ML041600273
| ML041600273 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/10/2004 |
| From: | Lanksbury R NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| 50-346/04-301 50-346/04-301 | |
| Download: ML041600273 (50) | |
Text
U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: MASTER Date: May 10, 2004 Facility/Unit: Davis Besse U1 Region: III Reactor Type: BW Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Value 75.0 Points Applicants Score
__________ Points Applicants Grade
__________ Percent
PART A - GENERAL GUIDELINES FOR TAKING NRC EXAMINATIONS 1.
[Read Verbatim] Cheating on any part of the examination will result in a denial of your application and/or action against your license.
2.
If you have any questions concerning the administration of any part of the examination, do not hesitate asking them before starting that part of the test.
3.
SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e., shift supervisor, senior shift supervisor, or whatever the title of the position may be).
4.
You must pass every part of the examination to receive a license.
5.
The NRC examiner is not allowed to reveal the results of any part of the examination until they have been reviewed and approved by NRC management. Grades provided by the facility licensee are preliminary until approved by the NRC. You will be informed of the official examination results about 30 days after all the examinations are complete.
PART B - WRITTEN EXAMINATION GUIDELINES 1.
[Read Verbatim] After you complete the examination, sign the statement on the cover sheet indicating that the work is your own and you have not received nor given assistance in completing the examination.
2.
To pass the examination, you must achieve a grade of 80.00 percent or greater; grades will not be rounded up to achieve a passing score. Every question is worth one point.
3.
For an initial examination, the nominal time limit for completing the examination is six hours; extensions will be considered under extenuating circumstances.
4.
You may bring pens, pencils, and calculators into the examination room. Dark pencil should be used to facilitate machine grading.
5.
Print your name in the blank provided on the examination cover sheet and the answer sheet. You may be asked to provide the examiner with some form of positive identification.
6.
Mark your answers on the answer sheet provided. Use only the answer sheets provided. If you decide to change your original answer, erase your selected answer completely and enter the desired answer. If the examiner is unable to determine which of the marks on your answer sheet is your selected answer because of poor erasure, the question will be marked incorrect and no credit will be given.
7.
If you have any questions concerning the intent or the initial conditions of a question, do not hesitate asking them before answering the question. Ask questions of the NRC examiner or the designated facility instructor only. When answering a question, do not make assumptions regarding conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question. For example, you should not assume that any alarm has activated unless the question so
states or the alarm is expected to activate as a result of the conditions that are stated in the question. Finally, answer all questions based on actual plant operation, procedures, and references. If you believe that the answer would be different based on simulator operation or training references, you should answer the question based on the actual plant.
8.
Restroom trips are permitted, but only one applicant at a time will be allowed to use the restroom.
9.
When you complete the examination, assemble a package including the examination cover sheet you have to sign and the answer sheets. Give it to the NRC examiner or proctor. Remember to sign the statement on the examination cover sheet indicating that the work is your own and that you have neither given nor received assistance in completing the examination. Your examination will be turned over to the stations training department for review/retention/destruction.
10.
After you have turned in your examination, leave the examination area as defined by the proctor or NRC examiner. If you are found in this area while the examination is still in progress, your license may be denied.
11.
Do you have any questions?
REACTOR OPERATOR Page 4 QUESTION: 001 (1.00)
Following a reactor trip, all but one rod of Groups 1 through 7 control rods is verified fully inserted. Adequate Shutdown Margin...
a.
does exist. No boration is required.
b.
does not exist. Boric acid addition to the Makeup Tank is preferentially used to ensure adequate Shutdown Margin.
c.
does not exist. Boration from the BWST is preferentially used to ensure adequate Shutdown Margin.
d.
may not exist. Reactor power is monitored and boration is initiated if an unexpected rise in neutron count rate is observed.
QUESTION: 002 (1.00)
The following plant conditions exist:
A Pressurizer vapor space leak occurred approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago.
An SFAS Level 2 actuation occurred and all safety systems responded as expected.
BWST level is 9 ft.
RCS pressure is 925 psig; temperature is 400°F.
Subcooling margin was not lost.
Which one of the following actions should be performed prior to swapping LPI Pump suctions to the CTMT sump?
a.
Block and stop HPI pumps.
b.
Piggyback LPI to HPI pump suctions.
c.
Establish HPI alternate minimum recirc flowpath.
d.
Perform HPI flow balancing.
REACTOR OPERATOR Page 5 QUESTION: 003 (1.00)
Which one of the following describes the basis for tripping all Reactor Coolant Pumps (RCPs) on a loss of subcooling margin?
a.
To prevent possible core damage on a subsequent trip of the RCPs.
b.
To reduce RCS pressure by removing the pressure head developed by the RCPs.
c.
To prevent cavitation damage to the RCPs.
d.
To reduce the amount of heat being added to the RCS from the RCPs.
QUESTION: 004 (1.00)
Recirculation from the emergency sump has been accomplished following a large break LOCA.
Which one of the following actions protects the Containment Spray Pumps (CSP) from losing net positive suction head?
a.
Verify the "Emergency Sump Level Greater Than 2 Feet" red lights are lit.
b.
Verify emergency sump water temperature is less than the saturation temperature for the containment pressure.
c.
Verify CSP discharge valves throttle position amber lights are lit.
d.
Verify the CSP vent valves are open for continuous venting.
REACTOR OPERATOR Page 6 QUESTION: 005 (1.00)
The following plant conditions exist:
The plant was at 100% power.
A loss of both Makeup Pumps has occurred.
The reactor has been shutdown to Low Level Limits, approximately 28% power.
Which one of the following is the reason the reactor is tripped rather than continuing the rapid shutdown?
a.
The pressurizer level will lower with no ability to make up to the RCS.
b.
Tech. Spec. 3.0.3 requires the plant to be in Mode 3 within one hour.
c.
The loss of the boron injection flowpath will prevent the addition of boron to ensure adequate shutdown margin.
d.
The loss of seal injection requires tripping the RCPs within one hour to prevent seal damage.
QUESTION: 006 (1.00)
The following plant conditions exist:
The plant is in Mode 5.
The RCS is drained to 18 inches.
The running Decay Heat Pump has tripped.
The standby Decay Heat Pump has been started.
The maximum Decay Heat System flow that can be established is determined by comparing the running Decay Heat Pump __________ pressure to __________.
a.
suction; the reactor vessel maximum allowable cooldown rate b.
discharge; the reactor vessel maximum allowable cooldown rate c.
suction; RCS temperature d.
discharge; RCS temperature
REACTOR OPERATOR Page 7 QUESTION: 007 (1.00)
The following plant conditions exist:
A Level 1, 2, and 3 SFAS actuation has occurred.
Offsite power is available.
CCW Pump 1 did not start.
Which one of the following components is required to be stopped immediately?
a.
High Pressure Injection Pump 1 b.
Low Pressure Injection Pump 1 c.
Makeup Pump 1 d.
Emergency Diesel Generator 1 QUESTION: 008 (1.00)
The following plant conditions exist:
The plant is at 100% power.
An instrument failure has caused Tave to decrease to 575°F.
Annunciator 4-2-E, PZR LVL LO, is in alarm.
The instrument failure has been resolved and RCS Tave is recovering.
As Tave recovers, with no further operator action, RCS pressure will ____________ due to a.
decrease; colder Pressurizer spray bypass flow b.
increase; compressing the steam bubble resulting in an increase in superheat of the steam c.
decrease; insufficient Pressurizer heater capacity to compensate for low temperature water insurge d.
increase; makeup flow response to low Pressurizer level
REACTOR OPERATOR Page 8 QUESTION: 009 (1.00)
During a transient, RCS pressure has decreased below the RPS low pressure trip setpoint.
The reactor did not automatically trip.
Which of the following combinations are the PREFERRED ORDER for shutting down the reactor?
a.
Momentarily deenergize E2 and F2 simultaneously.
Depress the Reactor Trip pushbutton.
Trip BE211 and BF211 to deenergize the CRD System.
Manually trip Reactor Trip Breakers A, B, and C.
b.
