ML092400308
| ML092400308 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/13/2009 |
| From: | Division of Nuclear Materials Safety III |
| To: | |
| References | |
| 50-346/09-301 | |
| Download: ML092400308 (115) | |
Text
U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: July 20, 2009 Facility/Unit: Davis Besse U1 Region: I II III IV Reactor Type: W CE BW GE Start Time: 0800 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 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Value 75 Points Applicant=s Score Points Applicant=s Grade Percent
APPENDIX E POLICIES AND GUIDELINES FOR TAKING NRC EXAMINATIONS Each examinee shall be briefed on the policies and guidelines applicable to the examination category (written, operating, walk-through, and/or simulator test) being administered. The examinees may be briefed individually or as a group. Facility licensees are encouraged to distribute a copy of this appendix to every examinee before the examination begins. All items apply to both initial and requalification examinations, except as noted.
Part A: General Guidelines
- 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 to ask 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 manager).
- 4. You must pass every part of the examination to receive a license or to continue performing license duties. Applicants for an SRO-upgrade license may require remedial training in order to continue their RO duties if the examination reveals deficiencies in the required knowledge and abilities.
- 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 or given assistance in completing the examination.
- 2. To pass the examination, you must achieve an overall grade of 80.00 percent or greater, with 70.00 percent or greater on the SRO-only items, if applicable. If you only take the SRO portion of the exam (as a retake or with an upgrade waiver of the RO exam), you must achieve an overall grade of 80.00 percent or better to pass. SRO-upgrade applicants who do take the RO portion of the exam and score below 80.00 percent on that part of the exam can still pass overall, but may require remediation. 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 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the RO exam; 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for the 25-question, SRO-only exam; and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the combined RO/SRO exam. Notify the proctor if you need more time.
- 4. You may bring pens, pencils, and calculators into the examination room; however, programmable memories must be erased. Use black dark pencil for marking your answer sheets.
- 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, and do not leave any question blank.
Use only the paper provided; you may write anywhere on the provided examination. If you have a machine-gradable form that offers more than four answer choices (e.g., Aa@
through Ae@), be careful to mark the correct column.
- 7. If you have any questions concerning the intent or the initial conditions of a question, do not hesitate to ask them before answering the question. Note that questions asked during the examination are taken into consideration during the grading process and when reviewing applicant appeals. Ask questions of the NRC examiner or the designated facility instructor only. A dictionary is available if you need it.
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. Similarly, you should assume that no operator actions have been taken, unless the stem of the question or the answer choices specifically state otherwise. 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 leave.
Avoid all contact with anyone outside the examination room to eliminate even the appearance or possibility of cheating.
- 9. When you complete the examination, assemble a package that includes the examination cover sheet and the answer sheet, and 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. Leave all other items at your examination table face down. The examination will be retained by the station training department.
- 10. After turning 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 or revoked.
- 11. Do you have any questions?
REACTOR OPERATOR Page 1 of 75 Question# 001 If RE 609, Main Steam Line 1 Radiation Monitor was placed in the GROSS mode at 50% RTP, display count rate would . . .
- a. decrease due to lower detector sensitivity to N-16 gammas.
- b. increase due to greater sample flow rate through the detector.
- c. decrease due to detector saturation in the higher radiation field.
- d. increase due to extended band of isotopes RE 609 would detect.
REACTOR OPERATOR Page 2 of 75 Question# 002 Given the following conditions:
- Reactor power is 2%.
- The Motor Driven Feedwater Pump is the only source of feedwater available.
- Service Water Loop 1 has just been lost to the primary loads.
- Various system temperatures are being monitored and are as indicated below.
- MDFP lube oil temperature is 160°F.
- Main Generator cold gas temperature is 115°F.
- CCW HX outlet temperature is 115°F.
- CRD stator temperatures are at 160°F.
- An equipment operator reports the 50GS relay target is actuated for Service Water Pump #1.
Which ONE of the following actions is required to be performed at this time?
- a. Direct the equipment operator to reset the 50 GS relay and attempt one restart on the #1 Service Water Pump.
b Trip the reactor, trip all RCPs, and go to DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
c Transfer the MDFP from the Main Feedwater Mode to the Auxiliary Feedwater Mode per DB-OP-06225, MDFP Operating Procedure.
- d. Trip the reactor, initiate and isolate both SGs with the SFRCS Manual Actuation Switches, stop the MDFP, and go to DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
REACTOR OPERATOR Page 3 of 75 Question# 003 The plant was operating at 100% RTP when annunciator 9-1-F, INSTR AIR HDR PRESS LO alarmed. The Reactor Operator reported that instrument air pressure (using PI 810) reads 72 psig and the secondary plant appears stable.
Which of the following sets of actions is required to be performed under these circumstances?
- b. Maintain reactor power at the present level, dispatch operators to locate the cause of excessive air demand.
- c. Rapidly decrease power per DB-OP-0254, Rapid Shutdown, until instrument air increases to approximately 90 psig.
- d. Perform a rapid plant shutdown per DB-OP-02504, Rapid Shutdown, start the standby station air compressor and the emergency instrument air compressor.
REACTOR OPERATOR Page 4 of 75 Question# 004 The following plant conditions exist:
- The reactor has tripped.
- SG Pressures = 780 psig
- RCS Pressure = 1500 psig
- Incore Thermocouples = 600°F
- Containment Pressure = 22 psia.
- All safety equipment actuates as designed.
- The ROs have taken actions per Specific Rule 2.
Which one of the following sets of equipment responses best describes the expected equipment response to this event?
- a. Auxiliary Feedwater Pumps off High Pressure Injection running following Automatic Start Low Pressure Injection off Makeup Pumps stop automatically Containment Air Coolers running in Fast Speed Containment Spray Pumps running following Automatic Start
- b. Auxiliary Feedwater Pumps running following Automatic Start High Pressure Injection running following Automatic Start Low Pressure Injection running following Automatic Start Makeup Pumps stop automatically Containment Air Coolers shift to slow speed Containment Spray Pumps off
- c. Auxiliary Feedwater Pumps off High Pressure Injection off Low Pressure Injection off Makeup Pumps running following Automatic Start Containment Air Coolers running in fast speed Containment Spray Pumps running following Automatic Start
- d. Auxiliary Feedwater Pumps running following Automatic Start High Pressure Injection running following Automatic Start Low Pressure Injection running following Automatic Start Makeup Pumps running following Manual Start Containment Air Coolers shift to slow speed Containment Spray Pump off
REACTOR OPERATOR Page 5 of 75 Question# 005 Given the following conditions:
- The plant experienced a small break LOCA.
- An SFAS Level 1, 2, and 3 actuation occurred.
- There was a need to sample the containment and thus a need to re-open the Containment Air Sample Supply and Return containment isolation valves (CV5010A through CV5010E, and CV5011A through CV5011E) that were closed due to the SFAS actuations.
- The BLOCK pushbuttons on the Output Modules for the associated valves were PRESSED.
- The Containment Air Sample Supply and Return Isolation Valves were then re-opened.
After the valves were re-opened, the associated Safety Actuation Monitoring (SAM) lights for the Containment Air Sample Supply and Return Isolation Valves would be. . .
- a. NOT LIT.
- b. DIM.
- c. BRIGHT (NOT FLASHING).
- d. BRIGHT and FLASHING.
REACTOR OPERATOR Page 6 of 75 Question# 006 The plant has been operating at 100% RTP for 7 months. The following conditions were noted:
- Annunciator alarms:
- 2-2-B, MU TK LVL HI
- 4-2-E, PZR LVL LO Control Room Indications:
- MU Pump 1 Red light ON.
