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| number = ML081140054 | | number = ML081140054 | ||
| issue date = 03/10/2008 | | issue date = 03/10/2008 | ||
| title = | | title = March 05000400/2008301 Final SRO Written Examination & References | ||
| author name = | | author name = | ||
| author affiliation = NRC/RGN-II | | author affiliation = NRC/RGN-II | ||
| Line 14: | Line 14: | ||
| page count = 89 | | page count = 89 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000400/2008301]] | ||
=Text= | =Text= | ||
{{#Wiki_filter:Final Submittal | |||
(Blue Paper) | |||
!-l~W..s Zto8-3 0 / | |||
IIV It-hA.t LtCeIlse. ?X~ | |||
3/JO - ~/13 t '512,( /241"8 | |||
FINAL SRO | |||
WRITTEN EXAMINATION | |||
AND REFERENCES | |||
ES-401 Site-Specific SRO Written Examination Form ES-401-8 | |||
Cover Sheet | |||
u.s. Nuclear Regulatory Commission | |||
Site-Specific SRO Written Examination | |||
Applicant Information I | |||
Name: I | |||
Date: 3/21/08 Facility/Unit: HARRIS PLANT I | |||
Region: I D II [XJ III D IV D Reactor Type: W[K] CE D BWD GE D I | |||
I | |||
Start Time: Finish Time: I | |||
Instructions ,I | |||
I | |||
Use the answer sheets provided to document your answers. Staple this cover sheet I | |||
on top of the answer sheets. To pass the examination you must achieve a final grade I | |||
of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items I | |||
if given in conjunction with the RO exam; SRO-only exams given alone require a final grade I | |||
of 80.00 percent to pass. You have 8 hours to complete the combined examination, I | |||
and 3 hours if you are only taking the SRO portion. I | |||
I | |||
I | |||
I | |||
Applicant Certification I | |||
I | |||
All work done on this examination is my own. I have neither given nor received aid. I | |||
I | |||
I | |||
I | |||
Applicant's Signature I | |||
Results I | |||
RO/SRO-OnlylTotal Examination Values I / Points I | |||
I | |||
Applicant's Scores I / Points I | |||
I | |||
Applicant's Grade / / Percent I | |||
I | |||
I | |||
ES-401, Page 31 of 33 | |||
Name: -~-------------------- | |||
Harris 2008 SRO Exam Rev FINAL | |||
Form: 0 | |||
Version: 0 | |||
1. | |||
Initial conditions: | |||
* Theplant is at 80% Reactor powerand ramping UP at 1/2% per minute. | |||
* Tave and Tref are matched. | |||
* Rod Control is in AUTOMATIC. | |||
Current conditions: | |||
* ONE (1) Control Bank 0 Rod has just dropped and is stuck at 170 steps. | |||
* All Other Control BankO Rods are currently indicating 206 Steps. | |||
Assuming NO operator action is taken, which ONE of the following describes the | |||
DEMAND forrod motion, and the effect on Axial Flux Difference (AFD) for the channel | |||
NEAREST the control rod problem? | |||
ROD MOTION AFDEFFECT | |||
A. Outward Less Negative | |||
B. Outward More Negative | |||
C. Inward Less Negative | |||
D. Inward More Negative | |||
Thursday, March 20,2008 10:36:58 AM 1 | |||
Harris 2008 SRO Exam Rev FINAL | |||
2. | |||
Initial Plant Conditions: | |||
* The plant is Solid. | |||
Current Plant Conditions: | |||
* A controller failure has caused 1CS-38, Letdown Pressure Control valve, to shut. | |||
* The crew has just entered AOP-019, Malfunction of RCSPressure Control. | |||
Which ONE of the following describes the effect of this malfunction on RCS pressure | |||
and the actions required lAW AOP-019 to mitigate this event? | |||
A. RCS Pressure will increase; | |||
Ensure the RCP Seal Water Return valves are open | |||
B. RCS<Pressure will increase; | |||
Secure the running CSIP | |||
C. RCS Pressure will decrease; | |||
Ensure the RCP Seal Water Return valves are shut | |||
D. RCSPressure will decrease; | |||
Increase charging flow to raise RCS pressure | |||
3~ | |||
The plant is operating at 100% power when one control rod drops fully into the core | |||
causing PowerRange N-41 to read lower than the other power range channels. | |||
Which ONE of the following is the expected QPTR response over the next two to six | |||
hours and why? | |||
A. QPTR will increase due to the buildup of Xenon in the dropped rod's fuel assembly. | |||
B. QPTR will decrease due to the buildup Xenon in the dropped rod's fuel assembly. | |||
c. QPTR will increase due to the change in temperature in the dropped rod's fuel | |||
assembly. | |||
D. QPTR*wili decreasedueto the change *in temperature. in the dropped rod's fuel | |||
assembly. | |||
Thursday, March 20, 2008 10:36:58 AM 2 | |||
Harris 2008 SRO Exam Rev FINAL | |||
4. | |||
Given the following: | |||
* A plant startup is in progress. | |||
* Reactor power is 20%. | |||
* "B" RCP trips. | |||
Which ONE ofthe followinq describes the effect on the reactor and "B" loop Tave? | |||
A. Reactor remains at power; | |||
Loop "B" Tave lowers due to Thot lowering to the value of Tcold. | |||
B. Reactor remains at power; . | |||
Loop "B"Tave rises due to the decreased flow in the "B" loop. | |||
C. Reactor automatically trips; | |||
Loop "B" Tave lowers due to Thot lowering to the value of Tcold. | |||
D. Reactor automatically trips; | |||
Loop "B" Tave rises due to the decreased flow in the "B" loop. | |||
A. Lowering the setpoint of the Letdown Temperature Control Valve, TCV-144, by 10 | |||
of. | |||
B. Raising the flow setting of the boric acid flow controller by 2 turns during a blended | |||
makeup to the VCT. | |||
C. Raising the setting of the blended makeup flow totalizer by 100 gallons total during | |||
a blended makeup to theVCT. | |||
D. Lowering the setting of the boric acid batch totalizer by20 gallons total during a | |||
blended makeup to theVCT. | |||
Thursday, March 20,2008 10:36:58 AM 3 | |||
Harris 2008 SRO Exam Rev FINAL | |||
6. | |||
Which ONE of the following sets of parameters and conditions will satisfy the interlocks | |||
to open the Residual Heat Removal Hot Leg Suction valves (1RH-1, 2,39, and 40)? | |||
A. RCS temperature is 345 of, | |||
RCS pressure is 365 psig, | |||
RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut, | |||
RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut. | |||
B. ReS temperature is 335 of, | |||
RCS pressure. 355 psig, | |||
RHRdischarge toCSIP valves, 1RH-25 and 1RH-63, are shut, | |||
-RHRsuction from RWST valves, 1RH-322 and 1RH-323, are shut. | |||
C. RCStemperatureis 345 of, | |||
RCS pressure 355psig, | |||
RHR suction fromRWSTvalves,1 RH-322 and 1RH-323, are shut. | |||
RHRsuction from Containment sump valves 181-300, 301, 310, and 311 are shut. | |||
D. RHR temperature is 335°F, | |||
RCSpressureis 365psig, | |||
RHR discharge toCSIP valves, 1RH-25 and 1RH-63, are shut, | |||
RHR suction from Containment sump valves 181-300, 301, 310, and 311 are shut. | |||
Thursday, March 20, 200810:36:58 AM 4 | |||
Harris 2008 SRO Exam Rev FINAL | |||
7. | |||
Given the following: | |||
* The plant is in Mode 4. | |||
* RHR Train "A"is in service. | |||
* RHR Heat Exchanger Bypass Valve 1RH-20 is in automatic with the output at | |||
40% to maintain 3750 GPM. | |||
* RHRHeat Exchanger outlet valve 1RH-30demand position is set at30°k>. | |||
* The Instrument Air supply line to RHRHeat Exchanger Outlet Valve | |||
1RH-30< becomes severed .and is completely detached. | |||
* No other air operated valves are impacted by the failure. | |||
Which ONE of the foUowingdescribes the RHRsystemparameter changes from the | |||
initial steady state condition to final steady state condition? | |||
RHRHX Outlet Temp Total RHR flow | |||
A. Higher Lower | |||
B. Higher Higher | |||
c. Lower Higher | |||
D. Lower Lower | |||
Thursday, March 20, 200810:36:58AM 5 | |||
Harris 2008 SRO Exam Rev FINAL | |||
8. | |||
Given the following: | |||
* A reactor trip and safety injection have occurred. | |||
* RCS pressure is 1OOOpsig and lowering. | |||
* "A"*.CSIP fails to operate. | |||
* All other equipment operates as designed. | |||
Which ONE of the following describes the expected MCB Charging Flow indication | |||
(FI-122.1), and the Safety Injection flow indication (FI-943)? | |||
A. MCBCharging flow 0 gpm; | |||
Safety Injection flow is approximately 600 gpm | |||
B. MCBCharging flow 0 gpm; | |||
Safety Injection flow is approximately 450 gpm | |||
C. MCB Charging flow approximately 150 gpm; | |||
Safety Injection flow is approximately 150 gpm | |||
D. MCBChargingflow approximately 150 gpm; | |||
Safety Injection flow is approximately 450 gpm | |||
}} | }} | ||
Latest revision as of 17:32, 14 November 2019
| ML081140054 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/10/2008 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-400/08-301 | |
| Download: ML081140054 (89) | |
See also: IR 05000400/2008301
Text
{{#Wiki_filter:Final Submittal
(Blue Paper)
!-l~W..s Zto8-3 0 /
IIV It-hA.t LtCeIlse. ?X~
3/JO - ~/13 t '512,( /241"8
FINAL SRO
WRITTEN EXAMINATION
AND REFERENCES
ES-401 Site-Specific SRO Written Examination Form ES-401-8
Cover Sheet
u.s. Nuclear Regulatory Commission
Site-Specific SRO Written Examination
Applicant Information I
Name: I
Date: 3/21/08 Facility/Unit: HARRIS PLANT I
Region: I D II [XJ III D IV D Reactor Type: W[K] CE D BWD GE D I
I
Start Time: Finish Time: I
Instructions ,I
I
Use the answer sheets provided to document your answers. Staple this cover sheet I
on top of the answer sheets. To pass the examination you must achieve a final grade I
of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items I
if given in conjunction with the RO exam; SRO-only exams given alone require a final grade I
of 80.00 percent to pass. You have 8 hours to complete the combined examination, I
and 3 hours if you are only taking the SRO portion. I
I
I
I
Applicant Certification I
I
All work done on this examination is my own. I have neither given nor received aid. I
I
I
I
Applicant's Signature I
Results I
RO/SRO-OnlylTotal Examination Values I / Points I
I
Applicant's Scores I / Points I
I
Applicant's Grade / / Percent I
I
I
ES-401, Page 31 of 33
Name: -~--------------------
Harris 2008 SRO Exam Rev FINAL
Form: 0
Version: 0
1.
Initial conditions:
* Theplant is at 80% Reactor powerand ramping UP at 1/2% per minute.
* Tave and Tref are matched.
* Rod Control is in AUTOMATIC.
Current conditions:
* ONE (1) Control Bank 0 Rod has just dropped and is stuck at 170 steps.
* All Other Control BankO Rods are currently indicating 206 Steps.
Assuming NO operator action is taken, which ONE of the following describes the
DEMAND forrod motion, and the effect on Axial Flux Difference (AFD) for the channel
NEAREST the control rod problem?
ROD MOTION AFDEFFECT
A. Outward Less Negative
B. Outward More Negative
C. Inward Less Negative
D. Inward More Negative
Thursday, March 20,2008 10:36:58 AM 1
Harris 2008 SRO Exam Rev FINAL
2.
Initial Plant Conditions:
* The plant is Solid.
Current Plant Conditions:
* A controller failure has caused 1CS-38, Letdown Pressure Control valve, to shut.
* The crew has just entered AOP-019, Malfunction of RCSPressure Control.
Which ONE of the following describes the effect of this malfunction on RCS pressure
and the actions required lAW AOP-019 to mitigate this event?
A. RCS Pressure will increase;
Ensure the RCP Seal Water Return valves are open
B. RCS<Pressure will increase;
Secure the running CSIP
C. RCS Pressure will decrease;
Ensure the RCP Seal Water Return valves are shut
D. RCSPressure will decrease;
Increase charging flow to raise RCS pressure
3~
The plant is operating at 100% power when one control rod drops fully into the core
causing PowerRange N-41 to read lower than the other power range channels.