Depress the Reactor Trip pushbutton.
Momentarily deenergize E2 and F2 simultaneously.
Trip BE211 and BF211 to deenergize the CRD System.
Manually trip Reactor Trip Breakers A, B, and C.
c.
Momentarily deenergize E2 and F2 simultaneously.
Depress the Reactor Trip pushbutton.
Manually trip Reactor Trip Breakers A, B, and C.
Trip BE211 and BF211 to deenergize the CRD System.
d.
Depress the Reactor Trip pushbutton.
Momentarily deenergize E2 and F2 simultaneously.
Manually trip Reactor Trip Breakers A, B, and C.
Trip BE211 and BF211 to deenergize the CRD System.
REACTOR OPERATOR Page 9 QUESTION: 010 (1.00)
The following plant conditions exist:
A tube rupture has developed in SG2.
The reactor has been tripped.
An RCS cooldown is in progress.
RCS temperature is 500°F.
Which one of the following actions is performed in order to maintain the ability to steam the good SG to the condenser?
a.
Pull a fuse in ICS to defeat the turbine bypass valve 125 psi bias.
b.
Pull a fuse in ICS to defeat the main steam isolation valve to turbine bypass valve interlock.
c.
Use the SASS transfer switch to select the Main Steam Line 1 turbine header pressure transmitter.
d.
Use the SASS transfer switch to select SG1 outlet pressure transmitter.
QUESTION: 011 (1.00)
The following plant conditions exist:
The plant is at 50% power.
MFPT 1 is in service.
MFPT 2 is running on the ICS low speed stop.
In order for ARTS to be operable so that the reactor will trip if MFPT 1 trips, the ARTS Channel Bypass key switches are required to be in the __________ position and the ARTS Main Feed Pump Input Test toggle switches for MFPT 2 are require to be in the __________ position.
a.
NORMAL; OPERATE b.
NORMAL; TRIP c.
MFP; OPERATE d.
MFP; TRIP
REACTOR OPERATOR Page 10 QUESTION: 012 (1.00)
The following plant conditions exist:
A loss of offsite power has occurred.
While performing battery load shedding, RPS Channels 1 and 2 remain energized.
The reason for this is to maintain __________.
a.
RCS pressure instruments energized b.
a reliable indication of CRD breaker position c.
a reliable indication of RCS temperature d.
Source Range NIs energized QUESTION: 013 (1.00)
A Loss of Offsite Power (LOOP) has occurred, resulting in a reactor trip. After depressing the Main Turbine Trip pushbutton, Turbine Stop Valve 1 indicates open. Which one of the following actions is taken to ensure the Main Turbine is not operating?
a.
Close Main Steam Isolation Valve 1.
b.
Verify all four Control Valves are closed.
c.
Direct an EO to trip the Main Turbine at the front standard d.
Manually initiate SFRCS
REACTOR OPERATOR Page 11 QUESTION: 014 (1.00)
The following plant conditions exist:
The plant has just experienced a loss of 120 VAC Bus YAU while at 100%
power.
The crew has tripped the reactor.
SFRCS was actuated due to low deaerator level.
During implementation of DB-OP-02000 __________.
a.
makeup/HPI flow is initiated since the PORV failed open b.
emergency boration is initiated since APSR group position is lost c.
AVV1 is controlled locally since the AVV fails closed d.
AFPT1 is controlled locally since AFPT1 governor power is lost.
QUESTION: 015 (1.00)
The following plant conditions exist:
The plant is at 100% power.
Annunciator 1-6-E, DC BUS 1 TRBL alarms.
The AC input breaker to battery charger DBC-1P has tripped.
Which one of the following actions is required to be performed to prevent the loss of the 1P battery?
a.
Load shed DCMCC1.
b.
Place DBC-1N in service as DBC-1P.
c.
Place DBC-1PN in service as DBC-1P.
d.
Transfer D1P to DCMCC2.
REACTOR OPERATOR Page 12 QUESTION: 016 (1.00)
The following plant conditions exist:
The plant was at 100% power.
Outside air temperature is 85°F.
Lake temperature is 82°F.
A loss of subcooling margin has occurred.
SFAS Level 2 has actuated.
The Train 2 Service Water (SW) pump has failed to start.
Which one of the following is the effect the SW pump failure will have on safety-related equipment?
a.
CCW Pump 2 will trip on high cooler outlet temperature.
b.
ECCS Room 2 will exceed the maximum design room temperature.
c.
HPI Pump 2 will trip on high lube oil temperature.
d.
The Control Room will exceed the maximum design room temperature.
QUESTION: 017 (1.00)
The following plant conditions exist:
The plant is at 100% power.
Annunciator 9-1-F, INST AIR HDR PRESS LO, alarms.
Instrument air pressure on PI-810 reads 72 psig.
The secondary plant is stable.
Which one of the following actions is required?
a.
Manually trip the reactor based on low air pressure.
b.
Commence a rapid shutdown based on low air pressure.
c.
Commence a rapid shutdown when a secondary plant upset begins.
d.
Manually trip the reactor when a secondary plant upset begins.
REACTOR OPERATOR Page 13 QUESTION: 018 (1.00)
The following plant conditions exist:
The reactor was at 100% power.
Makeup/HPI/PORV cooling was initiated due to a loss of all feedwater.
The MDFP has restored level in both SGs to 124 inches.
Which one of the following is used to attempt to regain primary to secondary heat transfer?
a.
Raise SG level using the MDFP.
b.
Lower SG pressure using the AVVs.
c.
Bump start an RCP.
d.
Close the PORV to recover subcooling margin.
QUESTION: 019 (1.00)
The following plant conditions exist:
The plant was at 100% power.
A valid RPS trip signal failed to trip the reactor.
The reactor could not be tripped from the Control Room Which one of the following describes the methods available in the Control Room to reduce power and Tave prior to locally opening the reactor trip breakers?
a.
Manually insert control rods and lower turbine load.
b.
Manually insert control rods and start emergency boration.
c.
Manually open the turbine bypass valves and lower turbine load.
d.
Manually open the turbine bypass valves and start emergency boration.
REACTOR OPERATOR Page 14 QUESTION: 020 (1.00)
The following plant conditions exist:
A reactor startup is in progress following a mid-cycle outage.
Control Rod Group 6 is at 25% rod index.
Both source range nuclear instruments fail low.
The reactor startup is stopped, Control Rod Groups 1 through 7 are inserted and CRD breakers are opened...
a.
to comply with Tech. Specs.
b.
to disable the feed and bleed permissive.
c.
until Gamma-Metric source range instruments are calibrated.
d.
because the CRD out inhibit will prevent further rod withdrawals.
QUESTION: 021 (1.00)
A reactor startup is in progress.
Which one of the following is an indication that Intermediate Range NI-3 is over-compensated?
a.
IR NI-3 reads 3 X 10-6 amps IR NI-4 reads 8 X 10-7 amps b.
SR NI-1 and SR NI-2 read 8 X 105 cps IR NI-3 reads 2 X 10-11 amps c.
SR NI-1 and SR NI-2 read 3 X 104 cps IR NI-3 reads 8 X 10-11 amps d.
IR NI-3 reads 5 X 10-11 amps IR NI-4 is not on scale
REACTOR OPERATOR Page 15 QUESTION: 022 (1.00)
The following plant conditions exist:
The plant was at 100% power.
A large break LOCA has occurred.
During verification of proper SFAS incident levels 1 through 4 actuation, several components failed to actuate to their SFAS position:
CV 5074, CTMT VAC RLF VLV ISO MU 3, LETDOWN CLRS OUTLET RC 240A, PZR SAMPLE DR 2012B, CTMT NORMAL SUMP The reason for repositioning the out-of-position components to their SFAS position is to...
a.
prevent overheating letdown coolers since component cooling water is isolated to CTMT.
b.
prevent drawing PZR sample without Shift Manager permission.
c.
ensure the Makeup System is properly aligned to provide adequate core cooling.
d.
ensure containment is properly isolated to minimize release of radioactive.
material
REACTOR OPERATOR Page 16 QUESTION: 023 (1.00)
DB-OP-02504, Rapid Shutdown, provides the operator with an Attachment which contains guidelines for MINIMIZING the effects of Axial Power Imbalance (API) if the plant is to be stabilized ABOVE Low Level Limits.