- MU Pump 1 indicates 55 amps and STEADY.
- MU 32, PZR LEVEL CONTROL, indicates 100% demand.
- FI MU34, TRAIN 2 MAKEUP FLOW indicates 15 gpm.
- FI 6435, TRAIN 1 MAKEUP FLOW, indicates 0 gpm.
Which one of the following conditions would cause these symptoms to be observed?
- a. MU Pump #1 Locked Rotor.
- b. Isolation of letdown, MU2B CLOSED.
- c. Small RCS leak DOWNSTREAM of MU32.
- d. Failure CLOSED of PZR LEVEL CONTROL, MU32.
REACTOR OPERATOR Page 7 of 75 Question# 007 The plant was operating at 100% RTP with the following conditions:
- SW Pumps 1 and 2 are in service.
- SW Pump 3 is aligned to train 1.
- CCW Pump 1 is in service; CCW Pump 2 is in standby.
- TPCW Pumps 1 and 2 are in service.
Over the next fifteen minutes the following annunciators alarmed starting with the strainer alarms:
- (11-1-C) SW PMP 1 STRNR DISCH PRESS LO
- (11-2-C) SW PMP 2 STRNR DISCH PRESS LO
- (Control Room indicating lights for SWP 1 and2 are GREEN.)
- (11-1-B) CCW HX 1 OUTLET TEMP HI
- (11-3-F) TPCW HX OUTLET TEMP HI You should . . .
- a. isolate the non-seismic service water return headers in an attempt to isolate the service water system leak.
- b. start CCW Pump 2 to supply primary loads per DB-OP-02523, Component Cooling Water System Malfunctions.
- c. dispatch an operator to line up Circulating Water to supply SW Primary Loads per DB-OP-02511, Loss of Service Water Pumps/System.
- d. start TPCW Pump 3 to provide additional cooling to turbine plant cooling water loads per DB-OP- 02514, Loss of Turbine Plant Cooling Water Pump(s).
REACTOR OPERATOR Page 8 of 75 Question# 008 The following plant conditions exist:
- The plant is operating at 100% RTP.
- All systems are in a normal full power lineup.
- CCW Pump 1 is in standby.
- CCW Pump 2 is in running.
- CCW pump 3 is lined-up to CCW Train 1.
After scanning his panels, the RO reported:
- 11-5-B, CCW PMP 2 FLOW LO, is alarming.
- HIS 1418, CCW Pump 2, red light is on.
- All lights on CCW Pump 1 breaker, AC 113, are out.
What effects will the described condition have on the CCW Nonessential Header Isolation Valves (CC 5095, CC 5097, CC 2645, CC 5096, CC 5098, and CC 2649)?
- a. The valves will cycle (open and closed).
- b. The valves will remain in their current position.
- c. The valves will open, or if open, will remain open.
- d. The valves will close, or if closed, will remain closed
REACTOR OPERATOR Page 9 of 75 Question# 009 Given the following plant conditions:
- The plant is operating at 75% RTP.
- PZR level at 80 inches and lowering.
- RCS Pressure is 1800 psig and lowering.
Under these conditions, the ATC operator reports he has indications of a 300 gpm rupture leak in OTSG 2.
Choose the REQUIRED operator action.
- a. Restore PZR level by realigning the BWST suction valves, starting the second make-up pump, and place alternate injection in service.
- b. Close the Block Orifice Bypass valve and adjust the PZR Level Make-up valve (MU-32) setpoint to maintain PZR level.
- c. Verify the PZR heaters have de-energized. Verity PZR level control valve (MU-32) is opening to restore PZR level.
- d. Trip the reactor by manually depressing the Reactor Trip pushbuttons.
Ensure Letdown Isolation Valve (MU-2B) is closed.
REACTOR OPERATOR Page 10 of 75 Question# 010 Given the following conditions:
- A SGTR has occurred on SG 2.
- The reactor has been shutdown.
- RCS TH temperatures are 550°F.
- RCPs are off and are not available.
- An RCS cooldown and depressurization is in progress per DB-OP-02000, Section 8.0, Steam Generator Tube Rupture.
- The TBVs are being used for the RCS cooldown, and the PZR Vent Line Method is being used for the RCS depressurization.
- SG 2 level is 195 inches and rising.
(1) What action is required at this time?
(2) What action will be required if an SFRCS High Level Trip on SG 2 occurs?
(2) Continue cooldown on SG 1 using the TBVs.
(2) Continue cooldown on SG 1 using the TBVs.
(2) Continue cooldown on SG 1 using its AVV.
(2) Continue cooldown on SG 1 using its AVV.
REACTOR OPERATOR Page 11 of 75 Question# 011 The following plant conditions exist:
- The plant is at 98% power.
- Selected pressurizer level indication is from LT RC14-2.
- Selected pressurizer temperature indication is from TT RC15-1.
- A Loss of NNI-X DC Power just occurred.
- SASS functions as designed.
In accordance with DB-OP-02532, Loss of NNI/ICS Power, what actions are directed?
- a. Take manual control of EHC Control Panel and the SG/RX Demand Station and Manually Lower Turbine Load.
Manually control Pressurizer Heaters and Spray.
- b. Take manual control of EHC Control Panel but not the SG/RX Demand Station and Manually Lower Turbine Load.
Manually control Pressurizer Heaters and allow Pressurizer Spray to function in Auto.
- c. Take Pressurizer level transmitter and Pressurizer temperature transmitter to NNI-Y powered transmitters to allow compensated Pressurizer Level indication to be obtained.
- d. When MU Tank Level drops below 10 inches, verify both MU 3971, MU Pump 2 Suction Three-Way Valve, and MU 6405, MU Pump 1 Suction Three-Way Valve, transfer to the BWST.
REACTOR OPERATOR Page 12 of 75 Question# 012 The plant is operating at 100% power. Annunciator 2-1-A, LETDOWN RADIATION HI, alarms due to a small fuel leak. A steam generator tube leak has now developed and a rapid shutdown is in progress per DB-OP-02504, Rapid Shutdown. To minimize offsite releases you should place. . .
- a. the letdown filter in service.
- b. the vacuum system vent filter in service.
- c. an additional condensate polisher in service.
- d. the mechanical hogger in service and shut down the steam jet air ejectors.
REACTOR OPERATOR Page 13 of 75 Question# 013 The plant was operating at 100% RTP with all systems in their normal full-power lineup when a loss of all power to the Integrated Control System occurred.
If no operator actions are taken, what will be the status of the main feed pumps after the loss of ICS DC power?
The main feed pumps will . . .
- a. be tripped and coasting to a stop.
- b. coast down and run at 4400 rpm.
- c. accelerate and continue to run at the high speed stop (5300 rpm).
- d. coast down and continue to run at the turbine low speed stop (3900 rpm).
REACTOR OPERATOR Page 14 of 75 Question# 014 The plant was operating at 100% RTP. All plant systems were in their normal full power lineup with CCW Train 1 in operation. Ambient temperature was 35°F. The following then occurred:
- Loss of offsite power.
- 4160 Bus C1 locked out.
Which of the following describes the plant response to these conditions?
- c. SW Train 2 will cool CCW Train 2. Secondary loads will be cooled by the Station Fire Protection System.
- d. No cooling will occur until a control room operator manually aligns circ water to cool CCW Train 2 and secondary loads.
REACTOR OPERATOR Page 15 of 75 Question# 015 Given the following conditions:
- The reactor was at 90% power.
