ML022670133
| ML022670133 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/22/2002 |
| From: | Ernstes M Division of Reactor Safety II |
| To: | Scarola J Carolina Power & Light Co |
| References | |
| 50-400/02301 50-400/02301 | |
| Download: ML022670133 (123) | |
See also: IR 05000400/2002301
Text
Final Submittal
(Blue Paper)
Reactor Operator Written Examination
SHEARON HARRIS
EXAM 2002-301
50-400
AUGUST 26 - 29, 2002
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 1
Given the following conditions:
"* The Main Turbine is operating at 1800 rpm in preparation for synchronizing to the
grid.
"* Reactor power is being maintained at approximately 12% using the Condenser Steam
Dumps.
- Condenser Vacuum Pump 'A' is under clearance.
- Condenser Vacuum Pump 'B' trips.
Assuming NO operator actions, condenser vacuum degrades until ...
a. the turbine and the reactor trip, and condenser steam dump operation is blocked
b. the turbine trips, and condenser steam dump operation is blocked, but the reactor
remains critical
c. condenser steam dump operation is blocked, but vacuum stabilizes above the
turbine trip setpoint
d. the turbine and reactor trip, but vacuum stabilizes above the steam dumps
interlock setpoint
ANSWER:
a. the turbine and the reactor trip, and condenser steam dump operation is blocked
5/o
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 2
Given the following conditions:
A reactor trip and safety injection have occurred.
Steam Generator parameters have decreased to the following values:
SG LEVEL PRESSURE
A 32% 870 psig
B 12% 420 psig
C 34% 830 psig
NO operator actions have been taken.
Which of the following components is mispositioned?
a. LFCV-2051B, MDAFW FCV to B SG, CLOSED
b. lFCV-2051C, MDAFW FCV to C SG, OPEN
c. 1MS-70, MS B SG to AFW Turbine, CLOSED
d. 1MS-72, MS C SG to AFW Turbine, OPEN
ANSWER:
d. 1MS-72, MS C SG to AFW Turbine, OPEN
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 3
If a Containment Ventilation Isolation (CVI) signal occurred, which of the following
Containment Ventilation fans would NOT trip directly from the CVI signal, but would
trip as a result of being interlocked with other fans?
a. Normal Purge Supply fans (AH-82 A & B)
b. Pre-Entry Purge Makeup fans (AH-81 A & B)
c. Airborne Radioactivity Removal fans (S-lA & B)
d. CNMT Pre-entry Purge Exhaust fans (E-5 A & B)
ANSWER:
b. Pre-Entry Purge Makeup fans (AH-81 A & B)
&2 aý3. 0/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 4
Hydrogen concentration in the Waste Gas System, downstream of the catalytic
recombiners, is limited to 4% to ...
a. maintain levels below flammability limits.
b. ensure proper operation of the recombiner.
c. limit the volume of waste gas generated.
d. minimize the radioactive content of the waste gas decay tanks.
ANSWER:
a. maintain levels below flammability limits.
//t, 07/71, ;, ; J7
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 5
Given the following conditions:
- A large break LOCA has occurred.
- Containment pressure peaked at 15 psig and has decreased to 6 psig.
accordance with
- Actions are being taken to place the plant in cold leg recirculation in
EPP-010, "Transfer to Cold Leg Recirculation."
Pumps are
- Two (2) CSIPs, two (2) RHR Pumps, and two (2) Containment Spray
running.
recirculation and is in
- The crew has just completed alignment of Safety Injection for
the Reactor Operator
the process of verifying Containment Spray alignment when
notes Containment Sump level is 25%.
Which of the following actions should be taken?
a. * Stop both trains of Containment Spray
- Maintain both trains of RHR Pumps and CSIPs operating
b. * Stop both trains of Containment Spray
- Stop one (1) train of RHR Pumps and CSIPs
c. * Stop one (1) train of Containment Spray
- Stop one (1) train of RHR Pumps and CSIPs
d. * Stop both trains of Containment Spray
- Stop both trains of RHR Pumps and CSIPs
ANSWER:
d. * Stop both trains of Containment Spray
- Stop both trains of RHR Pumps and CSIPs
/4 b&,2641/t ,5
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 6
Given the following conditions:
- The plant is operating at 93% power.
- Condensate Pump 1B trips on motor overcurrent.
- Condensate Booster Pump 1B trips as a result of the trip of Condensate Pump lB.
Which of the following describes the effect of these events on the Main Feed Pumps
AND the required operator action?
a. * Main Feed Pumps IA and lB remain running
- Trip the reactor and go to PATH- I
b. * Main Feed Pumps 1A and lB remain running
0 Verify a turbine runback occurs
c. * Main Feed Pump 1B trips
- Trip the reactor and go to PATH-1
d. * Main Feed Pump lB trips
- Verify a turbine runback occurs
ANSWER:
c. * Main Feed Pump lB trips
- Trip the reactor and go to PATH-1
656 0,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 7
Given the following conditions:
- The plant is solid in Mode 5 with one (1) RCP in operation.
- RHR Pump A-SA is providing letdown flow with PK-145.1, LTDN PRESSURE
1CS-38, in MAN.
- CSIP A-SA is providing RCS makeup and seal injection.
If instrument air is lost to 1CS-38 (PCV-145), the operator should ...
a. trip CSIP A-SA.
b. trip RHR Pump A-SA.
c. maintain letdown flow using HC-142.1, RHR Letdown 1CS-28.
d. open one PRZ PORV.
ANSWER:
a. trip CSIP A-SA.
/9 04 S ,2 -0,?
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 8
Given the following conditions:
"* An I&C technician reports that both of the Control Room Normal Outside Air Intake
Isolation radiation monitors have failed detectors.
"* It will take somewhere between four (4) and eight (8) hours to replace the detectors.
Which of the following states the action which must be taken within one (1) hour, in
accordance with Technical Specification 3.3.3.1 ?
a. Establish operation of the Control Room Emergency Filtration System in the
Recirculation Mode of Operation
b. Initiate the preplanned alternate method of radiation monitoring
c. Return the monitors to service, or be in Hot Standby within the next six (6) hours
d. Perform a surveillance test on the Control Room Emergency Filtration System, or
be in Hot Standby within the next six (6) hours
ANSWER:
a. Establish operation of the Control Room Emergency Filtration System in the
Recirculation Mode of Operation
'1/2 ý,-,7
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 9
Given the following conditions:
- A reactor trip occurred from 75% power approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.
- The operating crew is attempting to close the Reactor Trip Breakers.
- All controls and switches are in their normal alignment for plant conditions.
Assuming all other conditions are met for closing the Reactor Trip Breakers, which of the
following sets of conditions would physically allow the breakers to close when the
REACTOR TRIP BREAKERS TRAINS A&B switch is taken to the CLOSE position?
a. * SG 'A' level is 18%
- IR channel N-36 is failed high
b. * SG 'A' level is 18%
- RCP 'A' is secured
c. * IR channel N-36 is failed high
- PRZ pressure is 1920 psig
d. * PRZ pressure is 1920 psig
- RCP 'A' is secured
ANSWER:
d. * PRZ pressure is 1920 psig
- RCP 'A' is secured
A14 m/ & //I
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 10
The plant is in Mode 1.
and what
When entering the Personnel Air Lock, how is the inside door checked closed
would be the consequences of attempting to enter with the inside door open?
a. * The outside door contains a visual indication (red/green light) of the inside
door's position
- Technical Specifications would be violated
b. * The equalizing valve will NOT open if the inside door is open
- Technical Specifications would be violated
c. * The outside door contains a visual indication (red/green light) of the inside
door's position
- An interlock will prevent entry if the inside door is open
d. * The equalizing valve will NOT open if the inside door is open
- An interlock will prevent entry if the inside door is open
ANSWER:
inside
c. * The outside door contains a visual indication (red/green light) of the
door's position
0 An interlock will prevent entry if the inside door is open
kl' )- / )g
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 11
Given the following conditions:
- Containment Pressure Channel I, PT-950A, is in TEST for surveillance testing
purposes.
- Containment Pressure Channel III, PT-952A, is failed low.
- A large break LOCA occurs and actual Containment Pressure reaches 21 psig.
Which of the following describes the response of the Containment Spray system?
a. NEITHER train of Containment Spray will automatically actuate
b. ONLY Train 'A' of Containment Spray will automatically actuate
c. ONLY Train 'B' of Containment Spray will automatically actuate
d. BOTH trains of Containment Spray will automatically actuate
ANSWER:
d. BOTH trains of Containment Spray will automatically actuate
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 12
Given the following conditions:
on both trains have
- Several Fuel Handling Building (FHB) area radiation monitors
reached the high alarm setpoint.
the operator to verify that the
- AOP-005, "Radiation Monitoring System," has directed
lineup.
FHB ventilation has shifted to the emergency exhaust
are RUNNING.
- Both FHB Emergency Exhaust Fans, E-12 and E-13,
Which of the following additional alignments is expected?
AH-59)
a. * FHB Operating Floor Supply Fans (AH-56, AH-57, AH-58,
SECURED
FL-D21, FL-D22)
- FHB Normal Exhaust Isolation Dampers (FL-D4, FL-D5,
OPEN
AH-58, AH-59)
b. * FHB Operating Floor Supply Fans (AH-56, AH-57,
RUNNING
FL-D21, FL-D22)
- FHB Normal Exhaust Isolation Dampers (FL-D4, FL-D5,
OPEN
AH-58, AH-59)
c. * FHB Operating Floor Supply Fans (AH-56, AH-57,
RUNNING
FL-D21, FL-D22)
- FHB Normal Exhaust Isolation Dampers (FL-D4, FL-D5,
SHUT
AH-57, AH-58, AH-59)
d. * FHB Operating Floor Supply Fans (AH-56,
SECURED
FL-D21, FL-D22)
- FEB Normal Exhaust Isolation Dampers (FL-D4, FL-D5,
SHUT
ANSWER:
AH-58, AH-59)
d. o FHB Operating Floor Supply Fans (AH-56, AH-57,
SECURED
FL-D21, FL-D22)
- FHB Normal Exhaust Isolation Dampers (FL-D4, FL-D5,
SHUT
3/4ý ý,) ,/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 13
Given the following conditions:
- A loss of offsite power has occurred with the plant at 100% power.
- The operating crew is performing the actions of EOP-EPP-001, "Loss of AC Power to
LA-SA and 1B-SB Buses."
- SGs 'A' and 'B' are being depressurized to 180 psig.
Which of the following describes the method used AND the bases for depressurizing SGs
'A' and 'B' to 180 psig?
a. e Method - Operate the SG PORVs 'A' and 'B' from the MCB
'C' to the RCS
b. * Method - Operate the SG PORVs 'A' and 'B' locally
'C' to the RCS
c. * Method - Operate the SG PORVs 'A' and 'B' from the MCB
d. * Method - Operate the SG PORVs 'A' and 'B' locally
ANSWER:
d. * Method - Operate the SG PORVs 'A' and 'B' locally
it21X 05 .2,C p
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 14
(DEI-131) activity has exceeded
Chemistry reports that the RCS Dose Equivalent Iodine
the limit and a shutdown is required.
than 5000 F to ...
The plant is to be placed in Hot Standby with T-avg less
fission products in
a. enhance the ability of the mixed bed demineralizers to remove
the event of a small break LOCA.
products on the core
b. minimize the deposition of fission products and activation
surfaces in the event of a large break LOCA.
in the event of a large
c. prevent additional fuel cladding oxidation from occurring
break LOCA.
in the event of a SGTR.
d. prevent the release of radioactivity to the environment
ANSWER:
in the event of a SGTR.
d. prevent the release of radioactivity to the environment
ty/ o7$AV/Yp
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 15
Given the following conditions:
- The plant is operating at 50% power.
- Bank 'D' Control Rods are at 140 steps.
- All control systems are in automatic and at program values.
- The Median Select AT Circuit output has failed high.