Which ONE of the following statements correctly describes that guidance? (Assume a HIGH power history.)
a.
Control Rods are maintained within a desired index to prevent positive API, with Boron concentration INCREASED for approximately four hours as Xenon builds toward its peak and then DECREASED to maintain the desired rod index.
b.
Control Rods are maintained within a desired index to prevent negative API, with Boron concentration DECREASED for approximately four hours as Xenon builds toward its peak, and then INCREASED to maintain the desired rod index.
c.
Control Rods are maintained within a desired index to prevent positive API, with Boron concentration DECREASED for approximately four hours as Xenon builds toward its peak and then INCREASED to maintain the desired rod index.
d.
Control Rods are maintained within a desired index to prevent negative API, with Boron concentration INCREASED for approximately four hours as Xenon builds toward its peak and then DECREASED to maintain the desired rod index.
REACTOR OPERATOR Page 17 QUESTION: 024 (1.00)
The following plant conditions exist:
The plant is at 23% power.
The turbine trips on low EHC fluid pressure.
Following the turbine trip:
1.
FW Valve P is 44 psid 2.
SG pressures are 870 psig.
3.
SG levels are 60 inches.
4.
Generator output is 24 MWE.
Which of the above listed parameters will require manual action(s) to establish normal conditions?
a.
1 and 2 b.
1 and 4 c.
2 and 3 d.
3 and 4 QUESTION: 025 (1.00)
The following plant conditions exist:
The plant was at 100% power.
A loss of off-site power has caused a reactor trip.
Which one of the following describes the response of Service Water Pump 2?
Service Water Pump 2 will start...
a.
immediately when EDG 2 output breaker closes.
b.
25 seconds after EDG 2 output breaker closes.
c.
immediately after the sequencer times out.
d.
20 seconds after the sequencer starts.
REACTOR OPERATOR Page 18 QUESTION: 026 (1.00)
The following plant conditions exist:
The plant was at 100% power.
A complete rupture of the Circ Water piping expansion joint at the main condenser inlet has caused a turbine and reactor trip.
Which one of the following identifies plant equipment required to be shutdown to prevent damage due to flooding?
a.
Both Main Feedwater Pumps b.
Both Auxiliary Feedwater Pumps c.
All three CCW Pumps d.
All three TPCW Pumps QUESTION: 027 (1.00)
The following plant conditions exist:
The plant was at 100% power for several months.
A loss of CCW to containment has led to a reactor trip and tripping of all RCPs.
Due to the loss of letdown, an RCS cooldown has been started.
The ______________ will be manually controlled to prevent exceeding a maximum cooldown rate of ______________ during the cooldown.
a.
Turbine Bypass Valves; 50°F/hr.
b.
Turbine Bypass Valves; 100°F/hr.
c.
Atmospheric Vent Valves; 50°F/hr.
d.
Atmospheric Vent Valves; 100°F/hr.
REACTOR OPERATOR Page 19 QUESTION: 028 (1.00)
Which ONE of the following combinations of Reactor Coolant Pump (RCP) parameters are inputs to the RCP Monitoring and Diagnostic System?
1.
Rotor horizontal displacement 2.
Reactor Coolant System pressure 3.
13.8KV Bus Amps 4.
Reactor Power 5.
RCP Component Cooling Water flow a.
1, 2, 4 b.
2, 3, 5 c.
1, 3, 4 d.
2, 4, 5 QUESTION: 029 (1.00)
Which ONE of the following pairs of electrical buses represents the power supplies for the Makeup Pumps?
a.
480 VAC essential buses E1 and F1 b.
480 VAC nonessential buses E2 and F2 c.
4160 VAC essential buses C1 and D1 d.
4160 VAC nonessential buses C2 and D2
REACTOR OPERATOR Page 20 QUESTION: 030 (1.00)
Reactor Coolant System inventory has been reduced to 40 inches to replace a Reactor Coolant Pump seal package. The #1 Decay Heat (DH) pump flow AND amps begin to swing erratically.
Which ONE of the following statements is correct:
a.
Raise CCW flow to #1 Decay Heat Cooler to lower RCS temperature which will raise #1 DH pump NPSH.
b.
Immediately start the #2 DH pump to provide core cooling.
c.
Stop the #1 DH pump if reducing flow does not stabilize flow and current.
d.
Increase RCS inventory by transferring DH pump 1 suction to the BWST by opening DH 2733, then closing DH 1517.
QUESTION: 031 (1.00)
Which ONE of the following describes the PREFERRED long term boron dilution flow path during a Large Break LOCA?
a.
HPI Pump 1-2 piggybacks from LPI Pump 1-2, which takes suction from the EMERGENCY SUMP. HPI Pump 1-2 discharges to the pressurizer auxiliary spray line.
b.
LPI Pump 1-2 takes suction from RCS LOOP 2 HOT LEG and discharges through DH Cooler 1-2 to the reactor vessel.
c.
HPI pump 1-2 piggybacks from LPI pump 1-2, which take suction from RCS LOOP 2 HOT LEG. HPI pump 1-2 discharges to the RCS Loop 2 Cold Legs d.
LPI pump 1-2 takes suction from the EMERGENCY SUMP and discharges through DH cooler 1-2 to the pressurizer auxiliary spray line.
REACTOR OPERATOR Page 21 QUESTION: 032 (1.00)
To what location does the Quench Tank relief valve relieve on high pressure?
a.
Reactor Coolant Drain Tank b.
Containment Normal Sump c.
Containment Vent Header d.
Train 1 ECCS Room Sump QUESTION: 033 (1.00)
The following plant conditions exist:
PZR PORV outlet temperature is 255°F PZR Quench Tank level is 9.6 ft.
PZR Quench Tank temperature is 215°F (Assume level and temperature control in AUTOMATIC.)
Which ONE of the following is correct?
a.
Quench Tank Recirculating Pump started on HIGH temperature caused by the leaking PORV and level is automatically being controlled by draining to the RC Drain Tank.
b.
Quench Tank Recirculating Pump started on HIGH level caused by the leaking PORV and temperature is automatically being controlled by draining to the Containment Sump.
c.
Quench Tank Recirculation Pump started on HIGH temperature caused by the leaking PORV and level is automatically being controlled by draining to the Containment Sump.
d.
Quench Tank Recirculating Pump started on HIGH level, caused by the leaking PORV, and pressure is automatically being controlled by draining to the RC Drain Tank.
REACTOR OPERATOR Page 22 QUESTION: 034 (1.00)
Select the statement that describes the Component Cooling Water/Letdown interface.
a.
High Temperature on Letdown AND/OR High Pressure on CCW out of the Letdown Cooler will provide alarm and isolation functions.
b.
High Temperature ONLY on Letdown out of the Letdown Cooler will provide alarm and isolation functions.
c.
High Pressure ONLY on CCW out of the Letdown Cooler will provide alarm but no isolation functions.
d.
High Temperature on Letdown AND/OR High Pressure on CCW out of the Letdown Cooler will provide alarm but no isolation functions.
QUESTION: 035 (1.00)
The plant is operating at 100% power with all systems in their normal lineup. The Reactor Coolant System (RCS) is recovering from a transient that raised RCS pressure to 2225 psig.
Pressure had been reduced to 2195 psig when a loss of NNI-X DC power occurred. What is the effect of the loss of NNI-X DC on RC2, Pressurizer Spray Valve? (EWD E52B, sh. 10 and sh. 59 are attached) a.
RC2 will remain open to 40% and will have to be manually closed.
b.
RC2 will remain open to 40% and will have to be isolated using RC11, Pressurizer Spray Block Valve.
c.
RC2 will close and RCS pressure will have to be controlled using RC200, Pressurizer Vent Line Stop Valve and RC2A, Pressurizer PORV.
d.