Which ONE of the following is the expected QPTR response over the next two to six
hours and why?
A. QPTR will increase due to the buildup of Xenon in the dropped rod's fuel assembly.
B. QPTR will decrease due to the buildup Xenon in the dropped rod's fuel assembly.
c. QPTR will increase due to the change in temperature in the dropped rod's fuel
assembly.
D. QPTR*wili decreasedueto the change *in temperature. in the dropped rod's fuel
assembly.
Thursday, March 20, 2008 10:36:58 AM 2
Harris 2008 SRO Exam Rev FINAL
4.
Given the following:
* A plant startup is in progress.
* Reactor power is 20%.
* "B" RCP trips.
Which ONE ofthe followinq describes the effect on the reactor and "B" loop Tave?
A. Reactor remains at power;
Loop "B" Tave lowers due to Thot lowering to the value of Tcold.
B. Reactor remains at power; .
Loop "B"Tave rises due to the decreased flow in the "B" loop.
C. Reactor automatically trips;
Loop "B" Tave lowers due to Thot lowering to the value of Tcold.
D. Reactor automatically trips;
Loop "B" Tave rises due to the decreased flow in the "B" loop.
A. Lowering the setpoint of the Letdown Temperature Control Valve, TCV-144, by 10
of.
B. Raising the flow setting of the boric acid flow controller by 2 turns during a blended
makeup to the VCT.
C. Raising the setting of the blended makeup flow totalizer by 100 gallons total during
a blended makeup to theVCT.
D. Lowering the setting of the boric acid batch totalizer by20 gallons total during a
blended makeup to theVCT.
Thursday, March 20,2008 10:36:58 AM 3
Harris 2008 SRO Exam Rev FINAL
6.
Which ONE of the following sets of parameters and conditions will satisfy the interlocks
to open the Residual Heat Removal Hot Leg Suction valves (1RH-1, 2,39, and 40)?
A. RCS temperature is 345 of,
RCS pressure is 365 psig,
RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut,
RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut.
B. ReS temperature is 335 of,
RCS pressure. 355 psig,
RHRdischarge toCSIP valves, 1RH-25 and 1RH-63, are shut,
-RHRsuction from RWST valves, 1RH-322 and 1RH-323, are shut.
C. RCStemperatureis 345 of,
RCS pressure 355psig,
RHR suction fromRWSTvalves,1 RH-322 and 1RH-323, are shut.
RHRsuction from Containment sump valves 181-300, 301, 310, and 311 are shut.
D. RHR temperature is 335°F,
RCSpressureis 365psig,
RHR discharge toCSIP valves, 1RH-25 and 1RH-63, are shut,
RHR suction from Containment sump valves 181-300, 301, 310, and 311 are shut.
Thursday, March 20, 200810:36:58 AM 4
Harris 2008 SRO Exam Rev FINAL
7.
Given the following:
* The plant is in Mode 4.
* RHR Train "A"is in service.
* RHR Heat Exchanger Bypass Valve 1RH-20 is in automatic with the output at
40% to maintain 3750 GPM.
* RHRHeat Exchanger outlet valve 1RH-30demand position is set at30°k>.
* The Instrument Air supply line to RHRHeat Exchanger Outlet Valve
1RH-30< becomes severed .and is completely detached.
* No other air operated valves are impacted by the failure.
Which ONE of the foUowingdescribes the RHRsystemparameter changes from the
initial steady state condition to final steady state condition?
RHRHX Outlet Temp Total RHR flow
A. Higher Lower
B. Higher Higher
c. Lower Higher
D. Lower Lower
Thursday, March 20, 200810:36:58AM 5
Harris 2008 SRO Exam Rev FINAL
8.
Given the following:
* A reactor trip and safety injection have occurred.
* RCS pressure is 1OOOpsig and lowering.
* "A"*.CSIP fails to operate.
* All other equipment operates as designed.
Which ONE of the following describes the expected MCB Charging Flow indication
(FI-122.1), and the Safety Injection flow indication (FI-943)?
A. MCBCharging flow 0 gpm;
Safety Injection flow is approximately 600 gpm
B. MCBCharging flow 0 gpm;
Safety Injection flow is approximately 450 gpm
C. MCB Charging flow approximately 150 gpm;
Safety Injection flow is approximately 150 gpm
D. MCBChargingflow approximately 150 gpm;
Safety Injection flow is approximately 450 gpm
Thursday, March 20, 2008 10:36:58 AM 6
Harris 2008 SRO Exam Rev FINAL
9.
Given the following:
* "A" Train equipment is in service.
* A Reactor Trip occurs.
* All equipment is operating as designed.
* The crew is performing actions of Path-1.
* Conditions are as follows:
CH II CHIli
- - CH IV
PZR press. 1865psig 1865 psig 1845 psig NA
CNMTpress. 2.9 psig 3.1 psig 3.1 psig 2.9 psig
Which ONE of the following describes the status Of the Charging Safety Injection
Pumps?
A. Both CSIPs are running due to SI signal on low PZR pressure.
B. Both CSIPs are funning due to SI signal on high Containment pressure.
C. Only "A" CSIPis running, but "B" CSIP will be started automatically if the additional
requiredPZR pressure transmitter reaches the SI actuation setpoint.
D. Only "A" CSIP is running, but "B" CSIP will be started automatically if if the
additional requiredCNMT pressure transmitter reaches the SI actuation setpoint.
Thursday, March 20, 2008 10:36:58 AM 7
Harris 2008 SROExam Rev FINAL
10.
Initial Conditions:
* With the plant operating.at 1000/0 power and all equipment in its normal
lineup, the ROtakes the Reactor Trip switch to the TRIP position.
Current plant conditions are:
* Reactor Trip Breaker "A" Red indication exists.
* Reactor Trip BreakerB" Green indication exists.
* Reactor Power is 4% and lowering.
* Rod bottom lights are lit with the exception of FOUR Control BankD rods.
Their positions are as follows:
* H-8 - 16 steps
* K-2 - 220 steps
* M-12 - 8 steps
* M-8 - 20 steps
Which ONE of the following describes the condition of the reactor, and the action that
will be required?
A. The reactor is tripped;
Perform normal RCSboration for the stuck rods as directed by EPP-004
referencing OP-107, Charging and Volume Control System.
B. The reactor is tripped;
Initiate emergency boration for the stuck rods as directed by EPP-004 referencing
AOP-002, Emergency Boration.
C. The reactor is not tripped;
Manually insert control rods in accordance with FRP-S.1 until all rods are on
bottom.
D. The reactor is not tripped;
Initiate emergency boration for the stuck rods in accordance with FRP-S.1 until
adequate Shutdown Margin is verified.
Thursday, March 20, 2008 10:36:58 AM 8
Harris 2008 SROExam Rev FINAL
11.
Given the following:
* The plant is at 1000/0 power.
* A PressurizerPORV has a slow leak through the seat or disk.
* The respective PORV isolation valve cannot be closed.
* ALB-009-8.-1, PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR
TEMP, is actuated.
* PRT Level is 73%.
* PRT Temperature is 128 of.
* PRT Pressure is6.3 Psig.
Which ONEiofthefollowing parameters is causing the alarm, and which ONE of the
following is the action required to be performed from OP-100, Reactor Coolant System,
Section 8, InfrequentOperations?
A. Pressure;
Vent thePRT as necessary to control pressure.
B. Pressure;
Drain the PRTas necessary to control pressure while maintaining level within the
normal-band.
C. Temperature;
Recirculate the PRT contents through the RCDT Heat Exchanger to lower
temperature.
D. Temperature;
Drain PRT to the low end of the normal band and then refillwith demineralized
water to lowertemperature.
Thursday, March 20, 200810:36:58 AM 9
Harris 2008 SRO Exam Rev FINAL
12.
Given the following:
* The plant is at 1000/0 power.
* The temperature input to Letdown Heat Exchanger CCW flow control valve
TCV-144, fails low.
Which ONE of the following describes the impact on the plant and the action that is
required by the appropriate Annunciator Panel Procedure (APP)?
A. High CCW flow to Letdown Heat Exchanger;
Place TCV-144in manual and adjust flow to restore normal cooling.
B. High CCWfiow to Letdown Heat Exchanger;
Isolate letdown and place Excess Letdown in service.
C. High temperature letdown diversion to VCT;
Place TCV-144 in manual and adjust flow to restore normal cooling.
D. High temperature letdown diversion to VCT;
Isolate letdown and place Excess Letdown in service.
13.
Given the following:
* A reactortrip has occurred from 1000/0 power.
* Pressurizer pressure is 2050 psig and lowering.
* Pressurizer level is rising rapidly.
* Containment pressure is 1 psig and slowly rising.
Assuming NO operator action, which ONE of the following could have caused the
event in proqress?
A. Master Pressure Controller PT-444 output failed LOW
B. Both Pressurizer Spray Valves failed OPEN
C. Master Pressure Controller PT-444 output failed HIGH
D. Small break LOCAon an*RCS Hot Leg
Thursday, March 20, 200810:36:59AM 10
Harris2008SRO Exam Rev FINAL
14.
Given*thefollow.ing:
* A reactor trip has occurred.
* Safety Injection is actuated.
* All actions required in Path-1 have been taken.
* All RCPs are running.
* RCS pressure is 1450 psigand stable.
* Sifiow is 150 GPM.
* Containment pressure Is4.5 psig and slowly rising.
* SG pressures are 1050psig and stable.
Which ONE of the following describes the plant condition upon transition from Path-1?
A. RC.Ps should NOT be tripped.
SGs are required for subsequent RCS heat removal.
B. RCPsshould NOT be tripped.
SGs are NOT required for subsequent RCS heat removal.
C. RCPs should be.tripped.
SGs are-required for subsequent RCS heat removal.
D. RCPsshouldbe tripped.
SGs are NOT required for subsequent RCS .heat removal.
Thursday, March 20, 2008 10:36:59 AM 11
Harris 2008 SRO Exam Rev FINAL
15.
Initial Plant Conditions:
* The plant was at 100% power.
Currentplantcond itions are:
* A Loss of Off-site Power occurs.
* Bus 1A-SA is locked out.
* All other equipment has operated as designed.
* Diesel loading sequence is complete.
* RCS pressure is 2180 psig.
Assuming NO operator action has been taken, which ONE of the following describes
the status of the PZR Heaters?
A. ALL PZR Backup Heaters are DE-ENERGIZED.
B. Group B is the onlyPZRh.eater group ENERGIZED.
C. Group C is.the only PZR heater group ENERGIZED.
D. Groups Band C are the only PZR heater groups ENERGIZED.
Thursday, March 20, 2008 10:36:59 AM 12
Harris 2008 SRO Exam Rev FINAL
16.
Which ONE of the following describes the characteristics of a design basis Large Break
LOCA twenty (20) minutes into the event?
A. RCS temperature is at saturation temperature for intact SG pressure;
RCSpressure is stable below normal SI accumulator pressure, but above RHR
pump shutoff head.
B. ReS temperature is at saturation temperature for intact SG pressure;
RCSpressure is stable below RHR Pump shutoff head.
C. RCS temperature is below saturation temperature for intactSG pressure;
Res pressure is stable below normal SI accumulator pressure, but above RHR
pump shutoff head.
D. RCS temperature is below saturation temperature for intact SGpressure;
RCS pressure is stable below RHRPump shutoff head.
* The unit is at 100 % power.
* Unit electrical .aliqnment is normal.
* Aux Bus 1D deenergizes and is locked out.
Which ONE of the following loads will de-energize and automatically re-energize?
A. "A" .NSW* Pump
B. "B" NSW Pump
C. "A" CSIP
D. "B" CSIP
Thursday, March 20, 2008 10:36:59 AM 13
Harris 2008 SRO Exam Rev FINAL
18.
Given the following:
eTheplantis operating at 30% reactor power, steady state.
e I&Cotechniciansarepreparing to perform a calibration on Power Range Channel
N-41. .
e One I&C technician mistakenly pulls the control power fuses on N-42.
e Realizing his mistake, he reinserts the fuses for N-42 and then pulls the control
power fuses for the correct channel, N-41.
Which ONE of the following describes the status of the reactor after the N-41 fuses
were pulled and which bistable(s) in N-42 would be tripped?
A. The reactor is tripped;
PRPositive Rate Trip and PRNegative Rate Trip.
B. The reactor is tripped;
PRPostive Rate -Trip ONLY.
C. The reactor is NOT tripped;
PR Positive Rate Trip and PR Negative Rate Trip.
D. The reactor is NOT tripped;
PRPositiveRate Trip ONLY
19.