Which of the following will occur?
a. ALB-020-2-1, TURBINE AUTOMATIC LOADING STOP, alarms
b. ALB-013-8-3, BANK LO-LO INSERTION LIMIT, alarms
c. Bank 'D' Control Rods step inward
d. Charging flow increases
ANSWER:
b. ALB-013-8-3, BANK LO-LO INSERTION LIMIT, alarms
1-14 /6t'/(//S9
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 16
some selected 480-V
Which one of the following statements describes the reason why
MCC loads have two supply breakers in series?
a. The loads are safety-related, requiring redundant train protection
for the
b. The loads are in Containment, requiring redundant overcurrent protection
with different
c. The loads are safety-related, requiring redundant protection
overcurrent trip setpoints
redundant
d. The loads are capable of being operated from the ACP, requiring
control functions
ANSWER:
protection for the
b. The loads are in Containment, requiring redundant overcurrent
1//1 ) 22 ./ 2 7
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 17
Given the following conditions:
- Boric Acid Tank concentration is 7100 ppm.
Which of the following RWMU Flow Controller potentiometer settings will result in the
HIGHEST ACCEPTABLE total automatic Primary Makeup System flow rate for these
conditions?
a. 5.63
b. 6.25
C. 6.88
d. 7.50
ANSWER:
C. 6.88
- z./ A5
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 18
Given the following conditions:
- The site has experienced a loss of offsite power.
- EDG 'A' has started and sequenced all loads.
How long can the EDG operate at full load under these conditions with NO adverse
effects?
a. One (1) minute
b. Five (5) minutes
c. Until Jacket Water Cooler Outlet temperature exceeds 185 0 F
d. Until Lube Oil Cooler Outlet temperature exceeds 1850 F
ANSWER:
a. One (1) minute
3/4)0,40z ,. ,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 19
The plant is operating at 100% power with the following conditions:
Time Ambient Temp CT Basin Temp
1200 35 OF 64 OF
1600 20 OF 60 OF
2000 10 OF 58 OF
Which of the following describes the correct CT Deicing Gate Valve alignment for these
conditions?
1600 2000
a. Full Open Full Open
b. Full Open Half Open
c. Half Open Full Open
d. Half Open Half Open
ANSWER:
b. Full Open Half Open
WW z)7
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 20
Given the following conditions:
- A fire has occurred in cable spread Room A - RAB 286 which requires a plant
shutdown.
- 'A' SG pressure is 1000 psig.
- 'A' SG wide range level is 78%.
- 'A' SG narrow range level is unavailable.
Which of the following actions should be taken?
a. Decrease AFW flow to lower 'A' SG wide range level to < 75%
b. Decrease AFW flow to lower 'A' SG wide range level to < 57%
c. Increase AFW flow to raise 'A' SG wide range level to > 57%
d. Increase AFW flow to raise 'A' SG wide range level to > 75%
ANSWER:
a. Decrease AFW flow to lower 'A' SG wide range level to < 75%
x14 -- ,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 21
Given the following conditions:
- The plant is operating at 30% power.
- All control systems are in automatic.
- T-ref fails low.
Which of the following describes the INITIAL response of the rod control system?
a. Step in at 8 steps per minute to reduce Tavg to 553TF
b. Step in at 8 steps per minute to reduce Tavg to 557fF
0
c. Step in at 72 steps per minute to reduce Tavg to 553 F
d. Step in at 72 steps per minute to reduce Tavg to 557'F
ANSWER:
d. Step in at 72 steps per minute to reduce Tavg to 557fF
A 0o/At/A5-'
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 22
While establishing a bubble in the PRZ per GP-002, "Normal Plant Heatup From Cold
Solid to Hot Subcritical MODE 5 to MODE 3," letdown pressure control valve 1CS-38
(PK-145.1), Low Pressure Letdown Pressure Controller, opens.
Which of the following describes why PK-145.1 opens?
a. Thermal expansion of liquid in the pressurizer /
b. Change in CCW heat load
c. Spray valves are shut while drawing a bubble
d. Switchover of letdown to orifices from RHR-CVCS cross-connect
ANSWER:
a. Thermal expansion of liquid in the pressurizer
f/A 016X1 do4
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 23
Given the following conditions:
Valves
- Feed water flow is being transferred from the Main Feed Regulating Bypass
to the Main Feed Regulating Valves.
- All six (6) valves are in MANUAL control and are open.
- A reactor trip occurs and RCS Tavg stabilizes at no-load conditions.
Regulating Valves
Which of the following describes the expected status of the Main Feed
and the Main Feed Regulating Bypass Valves?
a. * Main Feed Regulating Valves OPEN
- Main Feed Regulating Bypass Valves OPEN
b. * Main Feed Regulating Valves OPEN
0 Main Feed Regulating Bypass Valves CLOSED
c. * Main Feed Regulating Valves CLOSED
- Main Feed Regulating Bypass Valves OPEN
d. * Main Feed Regulating Valves CLOSED
0 Main Feed Regulating Bypass Valves CLOSED
ANSWER:
C. Main Feed Regulating Valves CLOSED
Main Feed Regulating Bypass Valves OPEN
e9S
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 24
Given the following conditions:
- The plant is being heated up with RCS temperature at 280TF.
- Containment pressure is indicating (-) 0.8 inches WG.
Assuming NO operator actions, which of the following will automatically occur?
a. 1CB-2 & CB-D51 SA will open when Containment pressure decreases to (-) 1.0
inches WG; 1CB-6 & CB-D52 SB will open if Containment pressure continues to
decrease to (-) 2.25 inches WG
b. 1CB-6 & CB-D52 SB will open when Containment pressure decreases to (-) 1.0
inches WG; 1CB-2 & CB-D51 SA will open if Containment pressure continues to
decrease to (-) 2.25 inches WG
c. 1CB-2 & CB-D51 SA and 1CB-6 & CB-D52 SB will both open when
Containment pressure decreases to (-) 1.0 inches WG
d. 1CB-2 & CB-D51 SA and 1CB-6 & CB-D52 SB will both open when
Containment pressure decreases to (-) 2.25 inches WG
ANSWER:
d. 1CB-2 & CB-D51 SA and 1CB-6 & CB-D52 SB will both open when
Containment pressure decreases to (-) 2.25 inches WG
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 25
A loss of 125 VDC bus DP-1B-SB has just occurred.
Which of the following AFW Pumps, if any, are considered inoperable?
a. NO AFW pumps are inoperable
b. ONLY MDAFW Pump lB-SB is inoperable
c. ONLY the TDAFW Pump is inoperable
d. BOTH MDAFW Pump 1B-SB and the TDAFW Pump are inoperable
ANSWER:
d. BOTH MDAFW Pump lB-SB and the TDAFW Pump are inoperable
03 /ýý O0
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 26
Given the following conditions:
- The plant is being maintained at 1900 psig.
- RCS temperature is 500'F and stable.
~Csm lctdownt ztnd nor-mal letdown are both in zzrVmz.
c" C) dLý 14vr~-ma Lýcet-t&,ýs tCt
The following indications are noted:
"* Normal letdown is 67 gpm
"* RCP IA seal injection flow is 9 gpm
"* RCP 1B seal injection flow is 7 gpm
"* RCP 1C seal injection flow is 8 gpm
"* RCP 1A seal leakoff flow is 2.5 gpm
"* RCP 1B seal leakoff flow is 2.0 gpm
"* RCP IC seal leakoff flow is 2.5 gpm
In order to maintain pressurizer level constant, charging flow should be adjusted to
indicate ...
a. 36 gpm.
b. 43 gpm.
c. 50 gpm.
d. 74 gpm.
ANSWER:
c. 50 gpm.
d4A
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 27
Which of the following describes the start sequence of the Fire Pumps?
a. The Motor Driven Fire Pump will only start after a 30 second time delay if the
Diesel Driven Fire Pump has received a start signal and is not maintaining Ž 100
psig.
b. The Motor Driven Fire Pump will start at * 93 psig and the Diesel Driven Fire
Pump will start at * 83 psig.
c. The Diesel Driven Fire Pump will start at * 93 psig and the Motor Driven Fire
Pump will start at * 83 psig.
d. The Diesel Driven Fire Pump will only start after a 30 second time delay if the
Motor Driven Fire Pump has received a start signal and is not maintaining Ž 100
psig.
ANSWER:
b. The Motor Driven Fire Pump will start at * 93 psig and the Diesel Driven Fire
Pump will start at * 83 psig.
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 28
Given the following conditions:
- An operator is required to complete a valve lineup in an area where the radiation level
is 50 mrem/hour.
- The operator's current annual Total Effective Dose Equivalent (TEDE) is 1450 mrem.
- All of the operator's dose has been received while working at Harris Nuclear Plant.
What is the MAXIMUM time that the operator may work in this area and still remain
within CP&L's Annual Administrative Dose Limit?
a. One (1) hour
b. Eleven (11) hours
c. Fifty-one (51) hours
d. Seventy-one (71) hours
ANSWER:
b. Eleven (11) hours
fAI &04,/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 29
Given the following:
"* The unit is at 45% power.
"* RCP 'B' trips.
"* All SG level controllers are in AUTO.
"* NO operator action is taken.
Which of the following describes the response of SG 'B' level?
a. Increases to approximately 70% and stabilizes without any significant decrease in
level during the transient
b. Decreases to approximately 30% and stabilizes without any significant increase in
level during the transient
c. Increases to approximately 70% and then decreases to approximately 30% before
stabilizing
d. Decreases to approximately 30% and then increases to approximately 70% before
stabilizing
ANSWER:
d. Decreases to approximately 30% and then increases to approximately 70% before
stabilizing
b1 DS0/ 7 /9//I , De
4/i
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 30
Given the following conditions:
Shortly following a loss of offsite power, the following indications are noted on Train
'A' Emergency Safeguards Sequencer (ESS) light box:
CNMT FAN CNMT FAN CNMT FAN CNMT FAN SW BSTR PUMP
HIGH AH-2B LOW AH-2A LOW AH-2B START A
HIGH AH-2A
OFF OFF OFF LIT
LIT
- Prior to AUTO ACT COMPLETE MAN LOAD PERMITTED (Load Block 9)
lighting, a steam break occurs inside Containment, causing a Safety Injection.
Following completion of the sequencer, which of the following indications would be
expected on the Train 'A' ESS light box?
CNMT FAN CNMT FAN CNMT FAN CNMT FAN SW BSTR PUMP
HIGH AH-2B LOW AH-2A LOW AH-2B START A
HIGH AH-2A
LIT OFF OFF LIT
a. LIT
b. LIT LIT OFF OFF OFF
OFF LIT OFF LIT
c. OFF
OFF LIT OFF OFF
d. OFF
ANSWER:
c. OFF OFF LIT OFF LIT
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 31
Given the following conditions:
- A reactor trip and safety injection occurred several minutes ago.
- A loss of offsite power has just occurred.
- Both 6.9 KV buses IA-SA and lB-SB are being supplied by the diesel generators.
Which of the following components has NO power available?
a. Containment Fan Cooler AH-1
b. Containment Fan Coil Unit AH-37A
c. Primary Shield Cooling Fan S-2A
d. Reactor Support Cooling Fan S-4A
ANSWER:
b. Containment Fan Coil Unit AH-37A
2 /U . 0/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 32
Given the following plant conditions:
- The plant is operating at 100% power.
- 1CS-7, 45 GPM Letdown Orifice A, and lCS-8, 60 GPM Letdown Orifice B, are
closed.
- 1CS-9, 60 GPM Letdown Orifice C, is open.
- The Reactor Makeup System is setup properly and is in AUTO.
- VCT level transmitter, LT- 112, fails high.
Assuming NO operator action, which of the following describes the plant response?
a. Charging Pump suction is eventually lost as VCT level decreases
b. 1CS-120 (LCV- 15A), Letdown VCT/Hold Up Tank, aligns to the VCT and NO
automatic makeup will occur
c. ICS-120 (LCV-1 15A), Letdown VCT/Hold Up Tank, aligns to the HUT and a
CONTINUOUS makeup to the VCT will occur
d. 1CS-120 (LCV- 15A), Letdown VCT/Hold Up Tank, aligns to the HUT and
INTERMITTENT makeups at normal setpoints will occur
ANSWER:
d. 1CS-120 (LCV-115A), Letdown VCT/Hold Up Tank, aligns to the HUT and
INTERMITTENT makeups at normal setpoints will occur
St o611, 6 (0
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 33
Given the following conditions:
- CCW Pump 'A' needs to be removed from service for motor replacement.