RC2 will close and will have to be manually operated to control RCS pressure.
REACTOR OPERATOR Page 23 QUESTION: 036 (1.00)
Reactor Coolant System heatup is in progress per DB-OP-06900, Plant Heatup.
RCS temperature is 360°F RCS pressure is 675 psig PORV testing, per DB-SP-03363 is initiated. Which of the following conditions would require termination of the PORV cycle test?
a.
Quench Tank pressure of 85 psig b.
Reactor Coolant Drain Tank temperature of 165°F c.
Pressurizer level of 80 inches d.
RCS pressure drops to 600 psig QUESTION: 037 (1.00)
Which ONE of the following situations will occur if 120VAC essential AC power is lost to ARTS Channel 1?
a.
ARTS Ch. 1 will trip.
b.
The reactor will trip.
c.
The only result will be a loss of power alarm.
d.
ARTS Ch. 1 and Ch. 3 will both trip.
REACTOR OPERATOR Page 24 QUESTION: 038 (1.00)
During operation at 100% Power, with RPS channel 1 in manual bypass, RCS pressure exceeds the RPS high pressure trip setpoint. RPS channels 2 and 4 trip, but RPS channel 3 does not trip due to a failed pressure bistable. Which of the following statements is correct concerning the expected response of the CRD breakers?
a.
Only the "B" and "D" breakers will open.
b.
Breakers "A", "C", and "D" will open, breaker "B" will remain closed.
c.
Only the "A" and "C" breakers will open.
d.
All CRD breakers will open.
QUESTION: 039 (1.00)
The plant was operating at 100% power when PT2000, Containment Wide Range Pressure, failed to mid-scale (30 psia). What is the expected response?
a.
SFAS Channel 1 trips on high containment pressure. All SFAS level 1, 2, and 3 components for Channel 1 actuate to their SFAS condition.
b.
SFAS Channel 1 trips on high-high containment pressure. All SFAS level 1, 2, 3, and 4 components for Channel 1 actuate to their SFAS condition.
c.
SFAS Channel 1 trips on high containment pressure. All SFAS level 1, 2,and 3 components for Channel 1 remain in their pre-failure condition.
d.
SFAS Channel 1 trips on high-high containment pressure. All SFAS level 1, 2, 3, and 4 components for Channel 1 remain in their pre-failure condition.
REACTOR OPERATOR Page 25 QUESTION: 040 (1.00)
The following plant conditions exist:
The plant is operating at 95% power.
All plant systems are operating as designed.
Due to problems with cooling, containment temperatures are increasing.
Which ONE of the following is the expected effect of these conditions?
a.
Indicated Makeup Tank level will DECREASE.
b.
Actual Makeup Tank level will INCREASE.
c.
Indicated Pressurizer level will DECREASE.
d.
Actual Pressurizer level will INCREASE.
QUESTION: 041 (1.00)
A large break LOCA occurred. All systems functioned as expected. The following plant conditions exist:
The Borated Water Storage Tank Level is at 5 ft.
Both Containment Spray pumps are running.
Both Low Pressure Injection pumps are running.
Containment pressure is 18 psig and slowly rising.
Why is the pressure in the Containment rising?
a.
Containment Spray pump discharge valves have throttled to prevent runout with suction from the warmer Emergency Sump.
b.
Containment Spray pump discharge valves have throttled to prevent cavitation due to low BWST level.
c.
Containment Spray pump discharge valves have throttled to prevent cavitation with suction from the warmer Emergency Sump d.
Low Pressure Injection pump discharge valves have throttled to prevent cavitation with suction from the warmer Emergency Sump.
REACTOR OPERATOR Page 26 QUESTION: 042 (1.00)
A plant cooldown is in progress per DB-OP-06903, Plant Shutdown and Cooldown, with ONE Steam Generator.
RCS Pressure is 2155 psig RCS Temperature is 525°F The operator is directed to cool the RCS to less than or equal to the isolated Steam Generator average shell temperature. The reason for this is to...
a.
ensure the Steam Generator tubes will be in tension, since differential temperature limits are less restrictive with tubes in tension.
b.
raise subcooling margin, thereby minimizing the risk of drawing a bubble in the top of the idle loop's hot leg.
c.
ensure the Steam Generator tubes will be in compression, since differential temperature limits are less restrictive with tubes in compression.
d.
minimize thermal stress on the Steam Generator, HOT STANDBY conditions can be maintained without a MODE change.
QUESTION: 043 (1.00)
All feedwater has been lost to the steam generators. AFPs 1 and 2 have tripped on overspeed.
A local operator has been sent to take local speed control of the #1 auxiliary feedwater pump.
Which of the following sequences would the control room operator see as local control was established?
a.
AFPT 1 OVRSPD TRIP (10-2-G) clears, AFP-1 Flow is indicated on FI 6426, Steam Generator level and pressure are increasing.
b.
AFP-1 Flow is indicated on FI 6426, AFPT 1 OVRSPD TRIP (10-2-G) clears, Steam Generator level and pressure are increasing.
c.
AFPT 1 OVRSPD TRIP (10-2-G) clears, Steam Generator level and pressure are increasing, AFP-1 Flow indicated on FI 6426.
d.
AFP-1 Flow indicated on FI 6426, Steam Generator level and pressure are increasing, AFPT 1 OVRSPD TRIP (10-2-G) clears.
REACTOR OPERATOR Page 27 QUESTION: 044 (1.00)
The plant is operating at 45% power when a loss of D1P and DAP occurs.
The plant has stabilized at 27% power (Low Level Limits)
Condensate Pump 2 is running with 3.8 MPPH condensate flow as indicated on FI578, Condensate Total Pump Flow Deaerator levels indicate 7.5 feet and are slowly dropping.
What actions should be taken to control secondary system response?
a.
Trip the reactor, initiate AFW and SFRCS Isolation, then trip Condensate Pump 2 to prevent damage due to runout b.
Isolate CD578, Condensate Pump Minimum Recirc Flow Valve using CD79, CD578 Inlet Isolation Valve to reduce flow to within limits c.
Break Condenser vacuum using VS634 and VS635, Condenser Vacuum Breakers to raise Condensate Pump 2 suction pressure.
d.
Locally throttle CD2796, Condensate Backpressure Control Valve to prevent Condensate Pump 2 runout QUESTION: 045 (1.00)
The plant is operating at 100% power. Both MFW Pumps trip. All systems respond as designed. Assuming NO operator action, plant conditions 15 minutes after the SFRCS initiation would be:
a.
- Tave - 550°F
- SG level - 40 inches
- SG press - 995 psig b.
- Tave - 550°F
- SG level - 49 inches
- SG press - 995 psig c.
- Tave - 556°F
- SG level - 49 inches
- SG press - 1050 psig d.
- Tave - 556°F
- SG level - 40 inches
- SG press - 1050 psig
REACTOR OPERATOR Page 28 QUESTION: 046 (1.00)
Which ONE of the following describes steam binding in an Auxiliary Feed Pump?
a.
Hot water accumulates in the steam line ending up in the turbine casing, causing turbine overspeed when the Auxiliary Feed Pump is started.
b.
Hot Water accumulates in the pump casing causing turbine overspeed when the Auxiliary Feed Pump is started.
c.
Steam fills the pump casing and prohibits the pump from pumping water.
d.
Steam in the turbine casing condenses and fills the casing with water resulting in differential turbine temperatures and turbine shaft bowing.
QUESTION: 047 (1.00)
The following plant conditions exist:
The plant tripped from 100% power.
SG 1 pressure is 600 psig; level is 62 inches.
SG 2 pressure is 640 psig; level is 58 inches.
Which ONE of the following is the expected SFRCS response to these plant conditions?
a.
b.
c.
d.
REACTOR OPERATOR Page 29 QUESTION: 048 (1.00)
Which ONE of the following will cause the OUT OF SYNC light on YV2 to ILLUMINATE?
a.
Difference in voltage between the inverter and its reference.
b.
Difference in frequency between the inverter and bus Y2.
c.
