the loss of one of the two 48v DC power supplies on TRAIN 'A' SSPS.
The following "First Out" annunciators are lit:
1-XA-55-4C. Turbine Trip First
Window 73C - "RX TRIP BKRS RTA & BYA OPEN"
Window 74C - "RX TRIP BKRS RTB & BYB OPEN"
Window 74B - "MFPT A&B TRIPPED"
1-XA-55-4D Reactor Trip First Out
Window 76B "TURBINE TRIP"
Which ONE of the following identifies both the sequence of events of the unit trip, and the time
allowed to make the required NRC 50.72 notification?
Sequence of Events
A.
Turbine trip caused the Reactor trip.
B.
Turbine trip caused the Reactor trip.
C.
Reactor trip caused the Turbine trip.
D.
Reactor trip caused the Turbine trip.
NRC Notification Required Within
Four Hours
Eight Hours
Four Hours
Eight Hours
76 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
77
Given the following plant conditions:
Core burnup is 1200 MWO/MTU.
Indicated reactor power is stable at 100%.
VCT low level alarm annunciates.
Auto makeup has failed .
Actual VCT level had lowered to 5% before the crew completed the appropriate
corrective action.
Reactor power has stabilized at approximately 97% power.
If this event had occurred with core burnup at 16600 MWO/MTU, the magnitude of the change
in reactor power would be
(1)
, and the Significance Level of the Reactivity
Management Event classification would be recorded on the PER (Problem Evaluation Report)
by
(2)
_
(1)
(2)
A.
less
Reactor Engineering.
B.
greater
Reactor Engineering.
C.
less
the Management Review Committee.
D.
greater
the Management Review Committee.
77 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
78
Given the following:
Unit 1 is in Mode 5 following a refueling outag e.
The operating crew is drawing vacuum on the Reacto r Coolant System.
The RHR pump begins to show signs of cavitation.
Which ONE of the following identifies both how the RHR pump motor amps are affected when
the pump is cavitating, and the mitigating strategy that will be implemented if the cavitation
cannot be terminated?
Motor Amps
A.
Unstable and fluctuating.
B. Unstable and fluctuatin g.
C. Stable but reduced.
D. Stable but reduced.
Mitigating Strategy
Break vacuum per GO-1 0, Reactor Coolant System
Drain and Fill Operations, then enter AOI-14, Loss of
Immed iately enter AOI-14, Loss of RHR Shutdown
Cooling. Break vacuum as directed by the AOI.
Break vacuum per GO-1 0, Reactor Coolant System
Drain and Fill Operations, then enter AOI-14, Loss of
Immediately enter AOI-14, Loss of RHR Shutdown
Cooling. Break vacuum as directed by the AOI.
78 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
79
Given the following conditions:
The plant is operating at 100% power steady state conditions.
All systems are aligned normally.
A failure of the Pressurizer Spray Valve PCV-68-340D causes it to go full OPEN .
The OAC has attempted to take manual contro l of the Spray Valve, but is unable to
close it.
Pressu rizer pressure continues to LOWER.
What is the appropriate mitigation strategy and which procedure(s) will be used to implement
the strategy?
A.
Enter AOI-18, Malfunction of Pressurizer Pressure Control System, initiate a Reactor Trip,
trip RCP #1, then enter E-O, Reactor Trip or Safety Injection.
B. Refer to ARI-90-B, PZR PRESS LO DEVN BACKUP HTRS ON, isolate Train B Essenti al Air
to Conta inment to fail the Pressurizer Spray Valve closed, and then enter AOI-1 8.
C. Refer to ARI 90-B, PZR PRESS LO-DEVN BACKUP HTRS ON, isolate Train A Essential Air
to Containment to fail the Pressurizer Spray Valve closed, and then enter AOI-1 8.
S~ ~
D. Enter AOI- 18, Malfunction of Pressurizer Pressure Control~initiate a Reactor
Trip AND SI, trip RCP #1, then enter E-O, Reactor Trip or Safety Injection.
79 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
80
Given the following:
The plant is operating at 100% power.
The 125 V DC VITAL CHGR III fails and its output brea ker opens.