Which of the following design features is associated with this evolution AND what is the
basis for this design feature?
a. A key-operated interlock is used to prevent aligning CCW Pumps 'A' and 'C' to
6.9 KV Bus 1A-SA simultaneously
b. A key-operated interlock is used to prevent aligning CCW Pump 'C' to 6.9 KV
Buses lA-SA and 1B-SB simultaneously
c. A common breaker is used to prevent aligning CCW Pumps 'A' and 'C' to 6.9 KV
Bus 1A-SA simultaneously
d. A common breaker is used to preVent aligning CCW Pump 'C' to 6.9 KV Buses
1A-SA and lB-SB simultaneously
ANSWER:
a. A key-operated interlock is used to prevent aligning CCW Pumps 'A' and 'C' to
6.9 KV Bus 1A-SA simultaneously
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 34
Given the following conditions:
- The plant is currently operating at 30% power.
- Core bumup is 300 EFPD.
- Control Bank 'D' rods are inadvertently withdrawn from 135 steps to 155 steps.
BEFORE RCS temperature increases in response to the rod withdrawal, reactor power
will increase from 30% to approximately ...
a. 32%.
b. 36%.
c. 40%.
d. 44%.
ANSWER:
b. 36%.
bo l l SV
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 35
Given the following conditions:
- The plant is operating at 68% power.
- Control Bank D, Group 1, step counter indicates 187 steps.
- Control Bank D, Group 2, step counter indicates 187 steps.
- Control Bank D rod heights are as follows:
Group 1 Rod Steps
H2 186
B8 186
H14 192
P8 180
Group 2 Rod Steps
F6 186
F1O 198
K10 186
K6 180
Which of the following describes the Technical Specification action, if any, that must be
taken within one (1) hour for these conditions?
a. NO actions are required
b. Realign rods F1O and K6 within 12 steps of each other
c. Reduce power below 50%
d. Determine the position of the rods using the movable incore detectors
ANSWER:
a. NO actions are required
Ii/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 36
Given the following conditions:
- The AutoLog is NOT functioning.
- The Reactor Operator is maintaining a manual log.
The following log entries have been made:
- 0956 B-SB CSIP trip
- 1005 Started A-SA CSIP per AOP-018
- 1011 Established normal letdown
At 1030, the Reactor Operator realizes he forgot to make a 0957 entry that letdown had
been isolated.
Which of the following entries would be a proper entry in accordance with OMM-0 16,
Operator Logs?
a. * 1030 Isolated normal letdown
b. L.E. 1030 Isolated normal letdown
c. *0957 Isolated normal letdown
d. L.E. 0957 Isolated normal letdown
ANSWER:
d. L.E. 0957 Isolated normal letdown
k1 C"ý)" 1,2ý
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 37
Given the following conditions:
"* Following a large break LOCA, a transition has been made from EPP PATH- I to
EPP-010, "Transfer to Cold Leg Recirculation."
"* The operator attempts to open 1RH-25, RHR A to Charging Pump Suction Valve, and
1RH-63, RHR B to Charging Pump Suction Valve.
Which of the following describes a condition that prevents 1RH-63 from opening AND
the actions that should be taken?
a. * 1CS-752, CSIP 'B' Alternate Miniflow, failed to close.
decreases to 3% and then secure RHR Train 'B'.
b. a 1SI-301, CNMT Sump to RHR Pump 'B' Suction, failed to open.
decreases to 3% and then secure RHR Train 'B'.
c. * 1CS-752, CSIP 'B' Alternate Miniflow, failed to close.
- Close lCS-753, CSIP 'B' Alternate Miniflow Isolation, and open 1RH-63,
RHR B to Charging Pump Suction Valve.
d. * 1SI-301, CNMT Sump to RHR Pump 'B' Suction, failed to open.
RHR B to Charging Pump Suction Valve.
ANSWER:
c. * 1CS-752, CSIP 'B' Alternate Miniflow, failed to close.
RHR B to Charging Pump Suction Valve.
3/4 b0 k koq,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 38
Given the following conditions:
- The plant is operating at 100% power.
- Spent fuel is being moved in Spent Fuel Pool 'B'.
- The suction pipe from Spent Fuel Pool 'B' to the Spent Fuel Pool Cooling Pump
completely severs.
Level in the Spent Fuel Pool will decrease and stabilize at ...
a. 18 feet above the fuel assemblies. Makeup should be initiated using AOP-013,
"Fuel Handling Accident."
16,
b. 18 feet above the fuel assemblies. Makeup should be initiated using OP-1
"Fuel Pool Cooling System."
c. 21 feet above the fuel assemblies. Makeup should be initiated using AOP-013,
"Fuel Handling Accident."
OP-1 16,
d. 21 feet above the fuel assemblies. Makeup should be initiated using
"Fuel Pool Cooling System."
ANSWER:
above
18 feetPool Cooling assemblies. Makeup should be initiated using OP-1 16,
the fuelSystem."
"Fuel
A/A D336),2CD3
o
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 39
Given the following conditions:
"* The plant has tripped from 100% power due to a trip of B'RCP.
"* 'A' and 'C' RCPs are running.
Which of the following is the expected RVLIS Dynamic Head indication?
a. 36%
b. 41%
c. 63%
d. 100%
ANSWER:
c. 63%
-P,/,4t 0
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 40
Given the following conditions:
- The plant is operating at 40% power.
- AOP-005, "Radiation Monitoring System," has been entered.
As a result of the high alarm, which of the following will automatically close?
a. 1CC-252, RCP Thermal Barrier Flow Control Valve
b. 3WC-4, WPB CCW Surge Tank Overflow Valve
c. 1CC-304, CCW to Gross Failed Fuel Detector
d. 3WC-7, WPB CCW Surge Tank Drain Valve
ANSWER:
b. 3WC-4, WPB CCW Surge Tank Overflow Valve
'1/4 ~l o
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 41
The following post-SGTR cooldown procedures all cooldown and depressurize the
to RHR conditions:
- EPP-017, "Post SGTR Cooldown Using Backfill"
- EPP-018, "Post SGTR Cooldown Using Blowdown"
- EPP-019, "Post SGTR Cooldown Using Steam Dump"
in EPP-017
Which of the following describe how the depressurization and cooldown
differs from that in EPP-018 and EPP-019?
a. * EPP-017 maintains RCS pressure above the ruptured SG pressure
pressure
b. * EPP-017 maintains RCS pressure below the ruptured SG pressure
pressure
c. * EPP-017 maintains RCS pressure below the ruptured SG pressure
SG pressure
- EPP-018 and EPP-019 maintain RCS pressure above the ruptured
d. * EPP-017 maintains RCS pressure the same as the ruptured SG pressure
ANSWER:
b. * EPP-017 maintains RCS pressure below the ruptured SG pressure
pressure
4 C.'. y7
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 42
Given the following conditions:
- A Control Bank 'D' rod has dropped into the core while operating at 100% power.
- The operating crew has reduced power to 74%.
- Three (3) hours later, they are attempting to withdraw the dropped rod.
In accordance with AOP-001, "Malfunction of Rod Control and Indication System," to
maintain programmed Tavg while recovering the dropped rod ...
a. raise turbine load.
b. reduce turbine load.
c. borate the RCS.
d. dilute the RCS.
ANSWER:
a. raise turbine load.
3/4,d
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 43
The plant is in Mode 1.
VCT pressure has decreased to 8 psig.
Which of the following is the effect on the plant?
a. VCT water flashes to steam
b. Insufficient cooling is available to the No. 2 RCP seals
c. Insufficient seal injection is available to the RCPs
d. CSIPs begin cavitating due to gas binding
ANSWER:
b. Insufficient cooling is available to the No. 2 RCP seals
4b116 . D00
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 44
Given the following conditions:
- A plant startup is being performed per GP-005, "Power Operation (MODE 2 to
MODE 1)."
- The Steam Dump Controller has been incorrectly set at 89%.
While preparing to latch the Main Turbine, RCS temperature will be maintained at
approximately ...
a. 553TF.
b. 557 0F.
c. 562TF.
d. 5640 F.
ANSWER:
c. 5620 F.
4K/4 03M6
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 45
Given the following conditions:
"* The plant is operating at 100% power when a high radiation condition occurs inside
containment.
"* RC-3561A, Containment Ventilation Isolation radiation monitor (Train A), goes into
high (RED) alarm.
"* RC-3561B, Containment Ventilation Isolation radiation monitor (Train B), is out-of
service for testing.
"* RC-3561C, Containment Ventilation Isolation radiation monitor (Train A), does
NOT respond to the high radiation condition.
"* RC-3561D, Containment Ventilation Isolation radiation monitor (Train B), goes into
high (RED) alarm.
Which train(s) of Containment Ventilation Isolation will actuate, if any?
a. NEITHER Train 'A' NOR 'B'
b. Train 'A' ONLY
c. Train 'B' ONLY
d. BOTH Train 'A' AND 'B'
ANSWER:
d. BOTH Train 'A' AND 'B'
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 46
Given the following conditions:
- The unit is in Mode 4, performing a cooldown on RHR.
- Both trains of CCW are in service.
- NSW Pump 'A' is operating.
- NSW Pump 'B' is in standby.
- Both ESW Pumps are available, but are NOT running.
- NSW Pump 'A' experiences a sheared shaft.
Which of the following automatically occurs AND what is the effect on the plant
cooldown?
a. * ESW aligns on a low flow signal to cool Train 'A' CCW ONLY
b. * ESW aligns on a low flow signal to cool BOTH trains of CCW.
c. * ESW aligns on a low pressure signal to cool Train 'A' CCW ONLY.
d. * ESW aligns on a low pressure signal to cool BOTH trains of CCW.
ANSWER:
d. * ESW aligns on a low pressure signal to cool BOTH trains of CCW.
4 NV6AA6t t O/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 47
per EOP
Which of the following conditions would permit securing Containment Spray
PATH-1 Guide?
a. * Actuation caused by a LOCA
- Time since LOCA occurred is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- Containment pressure is 9 psig
b. * Actuation caused by a LOCA
- Time since LOCA occurred is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- Containment pressure is 5 psig
c. * Actuation caused by a Steam Line Break
- Time since Steam Line Break occurred is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- Containment pressure is 5 psig
d. * Actuation caused by a Steam Line Break
- Time since Steam Line Break occurred is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- Containment pressure is 9 psig
ANSWER:
c. * Actuation caused by a Steam Line Break
"* Time since Steam Line Break occurred is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
"* Containment pressure is 5 psig
41A 0.X( d6'OY0
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 48
Given the following conditions:
"* The plant is in Mode 3 with Tavg at 557F.
"* All systems are in their normal alignment.
"* Safety Injection is manually actuated inadvertently.
Which of the following describes the impact on Instrument Air inside Containment?
a. e IA-819, Containment Instrument Air, closes
- SI and Phase A must BOTH be reset to allow opening IA-819
b. * IA-819, Containment Instrument Air, closes
- ONLY SI must be reset to allow opening IA-819
c. * IA-819, Containment Instrument Air, closes
- ONLY Phase A must be reset to allow opening IA-819
d. e IA-819, Containment Instrument Air, remains open
- NO actions are required to be taken to restore IA to Containment
ANSWER:
c. * IA-819, Containment Instrument Air, closes
- ONLY Phase A must be reset to allow opening IA-819
114 02k/o
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 49
Given the following conditions:
- The unit is operating at 100% power.
- A turbine trip signal is received.
- All automatic actions occur, EXCEPT one (1) Throttle Valve fails to close.
Assuming NO operator actions, which of the following describes the expected FINAL
to
CONDITION of SG pressure and Turbine First Stage Impulse Pressure as compared
the 100% power conditions?
a. * SG pressure INCREASES
- Turbine First Stage Impulse Pressure INCREASES
b. * SG pressure INCREASES
- Turbine First Stage Impulse Pressure DECREASES
c. * SG pressure DECREASES
- Turbine First Stage Impulse Pressure INCREASES
d. * SG pressure DECREASES
- Turbine First Stage Impulse Pressure DECREASES
ANSWER:
b. * SG pressure INCREASES
- Turbine First Stage Impulse Pressure DECREASES
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 50
Given the following conditions:
- A reactor trip occurred due to a loss of offsite power.