Given the following:
e Pressurizer Pressure Protection Channel PT-455 has failed off-scale HIGH.
e NO Operator action has been. taken.
Which ONE of the following identifies the MINIMUM additional channels required to
meet the ESF andRPS actuation logic to initiate a reactor trip and safety injection on
Press urizerP ress ure?
A. Reactor Trip-1; Safety Injection - 1
B. ReactorTrip-1 ;Safetylnjection-2
C. ReactorTrip- 2; Safety Injection -1
D. Reactor Trip .. 2; Safety Injection - 2
Thursday, March 20, 2008 10:36:59 AM 14
Harris 2008 SRO Exam Rev FINAL
20.
Given the following:
* A LOCA has occurred.
* RCS. pressure is 200 psig.
* "A" Containment Spray Pump is Out of Service.
* Containment pressure is 12 psigand slowly increasing.
* Train "B" Phase A has failed to actuate.
* Normal Containment Purge was in service atthetime of the LOCA.
* The Containment Ventilation Isolation Signal (CVIS) fails to actuate.
* All other ECCS equipment is running as required.
Assuming no action by the crew, which ONE of the following describes the effect on
the plant?
A. Containment Normal.PurgeMakeup fans will trip and their associated dampers
SHUT.
B. Offsite dose consequences. will exceed the guidelines of 10CFR100.
C. Normal Containment Purge Makeup valves (1CP-6 and 9) will remain OPEN.
D. Only half of the Containment penetrations required for containment isolation will be
isolated.
21.
Given the following:
* The plantisat20% power.
* Rod Control is in AUTO.
* The operating crew is preparing to stop RCP 1C'due to rising vibration.
Assuming that reactor power is maintained at200JO, which ONE of the following
describes the expected indications on Loop 1 and Loop 3 flowrates when RCP 1C is
stopped?
Loop 1 Flowrate Loop 3 Flowrate
A. increase to 11 0°/0 decreases to ooJO and stabilizes
B. increase to 110% decreases to 0% then increases to 100/0
C. increase to 1200/0 decreases to 00/0 and stabilizes
D. increase to 1200/0 decreases to 0% then increases to 10%
Thursday, March 20,2008 10:36:59 AM 15
Harris 2008 SRO Exam Rev FINAL
22.
Given the following:
* The plant is at 600/0 power during a plant startup.
* Steam Dumps are in the Tave mode of control.
* First Stage Pressure TransmitterPT-446 fails high.
Assuming the reactor remains at power, which ONE of the following describes the
effect on the steam dump system?
A. Steam Dumps will receive an arming signal.
B. Steam Dumps will receive a modulation (open) signal.
C. Steam Dumps will NOT arm if required.
D. Steam Dumps will NOT modulate if required.
23.
Given the following:
* The crew is performing EPP-004, Reactor Trip Response.
* .Natural circulation verification is in progress.
* Core Exit Thermocouples G2 and K5havefailed due to open circuits.
With these open circuit failures, the input from these thermocouples to the Inadequate
Core Cooling.Monitor(ICCM)willbe and the subcoolng margin
calculated bylCCM will be _
A. failed low;
higher
B. failed low;
unaffected
C. failed high;
lower
D. failed high;
unaffected
Thursday, March 20, 200810:36:59AM 16
Harris 2008 SRO Exam Rev FINAL
24.
Initial.Conditions:
* Containment Cooling isin the Normal Cooling Mode of operation with Train "A"
in service.
* Containment temperature has been slowly rising.
Current Conditions:
* The crew has placed the Containment Cooling system in Maximum Cooling
Mode per OP-169, Containment Cooling System.
* Containment temperature is now lowering.
Which ONE of the following identifies the MINIMUM temperature at which a Technical
Specification action statement must be entered and the expected alignment for the
Containment Cooling System?
A. 118°F
BOTH fans in AH-3 and AH-4 in high speed AND ONE (1) faninAH-1 and AH-2 in
high speed. \
B.118°F
BOTH fans in AH-3 andAH-4 in high speed AND BOTH fans in AH-1 and AH-2 in
high speed.
C. 120 OF
BOTHfansinAH-3 and AH-4 in high speed AND ONE (1) fan in AH-1 and AH-2 in
high speed.
D. 120 OF
BOTH fans inAH-3and AH-4 in high speed AND BOTH fans inAH-t and AH-2 in
high speed.
Thursday, March 20,2008 10:37:00 AM 17
Harris 2008 SRO Exam Rev FINAL
25.
Given the following:
* The plant is at 100% power. *
* VCT level Channel LT-112 fails high.
Assuming NO operator action, which ONE of the following describes the function(s)
lostduetothisfailure?
A. ONlYDivertto RHT will be disabled
B. ONLY AutoSwapover from RWST will be disabled.
C. Auto Swapover from .RWSTAND Auto Makeup will be disabled.
D. Divert toRHT AND Auto Makeup will be disabled.
Thursday, March 20, 20081 0:37:00 AM 18
Harris 2008 SROExam Rev FINAL
26.
Initial conditions:
* The plant isat1 000/0 power.
* Train "B" Containment Fan Cooling is in service.
Current conditions:
* A Safety Injection signal has occurred.
* All equipment is operating as designed.
Which ONE of the following describes the operation of Containment Cooling?
One fan in each Fan Cooler Unit is operating in...
A. LOW speed;
Normal Service Water aligned.
B. HIGH speed;
Normal Service Water aligned
C. LOW speed;
Emergency Service Water aligned
D. HIGH speed;
Emergency Service Water aligned
Thursday, March 20, 200810:37:00 AM 19
Harris 2008 SROExam Rev FINAL
27.
Initial conditions:
* "A" Boric Acid pump is under clearance for motor replacement.
Current conditions:
* 1B-SBEmergency Safety Bus locks out due to an 86UV failure.
* The crew is performing an Emergency Boration in accordance with AOP-002,
Emergency Boration, due to. a secondary load rejection.
* The ROperforms the required valve alignment to provideaboration source.
Which ONE of the following describes the action and/or verification required to ensure
that the requiredboration flow is achieved?
A. Verifyaminimumof30GPMon FI-110,Emergency Boration flow.
B. Verify a minimum of 30GPM on FI-113,Boric Acid flow.
C. Adjust FCV-122 as necessary to achieve a minimum of 30 GPM onFI-122.1,
Charging Header flow.
D. Adjust FCV-122 as necessary to achieve a minimum of 90 GPM on FI-122.1,
Charging Header flow.
Thursday, March 20, 200810:37:00 AM 20
Harris 2008 SRO Exam Rev FINAL
28.
Given the following:
* The plant is in Mode 5.
* An RCSleak and lossofRHR occurs..
* The crew is performing actions of AOP-020, Loss of RCS Inventory or Residual
Heat Removal While Shutdown.
* The crew is aligning to provideRCSMakeup using CSIP flow in accordance with
section 3.6, EstabHshingSI Following a Major RCS Leak.
Which ONE of the following describes the required actions to provide RCSmakeup in
this condition?
A. Start ONE (1)CSIP;
initiate flow though the BIT
B. Start ONE(1)CSIP;
Initiate flowthoughthenormal charging line
C. Start TWO (2) CSIPs;
Initiate flow though the BIT
D. Start TWO (2)CSIPs;
Initiate flowthouqhthenormal charging line
Thursday, March 20, 2008 10:37:00 AM 21
Harris 2008 SRO Exam Rev FINAL
29.
Initial Cond itions:
* Surveillance testing is in progress on Containment Spray Train "A".
* "A" Containment Spray Pump is running.
* 1CT-24-SAand.1CT-25-SB, Containment Spray Eductor Test Valves, are open
for. testing.
* 1CT.:.50-SA,ContainmentSpray Pump 1A-SA Discharge Valve, is closed.
Current conditions:
* A LOCA occurs.
* RCS pressure is 600 psig.
* Containment Pressure is 10.5psig.
Which ONE of the following correctly lists the position of the Containment Spray
Eductor Test Valves and the 1A-SA Discharge Valve for the current plant conditions?
1CT-24-SA and 1CT-25-SB 1CT-50-SA
A. OPEN OPEN
B. CLOSED OPEN
C. OPEN CLOSED
D. CLOSED CLOSED
Thursday, March 20, 2008 10:37:00 AM 22
Harris 2008 SRO Exam Rev FINAL
30.
Given the following:
The plant is in Mode 1.
12:00 Containment Spray Pump 1A-SA declared INOPERABLE due to a failed
surveillance.
12:27 Containment Spray Pump 1B-SB also declared INOPERABLE due to the
results ofa common cause failure analysis.
14:21 ContalnrnentSprayPump 1A-SA returned to OPERABLE status.
14:40 Containment Spray Pump 1B-SB returned to OPERABLE status.
Which ONE of the following describes the Technical Specification requirements for
operation of the plant?
Actions to initiate a plant shutdown must commence no later than ...
A. 12:27;
The shutdown maybe terminated no earlierthan 14:21.
B. 12:27;.
The shutdown may be terminated no earlier than 14:40.
C. 13:27;
The shutdown maybe terminated no earlier than 14:21.
D. 13:27;.
The shutdown maybe terminated no earlier than 14:40.
Thursday, March 20, 200810:37:00 AM 23
Harris 2008 SRO Exam Rev FINAL
31.
Given the following:
* The plant is operating at 100 % power.
* A failure of thePT-444 input to PK-444A, Pressurizer Pressure Master
Controller, caused actual pressurizer pressure to decrease to 2190 psig.
* PK-444Ahas been placed in MANUAL..
Which ONE of the following describes the action required to return pressure to 2235
psig?
A. Decrease the controller output.
B. Increase the controller output.
C. Lower the pressure setpoint adjustment.
D. Raise the pressuresetpoint adjustment.
Thursday, March 20, 2008 10:37:00 AM 24
Harris 2.008 SRO Exam Rev FINAL
32.
Given the following:
* The unit is in Mode 6.
* Refueling activities are in progress.
* A fuel assembly has been ruptured during removal from the core.
* Radiation levels are rising steadily and are currently as follows:
* REM-01 LT-3502A-SA, Cnmt RCS Leak Detection Monitor, is in HIGH
ALARM
* REM-01 LT-3502B-SB, Cnmt Pre-Entry Purge Monitor, is in HIGH
ALARM
Which ONE of thefoHowing describes the system isolation signal(s), if any, that have
been automatically initiated, and action required in' accordance with AOP-013, Fuel
Handling Accident?
A. ONLY a Containment Pre-Entry Purge isolation signal has been initiated.
Perform an evacuation from Containment.
B. BOTH Normal Containment Purge AND Containment Pre-Entry Purge isolation
signals have been initiated.
Perform an evacuation from Containment.
C. ONLY a Containment Pre-Entry Purge isolation signal has been initiated.
Dispatch Radiation Protection to determine if Containment Evacuation is required.
D. BOTH Normal Containment Purge AND Containment Pre-Entry Purge isolation
signals have been initiated.
Dispatch Radiation Protection to determine if Containment Evacuation is required ..
Thursday, March 20, 2008 10:37:00 AM 25
Harris 2008 SRO Exam Rev FINAL
33.
Given the following:
* The plant is at 100% power.
* A transient on SGlevel required a reactor trip, but the reactor did not trip.
* The crew is performing FRP-S.1, Response To Nuclear Power Generation /
ATWS.
* The crew notes that the Pressurizer pressure is 2350 psig.
* Control rods are inserting in AUTO.
* All Pressurizer PORVvaive position indicating green lights are on and red
lights are off.
Which ONE ofthe following actions are required in relation to thePZR PORVs?
A. Verify ONLY ONE Pressurizer PORVand Block valve OPEN;
reduce pressure to less than 2135psig.
B. Verify ALL Pressurizer .PORVs and Block valves OPEN;
reduce pressure to less than 2135 psig.
c. Verify ONLY ONE Pressurizer PORV and Block valve OPEN;
reduce pressure to less than 2235 psig.
D. Verify ALL Pressurizer PORVsand Block valves OPEN;
reduce pressure to less than 2235 psig.
Thursday, March 20,200810:37:00 AM 26
Harris 2008SRO Exam Rev FINAL
34.
Given the following:
* The plant is at40%power.
* Intermediate Range Channel N-35 loses compensating voltage.
* I&Ciscalied to investigate.
* Prior to any action by I&C, a reactor trip occurs.
Which ONE of the following describes the expected Source Range response in this
condition and why?
A. Source Range Instruments wilJ automatically energize prematurely; they must be
manually de-energized until approximately 5 minutes post-trip to prevent damage to
the detectors.