The inverter is looking for an in-sync supply for power.
d.
Difference in current between the inverter and its reference.
QUESTION: 049 (1.00)
Which ONE of the following identifies a combination of loads, which are ALL powered from DC MCC 1?
1.
RCP 1-1 Backup (DC) Oil Lift Pump 2.
RCP 1-2 Backup (DC) Oil Lift Pump 3.
Emergency Seal Oil Pump 4.
Emergency Bearing Oil Pump (Main Turbine) 5.
Inverter YVA 6.
Inverter YVB a.
1, 3, 6 b.
1, 4, 5 c.
2, 3, 5 d.
2, 4, 6
REACTOR OPERATOR Page 30 QUESTION: 050 (1.00)
While attempting to start EDG 1 for the monthly test the following alarms actuate:
1-1-A EDG 1 TROUBLE 1-1-B EDG 1 FAULT 1-2-A EDG 1 AIR RCVR PRESS LO The local operator reports the following alarms:
43-1-B UNIT LOCKOUT 43-1-C FAIL TO START 43-1-D FAIL TO REACH RATED SPEED & VOLTAGE 43-3-B LOW AIR START PRESSURE What is the expected status of EDG 1 starting air at this time?
a.
EDG Starting Air Compressor 1-1 is running to repressurize EDG Air Receiver 1-1-1 after which the Starting Air System will attempt another EDG 1 start.
b.
EDG Starting Air Compressor 1-2 is running to repressurize EDG Air Receiver 1-1-2 and EDG 1 will remain locked out until the local lockout relay is reset.
c.
EDG Starting Air Compressor 1-1 is locked out and EDG Air Receiver 1-1-1 will remain at low pressure until the local lockout relay is reset.
d.
EDG Starting Air Compressor 1-2 is locked out and EDG Air Receiver 1-1-2 will remain at low pressure until EDG Starting Air Compressor 1-3 is placed in service.
REACTOR OPERATOR Page 31 QUESTION: 051 (1.00)
Preparations were in progress to release Clean Waste Monitor Tank 1 when it was discovered that RE1770A, Clean Waste Radiation Monitor detector has failed and was declared INOPERABLE. For a release from the clean liquid waste to proceed, ___________.
a.
RE1770A must be repaired.
b.
two independent samples, calculations and valve lineups must be performed.
c.
the release path must be realigned to use RE1878A & B, Miscellaneous Waste Radiation Monitors.
d.
RE1770B must be verified operable.
QUESTION: 052 (1.00)
A LOCA causes Reactor Coolant System pressure to drop to 1400 psig. Which ONE of the following describes the response of the Service Water System?
a.
Cooling of Turbine Plant Cooling Water will swap from service water to circulating water.
b.
Cooling water to Turbine Plant Cooling Water will be terminated and must be manually realigned.
c.
Cooling water to the containment air coolers will throttle to maintain containment air temperature.
d.
Cooling water flow to all three containment air coolers will be maximized.
REACTOR OPERATOR Page 32 QUESTION: 053 (1.00)
The following plant conditions have occurred while operating in MODE 1 at 95% RTP:
1.
Annunciator Alarms (11-3-C) SW PMP 3 STRNR DISCH PRESS LO (11-6-C) SW PMP 3 STRNR DP HI (11-3-B) CCW HX 3 OUTLET TEMP HI 2.
Computer Alarms (X002) SW PMP MTR TRBL (T083) CC HX 3 OUT TEMP (P945) SW HDR 1 PRESS Which ONE of the following sections of DB-OP-02511, LOSS OF SERVICE WATER PUMPS/SYSTEMS, would you enter based on the above conditions?
a.
Loss of all Service Water pumps b.
Service Water Non-Seismic Line Rupture c.
Loss of SW Loop 2 d.
Loss of SW Loop 1 QUESTION: 054 (1.00)
Under which ONE of the following circumstances will the Emergency Instrument Air Compressor supply Station Air loads?
a.
When a spool piece between the Emergency Instrument Air compressor and the Station Air header has been installed.
b.
When started by local operator action, since the Emergency Instrument Air compressor is normally lined up to station air.
c.
When the Emergency Instrument Air compressor is lined up to station air and Emergency Instrument Air receiver pressure is GREATER than 95 psig.
d.
When Instrument Air receiver pressure is LESS than 95 psig so the Instrument Air and Station Air are operated as a common system.
REACTOR OPERATOR Page 33 QUESTION: 055 (1.00)
Which ONE of the following combinations are ALL design features of Containment Vessel Isolation valves?
1.
Located as close as practical to the CTMT vessel when the valve is located OUTSIDE CTMT.
2.
Leakage is MINIMIZED by double barriers.
3.
All remote operated CTMT isolation valves located INSIDE CTMT are motor operated.
4.
All remote operated CTMT Isolation valves are CLOSED by SFAS actuation.
a.
1, 2 b.
3, 4 c.
1, 3 d.
2, 4 QUESTION: 056 (1.00)
Under which of the following plant conditions will the RCS Hot Leg Level Monitoring System provide valid direct display of RCS Hot Leg Level?
1.
Plant in Mode 5 with RCS drained below pressurizer level 2.
Plant in Mode 5 with RCS filled and vented with pressure below 150 psig 3.
Plant in Mode 3 ready to enter Mode 2 4.
Plant in Mode 1 at full power 5.
Plant in Mode 3 with natural circulation cooldown in progress 6.
Plant in Mode 4 ready to transition from OTSG cooldown to Decay Heat cooldown a.
1, 2, 5 b.
1, 3, 6 c.
2, 4, 5 d.
3, 4, 6
REACTOR OPERATOR Page 34 QUESTION: 057 (1.00)
The plant is operating at 100% power with all systems in normal lineup when a loss of NNI-X DC power occurs. Which ONE of the following describes the effect on Pressurizer level control and the necessary compensatory measures?
a.
MU32 flow controller fails to 0%. The alternate injection line must be used to provide makeup flow.
b.
MU32 flow controller fails to mid-scale (50%). The normal makeup line must be isolated and the alternate injection line must be used to provide makeup flow.
c.
MU32 flow controller functions normally but the level input becomes uncompensated Pressurizer level. The level setpoint must be adjusted for the difference between compensated and uncompensated level using curve CC 4.1 of DB-PF-06703, Miscellaneous Operations Curves.
d.
MU32 flow controller does not function in automatic. The level controller must be operated in manual to provide makeup flow.
REACTOR OPERATOR Page 35 QUESTION: 058 (1.00)
Initial Conditions Safety Rod Groups 1 through 4 are full out Regulating Rod Groups 5 and 6 are full out APSRs are at 30% withdrawn 100% Reactor Power ICS full automatic Group select switch positioned at 8 Single select switch positioned at ALL Which ONE of the following sets of lamp status would represent the above conditions on the PI Panel?
a.
Group 6 ON Control Lamps ON Group 7 ON Control Lamps ON Group 8 ON Control Lamps ON b.
Group 6 100% Lamps ON Group 7 ON Control Lamps ON Group 8 ON Control Lamps ON c.
Group 6 100% Lamps ON Group 7 ON Control Lamps ON Group 8 ON Control Lamps OFF d.
Group 6 ON Control Lamps OFF Group 7 ON Control Lamps OFF Group 8 ON Control Lamps OFF QUESTION: 059 (1.00)
Which ONE of the following combinations represents the correct association of NI channels to power sources?
a.
NI-1 & NI-5 are powered from Y1 and NI-2 & NI-6 are powered from Y2 b.
NI-4 & NI-8 are powered from Y4 and NI-3 & NI-7 are powered from Y3 c.
NI-2 & NI-6 are powered from Y1 and NI-4 & NI-8 are powered from Y3 d.
NI-2 & NI-4 are powered from Y2 and NI-1 & NI-3 are powered from Y4
REACTOR OPERATOR Page 36 QUESTION: 060 (1.00)
A LOCA had occurred resulting in depressurization of the RCS to 200 psig. As a result, the following sequence of events occurred:
Reactor trip on low RCS pressure RCPs were tripped due to a loss of subcooling margin The Control Room SRO has asked you to check for inadequate core cooling. You observe that the subcooling margin meters have a red light lit on them. Which ONE of the following statements is correct?
a.