- The plant is being cooled down on RHR per EPP-006, "Natural Circulation
Cooldown with Steam Void in Vessel with RVLIS."
- RCS cold leg temperatures are 190TF.
- Steam generator pressures are 50 psig.
- RVLIS upper range indicates greater than 100%.
- Three CRDM fans have been running during the entire cooldown.
Steam should be dumped from all SGs to ensure ...
a. boron concentration is equalized throughout the RCS prior to taking a sample to
verify cold shutdown boron conditions.
b. all inactive portions of the RCS are below 200TF prior to complete RCS
depressurization.
c. RCS and SG temperatures are equalized prior to any subsequent RCP restart.
d. RCS temperatures do not increase during the required 29 hour3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> vessel soak period.
ANSWER:
b. all inactive portions of the RCS are below 200TF prior to complete RCS
depressurization.
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 51
Given the following conditions:
"* During a reactor startup, power has been stabilized at 10-8 amps.
"* Main Feed Pump 'A' is operating and maintaining SG levels at program level.
"* Main Feed Pump 'B' is secured.
"* Subsequently, SG 'B' level increases to 85%.
Which of the following is the expected status of the following pumps?
a. e Main Feed Pump 'A' RUNNING
- Motor Driven AFW Pumps OFF
- Turbine Driven AFW Pump OFF
b. * Main Feed Pump 'A' OFF
- Motor Driven AFW Pumps RUNNING
- Turbine Driven AFW Pump OFF
c. . Main Feed Pump 'A' OFF
- Motor Driven AFW Pumps OFF
- Turbine Driven AFW Pump RUNNING
d. * Main Feed Pump 'A' OFF
- Motor Driven AFW Pumps RUNNING
- Turbine Driven AFW Pump RUNNING
ANSWER:
b. * Main Feed Pump 'A' OFF
"* Motor Driven AFW Pumps RUNNING
"* Turbine Driven AFW Pump OFF
1/4 059Kw0
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 52
Given the following conditions:
0 A loss of offsite power has occurred.
Both Emergency Diesel Generators are loaded.
ALB-024-3-2, DIESEL GENERATOR A TROUBLE, alarms.
0 An operator is sent to investigate and reports the following conditions:
Turbo Oil Press 28 psig and stable
Lube Oil Press 30 psig and stable
Fuel Oil Press 1.5 psig and stable
Day Tank Level 56% and slowly decreasing
Starting Air Pressure 227 psig and slowly decreasing
Jacket Water Pressure 17 psig and stable
Control Air Pressure 53 psig and stable
Which of the following compone nts should have automatically started based on these
conditions?
a. Lube Oil Circulating Pump
b. Auxiliary Lube Oil Pump
c. Fuel Oil Transfer Pump
d. Starting Air Compressor
ANSWER:
b. Auxiliary Lube Oil Pump
// 15(o 19Ai-
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 53
Given the following conditions:
- PRZ pressure is 1685 psig.
- PRT pressure is 15 psig.
Which of the following indications support a diagnosis that a PRZ PORV is stuck open?
TEMP
DOWNSTREAM
PRZ LEVEL OF PORV
a. Increasing 613 0 F
b. Increasing 250 0 F
c. Decreasing 613 0F
d. Decreasing 2500 F
ANSWER:
b. Increasing 2500 F
3/411
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 54
Given the following conditions:
- A Reactor Startup is being performed.
- Initial Source Range Count Rate was 200 count per second (cps).
- 2500 pcm has been inserted into the core by withdrawing control rods and Source
Range Count Rate has increased to 400 cps.
- Rod withdrawal is continued, and an additional 1250 pcm is added to the core.
Which of the following identifies the approximate condition of the core?
a. The reactor is subcritical with a stable count rate of 500 cps
b. The reactor is subcritical with a stable count rate of 600 cps
c. The reactor is subcritical with a stable count rate of 800 cps
d. The reactor is critical with an increasing count rate
ANSWER:
c The reactor is subcritical with a stable count rate of 800 cps
//A5/ DA
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 55
During a plant cooldown and depressurization in preparation for a refueling, the SIS
Accumulators are depressurized and then drained.
The normal drain path for the SIS Accumulators is through the Reactor Coolant Drain
Tank ...
a. to the Recycle Holdup Tank.
b. to the Waste Holdup Tank.
c. via the Spent Fuel Pool Cooling System to the Refueling Water Storage Tank.
d. via the Spent Fuel Pool Cooling System to the Transfer Canal.
ANSWER:
a. to the Recycle Holdup Tank.
3/4oNS /,/ 07
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 56
Given the following conditions:
"* The plant is in Hot Standby.
"* Letdown flow is 105 gpm.
"* CSIP 'B' is operating.
"* A loss of 125 VDC Emergency Bus DP-1B-SB occurs.
With NO operator actions, which of the following is the response of the plant?
a. Seal injection will be lost
b. Charging pump suction will shift to the RWST
c. Letdown line flashing will occur
d. RCS inventory will be lost
ANSWER:
d. RCS inventory will be lost
414 oggn/q vý'o9s
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 57
Which of the following sets of conditions would require that the Reactor Coolant Pumps
be secured?
a. * RCS is currently at 5250 F during a plant heatup
- Operating CSIP has tripped
- CCW Heat Exchanger outlet temperature is 95 0 F
b. * RCS is currently at 375 0 F during a plant heatup
- Operating CSIP has tripped
0
- CCW Heat Exchanger outlet temperature is 11 2 F
c. * RCS is currently at 525°F during a plant heatup
- CSIP 'A' is operating
& CCW Heat Exchanger outlet temperature is 108TF
d. * RCS is currently at 375 0 F during a plant heatup
- CSJP 'A' is operating
- CCW Heat Exchanger outlet temperature is 122 0 F
ANSWER:
b. * RCS is currently at 3750 F during a plant heatup
"* Operating CSIP has tripped
"* CCW Heat Exchanger outlet temperature is 1120 F
"* ALB-5-1-2B, RCP THERM BAR HDR LOW FLOW, is alarming
S0o9f3. oS
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 58
Given the following conditions:
- A loss of offsite power has occurred.
- ERFIS is out-of-service.
- SG pressures are at 885 psig and decreasing slowly.
- RCS pressure is 1935 psig and stable.
0
- Core exit thermocouples are.624 F and stable.
- RCS hot leg temperatures are 605TF and stable.
0
- RCS cold leg temperatures are 532 F and decreasing slowly.
The operator is verifying natural circulation flow in EPP-004, "Reactor Trip Response."
Which of the following describes the status of natural circulation flow criteria per
004?
a. The natural circulation criteria of EPP-004 has been met
b. RCS cold leg temperature criteria has NOT been met
c. RCS hot leg temperature criteria has NOT been met
d. RCS subcooling criteria has NOT been met
ANSWER:
d. RCS subcooling criteria has NOT been met
4/ 0 /7f3.e0/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 59
Which of the following would require that Independent Verification be performed in
accordance with OPS-NGGC-1303, "Independent Verification?"
a. During Mode 5, a valve in the Containment Spray system is being repositioned for
testing and the OP lineup will be completed prior to Mode 4 entry
b. During Mode 1, a valve in the Main Steam system is being placed under clearance
and the valve is only accessible with a manlift
c. During Mode 4, a valve in CVCS inside containment is being positioned for
draining and the valve is located in an area where the temperature is 134°F
d. During Mode 3, a valve in CVCS is being placed under clearance and the valve is
located in a radiation field of 175 mRem/hr with an estimated verification time of
6 minutes
ANSWER:
b. During Mode 1, a valve in the Main Steam system is being placed under clearance
and is only accessible with a manlift
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 60
Given the following conditions:
o Train 'A' RHR has just been placed in service in accordance with GP-007, "Normal
Plant Cooldown MODE 3 to MODE 5."
- Interlock P-12 has been bypassed and the Condenser Steam Dumps are in operation.
- Train 'A' equipment is in operation.
- Both CSIPs are still available.
- RCP 'C' has been secured for the cooldown.
A loss of 6.9 KV Bus 1A-SA occurs and EDG 1A-SA fails to start.
Which of the following describes the impact of the loss of Bus 1A-SA on the plant?
a. TDAFW Pump becomes inoperable
b. RCPs 'A' and 'B' must be secured
c. RHR cooling capability is temporarily lost
d. Condenser steam dump capability is lost
ANSWER:
c. RHR cooling capability is temporarily lost
414 667113,02
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 61
Given the following conditions:
"* FRP-P. 1, "Response to Imminent Pressurized Thermal Shock," is being performed.
"* Safety Injection CANNOT be terminated due to inadequate RCS subcooling.
"* However, RCS subcooling is adequate to start an RCP.
Which of the following describes the bases for RCP operation under these conditions?
a. Provide additional RCS subcooling
b. Provide mixing of injection water and reactor coolant
c. Supply additional heat input into the RCS
d. Provides normal sprays for the depressurization
ANSWER:
b. Provide mixing of injection water and reactor coolant
hi-ocf d,02
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 62
Given the following conditions:
- REM-3502A, Containment RCS Leak Detection Radiation monitor, is in service.
- REM-3502B, Containment Pre-Entry Purge Radiation monitor, is in service.
Which of the following describes the effect on these monitors if a Containment Isolation
Phase 'A' actuation occurs?
a. * REM-3502A remains in service
- REM-3502B remains in service
b. * REM-3502A remains in service
- REM-3502B is isolated
c. e REM-3502A is isolated
- REM-3502B remains in service
d. o REM-3502A is isolated
- REM-3502B is isolated
ANSWER:
c. e REM-3502A is isolated
- REM-3502B remains in service
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 63
Given the following conditions:
"* A LOCA has occurred inside Containment, resulting in a reactor trip and a safety
injection.
"* A transition has just been made from EPP PATH- I to FRP-P. 1, "Response to
Imminent Pressurized Thermal Shock."
- Containment pressure is 7 psig and increasing slowly.
- All RCPs have been secured.
- Pressurizer level is off-scale low.
- RVLIS Full Range indicates 88%.
0
- Core exit thermocouples are 240 F and decreasing
- RCS cold leg temperatures are 230'F and decreasing.
- RCS pressure is 285 psig and stable.
0
- ERFIS indicates subcooling is 177 F.
- SG levels are as follows:
SG LEVEL
A 32%
B 10%
C 26%
Which of the following actions should be taken in accordance with FRP-P. 1, "Response
to Imminent Pressurized Thermal Shock?"
a. Maintain total AFW flow >210 KPPH until at least one (1) SG is >40% level
c. Maintain cold leg injection flow, but secure one (1) CSIP
d. Return to EOP-PATH-1
ANSWER:
a. Maintain total AFW flow >210 KPPH until at least one (1) SG is >40% level
4 /
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 64
Given the following conditions:
- A loss of secondary heat sink has occurred.
- Attempts are made to restore main feedwater using FRP-H. 1, "Response to Loss of
Secondary Heat Sink."
- All RCPs are stopped.
- SG level wide range levels are all below 5%.
- Core exit thermocouple temperatures are increasing.
- PRZ pressure is 2180 psig and increasing rapidly.
Which of the following describes the sequence of actions to be taken?
a. * Actuate Safety Injection
- Verify all PRZ PORVs automatically open when pressure increases
b. e Actuate Safety Injection
- Open all PRZ PORVs after verifying Safety Injection flowpath
c. * Open all PRZ PORVs
- Verify Safety Injection automatically actuates when pressure decreases
d. * Open all PRZ PORVs
- Actuate Safety Injection after verifying the PRZ PORVs are open
ANSWER:
b. * Actuate Safety Injection
- Open all PRZ PORVs after verifying Safety Injection flowpath
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 65
Given the following conditions:
- Reactor power is 8%.
- The turbine is at 1800 rpm, in preparations for synchronizing to the grid.