B. Source Range Instruments will automatically energize prematurely; they must be
manually de-energized until approximately 15 minutes post-trip to prevent damage
to the detectors.
C. Source Range Instruments will not automatically energize when required; they must
be manually energized approximately 5 minutes post-trip to prevent a loss of
reactor power indication. .
D. SourceRanqelnstruments wilJ not automatically energize when required; they must
be manually energized approximately 15 minutes post-trip to prevent a loss of
reactor power indication.
Thursday, March 20, 20081 0:37:00 AM 27
Harris 20'08SRO Exam Rev FINAL
35.
Initial plant conditions:
* The plant isin Mode.6 with Refueling in progress.
Current plant conditions are:
* Fuel movement has stopped due to a problem with the Manipulator.
* The Main Control Room has been informed that initial troubleshooting is in
progress on the Manipulator.
* The troubleshooting team desires to operate TS-5, the TROLLEY INTERLOCK
BYPASS switch to permit forward and reverse motion of the trolley without the
gripper tube at its top limit.
Which ONE of the following describes the permission and concurrence, if any, required
for this action?
A. The SRO~FueIHandlingmustapprove. No concurrenceis required.
B. TheSRO-Fuel Handling must approve with the concurrence of the SSO.
C. The SSO must approve with concurrence of the Manager -Mechanical
Maintenance.
D. The SSG must approve. No concurrence is required.
Thursday, March 20, 2008 10:37:00 AM 28
Harris 2008 SRO Exam Rev FINAL
36.
Given the following:
* Refueling isin progress.
* A spent fuel assembly is being moved inthe Fuel Handling Building (FHB) when
it's damaged by contacting a wall of the pool.
* Spent Fuel Pool area radiation monitor RM-1 FR-3566A-SA is in HIGH alarm.
* Spent Fuel Pool area radiation monitor RM-1 FR-3567B-SB is in ALERT.
Which ONE of the following describes the effect on the plant?
A. ONLY "A" train of Fuel Handling Building Ventilation Emergency Exhaust has
received an automatic start signal.
B. BOTH "A"and "B"trains of Fuel Handling Building Ventilation Emergency Exhaust
have received automatic start signals.
c. NEITHER train of Fuel Handling Building Ventilation Emergency Exhaust has
received an automatic start signal, and manual start is NOT required.
D. NEITHERtrainof Fuel Handling Building Ventilation Emergency Exhaust has
received an automatic start signal, but manual start is required byAOP-013, Fuel
Handling Accident.
Thursday, March 20, 20081 0:37:01 AM 29
Harris 2008 SRO Exam Rev FINAL
37.
Given the following:
* A Steam Generator Tube Rupture has occurred.
* Off-Site power has been lost.
* BothDG's are operating as required.
* Pressurizer level indicates 10% and lowering slowly.
* All plant equipment hasrespondedas expected for the plant conditions.
Which ONE of the following describes a plant concern during the performance of
Path-2 for these conditions?
A. Voiding in the inactive regions of the RCS during the rapid RCS cooldown to target
temperature.
B. Loss of RCSsubcoolingduring depressurization using main or auxiliary spray.
C. Voiding in the inactive regions of the RCS during depressurization using a PZR
PORV.
D. Loss of RCSsubcoolingdue.to the time required to cooldown to target temperature
with condenser steam dumps unavailable.
Thursday, March 20, 2008 10:37:01 AM 30
Harris 2008 SRO Exam Rev FINAL
* A reactor trip has occurred from 100°11> power.
* All systems functioned as designed.
Which ONE of the following describes the position of valves associated with the Main
Turbine? .
A. ThrottleValves-CLOSED
~ntercept Valves CLOSED
Reheat Stop Valves - OPEN
B. Governor Valves - OPEN
Intercept Valves - OPEN
Reheat Stop Valves - CLOSED
C. Throttle Valves -CLOSED
Intercept Valves- CLOSED
Reheat Stop Valves - CLOSED
D. Governor Valves -OPEN
Intercept Valves - CLOSED
Reheat Stop Valves - CLOSED
Thursday, March 20,2008 10:37:01 AM 31
Harris 2008 SROExam Rev FINAL
39.
Given the following:
* A Steam Line break has occurred on "C" SG.
* The crew has performed actions contained in EPP-014, Faulted SG isolation.
* SG "C" pressure is 50psig.
_. SG "C" WR level is off-scale low.
* SG "A" and "B">NR levels are beinq controlled at 250/0.
* SG "A" and "B" pressures are approximately 900 psig and stable.
Which ONE of the following describes the action required lAW EPP-014, and the
reason for this action?
A. IsolateAFWflow to SG"C";
Minimize RCS cooldown and the mass and energy release from the steam line
break
B. Isolate AFW flow toSG "C" ;
Failure of components in "C" SG may occur due to thermal shock
C. InitiateAFW flow to SG "C" at the MINIMUM verifiable rate;
Feeding the "C" SG is required for cooldown, but high AFW flow rates may cause
an excessive RCScooldown requiring an undesired transition out of EPP-014
. D. Initiate AFW flow to SG "C"atthe MINIMUM verifiable rate;
Feeding. the "C"SG isrequired for cooldown, but high AFW flow r(3tes may cause
failure of SG"C" components due to thermal shock
Thursday, March 20, 2008 10:37:01 AM 32
Harris 2008 SRO Exam Rev FINAL.
40.
Initial Plant Conditions:
e The plant is at 1000/0 power.
Current Plant Conditions:
eAspuriousturbine trip occurs.
e TheC-8 interJockfails to operate.
e All other plant equipments responds as expected.
Which ONE ofthe following describes the response of the Steam Dump Control
System (SDCS) and the overall effect on the ReS temperature?
A. SDCS will control temperature using the Turbine Trip Controller;
RCS temperaturewillbe controlled at normal no-load temperature.
B. SDCSwili control temperature using the Load Rejection Controller;
Res temperature will be controlled at normal no-load temperature.
C. SDCS will control .temperature usinq the Turbine Trip Controller;
RCS temperature will be controlled at approximately 3 degrees above normal
no-load temperature.
D. SDCS will control temperature using the Load Rejection Controller;
RCStemperature will be controlled at approximately 3 degrees above normal
no-load temperature.
Thursday, March 20, 2008 10:37:01 AM 33
Harris 2008 SRO Exam Rev FINAL
41.
Given the following:
* The Reactor is critical atthe *POAH.
* The crew is preparing to perform a turbine startup lAW GP-005, Power
Operation.
Which.>ONE of the following describes the expected rod height for Control Bank "0"
rods lAW GP-005 and the basis for this band?
A. Between 95.and 115 steps;
Helps .ensurelR trip and rod stop bistable setpoints are not reached before they
can be blocked
B. Between 130 and 150 steps;
Helps ensure IR trip and rod stop bistable setpoints are not reached before they
can be blocked
c. Greater than 95 steps;
Minimum height required to remain above Rod Insertion Limit
o. Greater than 130 steps;
Minimum height required to remain above Rod Insertion Limit
Thursday, March 20,2008*10:37:01 AM 34
Harris 2008 SRO Exam Rev FINAL
42.
Initial Conditions:
* The plant isat1 00% power.
* Testing isin progress on the AFW system,
* The"A"MDAFWpumpis running with the MDAFW FCVs 200/0 open.
Current Conditions:
* Atripofboth MFW pumps occurs.
* ThelowestSGlevelsduring the transient were:
* SG "A" = 18%
*SG "B" = 24°Jb
* SG "C"= 28%
Assuming NO operator actions have occured, which ONE of the following describes the
currentstatus of the MDAFW Flow Control Valves (FCVs) and TDAFW pump for this
event?
MDAFW FCVs TDAFW Pump
A. 20 0Jb Open Running
B. 20% Open Secured
C. Fu*1I Open Running
D. Full Open Secured
Thursday, March 20,200810:37:01 AM 35
Harris 2008 SRO Exam Rev FINAL
43.
Given the following:
* The plant is at 100% power.
* An ExtrerneHl-HlIevel is received in Feedwater Heater 1A.
Which ONE ofthe following describes the impact on the unit and the action, if any, that
is required in accordance withOP-136, Feedwater Heaters?
A. ONLY FeedwaterHeaters 1Aand2A are bypassed;
Reduce Turbine Load to less than 70%.
B. ONLY Feedwater Heater1A and2A are bypassed;
Ensure reactor power less than 1000/0, NO additional power restrictions are required
C. FeedwaterHeaters 1A,2A,1 B,and2B are bypassed;
Reduce Turbine Load to less than 700/0.
D. Feedwater Heaters lA,2A, 1B,and2B are bypassed;
Ensure reactor power less than 100%, NO additional power restrictions are required
Thursday, March 20,2008 10:37:01 AM 36
Harris 2008 SRO Exam Rev FINAL
44.
Given the following:
* The plantwas operating at 98% power when a loss of off-site power occurred.
* Twenty minutes later, the following plant conditions exist:
* RCSpressure is 2235 psig and stable.
* RCS Loop THOT is 596°F in all 3 loops and lowering.
* RCS Loop TCOLD is 552°F in all 3 loops and lowering.
* Core exit TCsindicate approximately 600°F and lowering slowly.
* Steam Generator pressures are approximately 1048 psig and stable.
Which ONE of the following describes the current plant conditions?
(Steam Tables are provided.)
A. Natural Circulation does not exist.
Heat removal must be established by opening the condenser steam dumps.
B. Natural Circulation exists.
Heat removal is being maintained by condenser steam dumps.
C. Natural Circulation does not exist.
Heat removal must be established by opening the SG PORVs.
D. Natural Circulation exists.
Heat removal isbelnqrnaintained by SG PORVs.
Thursday, March 20, 2008 10:37:01 AM 37
Harris 2008 SRO Exam Rev FINAL
45.
Given the following:
* Theplantisin Mode 3.
* A loss of DC Bus DP-1B-SB has occurred.
* The crew is performing actions of AOP-025, Loss of One Emergency AC Bus
(6.9 kV) or ONE Emergency DC Bus (125V)
Which ONE of the following describes the reason for ensuring that letdown orifice
valves are shut in accordance with AOP-025?
A. Prevent water hammer or flashing in the letdown line.
B. Prevent RCS leakage in excess of Technical Specification limits.
C. Minimize reduction in PZRlevel with loss of charging flow.
D. Prevent damage to the Regenerative Heat Exchanger.
46.
For the Steam Generator Water Level Control System (SGWLCS), which ONE of the
following describes this system's normal operation and program level input?
A. SGWLCSisa leveld.ominant system that ultimately adjusts Feed Reg valve
position by level error.
Program level is variable based on input from Turbine First Stage pressure.
B. SGWLCS is a level dominant system that ultimately adjusts Feed Reg valve
position by level error.
Program level is constant at 57% NR.
c. SGWLCS. isaflow dominant system that ultimately adjusts Feed Reg valve position
by mismatch in steam flow vs. feed flow.
Program level is variable based on input from Turbine First Stage pressure.
D. SGWLCS isa flow dominant system that ultimately adjusts Feed Reg valve position
by mismatch in steam flowvs.feed flow.
Program level is constant at 57% NR.
Thursday, March 20, 2008 10:37:01 AM 38
Harris 2008 SRO Exam Rev FINAL
47.
Given the following:
* The plant is at 100% power.
* The following alarm has just been received:
* ALB-04-2-2, REFUELING WATER STORAGE LOW LEVEL
* All otherMCR alarms are clear
* The crew enters AOP-008, Accidental Release of Liquid Waste
Which ONE of the following describes the setpointfor the alarm received, and the
action required maccordance with AOP-008?
A. 94.3%;
Immediately begin refilling the RWST to above the alarm setpoint
B. 94.3°;0;
Stop all additions to the RWST
C. 23.4%,;
Ensure RHRandContainment Spray Pumps are de-energized
D. 23.4%.
EnsureCSIP suctions areisolatedfrorn the RWST
48.
Which ONE of thefollowinq instruments failures will cause actual feedwater flow to the
affected SG to INITIALLY lower? (Assume selected)
A. SG level fails low
B. Feedwaterflow fails low
C. Steam pressure fails high
D. Steam flow fails low
Thursday, March 20,200810:37:02 AM 39
Harris 2008 SRO' Exam Rev FINAL
49.
Given the following:
* A Gaseous Waste release of Gas Decay Tank C is in progress.
* An ALERT alarm is received on REM-3546, WPB Stack 5 PIG monitor.
* Activity level is stable just above the ALERT setpoint.