A report is received that there is arcing occurring on Vital Battery III.
The Shift Manager directs that 0-BKR-236-3/109 125V Vital Battery III Breaker, between
Vital Battery III and Vital Battery Board III be opened.
The Unit Supervisor has determined that power to Vital Battery Board III will be restored
using Vital Battery V, in conjunction with the Spare Battery Charger.
Vital Battery V is currently in service to Battery Boa rd V.
Which ONE of the following describes the expected indication on 1-EI-57-94 , Vita l Batt BD III
AMPS which will confirm that power has been restored to Battery Board III, AND what is the
operability status of Vital Battery Board III?
1-EI-57-94 (Satt SO III Amps) Indication
A.
Indicating UPSCALE from zero.
B.
Indicating DOWNSCALE from zero.
C.
Indicating UPSCALE from zero.
D.
Indicating DOWNSCALE from zero.
80 of 100
Operability Status of Vital Satt. SO III
Can NOT be considered operable with
both Vital Battery V and the spare charger
connected concurrently.
Can NOT be considered operable with
both Vital Battery V and the spare charg er
connected concurrently.
Operable with the spare charger and Vital
Battery V connected to the Battery Board
and with all applicable surveillanc es on
Vital Battery V satisfied.
Operable with the spare charger and Vital
Battery V connected to the Battery Board
and with all applicable surveillances on
Vital Battery V satisfied.
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
81
With the plant at full power, and during the Shift Turnover for the 1900 shift , the Unit Supervisor
is informed of the following:
1-LS-63-50A (RWST Low Level) was declared inoperable at 1000 that day.
It was placed in the configuration required by Technical Specifications at 1400, and is
expected to rema in inoperable until 2300.
A requ ired surveillance instruction on 1-LS-63-51A (RWST Low Level ) must be
completed by 2330 today to prevent being out of frequency due to exceeding the NRC
late date.
The surveillance involves having 1-LS-63-51 A in the required configuration for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
If the surv eillance is completed by 2330, which ONE of the following describes the expected
effect on the automatic switchover to containment sump function while 1X63-51A is out of
.
?
~~A
service .
~_.....
A.
Functiona l. Even though two level switches are TRIPPED and are inoperable, the
remaining operable level switches are sufficient for switchover to be functional.
B.
Functional. Even though two level switches are BYPASSED, the remaining level
switches are sufficient for switchover to be functional.
C.
Not functional, because two level switches are TRIPPED and at least three level
switches are required for switchover to be functional.
D.
Not functional, because two level switches are BYPASSED, and at least three level
switches are required for switchover to be functional.
81 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
82
Given the following:
The unit is at 100% power and all equipment is available.
A planned Cask Decont amination Collector Tank (CDCT) release is in progress when
the following occurs:
- Annunciator 181-A "WDS RELEASE LINE 0-RM-90-122 L1Q RAD HI" alarms.
- The Monitor Tank level is 70% and lowering.
Which ONE of the following identifies wheth er the release permit was violated and the release
permit requirements to allow the CDCT release to continue, in acco rdance with SOI-77.01,
Liquid Waste Disposal?
Permit Violated
Release of CDCT
The same release permit can be used
follow ing independent verification of
correct valve lineup .
A new release permit must be generated .
I
The release permit would be
violated because the liquid
released was not sampled
. prior to the release .
The release permit would be
! violated becau se the liquid
i released was not sampled
A.
i
I prior to the release.
,
The release permit was NOT
C.
violated because the release
The same release permit can be used
was terminated by the high
following independent verification of
rad signa l.
correct valve lineup .
The release permit was NOT
, D.
violated because the releas e
A new release permit must be generated .
,
. was terminated by the high
I
I rad signal.
I
i
I
~---I--------+----------J
lB.
82 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
83
Given the following plant conditions:
Unit 1 was at 100% power when a Main Control Room (MCR) evacuation was required.
The crew entered AOI-27, Main Control Room Inaccessibility.
The crew performed ES-0.1, Reactor Trip Response, prior to leaving the MCR.
While performing actions from the ACR a Safety Injection occurs.