Use the incore thermocouples as the input to the subcooling margin meters due to their faster instrument response time for present RCS conditions.
b.
Use the T-hot as the input to the subcooling margin meters due to their faster instrument response time for present RCS conditions.
c.
Inform the Control Room SRO that inadequate core cooling exists for the present RCS conditions.
d.
Use the T-hot and RCS pressure to determine the status of the subcooling margin for the present RCS conditions.
QUESTION: 061 (1.00)
The plant has recently returned to power following a refueling outage. The following alarms are received:
3-3-B SFP TEMP HI 3-5-B SFP HX TOTAL FLOW LO Actions to raise flow have been unsuccessful. Which one of the following systems can be used to reduce the SFP temperature?
a.
Demineralized water via makeup to the SFP.
b.
Decay Heat system via crossconnect.
c.
Service Water via lineup to the SFP Coolers d.
BWST Recirculation system via makeup to the SFP.
REACTOR OPERATOR Page 37 QUESTION: 062 (1.00)
The plant at 70% power. OTSG 1 startup level is 128 inches. The selected OTSG 1 startup level instrument feeding ICS rapidly fails to mid-scale. Which ONE of the following describes how the effect on the plant would be different with SASS in automatic versus the effect with SASS unable to transfer, and what actions would need to be taken?
a.
In automatic, SASS would cause a transfer to the non-selected instrument. The same button would stay depressed; however, both would be illuminated. The operator would need to select the new instrument to ensure SASS did not transfer back to the original instrument when power changed b.
There would be no difference because even in automatic, OTSG 1 startup level would not transfer due to the difference between actual and mid-scale being less than 3% at this power level. No action would be necessary because startup level provides no control function at this power level.
c.
In automatic, SASS would cause a transfer to the non-selected instrument. The previously selected instruments pushbutton would "pop out" and both buttons would be illuminated. No action would be necessary, because the previously selected instrument is "locked out" of selection until SASS is reset d.
There would be no difference since regardless of whether SASS is in auto or not, an automatic transfer to the non-selected instrument would occur. The operator would need to reset SASS to ensure another instrument failure will be detected if it occurs.
REACTOR OPERATOR Page 38 QUESTION: 063 (1.00)
A Reactor trip has occurred, and it was identified that the Turbine Bypass Valves are in HAND with zero demand. Which ONE of the following statements describes how the Turbine Bypass Valves will respond to increasing Steam Generator pressure with no operator actions being taken? The Turbine Bypass Valves will _______________.
a.
maintain Steam Generator pressure at 995 psig b.
maintain Steam Generator pressure at 1025 psig c.
remain closed d.
maintain Turbine Header pressure at 920 psig QUESTION: 064 (1.00)
The following sequence of events has occurred:
The Main Turbine tripped at 35% reactor power.
Main Stop Valve 1 failed to close.
Main Control Valve 1 failed to close.
After completion of the appropriate steps of DB-OP-02500, Turbine Trip, the plant status will be:
a.
reactor power at 28%, steam generator level control on low level limits, and steam generator pressure control on TBVs.
b.
reactor power at 0%, steam generator level control on low level limits, and steam generator pressure control on the MSSVs.
c.
reactor power at 28%, steam generator level control on auxiliary feedwater, and steam generator pressure control on TBVs.
d.
reactor power at 0%, steam generator level control on auxiliary feedwater, and steam generator pressure control on the MSSVs.
REACTOR OPERATOR Page 39 QUESTION: 065 (1.00)
The following plant conditions exist:
The monthly surveillance (DB-SS-03250) for EVS Fan 1 is in progress.
CV 5024, EVS Motor Operated Inlet Damper, is closed.
EVS Fan 1 has been running for 10 minutes.
RE 8447, FH Area Ventilation Exhaust Monitor in Train 2 trips Which ONE of the choices below identifies EVS operation under these conditions?
a.
Both EVS fans will be ON, taking suction from the Fuel Handling Area.
b.
EVS Fan #1 will be OFF. EVS Fan #2 will be ON, taking suction from the Fuel Handling Area.
c.
Both EVS fans will be ON, taking suction from MPR 4.
d.
EVS Fan #1 will be ON, taking suction from #4 MPR. EVS Fan #2 will be OFF.
QUESTION: 066 (1.00)
The plant is in Mode 6. Fuel Handling activities are in progress. Which one of the following individuals is responsible to directly monitor the indications of core reactivity during fuel handling activities within the Reactor Vessel?
a.
Reactor Engineer b.
Control Room Operator c.
Fuel Handling Director d.
Unit Supervisor
REACTOR OPERATOR Page 40 QUESTION: 067 (1.00)
The Control Rod Drive Exercise Test is scheduled for the upcoming shift. DB-OP-06402, CRD Operating Procedure, can be verified current by...
a.
using the Curator controlled view library.
b.
referring to NG-DB-00225, Procedure Use and Adherence.
c.
referring to Operations Directive PR-01, Operations Procedure Maintenance.
d.
using the Production - Shared Services module in SAP.
QUESTION: 068 (1.00)
The following plant conditions exist:
A reactor startup is in progress Current rod index is 285 The upper rod index limit is 285 Initial count rate was 4 x 101 cps on source range NI 1 and 2 Current count rate is stable at 6 x 102 cps on source range NI 1 and 2 Which ONE of the following is the next action to be taken?
a.
Add demineralized water to lower rod index and continue the reactor startup b.
Insert Control Rod Groups 2 through 7 and evaluate c.
Withdraw Control Rod Group 7 and continue the reactor startup d.
Begin emergency boration to achieve 1% shutdown margin
REACTOR OPERATOR Page 41 QUESTION: 069 (1.00)
DB-OP-00016, Temporary Configuration Control, provides a controlled method for...
a.
hanging clearance tags in components and systems.
b.
establishing plant conditions for temporary plant modifications.
c.
hanging Operations caution tags on components and systems.
d.
establishing plant conditions addressed by an operating procedure.
QUESTION: 070 (1.00)
The plant is in Mode 6. A full core reload is in progress. Which of the following individuals are required to be in direct communication with the Control Room Operator?
1.
Shift Manager 2.
Fuel Handling Director 3.
Reactor Engineer 4.
Bridge Spotter 5.
Main Fuel Handling Bridge Operator 6.
Transfer Mechanism Operator a.
1, 3, 5 b.
1, 2, 4 c.
2, 5, 6 d.
3, 4, 6
REACTOR OPERATOR Page 42 QUESTION: 071 (1.00)
Which ONE of the following is required for an operator to enter a room posted as a High Radiation Area (HRA) to perform a normal valve lineup?
a.
A whole-body count prior to and after the HRA access b.
Dedicated Radiation Protection coverage while in the HRA c.
Sign onto a Radiation Work Permit specifically for the HRA d.
A key to the HRA barrier entryway QUESTION: 072 (1.00)
The plant is in Mode 5. An operator has been performing a valve lineup on the letdown cooler.
For the last half hour, two maintenance workers have been working three feet away from the operator. Both maintenance workers digital reading dosimeter (DRD) begin to continuously alarm. The operator looks at his DRD, which is reading 0 mrem.
Which ONE of the following actions must be taken?
a.
Remain in Containment and promptly notify the Shift Manager.
b.
Exit Containment with the maintenance workers and promptly notify Radiation Protection.
c.
Remain in Containment and continue working until the DRD alarms.
d.
Exit Containment with the maintenance workers and rezero all the DRDs.
REACTOR OPERATOR Page 43 QUESTION: 073 (1.00)
The plant is at 28% power on low level limits.
RCS Temperature is 582°F and stable.
Annunciator 12-1-A, MN STM LINE 1 RAD HI, is in alarm.
Annunciator 9-4-A, VACM SYS DISCH RAD HI, is in alarm Both Makeup Pumps are running.
Letdown is isolated.