Which ON.E of the following describes the action required in accordance with
OP-120.07?
A. The release MUST be stopped; release may continue under the same release
permit after REM-3546is determined to be operable and curie content of the
release is determined to be within limits.
B. The release MUST be stopped; a newrelease permit must be generated prior to
resuming the decay tank release.
C. The release may continue; if activity level approaches or exceeds the HIGH alarm
setpoint, stop the release; release may continue under the same release permit
afterREM-3546 is determined to be operable and curie content of the release is
determined. to be within limits.
D. The release may continue; if activity level approaches or exceeds the HIGH alarm
setpoint, stop the release; a new release permit must be generated prior to
resuming the decay tank release.
Thursday, March 20, 200810:37:02 AM 40
Harris 2008 SRO Exam Rev FINAL
50.
Given the following:
* The plant is operating at 50% power.
* The Turbine Driven AFW pump was taken OOS 12 hours ago for bearing
replacement.
* Both Motor Driven AFWpump motors have been determined to be
INOPERABLE due to a common cause failure analysis.
Which ONE of the following actions is required?
A. Immediately initiate action to restore one AFW train to operable status; power
operation is currently allowed with all three AFW Pumps Inoperable.
B. Restore at least2 AFW Pumps to service within 1 hour, or be in Hot Standby within
the following 6 hours.
C. Restore at least 1 AFW Pump to service within 1 hour, or be in Hot Standby within
the following 6 hours.
D. Immediatelyentertheaction of TS 3.0.3 and be in at least HOT STANDBY within 7
hours from the time itwas determined that no AFWpumps were operable.
Thursday, March 20, 2008 10:37:02 AM 41
Harris 2008 SROExam Rev FINAL
51.
Given the following:
* The plant is in mode 3
* RCS heatup is in progress
As AFW flow to the steam generators is increased, what will happen to the initial heat
transfer rate between RCS and the steam generators and why?
The heat transfer rate will ...
A. increase;
because the cooler AFW water will increase the delta T between the RCS and the
steam generators.
B. decrease;
because the cooler AFW water will decrease the delta T between the RCS and the
steam generators.
C. increase;
because increasing SGlevel causes SG pressureand saturation temperature to
increase.
D. decrease;
because increasing SG level causes SG pressure and saturation temperature to
decrease.
Thursday, March 20,200810:37:02 AM 42
Harris 2008 SRO Exam Rev FINAL
52.
Given the following:
* The, plant is at 100% power.
* Recovery from a Loss of Instrument Bus 1DP-1A-S1 is in progress.
* The crew has de-energized the associated Process Instrumentation Cabinet
(PIC) in preparation for energizing Instrument Bus 1DP-1A-S1.
* The crew i,s evaluating bistable status prior to energizing the bus.
Which ONE of the following describes the reason for checking bistable status?
A. When the lnstrurnentbusis enerqized with the PICdeenergized, a reactor trip may
occurdue to 'de-energize to actuate' bistables becoming actuated. Checking other
bistables ensures a Reactor Trip will not occur.
B. When the PIC is enerqized after the Instrument Bus is energized, 'energize to
actuate' bistables may experience a momentary inadvertent trip. Checking other
bistables ensures an ESF actuation will not occur.
C. Bistables are checked to ensure that each parameter for Process or Protection
goes to its required state when.the Instrument Bus and PIC are energized.
D. Bistablesare checked to ensure that all lights are out, verifying that the PIC normal
and alternate supply breakers are open prior to reenergizing the Instrument Bus.
Thursday, March 20,2008 10:37:02 AM 43
Harris 2008 SROExamRev FINAL
53.
lnitial Plant Conditions:
* Yesterday, a loss ofESW Header "A" occurred due to a failure shaft shear of the
"A"ESW Pump.
* The crew completed AOP-022, Attachment 1, Equipment Alignment Due to Loss
of an ESWHeader.
* The crew implemented OWP-SW, Operations Work Procedure Service Water,
due to the extended loss of the "A" ESWheader.
Current Plant Conditions:
* A loss of off-site power occurs coincident with a safety injection
actuation.
Which ONE of the following describes the alignment of ESW loads forthe current plant
condition?
A. "A" EDGwillNOT automaticaHystart because implementation of OWP-SW places
the diesel in MAINTENANCE MODE.
B. "A"EDG will automatically start, but must be manually tripped because it will have
no ESW flow.
C. "A"EDG will NOT automatically start because implementation of OWP-SW will
have barred the diesel.
D. "A"EDG will automatically start, but operators must realign NSW to the ESW
header.
Thursday, March 20,200810:37:02 AM 44
Harris 2008 SRO Exam Rev FINAL
54.
Given the following:
* The plant is in Mode 3.
* AFW Pump 1.A-SA is operating to provide secondary inventory.
* DC BusDP-1A~SA becomes de-energized.
Which ONE of the foHowing describes the effect on the operating AFW pump?
A. MCR control switch indication is extinguished.
Pump remains runninq.
MCRbreaker control is lost
B. MCR control switch indication is extinguished.
Pump remains running.
MCR breaker control is available
C. MCRcontrol switch indication is available.
Pump trips.
MCRbreakercontrol is lost
D. MCR control switch indication is available.
Pump trips.
MCRbreaker control is available
A. 6500 KWata power factor of 0.8 leading
B. 6500 KWat a power factor of 0.8 lagging
C. 7150 KWatapowerfactor of 0.8 leading
D. 7150 KWatapower factor of 0.8 lagging
Thursday, March 20,2008 10:37:02 AM 45
Harris 2008 SRO Exam Rev FINAL
56.
Given the following:
* The unit is in Mode 4.
* Maintenance reports that the inner door on the Containment Emergency Airlock
will not seal properly after leaving Containment.
* The crew has declared the inner door .INOPERABLE.and closed the outer door.
Which ONE of the foHowingdescribes the status of CONTAINMENT INTEGRITY, per
Technical Specification Definitions, and the required Technical Specification action?
A. Containment Integrity IS met;
Immediately verify the outer door closed
B. Containment Integrity IS NOT met;
Immediately verify the outer door closed
C. Containment Integrity IS met;
Verify the outer door closed within 1 hour.
D. Containment Integrity.IS.NOT met;
Verify the outer door closed withint hour.
57.
Which ONE of the following would be used to change the alarm setpoints from the
Main ControtRoom of a safety related radiation monitor?
A. RM-11
B. RM-23
C. RM-23P
D. RM-80
Thursday, March 20,2008 10:37:02 AM 46
Harris 2008 SRO Exam Rev FINAL
58.
Given the following:
* The crew enteredFRP-C.1, Response to Inadequate Core Cooling, with the
following cond itionspresent:
* Loss of Offsite has occurred
* Core Exit temperature is 737 degrees F
* RCSpressure is 1650psig
* RVLIS is 360/0
Which ONE of the following describes the condition of the RCS and the actions
required in response to this condition?
A. Saturated, heat transfer is degraded;
Establish an *RCS Vent path to lower pressure and temperature
B. Saturated ,heat transfer is in jeopardy;
Reinitiate High Pressure Safety Injection to restore core cooling
C. Superheated, heattransferisdegraded;
Establish an RCS Vent path to lower pressure and temperature
D. Superheated, heat transfer isin jeopardy;
ReinitiateHigh Pressure Safety Injection to restore core cooling
Thursday, March 20,200810:37:02 AM 47
Harris 2008 SRO Exam Rev FINAL
59.
Given the following:
* The plant is operating at55% power.
* The following annunciator is received in the Control Room:
* APP-ALB-002-7-2, SERV WTRPUMPS DISCHARGE LOW PRESS
* TheROnotesthat Cooling Tower Basin Level is decreasing rapidly.
* Service Water header pressure is 45 psig and lowering.
* One minute later, Service Water header pressure is 25psig and continues to
lower.
* CTMU cannot maintain Cooling Tower Basin level.
* ThecrewehtersAOP-022, Loss of Service Water and completes the immediate
actions.
* APP-ALB-002-7-2is stiJlinand the Cooling Tower Basin Level continues to
decrease rapidly.
* RABOperator reports that a large volume of water is gushing from overhead
piping in the vicinity of1 SW-276, Headers A & B Return To Normal SW Header
valve. The area is inaccessible.
* All automatic plant systems have functioned as designed.
Which ONE of the following describes the location of the leak, and the action required?
A. Unisolable leak located in the Normal Service Water System;
Trip the reactor and go toPATH-1.
B. UnisolableJeakIocated in the Emergency Service Water System;
Trip the reactor and go toPATH-1.
C. Isolableleak locatedinthe Normal Service Water System;
EnsureNSW is properly aligned to equipment listed in AOP-022, Attachment 1.
D. Isolable leak located in the Emergency Service Water System;
EnsureESW is properly aligned to equipment listed in AOP-022,Attachment 1.
Thursday, March.20, 200810:37:02 AM 48
Harris 2008 SROExam Rev FINAL
60.
Which ONE of the following describes the operation of Service Air Header Isolation
Valve, 1SA-506?
A. Closes automatically when Instrument Air. header pressure decreases below 75
psig;
Automatically reopens when pressure increases above 79 psig.
B. Closes automatically when InstrumentAir header pressure decreases below 75
psig;
Must be manually reopened .whenpressure increases above 79 psig.
C. Closes automatically when Instrument Air header pressure decreases below 90
psig;
Automatically reopens when pressure increases above 94 psig.
D. Closes automatically when Instrument Airheader pressure.decreases below 90
psig;
Mustbe manually reopened when pressure increases above 94 psig.
Thursday, March 20,200810:37:03 AM 49
Harris2008SRO Exam Rev FINAL
61.
Given the following:
* The plant is at 1000/0. power.
* An inadvertent Containment Spray actuation has occurred on Train "A".
* Train "A" Containment Spray has been secured.
* Containmentpressureindicates (-)2.4 inches H20.
Which ONE of the following describes how Containment pressure will be restored to
within limits?
A. Containment Vacuum Relief system will operate to restore containment pressure to
-1.5 inches H20. No other actions are required.
B. ContainmentVacuumRelief system will operate to restore containment pressure to
-1.5 inches H20. Containment purge operation is then required to restore to -1.0
inches H20.
C. ContainmentVacuumReliefsystemwilloperate to restore containmentpressure to
-1 ~OinchesH20.No other actions are required.
D. ContainmenfVacuum Relief system will operate to restore containment pressure to
-1.0 inches H20. Containment purge operation is then required to restore to -0.5
inches H20.
Thursday, March 20,200810:37:03 AM 50
Harris 2008 SRO Exam Rev FINAL
62.
"{he plant is at 100% P~A<9 3/~((;)t' Th.-z pUtfl! .~ r;,., loo:5z, I? O"'e12- ~ i 1-{,.\
V ~ertJi ?iY'<U\} 0" +oq 'S ea-u l c.e. ..
The operating crew has entered EPP-013, LOCAOutside Containment due to MCB
indications.
Which ONE of the following describes the leak location that would be isolated first in
accordance with EPP-013, LOCAOutside Containment, and the method for
confirmation of leak isolation?
A~ Excess Letdown Heat Exchanger;
PZRlevel rising.
B. Excess Letdown Heat Exchanger;
RCSpressurerising.
C. RHRHeat Exchanger;
PZR level rising.
D. RHR Heat Exchanger;
RCS pressure rising
Thursday, March 20, 2008 10:37:03 AM 51
Harris 2008 SRO Exam Rev FINAL
63.
Given the following:
* The reactor was tripped on simultaneous loss of the Main Feedwater Pumps.
* All AFW was subsequently lost.
* RCS Bleed and Feedisin progress in accordance with FRP-H.1, RESPONSE
TO LOSS OF SECONDARY HEAT SINK.
* Core Exit Thermocouples have stabilized atan average of 595 OF.
* Main Feedwater Pump "A" hasbeen started.
* Containment pressure is 1.0 psig and stable.
Which ONE of the following describes the method-and rate of establishing feedwater
flow?
A. Feed one Steam Generator at the MINIMUM controllable rate untila SG WIDE
range level is>15% using the respective Feedwater Control Bypass Valve.
B. Feed one Steam Generator at the MAXIMUM rate until a SGNARROW range level
is >25 % u s i n g the respective Feedwater Control Bypass Valve.
c. Feed all Steam Generators at the MINIMUM controllable rate until a SGWIDE
range level is >15% using the Feedwater Control Valves.
D. Feed all Steam Generators attheMAXIMUMrate until aSG NARROW range level
is >25% using the FeedwaterControl Valves.
64.
Given the following:
* A reactor trip and loss of off-site power have occurred.