- A loss of NNI-X AC power occurred.
- Plant conditions have been stabilized.
Which of the following actions is required to be taken per DB-OP-02532, Loss of NNI/ICS Power?
- a. Maintain PZR level using MU 32, Makeup Flow Controller, in MANUAL.
- b. Maintain SG pressure using local operators at the Atmospheric Vent Valve
- c. Maintain RCS pressure using RC-2, Pressurizer Spray Valve, in MANUAL.
- d. Re-Establish RCP Seal Injection flow using MU216, RCP Seal Injection Flow Controller Bypass Valve.
REACTOR OPERATOR Page 16 of 75 Question# 016 The following plant conditions exist:
- AF 6451, Auxiliary Feed Pump 2 Level Control Valve, failed open.
- AFP 2 Governor Control failed as is.
- EDG 2 will not start.
Which of the following will cause the above conditions?
- a. Loss of YBU.
- b. Loss of Y2.
- c. Loss of D2P.
- d. Loss of D2N.
REACTOR OPERATOR Page 17 of 75 Question# 017 Given the following conditions:
- The plant is in Mode 5.
- The plant is drained down with RCS level at 30 inches above the Hot Leg center line.
- It is 10 days after reactor shutdown.
- Refueling Canal temperature is 100°F If a loss of Decay Heat Removal occurs under these conditions and a source of decay heat removal is not restored, of the following choices, what is CLOSEST time (in minutes), it would take for the RCS to boil down to an RCS level corresponding to the Top of Core?
- a. 35 minutes
- b. 39 minutes
- c. 155 minutes
- d. 190 minutes
REACTOR OPERATOR Page 18 of 75 Question# 018 The plant was operating at 100% RTP when a main feedwater pump tripped. All equipment operated as designed. The following inputs to the ICS currently exist:
- Demanded Feedwater Flow is the equivalent of 90%.
- Actual Feedwater Flow is 60%.
- Demanded flux is the equivalent of 95%.
- Actual flux is 90%.
At this moment in time, which of the following describes how cross limits will affect the ICS?
Demanded flux signal will be modified with a ___(1)___(lower) signal because ___(2)___.
(1) (2)
- a. -25% Feedwater is limited by Reactor
- b. -25% Reactor is limited by Feedwater.
- c. -10% Feedwater is limited by Reactor
- d. -10% Reactor is limited by Feedwater.
REACTOR OPERATOR Page 19 of 75 Question# 019 The plant had been operating at 100% RTP for 2 years and had shutdown for a refuel outage. The following plant conditions exist:
- Mode 5
- Tave is 155°F
- RCS pressure is 60 psig
- PZR level is 85 inches
- SBODG is out of service RCS cooldown and depressurization was in progress using DHR Train 1 when the following annunciators actuated:
- 1-3-D, BUS C1 LOCKOUT
- 1-3-H, BUS D1 LOCKOUT
- 1-4-D, BUS C1 VOLTAGE
- 1-4-E, BUS A LOCKOUT
- 1-4-G, BUS B LOCKOUT
- 1-4-H, BUS D1 VOLTAGE Which of the following represent the final plant conditions?
- a. Mode 5, Natural circulation
- b. Mode 4, Natural circulation
- c. Mode 4, Gravity draining the BWST into the RCS
- d. Mode 5, Gravity draining the BWST into the RCS
REACTOR OPERATOR Page 20 of 75 Question# 020 The following plant conditions exist:
- Reactor Power is 95% and steady.
- RCS Pressure is 2150 psig and steady.
- Pressurizer Level is 218 inches and slowly lowering.
- MU TK LEVEL LO (2-2-C) is in alarm.
- RC MU FLOW HI TRN 2 (2-4-C) is in alarm.
- RCP Seal Flow is 9 GPM per RCP, total 36 GPM.
Which ONE of the following abnormal conditions would explain the above conditions?
- a. MU 32 fails open
- b. Normal MU line leak
- c. MU pumps are tripped
- d. Loss of suction to running MU pump
REACTOR OPERATOR Page 21 of 75 Question# 021 The plant was at full power operations when an upset caused a high pressure condition in the main steam system. The reactor tripped. The plant responded as expected with the TBVs controlling steam header pressure.
Two minutes later, without operator intervention, the balance of plant operator noticed that the TBVs had just closed and the AVVs have just opened.
A possible cause for this is:
- a. Loss of one circulating water pump.
- b. AVVs automatically opened at 1025 psig.
- c. Pressure is 18HgA in the main condenser.
- d. Steam Header Pressure error exceeded 125 psig.
REACTOR OPERATOR Page 22 of 75 Question# 022 Annunciator 9-3-A, UNIT VENT RAD HI has alarmed.
The control room operators determined that the cause of the annunciator was RE 4598BA in HIGH Alarm due to a valid release.
Regarding operation of the Control Room Emergency Ventilation System (CREVS), as supplementary actions, the operators . . .
- a. verify both Control Room Ventilation systems have shutdown ONLY.
- c. verify both Control Room Ventilation systems have shutdown AND verify both CREVS Trains automatically started ONLY.
- d. verify both Control Room Ventilation systems have shutdown AND Control Room HVAC Dampers have closed AND manually start both CREVS Trains.
REACTOR OPERATOR Page 23 of 75 Question# 023 The plant was operating at 100% RTP with the ICS in full automatic. An unexpected reduction in feedwater occurred with the following results:
- Pressurizer level is 280 inches and rising at 5 inches per minute.
- Reactor coolant outlet temperature is 619°F and rising at 2°F per minute.
- Pressurizer Spray is open as required.
- RCS pressure is 2320 psig and rising at 50 psi per minute.
Which of the following action is required?
- a. Manually trip the reactor.
- b. Initiate a controlled plant shutdown.
- c. Manually reduce reactor power to match current feedwater flow.
- d. No action is required. Monitor ICS response to the event and ensure the runback is tracking correctly. Take manual control only as necessary to stabilize the plant.
REACTOR OPERATOR Page 24 of 75 Question# 024 Given the following conditions:
- The reactor was at 90% power.
- A loss of NNI-Y AC power occurred.
- The following annunciator alarms were then received:
- (14-2-D) ICS/NNI 118V AC PWR TRBL
- (14-4-E) ICS INPUT MISMATCH
- (14-4-F) ICS INPUT TRANSFER.
- Plant conditions have been stabilized.
Which of the following is an action that is specified to be taken per DB-OP-02532, Loss of NNI/ICS Power, and what is the reason for the action?
- b. Transfer PZR temperature to TT RC15-2 using HS RC15 due to loss of PZR temperature compensation.
- c. Control MU Tank level by positioning MU 11, Three-Way (Letdown to Radwaste or MU Tank), as necessary, due to loss of the 18-inch automatic transfer of MU 11 back to the MU Tank.
- d. Control RCS letdown flow by closing MU 85, Letdown Flow Control Inlet Isolation to MU 6, and cycling MU 4, Letdown Block Orifice Isolation, as necessary, since MU 6, Letdown Flow Control Valve fails to 50% open.
REACTOR OPERATOR Page 25 of 75 Question# 025 The plant was operating at 100% RTP when a loss of all feedwater occurred. The main turbine tripped and, while executing procedures, three RCPs were tripped (2-2 is running). Currently RCS pressure is 2340 psig and RCS temperature is 598°F.
If auxiliary feedwater pump 1 becomes available, you should maintain SG ___(1)___ level at ___(2)___ inches on the startup range.