Which ONE of the following will be the status of the MSIVs when the crew establishes control
from the Aux Control Room and describes the correct proced ure usage?
A.
B.
C.
D.
MSIV Status
Open
Open
Closed
Closed
Procedure Usage
AOI-27 will be the controll ing procedure because it is written with
mitigating actions to respond to a Safety Injection.
E-O, Reactor Trip or Safety Injection, would be used because
AOI-27 is written assuming no other accident is occurring .
AOI-27 will be the controll ing procedure because it is written with
mitigating actions to respond to a Safety Injection.
E-O, Reactor Trip or Safety Injection, would be used because
AOI-27 is written assuming no other accident is occurring.
83 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
84
Given the following:
The crew is performing FR-H.2, Steam Generator Overpressure, for an overpressure
condition on SG #2.
When the step is addressed to check affected SGs NR level it is noted that the SG #2
level is indicating 94% narrow range.
Which ONE of the following identifies the correct crew actions as a result of the SG level
morcatmq 94% ?
A.
Continue in FR-H.2, but do not initiate any steam release until TSC evaluation is complete.
B.
Continue in FR-H.2, steam release may continue until NR level indicates 100%.
C
Transition to FR-H .3, Steam Generator High Level, but do not initiate any steam release
until TSC evaluation is complete.
D.
Tran sition to FR-H.3, Steam Generator High Level, steam release may continue until NR
level indicates 100%.
84 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
85
Given the following:
Unit 1 experien ced a Reacto r Trip and Safety Injection.
The crew transitioned to FR-Z.1, High Containment Pressure, from E-1, Loss of
Reactor or Secondary Coolant.
While FR-Z.1 was being performed, the crew transitioned to FR-P.1, Pressurized
Thermal Shock.
The STA reports the conta inment pressure has dropped and the containment status
tree is GREEN and that no other RED or ORANGE paths exist.
Which ONE of the following identifies the basis of the FR-P.1 step for checking RCS pressure
greater than 150 psig, and the procedure the crew will implement if a transition is made from
FR-P.1 during performance of the step?
A.
To preclude the need to perform FR-P.1 actions, since pressurized thermal shock is not a
serious concern for a large-break LOCA ;
Transition is made back to E-1.
B. To preclude the need to perform FR-P.1 actions, since pressurized thermal shock is not a
serious concern for a large-brea k LOCA;
Transition is made back to FR-Z.1.
C. To avoid delays caused by unnecessary soak periods required by FR-P .1.
Transition is made back to E-1.
D. To avoid delays caused by unnecessary soak periods required by FR-P.1.
Transition is made back to FR-Z.1 .
85 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
86
Given the following:
Unit 1 was in Mode 2 with startup in progress when a loss of off-site power occurred .
The decision was made to place the plant in Mode 5.
The crew implemented ES-O.2, Natural Circulation Cooldown, and started cool ing the
plant down .
Four (4) hours after the cooldown was initiated both trains of offsite power were restored
to the plant.
The crew determines all criteria to restart the RCPs are met except for the #1 seal
leakoff flow on RCP #2 which is lower than the normal operating band .
Which ONE of the following identifies a change that causes an increase in the # 2 RCP seal
leakoff flow and the actions to be taken and procedure to be used if the seal leakoff flow cannot
be established within the normal operating band ?
A.
Lower PRT pressure;
Start RCP #1, continue performing ES-O.2 until all RCS temperatures are less than 200°F,
then transition to GO-6, Unit Shutd own From Hot Standby To Cold Shutdown.
B. Lower PRT pressure;
Start the other 3 RCPs and immediately transition from ES-O.2 to GO-6, Unit Shutdown
From Hot Standby To Cold Shutdown.
C. Lower VCT pressure;
Start RCP #1, continue performing ES-O.2 until all RCS temperatures are less than 200°F,
then transition to GO-6, Unit Shutdown From Hot Standby To Cold Shutdown.
D. Lower VCT pressure;
Start the other 3 RCPs and immediatel y transition from ES-O.2 to GO- 6, Unit Shutdown
From Hot Standby To Cold Shutdown.