- A reactor trip occurs.
Which of the following describes why the Main Turbine must be tripped under these
conditions?
a. Prevent an uncontrolled RCS cooldown
b. Generate an additional reactor trip signal
c. Minimize the depletion of SG inventory
d. Minimize the pressure increase in the RCS
ANSWER:
a. Prevent an uncontrolled RCS cooldown
3/4l 0D 7 E/X,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 66
Given the following conditions:
- PRZ pressure is being controlled in automatic at 2235 psig.
- Pressure transmitter PT-444 fails high.
- Approximately 10 seconds after the failure, the operator places PK-444A in
MANUAL.
Which of the following actions is the operator required to take to restore PRZ pressure to
2235 psig?
a. Raise controller output to cause heaters to energize and spray valves to close
b. Raise controller output to cause spray valves to open and heaters to deenergize
c. Lower controller output to cause heaters to energize and spray valves to close
d. Lower controller output to cause spray valves to open and heaters to deenergize
ANSWER:
c. Lower controller output to cause heaters to energize and spray valves to close
A/14 0, Z
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 67
The plant is in Mode 3 with the Shutdown Banks withdrawn when the following events
occur:
- The reactor trip breakers open.
- ALB-15-2-2, PIC 1-2-3-4-9-10-13-14 POWER FAILURE, alarms.
- ALB-15-4-3, PIC 17-18 POWER FAILURE, alarms.
- Most lights in the top row of Trip Status Light Boxes are energized.
- Several lights in each of the other rows of Trip Status Light Boxes are energized.
- ALB-15-1-4, 60 KVA UPS TROUBLE, remains clear.
- ALB-15-1-5, 7.5 KVA UPS TROUBLE, remains clear.
- ALB-15-3-2, PIC 5-6-7-8-11-12-15-16 POWER FAILURE, remains clear.
- ALB-15-5-3, PIC 19 POWER FAILURE, remains clear.
Which of the following buses have been lost?
a. Instrument Bus S-I
b. Instrument Bus S-II
c. UPS Bus UPP-1A
d. UPS Bus UPP-1B
ANSWER:
a. Instrument Bus S-I
PA )57/9 d /5
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 68
Given the following conditions:
- The crew diagnosed a SG tube leak.
- REM- 1BD-3527, Steam Generator Blowdown, went into high (RED) alarm.
- In response to the alarm on REM-1BD-3527, the crew performed the required actions
of AOP-016, "Excessive Primary Plant Leakage," Attachment 1, "Primary-To
Secondary Leak."
Which of the following describes the expected indicated trend on REM- 1BD-3527 after
the completion of Attachment 1?
a. Stabilizes and then decreases
b. Stabilizes and remains constant
c. Increases and stabilizes at full scale
d. Stabilizes and then increases
ANSWER:
a. Stabilizes and then decreases
/i/ 037/J ,41 13
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 69
Given the following conditions:
"* FRP-C. 1, "Response to Inadequate Core Cooling," is being performed following a
small break LOCA.
"* Containment pressure is 8.5 psig.
"* Core exit thermocouples are >1400'F.
"* All efforts to establish SI flow have failed.
"* The crew has started RCP 'C' in an attempt to lower core exit temperatures, but
temperatures have remained above 1300'F.
"* SG 'C' level is 55%.
"* SGs 'A' and 'B' are off-scale low.
Which of the following actions should be taken?
a. Open the PRZ PORVs and RCS vent valves
b. Start RCPs 'A' and 'B' one at a time
c. Close any open PRZ PORVs and RCS vent valves
d. Refill and repressurize the SI Accumulators for continued injection
ANSWER:
a. Open the PRZ PORVs and RCS vent valves
/V, o0YE , v5
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 70
Given the following conditions:
"* The unit is in the Source Range during a reactor startup.
"* Power is lost to Instrument Bus S-III.
- A reactor trip occurs.
Which of the following signals caused the reactor trip?
a. Source Range High Count Rate
b. Intermediate Range High Flux
c. Power Range Neutron Flux (Low Setpoint)
d. Turbine Trip
ANSWER:
d. Turbine Trip
hA o,;,¢ý,-
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 71
After plant control is completely shifted to the Auxiliary Control Panel in accordance
with AOP-004, "Remote Shutdown", which of the following actions will the operators
have to manually perform?
a. Align CSIP suction to the RWST
b. Transfer control of the EDGs to the local control panels
c. Open the reactor trip breakers
d. Block SIAS to the Emergency Sequencers
ANSWER:
a. Align CSIP suction to the RWST
I/pt
ý)6214 ý /I -,-/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 72
Given the following conditions:
"* During a plant startup, Main Feed Water is aligned to the SGs through the Feed Reg
Valve Bypass FCVs.
"* The controller for FCV-479, SG 'A' Feed Reg Valve Bypass FCV (FK-479. 1), has
just been placed in AUTO.
"* The controller for FCV-489, SG 'B' Feed Reg Valve Bypass FCV (FK-489.1), is still
in MANUAL.
"* The controller for FCV-499, SG 'C' Feed Reg Valve Bypass FCV (FK-499.1), is still
in MANUAL.
"* FCV-479 begins going open.
Which of the following failures could have caused the response of FCV-479?
a. SG 'A' Feed Flow Channel FT-475 failing low
b. SG 'A' Steam Flow Channel FT-476 failing high
c. SG 'A' Level Channel LT-476 failing high
d. Power Range Channel N-44 failing high
ANSWER:
d. Power Range Channel N-44 failing high
,/63.-q ,0 /
-j/3
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 73
Which of the following describes why RCP trip criteria is included in PATH-2?
a. Protect against operator misdiagnosis since RCS pressure should not decrease to
the trip criteria during a SGTR
b. Decrease leakage from the RCS since the total leakage for the duration of the
SGTR is less than it would have been with the RCPs in service
in
c. Prevent heatup of the RCS since a heatup of the RCS due to the RCPs being
service increases leakage to the ruptured SG
one RCP
d. Protect the RCPs from operating with inadequate AP across the number
seal as a result of the RCS depressurization from the SGTR
ANSWER:
to
a. Protect against operator misdiagnosis since RCS pressure should not decrease
the trip criteria during a SGTR
1/2 )c38FK3, /9
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 74
Which of the following describes how the Emergency Sequencer is reset following a loss
of AC power to 6.9 KV Bus 1A-SA which results in actuation of the Sequencer UV
Program?
a. The operator resets the program by turning the SI Reset switch to RESET at least
2.5 minutes after Load Block 9 is completed
b. The operator resets the program by placing both Reactor Trip Breaker A-SA and
Reactor Trip Breaker B-SB to the closed position momentarily after all actuation
signals have been cleared
c. The program automatically resets when Auxiliary Bus D To Emergency Bus A
SA Breaker 104 and Emergency Bus A-SA To Aux Bus D Tie Breaker 105 SA are
closed during the restoration of offsite power
d. The program automatically resets when Diesel Generator A-SA Breaker 106 SA is
opened during the restoration of offsite power
ANSWER:
c. The program automatically resets when Auxiliary Bus D To Emergency Bus A
SA Breaker 104 and Emergency Bus A-SA To Aux Bus D Tie Breaker 105 SA are
closed during the restoration of offsite power
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 75
Given the following conditions:
- FRP-S. 1, "Response to Nuclear Power Generation / ATWS," is being performed.
- The operating crew is about to exit FRP-S.1.
Boration should continue even after exiting FRP-S. 1 to ensure ...
a. adequate shutdown margin is established since the criteria for exiting FRP-S. 1 is
only that the reactor be subcritical.
b. the reactor becomes subcritical since the criteria for exiting FRP-S. 1 is only that
the power range channels indicate < 5%.
c. cold shutdown boron concentration is achieved since additional boron, beyond that
needed to make the reactor subcritical, is required to compensate for the cooldown
portion of the recovery.
d. refueling boron concentration is achieved since additional boron, beyond that
needed to make the reactor subcritical, is required to allow for core offloading to
inspect for fuel damage.
ANSWER:
a. adequate shutdown margin is established since the criteria for exiting FRP-S.1 is
only that the reactor be subcritical.
A D2.g
O
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 76
Given the following conditions:
"* Spent resin is being sluiced from the Cation Demineralizer to a Spent Resin Storage
Tank.
"* The operator reports that it appears that a pipe in the overhead of a hallway is plugged
with resin.
"* HP reports the results of a radiation survey as follows:
& 2500 mr/hr on contact with pipe
- 1200 mr/hr @ 18 inches from the pipe
- 5 mr/hr at floor level below the pipe
Which one of the following describes the required radiological postings?
a. NO postings are required because a ladder is required to access the pipe area
b. Very High Radiation Area with red flashing light
c. High Radiation Area with a red flashing light
d. High Radiation Area, but NO red flashing light required
ANSWER:
c. High Radiation Area with a red flashing light
6ý >0- ) 3
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 77
Given the following conditions:
- A makeup to the PRT is in progress per OP-100, "Reactor Coolant System."
Which of the following signals will automatically terminate the PRT makeup AND how
will the valves respond?
a. * ONLY a Phase A signal
0 1RC-161, RMW TO CNMT, closes
b. * ONLY a Phase A signal
c. * EITHER a Phase A signal OR a Phase B signal
d. * EITHER a Phase A signal OR a Phase B signal
S1RC-161, RMW TO CNMT, remains open
ANSWER:
a. * ONLY a Phase A signal
"* 1RC-161, RMW TO CNMT, closes
"* 1RC-167, RMW TO PRT, remains open
1161
SOD4,T
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 78
Given the following conditions:
Emergency Boration is required.
0 1CS-278, Emergency Boric Acid Addition, is failed CLOSED.
Which of the following alignments will provide adequate boric acid flow?
1CS-155 1CS-291 1CS-292 1LCS-165 1CS-166
Boric Makeup Makeup
Suction Suction Outlet Outlet
Acid to to CSIP to VCT
Boric Suction FCV
Acid FCV
FCV 115B 115D
113A
CLOSED OPEN
a. CLOSED OPEN CLOSED CLOSED CLOSED
OPEN CLOSED CLOSED OPEN CLOSED
b. OPEN CLOSED
OPEN OPEN
C. CLOSED OPEN CLOSED CLOSED CLOSED
OPEN CLOSED OPEN CLOSED
d. OPEN CLOSED CLOSED
ANSWER:
d. OPEN CLOSED CLOSED OPEN CLOSED OPEN CLOSED
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 79
The compensating voltage on Intermediate Range (IR) channel N-35 is set too low,
resulting in N-35 stabilizing at 2 x 10.10 amps during a reactor shutdown.
If IR channel N-36 fails low ...
a. BOTH SR NIs will automatically energize.
b. ONLY SR channel N-31 will automatically energize.
c. ONLY SR channel N-32 will automatically energize.
d. NEITHER SR NI will automatically energize.
ANSWER:
d. NEITHER SR NI will automatically energize.
I// 033/9XIe /
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 80
Which of the following is an acceptable condition in accordance with AOP-010,
"Feedwater Malfunctions?"
a. * Power level at 65%
& No (0) Heater Drain Pumps operating
b. * Power level at 98%
- One (1) Heater Drain Pump operating
c. * Power level at 92%
- No (0) Heater Drain Pumps operating
d. * Power level at 70%
- One (1) Heater Drain Pump operating
ANSWER:
b. * Power level at 98%
"* One (1) Heater Drain Pump operating
"* Two (2) trains of Feed Water Pumps (FWP, CBP, CP) operating
/0 05q/9/1,03
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 81
Which of the following describes the automatic operation of 1SA-506, Service Air
Header Isolation Valve?
a. Opens if Instrument Air pressure decreases to < 90 psig
b. Closes if Service Air pressure decreases to < 90 psig
c. Opens if Service Air pressure decreases to < 90 psig
d. Closes if Instrument Air pressure decreases to < 90 psig
ANSWER:
d. Closes if Instrument Air pressure decreases to < 90 psig
1614 079A1/40~o/
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 82
Given the following conditions:
- PATH-2 is being performed in response to a tube rupture on SG 'C'.