(1) (2)
- a. 1 40
- b. 1 49
- c. 2 49
- d. 2 124
REACTOR OPERATOR Page 26 of 75 Question# 026 Given the following conditions:
- The plant is in Cold Shutdown.
- DH pump 1 is in service for DHR cooling.
- DH pump 2 is in standby.
A loss of offsite power then occurs.
- 1-3-D, BUS C1 LOCKOUT annunciator alarms.
- No operator actions have been taken.
(1) What action is required to be taken with respect to EDG 1?
(2) What is the status of DHR cooling?
- a. (1) Trip EDG 1 from the Control Room.
(2) DH pump 2 is supplying DHR cooling.
- b. (1) Trip EDG 1 from the Control Room.
(2) No DHR cooling is presently in service.
- c. (1) Trip EDG 1 locally.
(2) DH pump 2 is supplying DHR cooling.
- d. (1) Trip EDG 1 locally.
(2) No DHR cooling is presently in service.
REACTOR OPERATOR Page 27 of 75 Question# 027 Given the following conditions:
- A LOCA has occurred.
- The reactor was shutdown.
- The crew transitioned to DB-OP-02000, Section 5.0, Lack of Adequate Subcooling Margin.
- The crew then transitioned to DB-OP-02000, Section 11.0, RCS Saturated with SGs Removing Heat Cooldown.
- BWST level is 9 feet.
- The crew is preparing to transfer the suction of the LPI pumps to the emergency sump per Attachment 7, Transferring LPI Suction to the Emergency Sump.
(1) Why is a specific route in the plant designated in Attachment 7 for the local operator to take in order to close the breakers for DH7A, DH7B, DH9A, DH9B, and HP31?
(2) What would be the effect if the transfer of the suction of the LPI pumps to the emergency sump was attempted with BWST level at 9.5 feet?
- a. (1) Failure to follow this route could result in an excessive dose to perform the task.
(2) The transfer of the LPI suction could not be performed due to an interlock on the LPI suction valves.
- b. (1) The route specified has emergency lighting provided to allow safe performance of the task.
(2) The transfer of the LPI suction could not be performed due to an interlock on the LPI suction valves.
- c. (1) Failure to follow this route could result in an excessive dose to perform the task.
(2) The transfer of the LPI suction at this level would allow additional time to complete the transfer prior to loss of LPI suction.
- d. (1) The route specified has emergency lighting provided to allow safe performance of the task.
(2) The transfer of the LPI suction at this level would allow additional time to complete the transfer prior to loss of LPI suction.
REACTOR OPERATOR Page 28 of 75 Question# 028 Given the following conditions:
- A plant heatup is in progress.
- Three RCPs are running.
- RCS Temperature is 445°F.
- Seal Return Temperature is 179°F.
Under these conditions the following occurred:
- RCP Seal Injection was lost.
- RCP Seal Injection restoration was started to all RCPs 25 minutes ago.
- Component Cooling Water is operable and available to all RCPs.
- The SRO ordered the 4th RCP to be started.
When can the 4th RCP be started?
- a. IMMEDIATELY.
- b. After 5 minutes have elapsed.
- c. After RCS temperature is raised 5°F.
- d. After RCS temperature is raised 55°F.
REACTOR OPERATOR Page 29 of 75 Question# 029 The plant was operating at 100% power in a normal full-power line-up with the emergency diesel generator running for its monthly surveillance. The emergency diesel generator was paralleled with the grid and at full load when the pressurizer PORV opened. Operators were unable to shut the PORV block valve before RCS pressure decreased to 1500 psig. Which of the following describes the condition of the EDG and the SFAS load sequencer under these plant conditions?
The EDG. . .
- a. engine trips and the load sequencer is not started.
- b. engine remains running and the load sequencer is started.
- c. engine remains running and the load sequencer is not started.
- d. output breaker trips, then recloses. The load sequencer is then started.
REACTOR OPERATOR Page 30 of 75 Question# 030 Given the following conditions:
- Power has been lowered from 100% to 50% per DB-OP-02504, Rapid Shutdown to remove Main Feed Pump 2 from service.
- Power will remain at 50% until Main Feed Pump 2 is repaired and returned to service.
- DB-OP-02504, Attachment 7, Plant Stabilization at a Lower Power Level is being implemented with a target rod index of 260.
- All ICS hand auto stations are in automatic.
Which of the following describes the expected operator actions under these conditions?
- a. Select Group 8 (APSRs) and restore Axial Power Imbalance to 0 to +10%. Leave all ICS controls in automatic to control reactor power at 50%.
- b. Allow the control rods to automatically withdraw until the target rod index is reached, then adjust RCS boron concentration to maintain target rod index and reactor power at 50%.
- c. Place the Diamond Control Panel in manual; manually withdraw control rods to the pre-event rod index, adjust boron concentration as necessary to maintain reactor power at 50%.
- d. Select Group 8 (APSRs) and establish a Group 8 position of 50% to prevent or minimize a positive Axial Power Imbalance. Leave all other ICS controls in automatic to control reactor power at 50%.
REACTOR OPERATOR Page 31 of 75 Question# 031 The following plant conditions exist:
- Power to 120V Bus Y4 was lost two minutes ago due to a bus fault.
- Applicable operating procedures have been entered.
- SFAS Channel 3 Containment Pressure Transmitter PT2002 has just failed high.
Based on the above conditions, what is the status of the Containment Spray System?
- a. ONLY Containment Spray Pump A is running with its discharge valve open.
- b. ONLY Containment Spray Pump B is running with its discharge valve closed.
- c. BOTH Containment Spray Pumps are running with their discharge valves open.
- d. NEITHER Containment Spray Pump is running; Both discharge valves are closed.
REACTOR OPERATOR Page 32 of 75 Question# 032 The plant was at 100 % rated thermal power with DH Pump 2 tagged out and disassembled for motor bearing replacement when a small break LOCA occurred. An SFAS Level 2 actuation occurred and all safety systems responded as expected.
Approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later the following conditions exist:
- BWST level is approaching 9 ft.
- RCS pressure is 500 psig; temperature is 460°F.
Which one of the following is the correct operator action for these conditions?
REACTOR OPERATOR Page 33 of 75 Question# 033 The plant was operating at 100% RTP with SFAS Channels 2, 3, and 4 sequencers operable. SFAS Channel 1 has been de-energized for maintenance.
If an SFAS Level 2 trip occurred in conjunction with a loss of offsite power, which of the following describes the response of HPI Pump 1 to these conditions?
HPI Pump 1 . . .
- a. starts as soon as AC 101 closes.
- b. starts five seconds after AC 101 closes.
- c. starts 25 seconds after AC 101 closes.
- d. does NOT start automatically.
REACTOR OPERATOR Page 34 of 75 Question# 034 The plant was operating at 100% power under normal operating conditions except for a small leak on the PORV seat when IA 2011 (Instrument Air Containment Isolation Valve) failed closed due to an air leak on its controller. Because of this the containment instrument air header depressurized.
The above conditions will cause:
- a. Quench Tank pressure to decrease due to RC 222, Quench Tank Vent to Vent Header, failing open.
- b. Quench Tank level to increase due to RC 229B, Quench Tank Outlet, failing closed.
- c. Reactor Coolant Drain Tank level to increase due to RC 232, Quench Tank Return, failing open.
- d. Reactor Coolant Drain Tank pressure to increase due to RC 2548, RCDT Gas Outlet to the Waste Gas System, failing closed.
REACTOR OPERATOR Page 35 of 75 Question# 035 Given the following conditions:
- The reactor is at 100% power.
- CCW Pumps 1-1 and 1-2 are running.