86 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
87
Given the following:
Unit 1 is at 100% power.
1-SI-99-10-B, 31 Day Functional Test of SSPS Train B and Reactor Trip Breaker B, is in
progress with Reactor Trip bypass breaker (BYB) closed.
Appendix F, Reactor Breaker Replacement. of 1-SI-99-1 O-B is in progress with Reactor
Trip Breaker B (RTB) racked out.
A feedwater transient occurs due to an electrical power loss , resulting in the MCR
operator MANUALLY tripping the reactor.
When Tavg , Pressurizer Pressure, and SG levels are stabilized post trip , the following
conditions are observed:
All 4 Diesel Generators running but NOT connected to the shutdown boards.
All Reactor Trip Breaker and Reactor Trip Bypass breaker indicating lights on 1-M-4 are
DARK except for the GREEN light on the Reactor Trip Bypass Breaker B (BYB) which is
LIT.
Which ONE of the following identifies both the position of Reactor Trip Breaker A (RTA) and the
correct SRO decision relative to completing 1-SI-99-10-B following the stabilization of the plant
and the electrical power restoration?
A.
B.
C.
D.
RTA Position
Closed
Closed
Tripped
Tripped
1-51-99-10-8 Status
The surveillance is required to be completed.
The surve illance is NOT required to be completed with the plant
in this Mode .
The surveillance is required to be completed.
The surveillance is NOT required to be completed with the plant
in this Mode.
87 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
88
Given the following:
Following a reactor trip the plant experienced a total loss of feedwater.
The condition caused the crew to initiate RCS bleed and feed .
SUbseque ntly the TDAFW pump was restored to service and the crew is ready to
establish AFW flow to the selected steam generator.
Other plant conditions includ e:
o
Selected SG Wide Range level is 4%.
o
RCS loop hot leg temperature at 558°F.
o
Core exit thermocouple temperatures are RISING.
In accordance with FR-H .1, Loss of Secondary Heat Sink, feedwater flow will be re-established
to the sele cted SG at ...
A.
the minimum detectable flow gpm .
B. less than 100 gpm until WR level >15%.
C. a rate that causes wide range leve l to rise and RCS hot leg to drop.
D. a maximum rate .
88 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
89
Given the following conditions:
The plant is shutdown In Mode 4 with all safety related equipment operable.
During the performance of surveillance 0-SI-215-21-A, DIESEL GENERATOR 1A-A
BATTERY QUARTERLY INSPECTION, it is reported that the Float Voltage values for
three (3) connected cells are as follows:
Cell 17 = 2.09 v
Cell 34 =2.06 v
Cell 39 =2.12 v
ALL other connected cells have Float Voltage values greater than 2.13 v.
ALL other parameters measured during the above surveillance are normal.
Which ONE of the following describes the status of DG 1A-A battery AND of the DG 1A-A?
REFERENCE PROVIDED
Status of Battery
A. Battery is degraded but it can
be considered operable for 31 days.
B. Battery is degraded but it can
be considered operable for 31 days.
C. Battery is inoperable.
D. Battery is inoperable.
NO Tech Spec or tracking only entry
required for DG.
Tech Spec tracking only entry required for DG.
DG is inoperable and Tech Spec tracking only
entry is required .
DG is inoperable and Tech Spec entry
is required.
89 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
90
Given the following conditions:
Unit 1 is operating at 100% power.
ERCW strainer 28 -8 plugs.
It is determined that the strainer must be isolated.
Which ONE of the following identifies the action directed by AOI-13, Loss of Essential Raw
Cooling Water, to mitigate the isolation of the 28 strainer and the PSA risk status the plant will
be in due to the strainer isolation?
AOI-13 actions
A.
Realign cooling water to the A train diesel generators.
8 .
Crosstie the 28 heade r with the 1A header until strainer is repaired .
C.
Realign cooling water to the A train diesel generators.
PSA risk
Orange
Orange
Red
D.
Crosstie the 28 header with the 1A header until strainer is repaired .
Red
90 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
91
Given the following plant condit ions:
During a startup, the plant is in Mode 4.