Pressurizer level is at 200 inches and decreasing at 5 inches/minute.
Which ONE of the following sets of actions should be taken?
a.
Continue in DB-OP-02531, Steam Generator Tube Leak and perform a normal Reactor shutdown to Mode 3.
b.
Continue in DB-OP-02531, Steam Generator Tube Leak and perform a rapid plant shutdown to Mode 3.
c.
Enter DB-OP-02000, immediately trip the Reactor and route to the Steam Generator Tube Rupture section after checking Specific Rule Criteria and Symptom Direction.
d.
Enter DB-OP-02000, route to the Steam Generator Tube Rupture section and Trip the Reactor after transferring steam loads to the Turbine Bypass Valves.
QUESTION: 074 (1.00)
The plant is at 100% power. An Alert has been declared. The state and local agencies are notified using the ___________ and the NRC is notified using the __________.
a.
4-Way Ringdown Circuit, Emergency Notification System b.
Computerized Automatic Notification System, Emergency Notification System c.
4-Way Ringdown circuit, Prompt Notification System d.
Computerized Automatic Notification System, Prompt Notification System
REACTOR OPERATOR Page 44 QUESTION: 075 (1.00)
The plant is at 100% power.
Annunciator 11-1-A, CCW RETURN RAD HI, is in alarm.
Annunciator 11-4-A, CCW SURGE TK LVL HI, is in alarm.
Computer Point P101, CC OUT LETDOWN HX PRESSURE is in alarm.
Which one of the following procedures and sections should be implemented first?
a.
DB-OP-02523, Component Cooling Water System Malfunctions, section for High Component Cooling Surge Tank Level b.
DB-OP-02523, Component Cooling Water System Malfunctions, section for Component Cooling Water Radiation Rising c.
DB-OP-06006, Makeup and Purification System, section for Recovery from Letdown Isolation (135 psig) d.
DB-OP-06006, Makeup and Purification System, section for Isolation of Letdown During Operation.
(********** END OF EXAMINATION **********)
REACTOR OPERATOR Page 45 ANSWER: 001 (1.00) a.
REFERENCE:
DB-OP-02000, Step 4.2 New Memory 000007-EK1..(KAs)
ANSWER: 002 (1.00) b.
REFERENCE:
DB-OP-02000, step 13.12 and Specific Rule 3.4 Modified Higher 000008-AA1..(KAs)
ANSWER: 003 (1.00) a.
REFERENCE:
B&W Tech Basis (for GEOG)
Document, Vol. 2, page III.B-2 Bank Memory 000009-EK3..(KAs)
ANSWER: 004 (1.00) c.
REFERENCE:
DB-OP-02000, Attach. 7 Bank Memory 000011-EK2..(KAs)
ANSWER: 005 (1.00) a.
REFERENCE:
DB-OP-02512, Caution 4.1.11.b Bank Higher 000022-AK1..(KAs)
ANSWER: 006 (1.00) c.
REFERENCE:
DB-OP-02527, Caution 4.1, Pg. 15 DB-OP-06012, Section 4.25 and 4.27 for DH Pump 1 & 2 respectively DB-OP-06703, curve CC 6.2 New Higher 000025-AA2..(KAs)
ANSWER: 007 (1.00) d.
REFERENCE:
DB-OP-02000, SR6 New Memory 000026-AK3..(KAs)
ANSWER: 008 (1.00) d.
REFERENCE:
DB-OP-02004, Alarm 4-2-E response, note 3.3 and step 3.3 New Higher 000027-AK3..(KAs)
ANSWER: 009 (1.00) d.
REFERENCE:
DB-OP-02000, Immediate Actions, Pg. 11 Modified Memory 000029-EA1..(KAs)
ANSWER: 010 (1.00) b.
REFERENCE:
DB-OP-02000, Step 8.19.7.c
& Attachment 6 New Memory 000038-EA1..(KAs)
ANSWER: 011 (1.00) b.
REFERENCE:
DB-OP-06224, Page 8 DB-OP-06901, step 3.30 New Higher 000054 2.2.22..(KAs)
ANSWER: 012 (1.00) d.
REFERENCE:
DB-OP-02521, Attachment 5 Bank Memory 000055-EA1..(KAs)
ANSWER: 013 (1.00) b.
REFERENCE:
DB-OP-02000, Immediate Actions Step 3.4, Pg. 13 &
Details pg. 14 New Memory 000056-AA2..(KAs)
ANSWER: 014 (1.00) c.
REFERENCE:
DB-OP-02541, step 4.1.1, &, pg 8 of 27 Modified New Higher 000057-AK3..(KAs)
ANSWER: 015 (1.00) c.
REFERENCE:
DB-OP-02001, Alarm 1-6-E
Response
New Higher 000058 2.4.10..(KAs)
REACTOR OPERATOR Page 46 ANSWER: 016 (1.00) b.
REFERENCE:
System Description, SD-018, Pg. 2-10 Modified Higher 000062 2.1.28..(KAs)
ANSWER: 017 (1.00) a.
REFERENCE:
DB-OP-02528, Step 4.1.1, 4.2.1, 4.3.1,& 4.4.1 Modified Higher 000065-AA2..(KA's)
ANSWER: 018 (1.00) b.
REFERENCE:
DB-OP-02000, Step 6.12 New Memory BW/E04-EK2.2 ANSWER: 019 (1.00) b.
REFERENCE:
DB-OP-02000, Step 3.3 New Memory 000024-AK1..(KA's)
ANSWER: 020 (1.00) a.
REFERENCE:
DB-OP-02505, Step 4.3.1 New Higher 000032-AK3..(KA's)
ANSWER: 021 (1.00) b.
REFERENCE:
DB-OP-06912, Step 4.27 Bank Higher 000033-AK1..(KA's)
ANSWER: 022 (1.00) d.
REFERENCE:
DB-OP-02000, Tech. Basis Document New Memory 000069-AK3..(KA's)
ANSWER: 023 (1.00) c.
REFERENCE:
DB-OP-02504, Attachment 1 Bank New Higher BW/A01-AA1.2..(KAs)
ANSWER: 024 (1.00) d.
REFERENCE:
DB-OP-02500, Step 4.1.5 and 4.1.7 New Higher 2.4.48..(KA's)
ANSWER: 025 (1.00) b.
REFERENCE:
System Description 18, Pages 2-28 Modified Higher BW/A05-AK2.1..(KAs)
ANSWER: 026 (1.00) a.
REFERENCE:
DB-OP-02517, Step 4.2.1.f, and AB discussion Bank Memory BW/A07-AK2.2..(KAs)
ANSWER: 027 (1.00) a.
REFERENCE:
DB-OP-06903, Step 8.9 New Higher BW/E09-EA2.2..(KAs)
ANSWER: 028 (1.00) a.
REFERENCE:
System Description SD 039A, Section 2.5.1.18 Modified Memory 003-A1.01..(KA's)
ANSWER: 029 (1.00) c.
REFERENCE:
DB-OP-06006, Att. 16 & 17 and OS 58 Sh1 & 2 Bank Memory 004-K2.02..(KA's)
ANSWER: 030 (1.00) c.
REFERENCE:
DB-OP-02527, Caution 4.1 and Att. 1 & 2 OS 004, sh. 2, CL 3 & 4 Bank Higher 005-A4.01..(KA's)
REACTOR OPERATOR Page 47 ANSWER: 031 (1.00) a.
REFERENCE:
DB-OP-02000, Attachment 12 Modified Memory 006-K1.04..(KAs)
ANSWER: 032 (1.00) b.
REFERENCE:
OS-001A sh. 3 New Memory 007-K3.01..(KAs)
ANSWER: 033 (1.00) a.
REFERENCE:
OS-001A, sh 3 & 4 Control Logic 9 & 10 Bank Higher 007-K4.01..(KAs)
ANSWER: 034 (1.00) a.
REFERENCE:
OS-002, Sh 1 Control Logics 2 & 4 Bank Memory 008-K1.02..(KAs)
ANSWER: 035 (1.00) d.