- CCW Pump 1-3 is spare and aligned to CCW Train 1.
A leak in the Auxiliary Building then occurs in the CCW system.
- CCW surge tank levels are as follows:
- Side 1 is steady at 33 inches.
- Side 2 is at 30 inches and lowering.
Which ONE of the following will be the condition of the plant as the event progresses, based on automatic actions occurring as expected and operator actions taken as required?
CC 1411A and CC 1411B (CCW CTMT isolation) auto closed.
CC 1328 and CC 1338 (CCW to CRD booster pump suction) auto closed.
Both CRD booster pumps have automatically tripped.
The plant is stable on natural circulation flow.
CCW pump 1-3 has automatically started on CCW surge tank lo-lo level.
CCW pump 1-2 was manually tripped.
- d. CCW pumps 1-1, and 1-2 are manually tripped due to low suction pressure.
REACTOR OPERATOR Page 36 of 75 Question# 036 When setting RC 49, Pressurizer Minimum Flow Spray Valve, a MINIMUM bypass spray flow of ___(1)___ is required to provide for boron equalization between the RCS and the Pressurizer and to prevent thermal shock of the PZR spray nozzles.
When setting RC 49, Pressurizer Minimum Flow Spray Valve, per DB-OP-06003, Pressurizer Operating Procedure, notifications are required to appropriate personnel ONLY if the total PZR heater output with the minimum spray flow exceeds the
___(2)___.
(1) (2)
- a. (1) 0.75 gpm the rated size of SCR Bank 1
- b. (1) 3.0 gpm the rated size of SCR Bank 1
- c. (1) 0.75 gpm the rated size of one Essential Bank of PZR heaters
- d. (1) 3.0 gpm the rated size of one Essential Bank of PZR heaters
REACTOR OPERATOR Page 37 of 75 Question# 037 Given the following conditions:
- Pressurizer pressure is 2155 psig.
- Quench tank pressure is 5 psig.
Which one of the following would be the approximate initial downstream tailpipe temperature (if local temperature indication was obtained) if RC 2A, Pressurizer Relief Valve, opened?
- a. 165°F
- b. 212°F
- c. 230°F
- d. 340°F
REACTOR OPERATOR Page 38 of 75 Question# 038 The following plant conditions exist:
- A plant startup is in progress with the Reactor at 77% power.
- Reactor Coolant Pump (RCP) 1-2 amps reads 100 amps.
- RCS loop 1 flow is lowering.
- Total RCS flow is lowering.
Which one of the following Reactor Protection System (RPS) indications can be expected for the conditions above?
- a. All four RPS Reactor Trip module lights will be bright.
- c. Only the Channel 2 RPS Cabinet Reactor Trip Module light will be bright.
REACTOR OPERATOR Page 39 of 75 Question# 039 The RPS RCS Pressure transmitters on RCS Loop 2 Hot leg have lost power.
This condition would cause the RPS RCS Pressure Trip Bistable output state lamps on
___(1)___ to become ___(2)___.
(1) (2)
- a. RPS Channels 1 & 3 dim
- b. RPS Channels 2 & 4 dim
- c. RPS Channels 1 & 3 bright
- d. RPS Channels 2 & 4 bright
REACTOR OPERATOR Page 40 of 75 Question# 040 The plant was operating at 100% power with all systems normal when the following occurred:
- R.C. Pressure Lo Bistable, BA 404, tripped on SFAS Channel 4.
- RCS pressure remained at 2155 psig.
Which one of the following describes all of the associated indications on the SFAS Output Modules?
A 1/5 light lights on all SA Levels ___(1)___ Output Modules in SFAS Channels
___(2)___.
(1) (2)
- a. 1 and 2; 2 and 4 ONLY
- b. 1 and 2; 1, 2, 3 and 4
- c. 1, 2 and 3; 1, 2, 3 and 4
- d. 1, 2 and 3; 2 and 4 ONLY
REACTOR OPERATOR Page 41 of 75 Question# 041 The following plant conditions exist during the refueling outage:
- Unit is in Mode 6.
- Core Refueling has been completed.
- Vessel Internal Indexing fixture is seated on the vessel flange.
- Making preparations to move Upper Plenum Assembly into the vessel.
- DH Pump 1 is in operation for decay heat removal.
- DH Pump 2 is being used to transfer water from the refueling canal to the BWST.
Radiological Technicians calling from containment note an increase in containment radiation levels and see a hole in the water above the reactor vessel. A control room operator notes oscillating amps on both Decay Heat Removal Pumps. The operator stops both Decay Heat Removal Pumps.
Which of the following is a Technical Specification-required IMMEDIATE action for this event?
- a. Evacuate containment.
- b. Secure the equipment hatch with at least 4 bolts.
- c. Add water from the Clean Waste Monitor Tank to raise reactor vessel level to the reactor vessel flange.
- d. Restore DHR loop to OPERABLE status OR Initiate action to establish 23 feet of water above the top of the reactor vessel flange.
REACTOR OPERATOR Page 42 of 75 Question# 042 The following plant conditions exist:
- The plant is operating at 100% power.
- All systems are in their normal full power lineup.
- EDG 2 is disassembled for preventative maintenance.
- CAC Fans 1 and 3 are running in FAST speed.
- CAC Fan 3 is aligned to the CAC 2 side.
If a loss of offsite power occurred under these conditions, what would be the status of the Containment Air Cooling Fans?
- a. ONLY Fan 1 stops.
- b. ONLY Fan 3 stops.
- c. BOTH Fan 1 and 3 stop.
- d. BOTH fan 1 and 3 stop and then ONLY Fan 1 restarts after 5 seconds.
REACTOR OPERATOR Page 43 of 75 Question# 043 The alarm that occurs when Containment Spray System (CSS) flow drops below 1100 gpm provides warning that . . .
- a. NPSH limits have been exceeded.
- b. flow has dropped below CSS system minimum flow rate.
- c. flow has dropped below the adequate CSS pump cooling flow rate.
- d. Containment Isolation Valves CS1530 and CS1531, Containment Spray Discharge Valves, have stroked to their throttled position.
REACTOR OPERATOR Page 44 of 75 Question# 044 Ten minutes after a main feedwater line rupture occurring just upstream of FW147 (FW check valve to SG 1), each AFPT will be supplied steam from ___(1)___.
Ten minutes after a main feedwater line rupture occurring just downstream of FW147 (FW check valve to SG 1), each AFPT will be supplied steam from ___(2)___.
(1) (2)
REACTOR OPERATOR Page 45 of 75 Question# 045 The plant is operating at 100% power.
The Motor Driven Feed Pump suction would be NORMALLY aligned to the ___(1)___
and the discharge would be NORMALLY aligned to the ___(2)___.
(1) (2)
- a. Deaerator Storage Tank Main Feed Water System
- b. Condensate Storage Tank Main Feed Water System
- c. Condensate Storage Tank Auxiliary Feed Water System
- d. Deaerator Storage Tank Auxiliary Feed Water System
REACTOR OPERATOR Page 46 of 75 Question# 046 Given the following conditions:
- The reactor was In Mode 3 at full RCS temperature and pressure.
- AFW flow was throttled to control flow to each SG.
A loss of an Essential DC Distribution Panel then occurs.
- AF6452, AFP 1 Level Control Valve has failed open.
Which Essential DC Distribution panel has lost power?
- a. D1N
- b. D1P
- c. D2N
- d. D2P
REACTOR OPERATOR Page 47 of 75 Question# 047 Given the following conditions:
- EDG 1 is operating in parallel at 2600 KW.