- SI termination criteria is being checked.
Over the last several minutes:
"* RCS subcooling has gone from 60'F to 63TF.
"* Levels in SG 'A' and 'B' have increased from 45% to 50%.
"* PRZ level has increased from 43% to 47%.
"* RCS temperature has gone from 472TF to 4680 F.
"* RCS pressure has gone from 885 psig to 880 psig.
The Unit-SCO asks if "RCS pressure is stable or increasing."
Which of the following describes how the operator should respond AND what actions
should be taken?
a. * RCS pressure is still decreasing.
- The cooldown must be stablized to determine if RCS pressure has stabilized.
b. e RCS pressure is still decreasing.
- SI cannot be terminated and a transition to the appropriate procedure must be
made.
c. o RCS pressure is stable.
- The cooldown must be stabilized in order to verify the trend.
d. * RCS pressure is stable.
- SI can be terminated.
ANSWER:
d. o RCS pressure is stable.
- SI can be terminated.
k1~4 9, , V/?
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 83
Given the following conditions:
- A large break LOCA has occurred.
- Containment hydrogen concentration is 1.2%.
- Containment pressure is 6 psig.
ago.
Which of the following describes the expected status of EHR lB-SB and the
Containment Hydrogen Purge System?
CONTAINMENT
EHR 1B-SB PURGE
a. In Standby Operating
b. In Standby Secured
c. In Service Operating
d. In Service Secured
ANSWER:
b. In Standby Secured
tie3z.
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 84
Given the following conditions:
- The plant is operating at 100% power.
- The Condenser Zone 1 low-pressure turbine boot seal ruptures, causing a turbine trip
and reactor trip.
- A complete loss of Zone 1 and Zone 2 vacuum occurs.
Which of the following will automatically actuate to stabilize RCS temperature instead of
Condenser Steam Dumps AND why does C-9 prevent Condenser Steam Dump
operation?
a. . Steam Generator PORVs
- Ensure the condenser does NOT reach saturation conditions
b. * Steam Generator PORVs
- Protect the condenser from an overpressure condition
c. * Atmospheric Steam Dumps
- Ensure the condenser does NOT reach saturation conditions
d. * Atmospheric Steam Dumps
- Protect the condenser from an overpressure condition
ANSWER:
b. * Steam Generator PORVs
- Protect the condenser from an overpressure condition
/dVf bslAI 3/b .
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 85
Which of the following sets of conditions would require that AOP-022, "Loss of Service
Water," be performed?
a. * ALB-002-1-1, EMER SERV WTR PMPS HDR STR HIGH AP OR LOSS OF
PWR, in alarm
0 Local strainer AP indicating 20 psid
b. * ALB-002-3-2, SW BSTR PUMP A AUTO START FAIL/OVERRIDE, in
alarm
in alarm
- SI actuated
c. * ALB-002-6-2, SERV WTR PUMPS DISCHARGE VLV NOT FULL OPEN,
in alarm
o NSW Pump 'A' has been started in Priming Mode
- NSW Pump discharge valve 10% open
d. * ALB-002-7-5, COMPUTER ALARM SERVICE WATER, in alarm
- Main Reservoir temperature indicating 94°F
- Aux Reservoir temperature indicating 88 0 F
ANSWER:
a. o ALB-002-1-1, EMER SERV WTR PMPS HDR STR HIGH AP OR LOSS OF
PWR, in alarm
"* Local strainer AP indicating 20 psid
"* ESW header pressure indicating 51 psig
O762 ,Z/ /1
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 86
Given the following conditions:
- The plant is operating at 60% power.
- RCS Tavg is on program.
- PRZ level is on program.
- The Median Tavg input to PRZ level fails high.
- The operator places LK-459, PRZ Master Level Controller, in MANUAL.
In order to control PRZ level at program level, the operator should be directed to control
PRZ level at ...
a. 36%.
b. 41%.
c. 46%.
d. 51%.
ANSWER:
c. 46%.
// , I,izt
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 87
Given the following conditions:
- The plant is operating at 90% power.
- Control Bank 'C' Rod D-4, located at the edge of the core near PR NI N-43, has
slipped to approximately 6 steps off the bottom of the core and appears to be stuck.
Which of the following parameters would be the LEAST AFFECTED by this rod
misalignment?
a. Quadrant Power Tilt Ratio calculations
b. Power Range Nuclear Instrument indications
c. Axial Flux Difference indications
d. Core Exit Thermocouple temperature indications
ANSWER:
c. Axial Flux Difference indications
IZ-1 9 D5S fi //,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 88
Given the following conditions:
- The unit is in a Refueling Outage.
- A spent fuel assembly is attached to the manipulator crane.
- A failure of the Reactor Vessel permanent cavity seal ring causes cavity level to drop
approximately 3" every minute.
- The Refueling Crew is in the process of placing the assembly in the Reactor Vessel
when a Loss of Off-Site Power occurs.
Upon the loss of off-site power there is NO means for ...
a. making up to the cavity.
b. monitoring radiological levels inside Containment.
c. monitoring the reactivity condition of the core.
d. placing this fuel assembly in the vessel.
ANSWER:
d. placing this fuel assembly in the vessel.
07 6,3664P/9/."
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 89
FRP-J. 1, "Response to High Containment Pressure," monitors the status of the ESW
Booster Pumps.
Which of the following is the concern if ESW Booster pumps fail to start while high
containment pressure conditions exist?
a. ESW Pump runout
b. Flooding of safety equipment in containment
c. Loss of containment cooling capability
d. Radioactivity release to the environment
ANSWER:
d. Radioactivity release to the environment
&ý WV/E/VE/K-3VA92
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 90
Given the following conditions:
- A plant cooldown is in progress.
- All three (3) RCPs are operating.
- ALB-010-8-5A, "CMPTR ALARM RX COOLANT," is in alarm and investigation
reveals RCP 'C' Radial Bearing Temp has exceeded the warning alarm setpoint and
is approaching the alarm limit of 2200 F.
- Seal injection to each RCP is approximately 10 gpm.
Which of the following conditions would direct opening the RCP No. 1 seal bypass valve
in accordance with OP-100, "Reactor Coolant System?"
a. * RCS pressure 850 psig
- RCP 'A' No. 1 seal leakoff 1.2 gpm
o RCP 'B' No. 1 seal leakoff 0.9 gpm
- RCP 'C' No. 1 seal leakoff 1.3 gpm
b. o RCS pressure 1060 psig
- RCP 'A' No. 1 seal leakoff 0.7 gpm
- RCP 'B' No. 1 seal leakoff 0.9 gpm
- RCP 'C' No. 1 seal leakoff 0.8 gpm
c. * RCS pressure 640 psig
o RCP 'A' No. 1 seal leakoff 1.2 gpm
- RCP 'B' No. 1 seal leakoff 1.1 gpm
- RCP 'C' No. 1 seal leakoff 1.1 gpm
d. e RCS pressure 1110 psig
o RCP 'A' No. 1 seal leakoff 1.2 gpm
- RCP 'B' No. 1 seal leakoff 0.8 gpm
- RCP 'C' No. 1 seal leakoff 0.9 gpm
ANSWER:
a. e RCS pressure 850 psig
"* RCP 'A' No. 1 seal leakoff 1.2 gpm
"* RCP 'B' No. 1 seal leakoff 0.9 gpm
"* RCP 'C' No. 1 seal leakoff 1.3 gpm
/4/ 0 63 K/, m
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 91
Which of the following sets of conditions would NOT permit waiving the Independent
Verification (IV) requirement for a clearance removal?
TIME TO AREA
DOSE RATE PERFORM IV TEMPERATURE
a. 120 mRem/hr 6 minutes 105°F
b. 180 mRem/hr 3 minutes 115 0F
c. 90 mRem/hr 4 minutes 125 0F
d. 60 mRem/hr 3 minutes 135 0F
ANSWER:
b. 180 mRem/hr 3 minutes 115°F
/,,ý q
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 92
Which of the following is the basis for the Technical Specification limit of 31 gpm on
Controlled Leakage?
a. Sufficiently low to ensure early detection of additional leakage
b. Allows limited known leakage with the ability to detect additional leakage
c. Ensures safety injection flow is greater than that analyzed for a LOCA
d. Keeps dose to a small fraction of limits in the event of a SGTR or steam line break
ANSWER:
c. Ensures safety injection flow is greater than that analyzed for a LOCA
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 93
The unit is operating at 100% power.
If 125 VDC Bus 1A-SA deenergizes due to a fault on the bus ...
a. the reactor will trip due to an undervoltage (UV) trip of Train SA reactor trip
breaker.
the reactor will trip due to a shunt trip of Train SA reactor trip breaker.
b.
an undervoltage trip signal will NOT be capable of opening Train SA reactor trip
breaker.
d. a shunt trip signal will NOT be capable of opening Train SA reactor trip breaker.
ANSWER:
d. a shunt trip signal will NOT be capable of opening Train SA reactor trip breaker.
LOD / /<t D,
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 94
A waste gas release is in progress when the WPB Stack 5 PIG radiation monitor, REM
lWV-3546, exceeds the high alarm setpoint.
Which of the following describes how the release will be automatically terminated?
a. Key-operated 3WG-229, Waste Gas Decay Tanks E & F to Plant Vent, CLOSES
b. 3WG-230, Gas Decay Tanks to Plant Vent Isolation Valve, CLOSES
c. Filtered Exhaust Fans, E-46, E-47, E-48, and E-49 TRIP
d. Running Waste Gas Compressor TRIPS
ANSWER:
a. Key-operated 3WG-229, Waste Gas Decay Tanks E & F to Plant Vent, CLOSES
0 06b 0A 2, (6
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 95
Given the following conditions:
"* The plant is at 22% power during a Technical Specification 3.0.3 required shutdown.
"* Source Range Channel N-31 has been declared inoperable as a result of failing to
meet Operational Test Criteria of MST-I0169.
"* The LEVEL TRIP switch has been placed in the BYPASS position per OWP-RP-19,
"Source Range N-3 1."
"* The I&C Supervisor states that both control and instrument power must be removed
from the N-31 drawer to replace a bistable module.
Should the control and instrument power fuses be removed AND why or why not?
a. NO, because removing both fuses will cause the reactor to trip when the fuses are
removed.
b. YES, provided only the instrument power fuses are removed or the reactor will
trip when power is reduced below P-10.
c. NO, because removing both fuses will cause the reactor to trip when power is
reduced below P-6.
d. YES, because removing both fuses will NOT cause a reactor trip to occur.
ANSWER:
c. NO, because removing both fuses will cause the reactor to trip when power is
reduced below P-6.
SD/5, S 0o3
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 96
1CS-50, Letdown to VCT/Demin, automatically bypasses the CVCS Demineralizers
when ...
0
a. TE-143, LP Letdown Temperature, exceeds 135 F to prevent an inadvertent
dilution event
b. TE-143, LP Letdown Temperature, exceeds 135 0 F to prevent damage to the
demineralizer resin
0
c. TE-144, Letdown HX Outlet Temperature, exceeds 135 F to prevent an
inadvertent dilution event
0
d. TE-144, Letdown HX Outlet Temperature, exceeds 135 F to prevent damage to
the demineralizer resin
ANSWER:
b. TE-143, LP Letdown Temperature, exceeds 135°F to prevent damage to the
demineralizer resin
1-11
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 97
Given the following conditions:
- During Mode 3 operations, a large break LOCA occurred concurrently with a loss of
offsite power.
- Both EDGs started and loaded.
- SI has NOT been reset and offsite power has NOT been restored.
If SG narrow range levels decrease to the following levels,
SG LEVEL
A 22%
B 17%
C 27%
which of the following describes the expected AFW pump operation?
- MDAFW Pump lB-SB running
- TDAFW Pump running
b. * MDAFW Pump lA-SA running
& MDAFW Pump lB-SB running
- TDAFW Pump secured
- MDAFW Pump lB-SB secured
- TDAFW Pump running
- MDAFW Pump lB-SB secured
- TDAFW Pump secured
ANSWER:
c. e MDAFW Pump lA-SA secured
"* MDAFW Pump lB-SB secured
"* TDAFW Pump running
,c14 D06/,U,0 ,2-
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 98
Given the following conditions:
"* A small break LOCA occurred and SI has been terminated in accordance with EPP
008, "SI Termination."