* The crew is performing acooldown using EPP-007 , Natural Circulation With
Steam Void in Vessel (Without RVLIS).
* Off-Site powerhasbeen restored.
* Preparations are being made to start an RCP.
Which ONE of the following describes the minimum PZR level required for RCP restart
in accordance withEPP~007, and the reason for the level?
A. 25%to ensure minimum inventory for adequate pressure control.
B. 65% to ensure minimum inventory for adequate pressure control.
C. 25% to ensure adequate volume for collapsing the void
D. 650/0 to ensure adequate volume for collapsing the void
Thursday, March 20, 2008 10:37:03 AM 52
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65.
Which ONE of the following describes the reason and requirements for depressurizing
theRCS in accordance with EPP-012, Loss of Emergency Coolant Recirculation?
A. To. minimize RCS leakage;
Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F [40°F
and 50°F];
B. To ensure SI Accumulator injection;
Depressurize theRCS to.achieveRCS subcooling between 10°F and 20°F [40°F
and 50°F];
C. To minimize ReS leakage;
Depressurize the RC,S to maintain RCS subcoolingjustabove lOaF [100°F];
D. To ensureSIAccumulatorinjection;
Depressurize the RCSto maintain RCS subcoolingjust above zo-r [100°F];
Thursday, March.20,200810:37:03 AM 53
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66.
Given the following:
* You are assigned as the RO on day shift.
* You have been called for Fitness for Duty screening.
* You must leave the Control Room for approximately 1.5 hours.
* TheSSOhasgivenperm.ission and directed no additional actions are required
beyond those 'stated °in OMM-002, Shift Turnover Package.
lAW OMM-002, which ONE of the following is the MINIMUM required for the shift
relief?
Note:
(Attachment 14, Documentation of Short Term Assumption of Duties)
(Attachment 5, Control Operator Shift Turnover Checklist)
A. Oral turnover to the remaining Board Operator. Both watchstanders Initial
Attachment 14. No log entry required.
B. Oral turnover to the remaining Board Operator. Both watchstanders Initial
Attachment 14 and document reliefforgreater than 1 hour in the Control Operator
log.
Co. Perform a turnover using Attachment 5. Both watchstanders Initial Attachment 5.
No log entry. required.
D. Perform a turnover using Attachment 5. Enter the information in the Control
Operators log, and sign the log over.
Thursday, March 20,200810:37:03 AM 54
Harris 2008 SRO Exam Rev FINAL
67.
Given the following:
* A power increase.isinproqress in accordance with GP-005, Power Operation.
* Average Power Range Nls indicate 40% power.
* Main Turbine load indicates 35% power.
* Average Loop Delta Tindicates 420/0 power.
Which ONE of the following describes the actions required in accordance with
GP-005?
A. Power must be reduced less than 30.% by all indications and a calorimetric
performed to determine actual .power.
B. Power increase should be stopped and a calorimetric must be performed to
determine actual power.
C. Power increase should be stopped and the PRNls adjusted to match turbine power.
D. Power increase may continue using turbine power and no further action is required
unless turbine power and average PRNlsdeviate by 50/0 or greater.
A. Lubrication of a valve stem prior to each scheduled testing of the valve.
B. Periodic or occasional venting of pumps priorto testing, not associated with the
surveillance being performed.
C. Adjusting the bolt torque on a valve collar prior to stroke time testing of the valve.
D. Operation ofa pump shortly before a test, if a situation could be avoided to operate
the pump while maintaining plant and personnel safety.
Thursday, March 20, 2008 10:37:03 AM 55
Harris 2008 SROExam Rev FINAL
69.
Given the following:
* The unit is in Mode 6.
* Refueling operations are in progress.
* The 30th fuel assembly is being loaded into the core.
* Current Boron Concentration is 2450 ppm.
According to GP-009, Refueling Cavity Fill, Refueling, and Drain of the Refueling
Cavity, Modes 5-6-5, which ONE of the foHowingwould require fuel loading operations
to be stopped immediately?
A. Communications is lost between Containment and the Control Room.
B. Water in the Spent FuelPool in not.clear enough to view the Fuel top Nozzles
without supplementalJighting.
C. Boron concentration drops by 10 ppm as determined by two successive samples of
Reactor Coolant.
D.Anunanticipatedrisein countrateby a factor of two occurs on 1 of2 operable
Source Range channels during any single loading step.
Thursday, March 20,200810:37:03 AM 56
Harris.2008,SRO ExamRev FINAL
70.
Given the following conditions at a work site:
* Airborne activity -5 DAC
* Radiation level- 40mrem/hr.
* Radiation level with shielding - 20 mrem/hr.
* Time to conduct task WITH respirator - 40 minutes.
* Time to conduct task WITHOUT respirator .. 30 minutes.
Assumptions:
* The airborne dose with a respirator will be zero.
* A dose rate of40mrem/hr will be received while placing the shielding. Assume
no benefit from shielding during placement.
* All tasks will performed by one worker.
* Shielding can be placed in 15 minutes with or without a respirator.
* The shielding will not be removed.
Which O.NE of the following would result in the lowestwhole body dose?
A. Conduct task WITHOUT respirator or shielding.
B. Conduct task WITH respirator and WITHOUT shielding.
C. Place shielding while wearing respirator and conduct task WITH respirator.
D. Place shielding while wearing respirator and conduct-task WITHOUT respirator.
Thursday, March 20, 200810:37:03 AM 57
Harris 2008 SRO Exam Rev FINAL
A. 2000mrem;
Superintendent- Radiation Protection
B. 2000 mrem;
Site Vice President
c. 4000 mrem;
Superintendent -Radiation Protection
D. 4000 mrem;
Site Vice President
Thursday, March 20,2008 to:37:03 AM 58
Harris 2008 SRO Exam Rev FINAL
72.
Initial Conditions:
* The unitis att 00% power.
Current Conditions:
* The following alarm is received:
* ALB-001-7-1, ACCUMULATOR TANK AHI..LO PRESSURE
* The RO.reportsthe following indications:
* Cold Leg AccumulatorA'tpressure is 650psig and slowly increasing
* Cold Leg Accumulator "A"level is 75% and slowly increasing
Which one of the following is the action required lAW the appropriate Annunciator
Plant Procedure andlheOPERABILITY of the "A" Cold <Leg Accumulator (CLA)?
A. Drain "A" CLA to lower pressure;
CLA "A" is INOPERABLE
B. Verify Nitrogen to the accumulators is isolated and vent excess accumulator
pressure;
CLA "A"is INOPERABLE
C. Drain "A"CLAto lower pressure;
CLA"A" is OPERABLE
D. Verify Nitrogen to the accumulators is isolated and vent excess accumulator
pressure;
CLA "A" is OPERABLE
Thursday, March 20, 2008 10:37:03 AM 59
Harris 2008 SRO Exam Rev FINAL
73.
Given the following:
* At 1302, a steam generator tube leak is identified.
* At 1318,a,plantshutdownis commenced dueto exceeding TS leakage limits.
* At 1319, an Unusual Event is declared by the Site Emergency Coordinator.
(SEC)
* At 1321, a reactortripoccurs,
* At 1327, the crew identifies SG "A"as the ruptured SG.
* At 1330, an ALERT is declared by the SEC.
Which ONE ofthe following describes the latest time that the initial notification to
State/County officialsANDthe*NRC*is due?
State/County NRC
A. 1334 1334
B. 1334 1419
C. 1345 1419
D. 1345 1430
Thursday, March 20,200810:37:04 AM 60
Harris2008SROExam Rev FINAL
74.
Given thefoHowing:
* One Shutdo.wnBank-A, Group 2 Rod has dropped into the core.
* The crew is recovering the dropped rod.
* ALB-13-7-1 ,RODCONT SYSTEM URGENT FAILURE is received.
Which ONE of the following describes the reason for the alarm and the plant
response?
A. Withdrawing the rod while the remaining Group 2 Lift Coils are deenergized.
Rod withdrawal is blocked until the alarm is reset.
B. Initiation of an "out" siqnalto SO Bank "A" Rods, and its Group 1 rods do not move.
Rod withdrawal is blocked until thealarm is reset.
C. Withdrawing the rod while the remaining Group 2 Lift Coils are deenergized.
Rod withdrawal is unaffected and recovery may continue.
D. Initiation of an "out" signal to SO Bank "A" Rods and its Group 1 rods do not move.
Rod withdrawal is unaffected and recovery may continue.
Thursday, March 20, 2008 10:37:04 AM 61
Harris 2008 SRO Exam Rev FINAL
75.
Given the following:
* The Unit has experienced aSBLOCA.
* EPP-0'09, Post LOCACooldown and Depressurization is in progress.
* All RCPs are running.
* RCS pressure is 1690psig.
* An RCScooldown has-been initiated by dumping steam to the atmosphere.
Which ONE.of the following describes the required RCP configuration lAW with
EPP-009, and the basis for this configuration?
A. All RCPs should be stopped;
minimize RCS inventory loss when the break uncovers
B. One RCP should be stopped;
produces effective heat transfer, provides boron mixing for RHR operations, and
providesRCSpressure control
C. All RCPsshould be Jeft running:
ensures symmetric heat transfer to the S/Gs, aids in ReS pressure control, and
prevents steam voiding in the Reactor vessel head
D. Two RCPs should be stopped;
minimizes RCS heat input and still produces effective heat transfer and RCS
pressure control
Thursday, March 20, 200810:37:04 AM 62
Harris<2008 SRO Exam Rev FINAL
76.
Which ONE of the following describes the Technical Specification basis for the
Pressurizer Code *safety valves?
The basis is that the combined reHefcapacityof all the pressurizer Code safeties is
greater than the maximum surge rate assuming AND _
A. a complete loss of load.directly resulting in a reactor trip from the turbine trip;
no operation of the pressurizerPORVs or the steam dumps
B. a complete loss of load with no reactor trip until the second trip setpoint is reached;
no operation. of the pressurizer PORVs or the steam dumps
C.a complete loss of load directly resulting in a reactor trip from the turbine trip;
no operation of the pressurizer PORVs, steam dumps operate as designed
D. a complete loss of load with no reactor trip until the second trip setpoint is reached;
no operation of the pressurizer PORVs, steam dumps operate as designed
Thursday, March 20,200810:37:04 AM 63
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* Following a turbine runback, the crew has stabilized the plant.
* Control Bank "O"Group Counters are at 180 steps.
* On ORPI, one Control Bank "0" rod indicates 198 steps; all others indicate 180
steps.
* The crew has entered AOP-001 and determined the rod to be immovable and
untrippable.
Which ONE of the following describes the expected alarm for the given plant conditions
and the technical specification implications of this event?
A.ALB~t3-6-1, RPIURGENT .ALARM;
Verify Shutdown Margin within 1 hour and be in Hot Standby within 6 hours.
B. ALB-13-8-5, COMPUTER ALARM RODDEV/SEQ NIS PWR RANGE TILTS;
VerifyShutdownMarqin within 1 hour. Power operation may continue provided that
accident analyses are revaluated to be satisfactory.
c. ALB-13-6-1, RPJURGENTALARM;
Verify Shutdown Margin within 1 hour. Power operation may continue provided that
accident analyses are revaluated to be satisfactory
D.. ALB-13-8-5, COMPUTER ALARM ROD DEV/SEQ NIS PWRRANGE TILTS;
Verify Shutdown Margin within 1 hour and bein Hot Standby within 6 hours.
Thursday, March ~0,20081 0:37:04 AM 64
Harris 2008 SRO Exam Rev FINAL
78.
Given the following plant conditions:
* A normalplant cooldown is in progress
* Both CSIPsare OPERABLE
Which of the following is the plant temperature at which Technical Specifications
require a MAXIMUM of ONE(1) CSIP to be OPERABLE and the basis for this
requirement?
A. 325 -r.
Prevents an uncontrolled cooldown due to a mass addition of cold water from the
RWST
B. 325°F;
Provides assurance that a mass addition pressure transient can be relieved by the
operationofasinglePORV
C. 350°F;
Prevents an uncontrolled cooldown duetoa mass addition of cold water from the
RWST
D. 350°F;
Provides assurance thatamass addition pressure transient can be relieved by the
operationofasinglePORV
Thursday, March 20,20081 0:37:04 AM 65
Harris 2008 SRO Exam Rev FINAL
79.
Given the following:
* The plant is.at 100% power.
* A loss of Component Cooling. Water has occurred.
* The crew is performing actions of AOP-014, Loss of Component Cooling
Water.