- A loss of offsite power then occurs.
(1) What is a concern associated with the operation of EDG 1?
(2) What action will be required to mitigate the effect?
- a. (1) EDG 1 will load shed and become reverse powered.
(2) Locally place the Isochronous-Droop switch for EDG 1 in the isochronous mode.
- b. (1) EDG 1 may overload reaching 3300 KW until an undervoltage condition occurs.
(2) Locally place the Isochronous-Droop switch for EDG 1 in the isochronous mode.
- c. (1) EDG 1 will load shed and become reverse powered.
(2) Align EDG 1 as the sole source of power to Bus C-1.
- d. (1) EDG 1 may overload reaching 3300 KW until an undervoltage condition occurs.
(2) Align EDG 1 as the sole source of power to Bus C-1.
REACTOR OPERATOR Page 48 of 75 Question# 048 The plant was operating at 100% RTP in a normal full power lineup when the following events occurred:
- A loss of breaker status indication for all B bus load breakers and all D1 Bus breakers.
- The reactor tripped.
- A Main Steam Safety Valve on SG 1 opened and stuck open.
Which one of the following should the control room operators perform?
- a. Perform an emergency shutdown of EDG 2.
- b. Direct an auxiliary operator to take local manual control of AFP2 to prevent SG overfeed.
- c. Direct an auxiliary operator to locally trip MFPT 1 because it cannot be tripped from the control room.
- d. Monitor the ICS to ensure the plant responds correctly. Take manual action only if necessary to compensate for unexpected equipment failure.
REACTOR OPERATOR Page 49 of 75 Question# 049 ONE purpose of the Makeup/Purification/Letdown system is to . . .
- a. provide seal water for Containment Spray Isolation valves CS 1530 and CS 1531.
- c. add hydrazine to the Reactor Coolant System (RCS) for oxygen control.
- d. add Oxygen to the Reactor Coolant System(RCS) for Hydrogen scavenging.
REACTOR OPERATOR Page 50 of 75 Question# 050 Given the following conditions:
- EDG 1 is running at 900 rpm.
- Bus C1 voltage is 4160 Vac.
- You have just closed breaker AC101, DG 1 To Bus C1, according to procedure.
Which ONE of the following is the action to be taken and the reason for the action?
- a. Go to raise on EDG 1 speed control switch to prevent a reverse power trip.
- b. Go to lower on EDG 1 speed control switch to prevent an overspeed trip of EDG 1.
- c. Go to raise on EDG 1 voltage regulator control switch to prevent an undervoltage condition on C1 bus.
- d. Go to lower on EDG 1 voltage regulator control switch to prevent an overvoltage condition on C1 bus.
REACTOR OPERATOR Page 51 of 75 Question# 051 An automatic reactor trip has occurred.
Approximately two minutes after the trip the following indications are present in the Control Room:
- RCS pressure is 1675 psig and stable.
- Subcooling Margin is 30°F in both loops.
- Pressurizer level is at 45 inches.
- OTSG steam pressure is 885 psig in both steam generators.
- CTMT pressure is at 14.8 psia.
- Thot is 539°F.
- Tcold is 532°F.
- A Second Makeup pump has been started.
- The Alternate Injection line is in service per DB-OP-02000 Attachment 8.
- Main Feedwater flow is 0 mpph to each OTSG.
- Both OTSG levels are approximately 49 inches on the startup range and stable.
Based on the above conditions, IDENTIFY which ONE of the following actions MUST be taken.
- a. Isolate Letdown.
- b. NO actions are required at this time.
- d. Actuate BOTH channels of SFRCS Initiation and Isolation.
REACTOR OPERATOR Page 52 of 75 Question# 052 The following plant conditions exist:
- A plant startup is in progress.
- Reactor power was being raised from 10% Rated Thermal Power (RTP) to 15% RTP.
The following event occurred:
- Reactor Coolant System (RCS) pressure rose to 2225 psig and then lowered.
The following indications were also observed:
- RC 2, Spray Valve, red indicator light is on.
- RC 10, Pressurizer Spray Block Valve, red indicator light is on.
- RC 2A, PORV, red indicator light is on.
- RC 11, PORV Block Valve, red indicator light is on.
- RCS Tave is fluctuating around 557°F.
- RCS pressure is slowly lowering.
- Subcooling margin is 35°F and slowly lowering.
- Makeup flow is steady.
Which ONE of the following describes the cause of the indications and the correct operator response?
Pressure is lowering due to. . .
- a. an overcooling event, all groups of Pressurizer Heaters should be turned on.
- b. an overcooling event, the PORV and Spray Block Valves should be closed.
- c. RC 2A or RC 2 being open, all groups of Pressurizer Heaters should be turned on.
- d. RC 2A or RC 2 being open, the PORV Block Valve and Spray Block Valve should be closed.
REACTOR OPERATOR Page 53 of 75 Question# 053 Given the following conditions:
- The reactor has tripped from 100% power.
- The Subcooling Margin is 0°F.
- RCPs are off.
- No HPI is available.
- RCS pressure is 785 psig.
- Thot is 518°F.
- Tcold is 516°F.
- OTSG pressure is 770 psig.
Select the mode of RCS cooling occurring for the present conditions.
- a. Forced convection
- b. Dual phase convection
- c. Single phase Natural Circulation
- d. Boiler-condenser Natural Circulation
REACTOR OPERATOR Page 54 of 75 Question# 054 Which one of the following effects will a loss of instrument air (zero psig indicated) have on the Chemical Addition System?
- a. No effect.
- b. MU 23 (flow control) fails CLOSED.
- c. Boric Acid Mix Tank pump will not start.
- d. Boric Acid Addition Tank immersion heaters will not ENERGIZE.
REACTOR OPERATOR Page 55 of 75 Question# 055 The plant was operating at 70% RTP when RCP 1-1 tripped. Which of the following seal injection flow rates is the MINIMUM required to ensure that Reactor Coolant Pump 1-1 seals will stage properly and prevent reactor coolant from leaking out of the pump seals into containment atmosphere?
- a. 1 gpm
- b. 3 gpm
- c. 6 gpm
- d. 9 gpm
REACTOR OPERATOR Page 56 of 75 Question# 056 Curve CC 4.3 of DB-PF-06703, Miscellaneous Operations Curves, provides a recommended pressurizer level versus reactor coolant system temperature for the ramp up in Tave from 0 - 28% power.
Which one of the following responses describes the direction provided in DB-OP-06901, Plant Startup to maintain PZR level in the recommended band?
- a. Isolate letdown and manually control makeup flow so pressurizer level remains constant.
- b. Maximize letdown flow so pressurizer level will remain constant with pressurizer level control in automatic.
- c. Allow pressurizer level to rise with Tave by making small setpoint changes to the pressurizer level controller.
- d. Allow pressurizer level to lower with Tave by making small setpoint changes to the pressurizer level controller.
REACTOR OPERATOR Page 57 of 75 Question# 057 The plant was in Mode 5 with DHR Train 1 in service. DHR was aligned as follows:
- DH 13B (DH Cooler 1 Bypass Flow Control) demand is 40%.
- DH 14B (DH Cooler 1 Outlet Flow Control) demand is 30%.
The following annunciators energized:
- 14-4-E, ICS INPUT MISMATCH
- 14-4-F, ICS INPUT TRANSFER While checking the control boards, the RO discovered that the NNI-Y AC power indicating light was NOT LIT.
Which ONE of the following describes the effect on DH System flow control?
- a. Flow will DECREASE because BOTH valves FAIL closed.