"* SI Reinitiation criteria has been met.
Which of the following are the correct order of actions to be taken?
a. Close the BIT valves, open the charging line isolation valves, and verify the
normal miniflow isolation valves open
b. Open the BIT valves, close the charging line isolation valves, and verify the
normal miniflow isolation valves open
c. Close the charging line isolation valves, open the BIT valves, and verify the
normal miniflow isolation valves closed
d. Open the charging line isolation valves, close the BIT valves, and verify the
normal miniflow isolation valves closed
ANSWER:
c. Close the charging line isolation valves, open the BIT valves, and verify the
normal miniflow isolation valves closed
/10 kA// fDAt/ 1 t 6 0
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 99
In accordance with the EOP User's Guide, which of the following is an approved
pre-emptive action?
a. Isolating AFW to a ruptured SG and closing the Main Steam Isolation Valve from
the ruptured SG immediately upon completion of the Immediate Actions of
PATH-1
b. Throttling AFW to supply all three (3) SGs at 100 KPPH per SG with one AFW
pump during the performance of EPP-FRP-S. 1, "Response to Nuclear Power
Generation - ATWS," with all SG narrow range levels below 5%
c. Restoring AFW to a faulted SG after it has been isolated to establish the maximum
cooldown rate available during the performance of PATH-2
d. Throttling AFW flow to all three (3) SGs at 50 KPPH per SG to maintain intact
SG levels between 25% and 50% immediately upon completion of the Immediate
Actions of PATH- I
ANSWER:
d. Throttling AFW flow to all three (3) SGs at 50 KPPH per SG to maintain intact
SG levels between 25% and 50% immediately upon completion of the Immediate
Actions of PATH- 1
Harris Nuclear Plant
August 2002 - RO Exam
ANSWER KEY
QUESTION: 100
Given the following conditions:
"* Following a large break LOCA, SI has been reset.
"* The crew has just completed the performance of EPP-010, "Transfer to Cold Leg
Recirculation," and have transitioned back to PATH-1.
"* A loss of offsite power occurs following the transition to PATH- 1.
Core cooling will be ...
a. automatically re-established when the Emergency Diesel Generator output breaker
closes.
b. automatically re-established upon completion of the Sequencer loading.
c. lost until the operator re-opens the RHR suction valves after the Emergency Diesel
Generator output breaker closes.
d. lost until the operator restarts the RHR pumps after the Emergency Diesel
Generator output breaker closes.
ANSWER:
d. lost until the operator restarts the RHR pumps after the Emergency Diesel
Generator output breaker closes.
0 3f3/4 o'-
Harris Nuclear Plant
RO Written Reference
RO SUPPLIED REFERENCES
AOP-036, Attachment 6 ............ SG Wide Range Level vs. SG Pressure
OP- 107, Attachment 19 ............. Makeup Concentration Limits
OP- 141, Attachment 5 ............... Cooling Tower Cold Weather Operation
Curves A- 11-6 through -I I ......... Differential and Integral Rod Worth Curves
Curves C-I1-I through -3 ........... Power Defect Curves
Steam Tables
SAFE SHUTDOWN FOLLOWING A FIRE
Attachment 6
Sheet 1 of 1
SG Wide Range Level vs. SG Pressure
1Im
85
I
8 70
2 KA
t5
2(0
300 2E 4D] wo w0O 90a O(0 103 11w0 12Ei
0 O
-END ATTACHMENT 6
AOP-036 Rev. 19 Page 99 of 105
Attachment 19
Sheet 1 of 9
Makeup Concentration Limits
These tables were derived per calculation HNP-I/INST-1056 using the equations of
Attachment 3 and provide a means to select an appropriate RWMU Total
Makeup Flow Rate (Q) which will yield a desired blended flow boron concentration when
matched to the BAT concentration and the Boric Acid Flow Rate span of 1 to 30 gpm.
It is necessary to select lower RWMU Total Makeup Flow Rates when high boron
concentrations are required because the Boric Acid Flow is limited by system configuration to
a maximum of 33 gpm. This maximum Boric Acid Flow capability however is not used as the
basis for these tables because it is necessary to allow some margin for possible system
performance degradation. Therefore a maximum Boric Acid Flow of 30 gpm is used as the
basis for the following tables.
Each sheet of the tables is applicable to a specific RWMU Total Makeup Flow Rate (Q).
The maximum ppm results have been rounded down to the nearest whole number and the
minimum ppm results have been rounded up to the nearest whole number.
OP-107 Rev. 42 Page 245 of 256
Attachment 19
Sheet 2 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 120gpm
To determine the maximum boron concentration for which makeup will be
reliable at 120 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 120 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 120 GPM MINIMUM PPM FOR 120 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 1750 59
7050 1762 59
7100 1775 60
7150 1787 60
7200 1800 60
7250 1812 61
7300 1825 61
7350 1837 62
7400 1850 62
7450 1862 63
7500 1875 63
7550 1887 63
7600 1900 64
7650 1912 64
7700 1925 65
7750 1937 65
OP-107 Rev. 42 Page 246 of 256
Attachment 19
Sheet 3 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 10Ogpm
1. To determine the maximum boron concentration for which makeup will be
reliable at 110 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 110 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 110 GPM MINIMUM PPM FOR 110 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 1909 64
7050 1922 65
7100 1936 65
7150 1950 65
7200 1963 66
7250 1977 66
7300 1990 67
7350 2004 67
7400 2018 68
7450 2031 68
7500 2045 69
7550 2059 69
7600 2072 70
7650 2086 70
7700 2100 70
7750 2113 71
OP-107 Rev. 42 Page 247 of 256
Attachment 19
Sheet 4 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 100qpm
To determine the maximum boron concentration for which makeup will be
reliable at 100 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 100 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 100 GPM MINIMUM PPM FOR 100 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 2100 70
7050 2115 71
7100 2130 71
7150 2145 72
7200 2160 72
7250 2175 73
7300 2190 73
7350 2205 74
7400 2220 74
7450 2235 75
7500 2250 75
7550 2265 76
7600 2280 76
7650 2295 77
7700 2310 77
7750 2325 78
OP-I07 Rev. 42 Page 248 of 256
Attachment 19
Sheet 5 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 90.pm
1. To determine the maximum boron concentration for which makeup will be
reliable at 90 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 90 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 90 GPM MINIMUM PPM FOR 90 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 2333 78
7050 2350 79
7100 2366 79
7150 2383 80
7200 2400 80
81
2416
7250
7300 2433 82
7350 2450 82
7400 2466 83
7450 2483 83
7500 2500 84
7550 2516 84
7600 2533 85
7650 2550 85
7700 2566 86
7750 2583 87
IOP-107 Rev. 42 Page 249 of 256
Attachment 19
Sheet 6 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 80opm
1. To determine the maximum boron concentration for which makeup will be
reliable at 80 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 80 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 80 GPM MINIMUM PPM FOR 80 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 2625 88
7050 2643 89
7100 2662 89
7150 2681 90
7200 2700 90
7250 2718 91
7300 2737 92
7350 2756 92
7400 2775 93
7450 2793 94
7500 2812 94
7550 2831 95
7600 2850 95
76501 2868 96
7700 2887 97
7750 2906 97
Page 250 of 256 1
OP-107 Rev. 42
Attachment 19
Sheet 7 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 70pm
1. To determine the maximum boron concentration for which makeup will be
reliable at 70 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 70 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 70 GPM MINIMUM PPM FOR 70 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 3000 100
7050 3021 101
7100 3042 102
7150 3064 103
7200 3085 103
7250 3107 104
7300 3128 105
7350 3150 105
7400 3171 106
7450 3192 107
7500 3214 108
7550 3235 108
7600 3257 109
7650 3278 110
7700 3300 110
7750 3321 111
OP-107 Rev. 42 Page 251 of 256
Attachment 19
Sheet 8 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 60rm
1. To determine the maximum boron concentration for which makeup will be
reliable at 60 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 60 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 60 GPM MINIMUM PPM FOR 60 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 3500 117
7050 3525 118
7100 3550 119
7150 3575 120
7200 3600 120
7250 3625 121
7300 3650 122
7350 3675 123
7400 3700 124
7450 3725 125
7500 3750 125
7550 3775 126
7600 3800 127
7650 3825 128
7700 3850 129
7750 3875 130
I OP-107 Rev. 42 Page 252 of 256
Attachment 19
Sheet 9 of 9
Makeup Concentration Limits for: RWMU Total Makeup Flow Rate Q = 50qpm
1. To determine the maximum boron concentration for which makeup will be
reliable at 50 gpm total flow, select the BAT boron concentration which is equal
to or lower than current BAT boron concentration.
2. To determine the minimum boron concentration for which makeup will be reliable
at 50 gpm total flow, select the BAT boron concentration which is equal to or
higher than current BAT boron concentration.
BAT BORON MAXIMUM PPM FOR 50 GPM MINIMUM PPM FOR 50 GPM
CONCENTRATION (PPM) MAKEUP MAKEUP
(30 GPM BA FLOW) (1 GPM BA FLOW)
7000 4200 140
7050 4230 141
7100 4260 142
7150 4290 143
7200 4320 144
7250 4350 145
7300 4380 146
7350 4410 147
7400 4440 148
7450 4470 149
7500 4500 150
7550 4530 151
7600 4560 152
7650 4590 153
7700 4620 154
7750 4650 155
OP-107 Rev. 42 Page 253 of 256
Attachment 5
Sheet I of 1
Cooling Tower Cold Weather Oreration
90
0
w
w 80
(5
a:
a. 70
wH
0
w 60
n
Ia:
w
a 50
z
0
-J
0
0
C- 40
32
30
-30 -20 -10 0 10 20 30 32 40
AMBIENT AIR TEMPERATURE (DEGREES F)
NORMAL OPERATION - COOLING TOWER DEICING GATE VALVES OPEN
U AS IS - COOLING TOWER DEICING GATE VALVES REMAIN AS IS
HALF OPEN - COOLING TOWER DEICING GATE VALVES HALF OPEN
K ABNORMAL OPERATION-'NO CONDENSER HEAT LOAD AREA. IN THIS AREA PERFORM
SECTION 8.6.
Rev. 17 Page 38 of 40
HARRIS UNIT 1 CYCLE 11
DIFFERENTIAL AND INTEGRAL
ROD WORTH CONTROL BANKS D and C
MOVING WITH 103 STEP OVERLAP
BOL (0*5 EFPD < 161), HZP, WITH NO XENON
- - - -r-iIr rr -i--rr i-i-I--F I LA I I I I ill I I
-18
-1800 ---
I i i i
I
I i
i
I t I I '
II
'
O * m m I L m I I m * m I B * * F m l k T p m L F i m m I m m m m i
-17
-1700 I
. ; .* . i l l- -( - - - -
16
rI&
-1600 t
q . . .
.... . . . . . *m I* Jm Jm .I ,. ) I q * i I r ! !
+/-
-15
-1500 I
-1400
£ J - -
4: -14
-1300 SL ! -13
-lJ0n
-12
-1200 m
-11 *m
"0 -1100
I -10
-1000
-9 0
-900
C3
0 0
-8
.~ -800 --4
-7
(5 -700
a I
i
LLJ
I-_z -600 I -6
-500 A
-i 1' .5
-400
TFFY El al -4
-300
EFlI
........ -3
. -2
-200 1 42l
__ -T-
ILhjiv4 - = I -1
-100
25 PCM/DIV
Im _
I- I
m
I
m
- m
_i_
.11111
m m i
-
I
I___tt-41
I I Im I-
0
0
-0 180 200 220 240
0
5 STEPS/DIV
20 40 [ 1-4-ý 60 80 100 120 140 160
0 103 231
BANK D
128 231
BANK C
CURVE NO. A-11-6 REV NO. 0
ORIGINATOR - a.C,.,P DATE 10/1;2/0
SUPERVISOR DATE
SUPERINTENDENT - ( e0/1'
SHIFT OPERATIONS DATE
HARRIS UNIT 1 CYCLE 11
DIFFERENTIAL AND INTEGRAL
ROD WORTH CONTROL BANKS D and C
MOVING WITH 103 STEP OVERLAP
MOL (161 < EFPD < 334), HZP, WITH NO XENON
-1800 - * -18
-1700
ml F -17
4-4-4-ýi i
Zn' -16
-1600 I LL23J ....L..L. I - I - J- J-4--S -4-441-4-4--h.- I-4- -4-4 -H--t-r- I -t- t- - I -,r-t- I r--r I -r-r-r 1-rr-1-- U
I +/-tzttt
. .
t-
.