GO-1, Appendix C, Mode 4-to-Mode 3 Review and Approval, has been completed up to
the last step, Operations Superintendent Hold Point , for granting approval to enter Mode
3.
During scaffolding removal activities, a worker contacts the air line to 1-FCV-62-93,
Charging Flow Control Valve, resulting in pulling the air line loose from the valve
operator, such that the air system remains intact, due to crimp ing of the line on the air
supply side of the break .
Which procedures will the Unit Supervisor use to respond to this event and the basis for taking
quick action to limit the effects?
A.
The Unit Supervisor will use AOI-1 0, Loss of Control Air to direct actions to prevent
Pressu rizer level from exceeding 92% in order to maintain the presence of a steam
bubble in the pressurizer.
B.
The Unit Supervisor will use AOI-10, Loss of Control Air, and direct actions to prevent the
level decrease to less than 17% to ensure subcooling margin can be maintained.
C.
The Unit Supervisor will use SOI-62.01, CVCS-Charging and Letdown and direct actions
to prevent the level decrease to less than 17% to ensure subcooling margin can be
maintained.
D.
The Unit Supervisor will use SOI-62 .01, CVCS-Charging and Letdown, to direct actions to
prevent Pressurizer level from exceeding 92% in order to maintain the presence of a
steam bubble in the pressurizer.
91 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
92
Given the following:
Unit 1 was operating in Mode 1 at 14% reactor power.
A loss of condenser vacuum occurs resulting in an automatic turbine trip.
The operating crew stabilizes the plant.
Which ONE of the following identifies both how the condenser circulating water box t:.Ts will be
affected and the notifications required due to the turbine trip in accordance with SPP-3.5,
Regulatory Reporting Requirements?
Water Box t:.T
Notifications required
A.
Rises
Internal TVA notifications only
B.
Rises
NRC and Internal TVA notifications
C
Lowers
Internal TVA notifications only
D.
Lowers
NRC and Internal TVA notifications
92 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
93
Given the following:
At0100
At0200
At 1100
At 1200
Unit 1 entered Mode 3 during shutdown for a refueling outage.
AOI-7.01, Maximum Probable Flood, was implemented due to extremely
heavy rainfall in the upstream watershed .
The plant is in Mode 4 on RHR with cooldown in progress with the RCS
pressu re 320 psig and temperature 220
0 F.
River System Operations (RSO) confirms the flood level at the plant is
predicted to crest at EI. 730' within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Which ONE of the following identifies both the Flood Stage Preparation level(s) that is/are
required to be completed . and how the cooling of the core will be maintained in accordance with
AOI-7 after the preparations are complete?
A.
Only the proc edure for Stage 1 Preparations is required to be completed.
Core cooling will be maintained by the steam generators with water being supplied by high
pressure fire protection with the RHR system removed from service.
B.
Only the procedure for Stage 1 Preparations is required to be completed .
Core cooling will be maintained by the Spent Fuel Pool cooling system crosstied with the
RHR system.
C. Both Stage 1 and Stage 1/ Preparations procedures are required to be completed.
Core cooling will be maintained by the steam generators with water being supplied by high
pressure fire protection with the RHR system removed from service.
D. Both Stage 1 and Stage II Preparations procedures are required to be completed.
Core cooling will be maintained by the Spent Fuel Pool cool ing system crosstied with the
RHR system.
93 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
94
Which ONE of the following satisfies the requirement of FHI-7 for the maximum number of fuel
assembl ies allowed outside of approved storage?
A.
Two unirradiated assemblies within the fuel-handling area .
B.
Two irradiated assemblies within the spent fuel storage pool boundary.
C.
One assembly in the transfer cart, two assemblies in the RCCA fixture and one assembly in
the refueling machine mast over its proper location in the reactor vessel.
D.
One assembly in the transfer cart, two assemblies in the RCCA fixture and one assembl y in
the refueling machine mast over the reactor side upender.
94 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
95
With the plant at full power, the Chem istry Lab has just informed the Unit Supervisor that the
RCS chloride level is 1650 ppb and that the SG chloride level is 200 ppb. The source of any
impurity ingress has NOT yet been identified.