- b. Flow will NOT change because BOTH valves FAIL as is.
- c. Flow will NOT change because NEITHER valve should be affected.
- d. Flow will INCREASE because BOTH valves FAIL to the 50% demand position.
REACTOR OPERATOR Page 58 of 75 Question# 058 Given the following conditions:
- RC pressure is 1600 psig
- Pressurizer level is ZERO (0) inches
- All components operated as designed
- No operator actions were taken Which valve(s) will have AUTOMATICALLY isolated letdown?
- a. MU1A and MU1B (Letdown Cooler Isolations)
- b. MU3 (Letdown Containment Isolation) and MU2B (Letdown Isolation)
- c. MU2A (Letdown Cooler Outlet Isolation) and MU4 (Block Orifice Isolation)
- d. MU2A (Letdown Cooler Outlet Isolation) and MU3 (Letdown Containment Isolation)
REACTOR OPERATOR Page 59 of 75 Question# 059 The following plant conditions exist:
- Reactor power is 92% and rising.
- RCS pressure is 2155 psig and rising.
- Tave is 584°F and rising.
- Neutron error is 2% in the "IN" direction.
- Rod Index is 293% and increasing.
- Diamond panel OUT COMMAND red light lit.
- Main Feedwater flow is rising.
- Turbine header pressure is 885 psig and stable.
You should . . .
- a. reduce the ULD MAX LOAD LIMIT.
- b. push the ROD STOP button and hold.
- c. place the SG/RX HAND/AUTO station in HAND and reduce the demand.
REACTOR OPERATOR Page 60 of 75 Question# 060 During a reactor start-up, you should expect the Control Rod Withdrawal Inhibit to be automatically deactivated / blocked when . . .
- a. any one Power Range NI channel exceeds 10% power.
- b. NI-5 and NI-6 Power Range NI channels exceed 10% power.
- c. NI-7 and NI-8 Power Range NI channels exceed 10% power.
- d. NI-5 and NI-7 Power Range NI channels exceed 10% power.
REACTOR OPERATOR Page 61 of 75 Question# 061 Given the following conditions:
- A reactor trip from 100% power occurred.
- The crew entered DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
- The crew has transitioned to Section 7.0, Overcooling, of DB-OP-02000.
- SG pressure is lowering in SG 1.
- RCS Loop 1 Tave is 440°F.
- SG 1 Shell temperature is 520°F as indicated on SPDS.
(1) Is the SG Tube to Shell differential temperature within limits at this time?
(2) What is the basis for the SG Tube to Shell differential temperature limits?
- b. (1) Yes (2) Limits Pressurized Thermal Shock to the SG shell when feedwater is initiated to a dry SG.
- d. (1) No (2) Limits Pressurized Thermal Shock to the SG shell when feedwater is initiated to a dry SG.
REACTOR OPERATOR Page 62 of 75 Question# 062 The plant was operating at 100% RTP with all major controls in AUTO when the diaphragm ruptured on the differential pressure (D/P) cell causing an instantaneous change in the level signal to the selected SG Operating Range level channel.
Which of the following correctly describes Steam Generator level response? (Assume NO operator actions.)
The control room SG Operating Level indicators indicates ___(1)___; actual SG level will ___(2)___.
(1) (2)
- a. HIGH lower until low level limit is reached
- b. HIGH remain the same due to SASS transfer
- c. LOW remain the same due to SASS transfer
- d. LOW rise until a cross-limit is reached
REACTOR OPERATOR Page 63 of 75 Question# 063 Given the following conditions:
- A reactor trip occurred from 100% power.
- 4160V Bus C1 and 4160V Bus D1 have lost power and can not be re-energized.
(1) What is a required action at this time?
(2) What is an indication of natural circulation cooling?
- a. (1) Initiate an RCS cooldown at a maximum rate of 50°F/hour.
(2) RCS Tcold and SG Tsat are 30°F apart.
- b. (1) Maintain HOT STANDBY condition.
(2) RCS Tcold and SG Tsat are 30°F apart.
- c. (1) Initiate an RCS cooldown at a maximum rate of 50°F/hour.
(2) RCS Thot and RCS Tcold are 40°F apart.
- d. (1) Maintain HOT STANDBY condition.
(2) RCS Thot and RCS Tcold are 40°F apart.
REACTOR OPERATOR Page 64 of 75 Question# 064 The following plant conditions exist:
- A liquid rad waste discharge is in progress from Clean Waste Monitor Tank 1 to the Collection Box.
- The Clean Waste System Out Rad HI annunciator (7-1-B, CLN WST SYS OUT RAD HI) is in alarm.
- The operator determines that the clean waste system outlet monitor l RE-1770A has failed high.
Which one of the following is the expected automatic response of the Clean Waste system?
- a. The operating Clean Waste System Transfer Pump trips and WC-1704 (Clean Waste Monitor Tank Outlet Valve) receives a close signal.
- b. The operating Clean Waste System Transfer Pump trips and isolation valve WC-1771 (Discharge from Clean Waste System) receives a close signal.
- c. Isolation valve WC-1771 (Discharge from the Clean Waste System) and WC-1701A and WC-1701B (Discharges to the Collection Box) will receive a close signal.
- d. Isolation valves WC-1771A and WC-1771B (Discharges to the Collection Box) receive a close signal and WC-1701C (Discharge to the Primary Water Storage Tank) will receive an open signal.
REACTOR OPERATOR Page 65 of 75 Question# 065 Fuel Handling (FH) Radiation Monitor RE-8446 has just failed HIGH. Radiation Monitor RE-8447 is reading normally. How will the plant respond to this failure?
- a. There will be NO automatic plant response.
- b. The running FH HVAC will NOT TRIP but one train of EVS will start.
- c. The running FH HVAC train WILL TRIP and one train of EVS will start.
- d. The running FH HVAC train WILL TRIP and BOTH trains of EVS will start.
REACTOR OPERATOR Page 66 of 75 Question# 066 For this calendar quarter, a licensed operator performed the following activities:
July 1: 0600-1800 hours ATC operator July 2: 0600-1800 hours Work Support Center July 3: 0600-1800 hours BOP operator July 4: 0600-1400 hours BOP operator July 16: 1800-0600 hours ATC operator What is the MINIMUM number of additional hours, if any, required in this calendar quarter for the operator to maintain an active license according to NT-OT-07001, "Training and Qualifications of Operations Personnel"?
- a. None
- b. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- c. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />
- d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
REACTOR OPERATOR Page 67 of 75 Question# 067 The plant has experienced a Severe Loss of Instrument Air during power operation.
PRIOR TO restoration of air and when possible, which ONE of the following is required to be done with any failed pneumatic valve controllers?
- a. The air supply to the controller should be ISOLATED and the controller VENTED.
- b. The air supply to the controller should be ISOLATED and the controller DEENERGIZED.
- c. The controller should be placed in MANUAL and the demand signal should be run down to the ZERO position.
- d. The controller should be placed in MANUAL and the demand signal should be MATCHED with actual position.
REACTOR OPERATOR Page 68 of 75 Question# 068 The plant is in MODE 3 with a startup in progress. Which ONE of the following departments should you contact to obtain a listing of surveillance requirements applicable for entry into MODE 2?
- a. Engineering
- b. Quality Assurance
- c. Outage Management
- d. Work Planning and Support
REACTOR OPERATOR Page 69 of 75 Question# 069 Given the following conditions:
- Reactor power is at 80% and stable.
- All ICS stations are in AUTO.
- Control Rod Group 7 suddenly starts to move out.
- There is no change in electrical load on the generator (MWe).