REFERENCE:
DB-OP-02532, steps 4.2.3 &
4.2.17 Elementary drawings E52B sh 10 & sh 59 New Higher 010-K2.02..(KAs)
ANSWER: 036 (1.00) a.
REFERENCE:
DB-SP-03363, step 2.2.1.e New Memory 010-A3.01..(KAs)
ANSWER: 037 (1.00) a.
REFERENCE:
Drawing E-28 Bank Memory 012-K1.01..(KAs)
ANSWER: 038 (1.00) d.
REFERENCE:
DB-OP-06403, Att. 4 Bank Higher 012-K4.04..(KAs)
ANSWER: 039 (1.00) c.
REFERENCE:
E16 Sheets 1 & 2 Modified Higher 013-K6.01..(KAs)
ANSWER: 040 (1.00) b.
REFERENCE:
Generic fund. Components module, Ch 7, pg 18 Bank Higher 022-K3.02..(KAs)
ANSWER: 041 (1.00) c.
REFERENCE:
BW Tech Basis Doc. Vol.2, page V.C-4 DB-OP-02000 Basis &
Deviation Document, pp.
216-219 Bank Higher 026-K1.01..(KAs)
ANSWER: 042 (1.00) a.
REFERENCE:
DB-OP-06903, Note 7.4 &
Limits and Precaution 2.2.9 Modified Higher 039-K5.05..(KAs)
ANSWER: 043 (1.00) a.
REFERENCE:
DB-OP-02010 Alarm 10-2-G response DB-OP-06233, Section 5.11 Bank Higher 039-A4.04..(KAs)
ANSWER: 044 (1.00) b.
REFERENCE:
DB-OP-02537, Step 4.1.1.c New Higher 056-A2.04..(KAs)
ANSWER: 045 (1.00) c.
REFERENCE:
DB-OP-02000, Specific Rule 4 Trip Recovery, Section 4.0 OS-008, Sh 1 & 5 Steam Tables Bank Higher 059-K3.03..(KAs)
REACTOR OPERATOR Page 48 ANSWER: 046 (1.00) c.
REFERENCE:
DB-OP-06233, Section 4.9 I.E.
Bulletin 85-001 SOER 84-03 Modified Memory 061-K5.05..(KAs)
ANSWER: 047 (1.00) d.
REFERENCE:
OS-17A, Control Description 1 DB-OP-02012 Annunc. 12-1-C & D and 12-2-C & D response Bank Higher 061-A1.02..(KAs)
ANSWER: 048 (1.00) a.
REFERENCE:
System Description 007, Section 2.4.5.2 DB-OP-06319, Section 5.0 Bank Memory 062-A3.04..(KAs)
ANSWER: 049 (1.00) b.
REFERENCE:
OS-060, Sh. 1 Bank Memory 063-K2.01..(KAs)
ANSWER: 050 (1.00) b.
REFERENCE:
OS-041B Control Logic 4 New Higher 064-K1.05..(KAs)
ANSWER: 051 (1.00) d.
REFERENCE:
DB-OP-03011, L&P 2.1.4 Modified Higher 073-K3.01..(KAs)
ANSWER: 052 (1.00)
- a.
REFERENCE:
OS-020, Sheet 2, Control Logics Bank Higher 076-A1.02..(KAs)
ANSWER: 053 (1.00) d.
REFERENCE:
DB-OP-02511, Section 2, symptoms Bank Higher 2.4.4 076..(KAs)
ANSWER: 054 (1.00) c.
REFERENCE:
OS-19B Control Logic 6 Bank Memory 078-K4.02..(KAs)
ANSWER: 055 (1.00) a.
REFERENCE:
10CFR50 App. A, GDC 55-57 DB-OP-02000, Tables 1 & 2 Modified Memory 2.1.27 103..(KAs)
ANSWER: 056 (1.00) a.
REFERENCE:
DB-OP-06432, Att. 2 New Higher 002-K1.07..(KAs)
ANSWER: 057 (1.00) b.
REFERENCE:
DB-OP-02532 Caution 4.2.5 and step 4.2.17 New Higher 011-K6.04..(KAs)
ANSWER: 058 (1.00) b.
REFERENCE:
DB-OP-06402, Att. 2 Bank Higher 014-A4.01..(KAs)
ANSWER: 059 (1.00) c.
REFERENCE:
DB-OP-06403, step 3.1.3 SD 044, Section 2.1.2.1.1 Bank Memory 015-K2.01..(KAs)
ANSWER: 060 (1.00) a.
REFERENCE:
DB-OP-02000, step 5.11 details Bank Memory 017-K5.02..(KAs)
REACTOR OPERATOR Page 49 ANSWER: 061 (1.00) b.
REFERENCE:
DB-OP-02003 alarm response for given alarms Modified Higher 033-K3.03..(KAs)
ANSWER: 062 (1.00) b.
REFERENCE:
SD-051, Non-Nuclear Instrumentation, Sections 2.1.1.1.2 & 2.1.1.1.3 DB-OP-06407, Attachment 1 DB-PF-06703, CC7.1 Modified Higher 035-A2.03..(KAs)
ANSWER: 063 (1.00) b.
REFERENCE:
SD-045, Fig, 2.1-14 Bank Higher 041-A3.05..(KAs)
ANSWER: 064 (1.00) d.
REFERENCE:
DB-OP-02500, step 4.1.2 Bank Higher 2.4.11 045..(KAs)
ANSWER: 065 (1.00) c.
REFERENCE:
OS-33B OS-33D OS-34, Sh.
1 Bank Higher 072-K4.02..(KAs)
ANSWER: 066 (1.00) b.
REFERENCE:
DB-OP-00030, step 5.6 New Memory 2.1.2..(KAs)
ANSWER: 067 (1.00) a.
REFERENCE:
NG-NA-00107, step 6.12 Bank Memory 2.1.21..(KAs)
ANSWER: 068 (1.00) b.
REFERENCE:
DB-OP-06912, Step 4.24 Bank Higher 2.2.1..(KAs)
ANSWER: 069 (1.00) c.
REFERENCE:
DB-OP-00016, step 1.1 New Memory 2.2.11..(KAs)
ANSWER: 070 (1.00) c.
REFERENCE:
DB-OP-00030 step 6.6 New Memory 2.2.28..(KAs)
ANSWER: 071 (1.00) c.
REFERENCE:
NG-DB-00240, step 6.6 NG-DB-00208, Att. 1 pages 14 & 17 New Memory 2.3.2..(KAs)
ANSWER: 072 (1.00) b.
REFERENCE:
DB-HP-01224, steps 6.4.4, 6.4.5 and 6.4.7 Bank Memory 2.3.4..(KAs)
ANSWER: 073 (1.00) d.
REFERENCE:
DB-OP-02531, Step 4.1.4 DB-OP-02000, step 3.1 Modified Higher 2.4.1..(KAs)
ANSWER: 074 (1.00) a.
REFERENCE:
RA-EP-02110, Section 6.2 &
6.5 New Memory 2.4.43..(KAs)
ANSWER: 075 (1.00) b.
REFERENCE:
DB-OP-02523, step 2.5 Modified Higher 2.4.45..(KAs)
(********** END OF EXAMINATION **********)
REACTOR OPERATOR Page 50 A N S W E R K E Y 001 a 002 b 003 a 004 c 005 a 006 c 007 d 008 d 009 d 010 b 011 b 012 d 013 b 014 c 015 c 016 b 017 a 018 b 019 b 020 a 021 b 022 d 023 c 024 d 025 b 026 a 027 a 028 a 029 c 030 c 031 a 032 b 033 a 034 a 035 d 036 a 037 a 038 d 039 c 040 b 041 c 042 a 043 a 044 b 045 c 046 c 047 d 048 a 049 b 050 b 051 d 052 a 053 d 054 c 055 a 056 a 057 b 058 b 059 c 060 a 061 b 062 b 063 b 064 d 065 c 066 b 067 a 068 b 069 c 070 c 071 c 072 b 073 d 074 a 075 b
(********** END OF EXAMINATION **********)