Based on the reported values, (1) what is the MOST restrictive Action Level that must be
entered and (2) the impact on plant operations caused by the Action Level entry?
ill
A.
Action Level 3 for RCS chloride level
B.
Action Level 3 for SG chloride level
C.
Action Level 2 for RCS Chloride level
D.
Action Level 2 for SG Chloride level
Initiate actions to take the reactor sub-critical
as quickly as practicable in a controlled
manner and reduce RCS temp erature to
< 250* F.
Initiate actions to take the reactor sub-critical
as quickly as practicable in a controlled
manner and reduc e RCS temperature to
< 250* F.
Restore parameter to below Action Level 1
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or reduce reactor power to less
than 5%.
Restore param eter to below Action Level 1
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or reduce reactor power to less
than 5%.
95 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
96
Given the following
Unit 1 at 100% power.
Diesel Generator (DG) 2A-A is to be removed from service for a maintenance outage
with a planned out of service of 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br />.
Which ONE of the following identifies Unit 1 equipment that is listed in Tech Spec 3.8.1, AC
Sources Operating, Bases Contingency Actions , as equipment that is to remain in service
concurrently during the DG 2A-A outage maintenance to be in compl iance with the Tech Spec?
A. Reactor trip breaker A (RTA).
B. TDAFW pump.
D. Any S/G AFW level control valve .
96 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
97
Which ONE of the following identifies BOTH the minimum decay time required to allow the
contents of a Gas Decay tank to decay prior to release and who can waive the minimum time in
accordance with SOI-77.02, Waste Gas Disposal system?
Decay Time Required
Who Can Waive
A.
60 days
Chemistry Duty Manager
B.
60 days
Radiation Prote ction Manager
C.
8 days
Chemistry Duty Manager
D.
8 days
Radiation Protection Manager
97 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
98
Given the following plant conditions:
Unit 1 is in Mode 4 with preparations being made for fuel moves.
As part of performing the Channel Operational Test (COT) for 0-RM-90-102, Spent Fuel
Pool Pit Area Monitor, a source check is to be performed.
What is the effect of performing the source check portion of this test, and what is the SRO 's
responsibility for Tech Spec/LCO Tracking Sheet entry?
A.
This will result in an automatic actuation of Train A of ABGTS. The SRO will make an entry
on the LCO Tracking Sheet that Train A of ABGTS is inoperable.
B.
RM-90-102 output will be blocked during the source check, the SRO will make an entry on
the LCO Tracking Sheet that Train A of ABGTS is inoperable.
C.
RM-90-102 output will be blocked during the source check, the SRO will make an entry on
the LCO Tracking Sheet that RM-90-1 02 is inoperable.
D.
This will result in an automatic actuation of Train A of ABGTS. The SRO will make an entry
on the LCO Tracking Sheet that RM-90-102 is inoperable.
98 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
99
Given the following:
Unit 1 experiences a Safety Injection due to a steam generator tube rupture on SG #1.
All Reactor Coolant Pumps were removed from service due to loss of support systems .
RCS cooldown at maximum rate to target incore temperature is in progress.
The STA reports that a RED path for FR-P.1, Pressurized Thermal Shock, exists on
RCS Loop 1 on the FR-O, Status Trees.
Which ONE of the following identifies when the transition to FR-P.1 should be made?
A. Immediately transition to FR-P.1 from E-3 because FR-P .1 provides actions to limit
cooldown and repressurization of the RCS.
B. Remain in E-3 until the cooldown is complete and then transition to FR-P .1 only if the RED
path still exists because the cooldown is needed to allow depressurization of the RCS.
C. Remain in E-3 until the cooldown is complete and then transition to FR-P .1 even if the RED
path no longer exists because the cooldown is needed to allow depressurization of the RCS.
D. Remain in E-3 until the safety injection is terminated, then transition to FR-P.1 only if the
RED path still exists because FR-P.1 provides actions to limit cooldown and repressurization
of the RCS.