* 3 minutes into the event, thele.ak is determined to be onCCWloop "A".
* "A"SurgeTanklevel indicates 20/0.
* "B" Surge Tank leveLindicates 38% and stable.
* TheCCW Non-Essential Loop was isolated from "A" Train and is now aligned to
the "B" Train.
Which ONE of the following describes the minimum actions required by AOP-014?
A. Trip the reactor,
Immediately trip RCPs, and enter Path-t.
B. TripaffectedCCWpump(s)
Continue attempts to locate the leak in accordance. with AOP-014. Mode 1
operations may.continue.
C. Trip the reactor,
Enter Path-1 and trip the RCPs within 10 minutes.
D. Trip affectedCCW pumpis)..'
Enter AOP-038 fora rapid shutdown while continuing attempts to locate the leak in
accordance with AOP-014.
Thursday, March 20, 2008 10:37:04 AM 66
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80.
Given the following:
* The plant is operating at 100% power
* All equipment is operating in normal lineups.
Current conditions:
* A loss of DC Bus DP-1A~SAoccurs .
.Which. ONE of the following describes the impact of this failure on the Reactor
Protection System and the actions required?
A. RTB "A"shunt trip coilwillbe disabled by the loss of DC bus and directly cause a
reactor trip;
Perform actions of Path-1 in parallel with AOP-025,Loss of One Emergency AC
Bus(6.9kV)OrOne Emergency DC Bus (125V)
B. RTB "A" shunttrip coil will be disabled by the loss of DC Bus but this will NOT
directly result in areactortrip:
Initiate a.manual reactor trip due to the effect on the plant of the loss of DC Power
supply and perform actions of Path-1 in parallel with AOP-025, Loss of One
Emergency ACBus(6.9kV)Or One Emergency DC Bus (125V)
C. RTB "A" undervoltage colt will lose power due to the loss of DC*Bus and directly
cause a reactor trip;
Perform actionsofPath-.t. Once Path-t is exited then enter AOP-025, Loss of One
EmergencyACBus(6.9kV)Or One Emergency DC Bus (125V)
D. RTB "A"undervoltagecoil will lose power due to the loss of DC Bus but this will
NOT directly result in a reactor trip;
Initiate a manual reactor trip due to the effect on the plant.of the loss of DC Power
supply and perform actions ofPath-1 in parallel with AOP-025, Loss of One
EmerqencyAt; Bus {6.9kV) Or One Emergency DC Bus (125V)
Thursday, March 20,2008 10:37:04 AM 67
Harris 2008SRO Exam Rev FINAL
81.
Given the following:
* A reactor startup isinproqress in accordance with GP-004, Reactor Startup
(Mode 3 to Mod.e2).
* ThefoHowingalarmis received:
'*ALB-013-3-2, INTERMEDIATE. RANGE LOSS OF COMPVOLTAGE
* SRChannel N-31 indicates 7X10 3 cps.
* SRChannelN-32indicates7X10 3 cps.
* IRChannelN-35indicates 8.7X10- 11 amps.
* IR Channel N-36 indicates 7.0X10.-10 amps.
Which ONE of the following describes the existing plant condition and the associated
Technical Specification requirements for continued operation?
A. N-35 is undercompensated;
Raising power above P-6ispermittedonceOWP-RP, Reactor Protection, is
implemented.
B. N-35is undercompensated;
Raising power above P-6is*NOTpermitted until the channel is restored to
OPERABLE.
C. N-36 isundercompensated;
Raisinq power above P-6 is permittedonceOWP-RP, Reactor Protection, is
implemented.
D. N-36 is undercompensated;
Raising power above P-6is NOT permitted until the channel is restored to
OPERABLE.
Thursday, March 20, 200810:37:04 AM 68
Harris 2008SROExam Rev FINAL
82.
Given the following:
* Plant is operating at 1000/0 power.
* Pressurizer level transmitter LI-459Aoutput has failed.
Which ONE of the following describes the Technical Specification actions required, if
any, and the Technical Specification basis for the High Pressurizer Water Level reactor
trip?
A. Enter T*.S.3.3.1, RPSlnstrumentation. The inoperable channel must be placed in a
trip condition within 6* hours;
Provides a backup trip to PZR High Pressure reactor trip and ensures that water
relief through thePZR safety valves will not occur.
B. EnterT.S.3.3.1 ,RPSlnstrumentation. The inoperable channel must be placed in a
trip condition within 6 hours;
Provides primary protection for loss of load events' and ensures that on a PZR level
channel failure, the PZRsafety valves will not lift prior to the PZR High Pressure
reactor trip.
C. ActionperT.S.3.3.1, RPS Instrumentation, is NOT required since 2 channels are
still available;
Provides a backup trip to PZR High Pressure reactor trip and ensures that water
relief through the PZRsafety valves will not occur.
D. Action per T.S. 3.3.1, RPS Instrumentation, is NOT required since 2 channels are
still available;
Provides primary protection for loss of load events and ensures that on a PZR level
channel failure, thePZRsafetyvalves will not lift prior to the PZR High Pressure
reactor trip.
Thursday, March 20,2008 10:37:04 AM 69
Harris 2008 SRO Exam Rev FINAL
83.
Given the following:
* The plant isin Mode 4.
* RHR Train"B" has been placed in service.
* ReS temperature is stable at 325°F.
* RCS pressure is 320 psig and lowering slowly.
* Containment sump level is 20 inches and rising slowly.
* REM-01LT-3502A-SA,Cnmt RCSLeak Detection Monitor, is in HIGH alarm.
* Pressurizer level is 24% and slowly lowering.
* Charging is in MANUAL with flow of 120 gpm.
Which ONE of the following-describes the correct procedure to address the event in
proqress and the mitigation actions this procedure will require?
A. AOP-016, Excessive RCS Leakage
Manually align high head Sifiow through the BIT
B. AOP-020, Loss of RCSlnventory or Residual Heat Removal While Shutdown
Manually align high head SI flow through the BIT
C. AOP-016, Excessive RCS Leakage
Stop all running RHR pumps andisolateRHR
D. AOP-020, Loss of ReS Inventory or Residual Heat Removal While Shutdown
Stop alLrunning RHRpumps and isolateRHR
Thursday, March 20, 200810:37:05 AM 70
Harris 2008SRO Exam Rev FINAL
84.
Given the following:
* A LOCA occurred 45 minutes ago.
* The crew is performing actions in accordance with EPP-010, Transfer to Cold
Leg Recirculation ~
* SwapovertoColdLegRecirculation is in progress.
* The followinqalarrnsare received:
* ALB-001-2-2, SPRAY PUMPA DISCHARGE LOW PRESS
* ALB-001-2,-5,SPRAYPUMP A SUCTION LOW PRESS
* Both alarms are received and clear intermittently over the course of about 1
minute.
* "A" RHRpump amps and discharge pressure are beginning to oscillate.
* The USCOdetermines that Train "A" recirculation sump performance is
degraded.
WhichONE of-the folloWin~ describes the actions performed. based on the
determination thatthe recirculation sump is degraded?
A. Remainin,EPP-010;
Stop "A" Containment Spray Pump.
B. Remain in EPP-010;
ThrottleCSIP flow to be slightly greater than the minimum flow requirements.
C. Go to EPP-012,Lossof Emergency Coolant Recirculation;
Stop "A"Containment Spray Pump.
D. Go to EPP-012, Loss of Emergency Coolant Recirculation;
Throttle CSIP ftowto be slightly greater than the minimum flow requirements.
Thursday, March 20,2008 10:37:05 AM 71
Harris 2008 SRO Exam Rev FINAL
85.
Given the following:
* A SGTR is in progress on "A" S/G.
*. All MSIVs failed to close.
* All required actions of Path-2havebeen completed
* A transition has been made to EPP-020, SGTRWITH LOSS OF REACTOR
COOLANT: SUBCOOLED RECOVERY.
* Containment sump levels are normal for the current plant conditions.
Which ONE ofthe following conditions would require consulting plant operations staff
to determine if recovery should be completed*usingEPP-021, SGTR WITH LOSS OF
REACTOR COOLANT: SATURATED RECOVERY?
A. RWST level of 70%
B. "A" SG.levelat 98%
C. RWST level of20%
D. RCSPressure of 360psig
Thursday, March 20,200810:37:05 AM 72
Harris 2008 SROExam Rev FINAL
86.
Initial conditions:
* Reactor power was at 100°A>.
* Main Steam flow indications were rising on all 3SGs.
* Reactor power roseto 103%.
* The reactor was manually tripped.
* SafetyJnjectionwClsmanuallyactuated.
* Main Steam Isolation. was manually actuated.
Current conditions:
* ReS pressure is 1700psig and stable.
* "A" and"B" SG pressures are 800 psig and stable.
* "C" SGpressureis50 psigand slowly lowering.
* Core Exit temperatureis440degreesF and rising.
* Pressurizer level is 12% and rising.
* SG "A" and "B"NR levels are 35% and rising.
* Containment pressure is 0.3psigand stable
* The USCG has just completed the steps in EPP-014, Faulted Steam Generator
Isolation, for isolating the "C" Steam Generator.
Which ONE of the following describes current status of SI Termination criteria and
which' procedure will be used to address SI Termination?
A. Conditions are met toterminateSI;
SI willbe terminated in EPP-014
B. Conditions aremetto terminate SI;
SI will be terminatedonceatransition is made to EPP-008,SI Termination
C. Conditio.nsareNOTmettoterminate SI;
SI will be terminated in EPP-014 once conditions are met
D. Conditions are NOT met to terminate SI;
SI will be terminated in EPP-008,*SI Termination, once conditions are met
Thursday, March 20,2008 10:37:05 AM 73
Harris 2008 SROExam Rev FINAL
87.
Given the following plant conditions:
* The plant-is in Mode 1.
* ALB-15-2-2,PIC 1-2-3-4~9-10-13-14POWER FAILURE, alarms
* ALB-15-1-4,60KVAUPSTROUBLE, remains clear
* ALB-15-1-5, 7.5 KVA UPS TROUBLE, remains clear
* ALB-15-1-3, PROTECTIONSYSAlBTROUBLEalarms
* Most lights in" the bottom row of Trip Status Light Boxes are energized
Which ONE ofthe following correctly identifies the effect on the plant and the Technical
Specification implications for this event?
A. Power has been lost to all "B" Train SSPS Slave and Master relays
Enter Technical Specification 3.0.3 immediately
B. Ability to placeAFW Isolation bistables in a tripped condition is lost
Enter Technical Specification 3.0.3 immediately
C. Power has been losttoall "B"Train SS.PS Slave and Master relays
Enter Technical Specification 3.0.3 after 6 hours
D. Ability to place AFW Isolation bistables ina tripped condition is lost
Enter Technical Specification .3.0.3 after 6 hours
Thursday, March 20, 200810:37:05AM *74
Harris 2008 SRO Exam Rev FINAL
88.
Given the following:
* The MCR has been evacuated and the crew has entered AOP-004, Remote
Shutdown.
* The ACP is manned. and operational.
Which ONE of the following describes how power will be monitored by the Wide Range
Neutron Flux Monitoring (WRFM) system after leaving the MCR, and what is the
MINIMUM EmergencyClassificatio.n for this event?
A. Neutron flux will be determined using two redundant WRFM(NI-60A2, N.I-60B2)
that willbothindicateacross the Source and Intermediate Range.
Alert.
B. Neutron fluxwill be determinedinitially using.oneWRFM (NI-60B2). Once it is
off-scalelowthenthe second WRFM(NI-60A2).is used to determine Source Range
flux;
Site Area Emerqency.
C. Neutron flux wilLbedetermined using two redundant WRFM (NI-60A2, NI-60B2)
that will both indicate across the Source and Intermediate Range.
Site Area Emergency.
D. Neutron flux will be determined initially using oneWRFM (NI-60B2).Once it is
off-scale low then the.secondWRFM(NI-60A2) is used to determine Source Range
flux;
Alert.
Thursday, March 20,20081 0:37:05 ~M 75
Harris 2008 SRO Exam Rev FINAL
89.
Given the following plant conditions:
* The plant is at 100% power
* A'Iossofpower to Safety Bus 1B-SBoccurs
* The "B"EDG fails to start
Which one of the following describes the effect on the plant and the Technical
Specification (T.S.) requirements that apply?
A. Will generate aContainmentVentilationlsolation Signal;
ONLY "B" Train containment vacuum breaker is INOPERABLE, enter T.S. 3.6.5,
Containment Vacuum Relief, restore in 72 hours or be in at least HOT STANDBY
within the next 6 hours.