I E
I ]
I J
I JI II I II
-15
-1500
-1400 Ia I J I d I I * d I * I I I I 1 * I I
-14
-1300
C-)
a
-1200
-1100
m
t -12
-11
-n
m
I.
0
-1000 fl 1111- IN+
-10
-10
r
0
-9 0
-900
-8 0
-800 4 F :1: 1 -
n t-i -J z
-700 *WT T Z I
- H:I+/-H:FNHTh2Th. -7
w
tflhiVTIiTI7IIVEIIEBIZIFI+/-Effl+/-EH
I I
I
z -600 Sm
I E i i i {
- f+M-+-* L -5
-500
+ThATh-VMYW 11 -4
-400
J4-1-H sd-M-4-H -3
-300
-k , -f--f- f
-2
-200
-1
-100
25 PCMIDIV
0
0 20 40 60 80 100 120 140 160 180 200 220 240
5 STEPS/DIV
0 103 231
BANK D
128 231
BANK C
CURVE NO. A-11-7 REV NO. 0
ORIGINATOR t. _, DATE /Q/;S7O/"5
SUPERVISOR DATE /, -zt-o\
SUPERINTENDENT
SHIFT OPERATIONS DATE -
HARRIS UNIT 1 CYCLE 11
DIFFERENTIAL AND INTEGRAL
ROD WORTH CONTROL BANKS D and C
MOVING WITH 103 STEP OVERLAP
EOL (334 < EFPD -507), HZP, WITH NO XENON
-2000 I--.' ZZ IZIt I
r -20
FI -'U.-) r -19
-1900 f I I
it 1r
-1800 I -18
a
I
- WflV -17
-1700
iii i-tm
I-- ffi
i-4-4-H-1-h- -- 16
-1600
-- 15
-1500'
--14 "m
-1400'
E -1300
TF1]T[TLLWiI I! I
11
I -13'::
m
0
CL
I -1200 H U-
4-4:1 H-+++/-+/-+/-A--
-d
H I
-12 -z z
o -1100. q II* II I I r Z I *
--o00
III".'
o *1000* tI
0 09
O
-900. 3: t rt 3! L
--4
S-800
a 1 mm J
-8
w
z -700
. . I11.1 '-7 (
-6
-600 ÷
S-L -i - -
--5
-500
-400 4Z1 17 I Ii'
--3
-300 -4
-i-i--V A- "-2
-200 1 * ! I I L ,
4 ----**
- I
9 T . Cl -;. . I i I 1
-1
-100
25 PCMIDIV
0
-lit- t27Z
- 0
0 20 40 60 80 100 120 140 160 180 200 220 240
5 STEI
103 231
0
BANK D
231
128
BANK C
CURVE NO. A-11-8 REV NO. 0
ORIGINATOR DATE /0/25?/0O
SUPERVISOR DATE ,z/.t/o4
SUPERINTENDENT- D
SHIFT OPERATIONS LDATE 16SLA
HARRIS UNIT 1 CYCLE 11
DIFFERENTIAL AND INTEGRAL
ROD WORTH CONTROL BANKS D and C
MOVING WITH 103 STEP OVERLAP
BOL (O:5 EFPD - 161), RFP, EQUILIBRIUM XENON
-1700 -17
-1600 -16
-1500 -15
I I
-1400
-1300
4 14 a, 4
-14
-13
-1200 -12 2
"1
-11 m
m:
E -1100
z
"I
0 -1000 -10~
CL
I-"
-900 0
0 -9
-8
r'C -800 0
1 4V I~, 4-+ 1c 11 ti f-+ -i
I-
-700 4 +-~ I
z-
Z II I 1 4+44H
I I I
-600 -4II-f -6
-500
-400 -4
-300 -3
-200 -2
-100 -1
25 PCMIDIV
0 0
0 20 40 60 80 100 120 140 160 180 200 220 240
5 STEPS/DIV
0 103 231
aaa
BANK D
128 231
BANK C
CURVE NO. A-11-9 REV NO. 0
ORIGINATOR " it, DATE /O/Z5/0/
SUPERVISOR DATE T
SUPERINTENDENT- DATE/ 1/0/
SHIFT OPERATIONS DATE /
HARRIS UNIT 1 CYCLE 11
DIFFERENTIAL AND INTEGRAL
ROD WORTH CONTROL BANKS D and C
MOVING WITH 103 STEP OVERLAP
MOL (161 < EFPD 5 334), HFP, EQUILIBRIUM XENON
-1800 18
.1'
T I ] + I I I I I F J. J* r
. . I
.. p I
II 111111;
!l I I I f I 4 -.
-1700
-1600 I t I .. I1 - JLL. I WA.... .1 - ....L...A..d
rnsmmmmm *4
SI- I -
IIj'!i,
- 11 -1-ti--nm
- -16
Fj!fII:K7TJILJ IJULJJIL
I r I I I t F I I I I I I I P . i
-1500
-1400
I I
711 111
I
VLLIJAA...LLIJIIIL
T I I
StJ
- 171ThT1Z2U1D2Z122ZF1
I
"-15
-14
-1300 -13
3i 1--
-1200 r7 HIfmn:i:H14izlAH -12 m
7i TYI.IAAJILLIIIILL
m
- (a
0. 4-TTT44444 -1 z
! 1 ! 1T-HH
I [ 1
-1100
' ' ll1 -
i I I I * I I E I
I' EXiiIH iii~i *-10 r
0 -1000
Aq K
0
C
-900
Ft . -9 0
C
cc * -8 0
-n
_j -800 -4
< K
r
cc
w
-700
zI
z -600 -
-500 I
t --7
--6
t 1T_IiI
T.............LI ni, .
-400 Z
-300 IaT _ _ _ _~~~~
Th*
I
--2
-200 wT__.J
7j:j -1
-100
25 PCM/DIV St -- I
- -
1-i--K-i-il
1**'-"t
--
'II
0
0
0 20 40 60 80 100 120 140 160 180 200 220 240
5 STEPS/DIV
0 103 231
BANK D
128 231
BANK C
CURVE NO. A-11-10 REV NO. 0
ORIGINATOR a-, DATE /./:Tht/0o1
SUPERVISOR DATE /z,/z V'
SUPERINTENDENT
SHIFT OPERATIONS ,DATEI
HARRIS UNIT 1 CYCLE 11
DIFFERENTIAL AND INTEGRAL
ROD WORTH CONTROL BANKS D and C
MOVING WITH 103 STEP OVERLAP
i
EOL (334 < EFPD < 507), HFP, EQUILIBRIUM XENON
jt -21
-2100
-2000. - -20
H-P -H- H -f-f-H I-i--I- -- 19
-1900 -
Hqq:q YE -- 18
-1800 I f-I-i-i- IFT117}71111111[IL.hI.t1li.1JLJ Hcizi+/-tzrr;
-1700
fl I 1! I A-H -17
-li I
-16
-1600
S
F l
SrI I I * & I I I I
w~I I I I I * I I I I
................I I I
I I -
m
-1500
E -1400
- l ** l I I I I I a T1TVYIIIIII]I[I]III!.......LLLLLIILLLLLLLIJItIt
I I, I I I ] l I I } I I ---I I I-I-tm-
Il I q i l
I "-152
a 1/2ttrtr -14m
.i -13z
&-1300 ----- - - - -- - - - - - - - - -
--I
-1200 -8
0
3: -1100
H-
H -110
O -1000 -0 -7
--9 -.
-j
.< -900
cr
a -800 ----------------------- ~~J-- t-.z
$
1!I -8 "*
C
LLI
--7 :33
z -700 7:- l
op
I I I --6 *
-600 -t--- _l
-500 m - I ....-. I I . Err
--5
'-4
-400
I 'I --3
-300 I I
-2
-200
EFF ---- -r t
--1
-100 1W#
JZ~fz4 fz22 m-i it
25 PCM/DIV
0"
0 20 40 60 80 100 120 140 160 180 200 220 240
5 STEPS/DIV
0 103 231
BANK D
128 231
BANK C
CURVE NO. A-11-11 REV NO. 0
ORIGINATOR 6 /9,/L DATE 10125101
SUPERVISOR c DATE /Z?,,
SUPERINTENDENT
SHIFT OPERATIONS DATE / k
HARRIS UNIT 1 CYCLE 11
POWER DEFECT vs. POWER LEVEL
for VARIOUS BORON CONCENTRATIONS
BOL (05 EFPD < 161)
0
-200
-400
-600
-800
E
0
a.
F
CL -1000
U
' -1200
0_
0
-1400
.-j
I,-
-1600 2100 ppm
1800 ppm
1500 ppm
-1800
1200 ppm
-2000
900 ppm
-2200
20 PCMIOIV
-2400
0 20 40 60 80 100
1 0/ 0/DIV
POWER LEVEL (PERCENT)
CURVE NO. C-11-1 REV NO. 0
0
ORIGINATOR DATE 1 /-)5-/o/
SUPERVISOR DATE ZZ,2/29y,/
SUPERINTENDENT
SHIFT OPERATIONS DATE 16 Q
HARRIS UNIT 1 CYCLE 11
POWER DEFECT vs. POWER LEVEL
for VARIOUS BORON CONCENTRATIONS
MOL (161 < EFPD - 334)
0
-200
-400
-600
-800
E
I-. -1000
uJ
U.
u,
a
-1200
Lu
0
a -1400
-1
0I-
-1600
-1800
1800 ppm
1500 ppm
-2000
1200 ppm
900 ppm
-2200
20 PCMI]IV 600 ppm
-2400
0 20 40 60 80 100
1 %mIV
POWER LEVEL (PERCENT)
C-11-2 REV NO. 0
CURVE NO.
ORIGINATOR -,.,, 2-&. DATE /0. -? -/5
SUPERVISOR DATE
SUPERINTENDENT
SHIFT OPERATIONS, j DATE
HARRIS UNIT 1 CYCLE 11
POWER DEFECT vs. POWER LEVEL
for VARIOUS BORON CONCENTRATIONS
EOL (334 < EFPDP 507)
0
-200
-400
-600
-800
-1000
E -1200
-1400
w
LA
-1600
0
CLl -1800
0
a
-2000
I
0
-2200
-2400
-2600
1200 ppm
-2800 900 ppm
600 ppm
-3000 300 ppm
0 ppm
-3200
20 PCMJDIV
-3400
0 20 40 60 80 100
1 %/DIV
POWER LEVEL (PERCENT)
CURVE NO. C-11-3 REV NO. 0
ORIGINATOR - DATE /O/a?5-/01
SUPERVISOR c-DATE ,o/-?/oi
SUPERINTENDENT
SHIFT OPERATIONS - DATE
Attachment 5
Sheet 1 of 1
loolina Tower Cold Weather Oneration
90
U
w
w 80
(9
UJ 70
w
0
0 60
Iz
0
CD
z 50
0
-J
L
0 40
0
C,
32
30
-30 -20 -10 0 10 20 30 32 40
AMBIENT AIR TEMPERATURE (DEGREES F)
Li NORMAL OPERATION - COOLING TOWER DEICING GATE VALVES OPEN
U AS IS - COOLING TOWER DEICING GATE VALVES REMAIN AS IS
H HALF OPEN - COOLING TOWER DEICING GATE VALVES HALF OPEN
ABNORMAL OPERATION-"NO CONDENSER HEAT LOAD" AREA. IN THIS AREA PERFORM SECTION 8.6.
ac_
AfptQ
OP-141 Rev. 17 Page 38 of 40