99 of 100
Watts Bar Nuclear Plant
2008 Initial License Written Exam
SENIOR REACTOR OPERATOR
Question Number:
100
Given the following conditions:
The plant is at full power.
A report was received of a tornado being sighted over the Watts Bar Training Center,
movin g in a northwest direction . The tornado continued to move across Highway 68 and
then dissipated without touching down onsite.
The MCR crew has just entered AOI-8, Tornado Watch or Warning .
Confirmation was received that no visible damage had been received to any structu res
or equipment on site.
The Shift Manager evaluates the Radiological Emerg ency Plan (REP ) and determines
the conditions for an NOUE were initially met but are now fully resolved .
Which ONE of the following identifies the ODS and NRC notification requirements in
accordance with the REP?
A.
B.
C.
D.
ODS notification
Report but not declare
the event.
Report but not declare
the event.
Declare and terminate the
event at the same clock time.
Declare and terminate the
event at the same cloc k time.
NRC Notification required within:
15 minutes.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
15 minutes.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
100 of 100
Battery Ce ll Parameters
3 . 8 . 6
3 .8
ELECTRI CAL POWER SYSTEMS
3 . 8 . 6
Battery Cell Parameters
LCO
3 .8 .6
APPLICABILITY :
ACTI ONS
Battery cel l
parameters
f or
125 V v i t a l
batteries and
125 V
diesel generato r
(DG) batteries shall b e within the limits
of Table 3.8 .6-1 .
When associated
DC electrical p owe r
subsystems and DGs are
required to be OPERABLE .
- ------- --- ------ - --- - - - --- - ----NOTE--- - - - - - --- - - - --- - --- - - - ---- - - -------
Separate Conditi on entry is all owed for each battery bank.
A.
CONDI TI ON
One or more
batte ries with one
o r
more battery
cell parameters
not
within Category A
or B limits .
A.I
AND
A.2
AND
A .3
REQUIRED
ACTION
Ve r ify pilot
cells
e lectrolyte level and
f loat
v o l t a ge meet
Table
3 . 8 . 6- 1
Ca t e go r y C l i mi t s .
Ve r i f y battery cel l
parameters meet
Ta ble
3 .8. 6-1
Category C limits .
Restore battery c e l l
parameters
t o
Ca t e go r y A and B l i mi t s
o f Table
3 .8 .6- 1 .
COMPLETION TIME
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
24 hours
AND
Once pe r
7 days
thereafte r
31
d a y s
(continued)
Wat t s
Ba r - Uni t
1
3 .8 -33
ACTI ONS (cont i nued )
CONDIT ION
REQUIRED ACTION
Batter y Ce l l
Paramete rs
3.8 .6
COMPLETION TIME
B.
Re qui red Actio n
and a ss ociate d
Comp l e t i on Time
o f
Co nd i t i o n A no t
met .
One
o r
mo r e
batter i e s with
average
electrol yte
t emperature o f the
representati ve
c e l l s
< 60 °F f or
vital b a tte r i e s
and < 50°F f o r
ba t t eries.
One
o r
mor e
batteries wit h one
or more ba t te r y
cell parameters
no t
withi n
Category C v a l ues .
B.1
De clare as s ociate d
battery i noperab le.
I mme d i a t e l y
SURVEI LLANCE REQUIREMENTS
SURVEI LLANCE
FREQUENC Y
SR
3 . 8 .6 .1
Wa tts
Ba r-Un i t
1
Ve r i f y battery cel l
paramete r s
me e t
Table
3 .8 .6- 1 Ca tego ry A limits.
3 .8-3 4
7 days
(c ontinue d)
SURVEILLANCE REQUI REMENTS
(continue d)
SURVEILLANCE
Battery Ce l l
Pa r ameters
3 . 8 . 6
FREQUENCY
SR
3 .8 .6 .2
SR
3 .8 .6.3
Watts Ba r - Un i t
1
Ve r i fy battery c e l l
parame t ers meet
Table 3 .8 . 6- 1 Category B l imits .
Ve r i fy average el e ctrolyte
t e mpe r a t u r e
o f representative
c e l ls is
~ 60 °F f or
vita l batteries and
~ 50°F f or the
batteries.