B. Will NOT generate a ContainmentVentilation Isolation Signal;
ONLY "B"Traincontainmentvacuum breaker is INOPERABLE, enter T.S. 3~6.5,
Containment Vacuum Relief, restore in 72 hoursorbe in at least HOT STANDBY
within the next 6 hours.
C. Will generate aContainmentVentiiation 'Isolation Signal;
Enter T.,S.3.0.3duetoinoperabilityofboth containment vacuum breakers
D. Will NOT generate a Containment Ventilation Isolation Signal;
Enter 1.S.3.0.3' due to inoperabilityofboth containmentvacuum breakers
Thursday, March 20, 200810:37:05 AM 76
Harris 2008 SROExam Rev FINAL
90.
Initial Conditions:
* The plant was at 100% power.
* Automatic Safety Injection occurs.
* The crew entersPath-1
Current Plant Conditions:
* Pressuriz.erlevel15% andslowlylowerinq
* RCS pressure 1400.psig.and slowly lowering
* RAB radiation levels are slowly rising
* RAB Sump levels are slowly rising
Which ONE (1) of the following describes the correct action to be taken?
A. Transition out ofPath-1to EPP-013, LOCAOutside of Containment, and isolate the
Low Head Safety Injection system.
B. Transition outofPath-1toEPP-013,LOCA Outside of Containment, and isolate the
High Head Safety Injection system.
C. RemaininPath-1and thencooldown and depressurize lAW EPP-009, Post-LOCA
Cooldownand Depressurization.
D. RemaininPath-1 and then establish cold leg recirculation lAW EPP-010, Cold Leg
Recirculation.
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* A LOCAhasoccurred on "B" Cold Leg.
* ECCS has NOT functioned as required.
,. All RCP's are TRIPPED.
* CET'sindicate 756°F.
* RVLISFull Range is 49%.
* Containment pressure is6 psig and rising slowly.
* All SG pressures are at 1050 psig.
Which ONE of the following procedures will the crew implement for these conditions,
and what actions will be taken to mitigate this event?
A. Enter FRP-C.1, Response To Inadequate Core Cooling;
Depressurize allintactSGsto 80psig by dumping steam at maximum rate.
B. Enter FRP-C.2, Response To Degraded Core Cooling;
Depressurize all intact 'SGs to 80 psigbydumpingsteam at maximum rate.
C. Enter FRP-C.1 ,Response To Inadequate Core Cooling;
Depressurize all intact SGs to 80 psig by dumping steam not to exceed a 100°F/hr
cooldown rate.
D. Enter FRP-C.2, Response To Degraded 'Core Cooling;
Depressurize all intact SGs to 80 psig by dumping steam notto exceed a 100°F/hr
cooldown rate.
Thursday, March 20, 2008 10:37:05 AM 78
Harris2008SRO Exam Rev FINAL
92.
Given. the following:
* A reactor trip has occurred .due to a loss of offsitepower.
* The operating crew is performing actions of EPP-005, Natural Circulation
Cooldown.
* "A" Train RVLIS is out of service.
* The crew has commenced RCScooldown and depressurization.
* RCSpressureis 1780 psig and trending DOWN.
* RCS Tave is 448 of and trending DOWN.
* All SGpressures are at 960 .psiq and trending DOWN slowly.
* Pressurizer level is 350/0 and trending UP slowly.
* Plant management determines that RCS cooldown rate MUST be performed at
approximately 60 °F/hrdue to secondary inventory concerns.
Which ONE of the following actions will be required in accordance with EPP-005?
A. Remain in EPP-0.05and continue cooldownand depressurization.
B. Actuate safety injection and go toPath-1, entry point A.
C. Transition to EPP-006, Natural Circulation Cooldown With Steam Void In Vessel
(With RVLIS).
D. Remain in EPP-005, stop depressurization and re-establish required subcooling .
Thursday, March 20, 2008 10:37:06 AM 79
Harris 2008 SRO Exam Rev FINAL
93.
Initial Conditions:
* A LOCA has occurred.
* The crew is performing actions of EPP-012, Loss of Emergency Coolant
Recirculation, based on plant conditions upon transition from Path-1.
* RWST level is 3% and lowering.
Current Conditions:
* Integrity CSF Status Tree indicates Orange.
Which ONE of the following describes the action and procedure usage required?
A. StopaH pumps taking suctionfromthe RWST;
Remain in EPP-012 because actions in EPP-012 are expected to cause an Orange
condition on *Integrity.
B. Reduce ECCSflow from the RWST toONE (1) train running;
Remain in EPP-Ot2 because actions in EPP-012 are expected to cause an Orange
condition on Integrity.
C. Stop all pumps taking suction from the RWST;
Go to FRP-P.1, Response to .Imminent Pressurized Thermal Shock.
D. Reduce ECCS flow from the RWSTto ONE (1)train running;
Go toFRP-P.1 ,Response to Imminent Pressurized Thermal Shock.
Thursday, March 20, 2008 10:37:06 AM 80
Harris 2008 SRO Exam Rev FINAL
94.
Given the following:
* The Unit experienced aStearn Generator Tube Rupture (SGTR)*on the "B"
Steam Generator (SG).
* The. crew is currently performing actions ot Path-z.
* After completing the initial cooldown using "A"and "C" Steam Generators, the
RO reports that"C"SG.pressurecontinues to lower.
Which ONE of the following correctly describes the NEXT action the crew should take
in accordance with Emergency Operating Procedures?
A. Immediately transition to EP.P-014, Faulted Steam Generator Isolation, to isolate
"C" SGand then go to EPP-020,SGTR With Loss Of Reactor Coolant: Subcooled
Recovery
B.' Immediately transition to EPP-014, Faulted Steam Generator Isolation, to isolate
the "C"SG and then return toPath-2 Entry Point J
C. CompletethedepressurizationinPath-2 to restore pressurizer .level, and then go to
EPP-020,SGTRWith Loss Of Reactor Coolant: SubcooledRecovery.
D. Complete the depressurization in Path-2 to restore pressurizer level, and then go to
EPP-014, Faulted Steam Generator Isolation.
Thursday, March 20, 200810:37:06 AM 81
Harris2008SRO Exam Rev FINAL'
95.
Initial Plant Conditions:
* The plant is at 100%.power.
* Chemistry, reports thefoHowing:
* Primary specific activity is 0.76microcuries per gram dose equivalent 1-131.
* Secondary specific activity is 0.03 microcuries per gram dose equivalent
1-131.
* Secondary conductivity isS micromhos.
Current Plant Conditions are:
* Chemistry reports the following:
* Primary specific activity is 0.85 microcuries per gram dose equivalent 1-131.
* Secondary specific. activity is 0.62 microcuriespergram dose equivalent
1-131.
* Secondary conductivity is 12 micromhos.
* The crew enters AOP-033, Chemistry Out of Tolerance.
Which ONE of the following actions is required in accordance with AOP-033?
A~ Remain in AOP-033 and checkforCondenser tube leakage. Initiate Turbine load
reductiontoless than 30%.
B. Go to AOP-032, HighRCS Activity based upon direction of AOP-033.
C. Remain in AOP-033 and isolate Auto-Chlorination of Service Water andCirc Water,
initiate Turbine load reduction to less than 30°/0.
D. Go to AOP-016, Excessive ReS Leakage, as directed by AOP-033.
Thursday, March 20,200810:37:06 AM 82
Harris 2008 SRO Exam Rev FINAL
96.
In Mode 1, which ONE of the following correctly states the basis for the Technical
Specification Safety Limits on the Reactor Core and the parameters that are used to
ensure that the Safety Limit is not violated?
A. Ensures Departure from Nucleate boiling does not occur by restricting operation to
within the nucleate b'oiling regime..
Reactor Thermal Power,HighestOperating Loop RCS Average Temperature, and
Pressurizer Pressure.
B. EnsuresDeparture from Nucleate boiling does not occur by restricting operation to
within the. nucleate boiling regime.
ReactorThermal Power, Highest Core Exit Thermocouple, and Pressurizer
Pressure.
C. Ensures Peak Centerline Temperature of the fuel is maintained less than 2200° F.
Reactor Thermal. Power,HighestOperatingLoop RCS Average Temperature, and
Pressurizer' Pressure.
D. Ensures Peak Centerline Temperature of the fuel is maintained less than 2200° F.
Reactor Thermal Power, Highest Core Exit Thermocouple, and Pressurizer
Pressure.
97.
Given the following plant conditions:
* Afuelshuffleisinpro,gressfollowinga refueling lAW FHP-014, Fuel and Insert
ShuffleSequence.
* You.are.thE3.SRO-FueIHandling forthefuelshuffle,
* A fuelassemblyhasjustbeen latched and raised for visual inspection.
* The Refueling Engineer reportsto you that the serial number on Attachment 1
does NOT matchthevisuallyverified serialnumber on the fuel assembly.
Which ONE(1) ofthefolJo.wingliststheactionsrequired by FHP-014, Fuel and Insert
Shuffle Sequence with regard to the latched fuel assembly?
A*. Lower the fuel assembly in the location it was removed from and unlatch
B. Move the fuel assembly to a temporary storage location and unlatch
C. Lower the fuel assembly in the location it was removed from but do NOT unlatch
D. Move the fuelassembly toa temporary storage location but do NOT unlatch
Thursday, March 20,2008 10:37:06 AM 83
Harris 2008 SRO Exam Rev FINAL
98.
Given the following plant conditions:
* The operating crew is lining up.to discharge the contents of the Treated L&HS
TankA to Cooling Tower Discharge IAWOP-120.1 0.04.
* It is also determined that a release is *required from the Secondary Waste
Sample Tank (SWST).
Which ONE (1}of the following provides the minimum approval requirements for this
release and what release of the SWST can occur simultaneously with the discharge of
the Treated L&HSTank IAW*OP-120.10.04?
A. Manager -Operations permission required;
ONLY a ContinuQusReleaseofSWSTmay occur simultaneously.
B. S-SO permission required;
ONLY a Continuous Release of SWSTmayoccur simultaneously.
C. Manager- Operations permission required'
BOTH a Continuous or a Batch Release of SWST may occur simultaneously.
D. S-SOpermission required;
BOTH a Continuous or a Batch Release of SWST may occur simultaneously.
Thursday, March 20, 2008 10:37:06 AM 84
Harris 2008SROExam Rev FINAL
99.
Initial plant conditions:
* "A" Train Equipment in service
* "B" *ESWPumpis under clearance for motor replacement
* TDAFW Pump is under clearance fortappet nut replacement
Time Log Entry
1230 SBLOCA inside containment (-200gpm)
1231 Reactor Trip & Safety Injection initiated
1236 Containment Pressure 3.3 psig and rising
1238 Loss of Offsite Power occurs
1240 Crew notes "A" CCW Pump has tripped and can not be restarted
1242 CURRENT TIME
All other plant equipment responds as expected for the event in progress.
Which ONE(1) of the following is the HIGHEST Emergency Classification entered for
this event asof CURRENT TIME?
A. ALERT, EAL5-1-2
B. ALERT, EAL8-2-2
C. SITE AREA EMERGENCY, EAL 2-1-3
D. SITE AREA EMERGENCY, EAL 8-2-3
Thursday, March 20, 200810:37:06 AM 85
Harris 2008 SRO Exam Rev FINAL
100.
Given the following:
* The plant is in Mode 6, Core Alterations in progress.
* Battery 1B-SBisout of service.
* Maintenance reports that Battery tA-SAelectrolyte is overflowing in several
cells.
Which ONE of thefollowinqis.theTechnical Specification action required and its
bases?
A. Restore an Emergency Battery to Operable status within 1 Hour;
A subsequent loss of off-site power would result in loss of all DC subsystems with
attendant 10ssofESF functions.
B.lmmediatelY suspendatloperations involvlnq Core Alterations, positive reactivity
changes, or movement of irradiated fuel;
A subsequent loss of off-site power would result in loss of all DC subsystems with
attendant loss of ESF functions.
C. Restore an Emergency Battery to Operable status within 1 Hour;
Sufficient control and instrumentation capability is no longer available to monitor
and maintain the unit status
D. Immediptely.suspendalloperationsinvolving Core Alterations, positive reactivity
changes,or movement of irradiated fuel;
Sufficient control and instrumentation capability is no longer available to monitor
and maintain theunitstatus
You have completed the.test!
Thursday, March 2Q, 200810:37:06 AM 86
Harris 2008-301 SRO Initial License Examination References
1. EAL Flowpath 06-1 Side One Only 2. Steam Tables }}