3 .8 -35
92 days
AND
Onc e wi thin
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a
bat tery
discharge
< 11 0 V f or
v i t a l batteries
(113 . 5 V f o r
v i t a l
battery Vi
o r
106. 5 V f or
DG batteries
AND
Once
wi t h i n
24
hours a f ter a
batter y
ove rcha r ge
> 150 V f or
v i t a l batteri e s
(1 55 V f o r
vita l
batte r y V)
o r
1 45
V f or DG
batte rie s
92
da ys
Batte r y Cell
Pa r ame te r s
3 .8 .6
Table
3 . 8.6- 1
(p age 1 o f
1 )
Battery Ce l l
Parameters Requi rements
CATEGORY A:
CATEGORY B:
CATEGORY C:
PARAMETER
LI MITS FOR EACH
LI MITS FOR EACH
ALLOWABLE LIMIT
DESI GNATED PILOT
CONNECTED CELL
FOR EACH
CELL
CONNECTED CELL
Electro l yt e
Leve l
> Min imum level
> Min imum l evel
Above
t op o f
indicati on mark,
indication mark,
plate s,
and not
and s: 1/4 inch
and s: 1/4
inch
ove r flowi ng
above max imum
a bove ma xi mum
l evel indicati on
l evel indicati on
mark (a)
ma rk (a)
Float Vol t a ge
~ 2 . 13 V
~ 2 .13 V
> 2 .07 V
Spe c i fi c Gr avity
~ 1 . 200
~ 1 .195
Not more than
(b ) (c)
0. 02 0 be l ow
AND
ave rage of all
--
c onnected ce l l s
Average
o f all
connected cells
AND
--
> 1 . 205
Average o f all
c onnec t ed cell s
~ 1.195
(a )
It is a cceptable f or t he electrolyte level to tempora rily increase above
the specified max i mum level during e q ua l i z i ng cha r ges provided i t
i s not
ove r f lowi ng .
(b)
Co r rec t e d
f or electrolyte t e mpe ratu r e and leve l .
Level co r rect ion
i s
no t
r e q u i r e d ,
howe ve r,
when battery c ha r g ing is < 2 amps when on fl oat
charge
f o r
v i t a l batteries and < 1.0 amp
f or
DG batte ries.
(c )
A battery cha r g i ng c u r r e nt
o f
< 2 amps when o n f l oa t
c ha r ge
f o r
vital
bat t e r ies and < 1. 0 amp
f or
DG batte r i es
i s
a c cepta b le
f o r
meeting
s peci f i c gravi ty limits f ol l owi ng a batte ry
r e c ha r ge ,
f or a max i mum o f
31 da ys .
When c ha rg i ng current
i s used t o sati sfy spec i fic g ravi ty
requi rements , specif ic g ravity o f
each c onnected ce l l
shal l
be measured
p r i o r
t o expiration o f
t he
31 da y a llowance .
Watt s Bar-Unit 1
3 .8-3 6
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RO EXAM
1
C
2
0
3
C
4
A
5
B
6
C
7
0
8
C
9
0
10
B
11
C
12
A
13
0
14
C
15
0
16
C
17
C
18
A
19
C
20
C
21
A
22
C
23
C
24
A
25
B
26
C
27
A
28
A
29
B
30
0
31
C
32
B
33
C
34
B
35
A
36
B
37
B
38
0
39
A
40
0
41
0
42
A
43
C
44
A
45
0
46
C
47
0
48
B
49
C
50
C
Watts Bar 2008-301 Written Examination Key:
51
A
52
C
53
0
54
A
55
A
56
A
57
0
58
0
59
C
60
0
61
C
62
A
63
C
64
C
65
0
66
A
67
0
68
0
69
C
70
C
71
B
72
0
73
B
74
C
75
B
SRO EXAM
76
C
77
B
78
A
79
0
80
0
81
B
82
B
83
0
84
C
85
B
86
0
87
C
88
0
89
0
90
0
91
0
92
C
93
C
94
C
95
A
96
A
97
A
98
C
99
0
100
B