- DB-OP-02516, CRD Malfunctions, is entered.
(1) What immediate action is required per DB-OP-02516?
(2) If control rod motion stops, but a transient is in progress due to a Reactor Power/Feedwater mismatch, what action is specified per DB-OP-02516 to allow Feedwater to control RCS Tave?
- a. (1) Depress AND Hold the ROD STOP pushbutton.
(2) Place the Reactor Demand H/A station AND the Diamond Control Panel in MANUAL.
- b. (1) Momentarily depress the ROD STOP pushbutton.
(2) Place the Reactor Demand H/A station AND the Diamond Control Panel in MANUAL.
- c. (1) Depress AND Hold the ROD STOP pushbutton.
(2) Leave all ICS stations in AUTO for optimal response.
- d. (1) Momentarily depress the ROD STOP pushbutton.
(2) Leave all ICS stations in AUTO for optimal response.
REACTOR OPERATOR Page 70 of 75 Question# 070 The plant is in Mode 5 with preparations being made for a plant startup/heatup. The following electrical plant conditions exist:
- The 120 VAC Inverter YV1 is supplied from the DC bus.
- Vital Bus Y1 has been manually transferred to the 480 VAC MCC via the constant voltage transformer.
- A risk assessment has not been performed.
Which of the following describes the status of moving the plant to Mode 4 with the associated plant heatup?
- a. Technical Specifications prohibit unlimited operation when the inverter is bypassed with power supplied via the constant voltage transformer. Entry into Mode 4 is NOT permitted until the inverter is restored.
- b. The applicable LCO is NOT met when the inverter is supplied form the DC bus regardless of the manual inverter bypass switch position. Entry into Mode 4 is NOT permitted until the inverter is restored.
- c. The applicable LCO is met provided the inverter is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 200°F. Entry into Mode 4 is permitted.
- d. The applicable LCO is NOT met. However, entry into Mode 4 is permitted provided the inverter is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering MODE 4.
REACTOR OPERATOR Page 71 of 75 Question# 071 A male radiation worker at Davis-Besse has just returned from 3 weeks of outage support at Beaver Valley in April 2009.
- His Total Effective Dose Equivalent (TEDE) received at Beaver Valley was 150 mrem.
- After a fall at home in May 2009, the worker had a hip x-ray estimated at 22 mrem exposure to the hip area.
- The workers current TEDE from Davis-Besse for this year is 75 mrem.
Based on these exposures, choose the calculated MAXIMUM annual non-emergency TEDE that he can receive at Davis-Besse for the remainder of this year without exceeding the Federal Exposure Limits assuming all required approvals are obtained.
- a. 4753 mrem.
- b. 4775 mrem.
- c. 4903 mrem.
- d. 4925 mrem.
REACTOR OPERATOR Page 72 of 75 Question# 072 Which ONE of the following process radiation monitors has an AUTOMATIC plant response associated with a HIGH alarm?
- a. RE 4597AB and BB, Containment Vessel
- b. RE 1412/1413, Component Cooling Water
- c. RE 8432, Service Water Discharge Header
- d. RE 5327/5328A, B, and C, Control Room Emergency Ventilation
REACTOR OPERATOR Page 73 of 75 Question# 073 Which of the following sets of parameters is kept within limits to prevent exceeding DNB limits?
- b. Axial Power Imbalance, RCS Pressure, PZR Level, Thermal Power
- c. RCS Temperature, Quadrant Power Tilt, PZR Level, Control Rod Position
- d. Axial Power Imbalance, Quadrant Power Tilt, RCS Flow, Control Rod Position
REACTOR OPERATOR Page 74 of 75 Question# 074 Main Control Room annunciator windows associated with Emergency Operating Procedure entry conditions are indentified by:
- a. the color of the alarm windows lamps
- b. their position within the corresponding alarm group
- c. the letter R in the lower left hand corner of the window
- d. an alternating beige and black border around the window
REACTOR OPERATOR Page 75 of 75 Question# 075 The unit had been operating at full power for several days when an event (not a fire) required evacuation of the Main Control Room. Abnormal Procedure DB-OP-2508, Control Room Evacuation, immediate actions have been completed.
In accordance with DB-OP-2508, the Primary Side Reactor Operator is responsible for ensuring that. . . .
- a. Reactor Coolant Letdown is restored.
- b. the Aux Feedwater Pumps are operating properly.
- c. instrument air to the Main Steam Atmosphere Vent is isolated.
- d. local shutdown control from the Aux Shutdown Panel is established.
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: July 20, 2009 Facility/Unit: Davis Besse U1 Region: I II III IV Reactor Type: W CE BW GE Start Time: 0800 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant=s Signature Results RO/SRO-Only/Total Examination Values 75 / 25 / 100 Points Applicant=s Scores / / Points Applicant=s Grade / / Percent
SENIOR REACTOR OPERATOR Page 1 of 25 Question# 076 The plant was operating at 35% power when the following conditions occurred:
- (1-5-F) DC PANEL VOLTAGE LO Annunciates
- The reactor does NOT trip
- The turbine trips Which of the following are the appropriate actions for these conditions?
- a. Enter DB-0P-02537, LOSS OF D1P AND DAP, trip the reactor, and GO TO DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
- b. Enter DB-0P-02537, LOSS OF D1P AND DAP and initiate a rapid power reduction while referring to DB-OP-02504, Rapid Shutdown.
- c. Enter DB-0P-02538, LOSS OF D2P AND DBP and GO TO DB-OP-02500, Turbine Trip.
- d. Enter DB-0P-02538, LOSS OF D2P AND DBP, trip the reactor, and GO TO DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
SENIOR REACTOR OPERATOR Page 2 of 25 Question# 077 A loss of both Main Feedwater Pumps has resulted in a reactor trip from 100% reactor power. The following plant conditions exist:
- Incore thermocouples read 1600°F.
- RCS pressure is 500 psig.
Which of the following should you direct based on these plant conditions?
- a. Trip ALL running RCPs.
- b. Establish one RCP running in each loop.
- c. Bump one RCP in each loop.
SENIOR REACTOR OPERATOR Page 3 of 25 Question# 078 Given the following conditions:
- The plant is operating at 100% power.
- A zone operator calls the control room and reports that he has found the stem on CV-5090 (Hydrogen Dilution System 1 Containment Isolation) broken.
Which one of the following is NOT required based on the given conditions?
- a. Initiate a condition report to identify the valve as failed.
- b. Direct the equipment operator to complete a material deficiency tag.
- c. Evaluate the problem as a potential loss of containment penetration isolation capability.
- d. Complete a 4-hour notification to the NRC of the failed hydrogen dilution train in accordance with 10 CFR 50.72.
SENIOR REACTOR OPERATOR Page 4 of 25 Question# 079 Given the following conditions:
- A reactor trip from 100% power occurred.
- The crew entered DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
- The crew has transitioned to Section 7.0, Overcooling, of DB-OP-02000.
- SG pressure is lowering in BOTH SGs.
- SG 1 has been determined to be the SG with the most significant steam leak based on the SG pressure and level decrease.
- Local reports have determined that SG 2 pressure is lowering due to a stuck open Main Steam Safety Valve (MSSV) on the associated MS line.
Based on Section 7.0, Overcooling, of DB-OP-02000, you should direct the control room operators to (PREFERRED action) . . .
- b. IMMEDIATELY establish trickle feed cooling to BOTH SGs, while observing Specific Rule 4, Steam Generator Control.
- c. isolate AFW flow to SG 1, and when SG 1 boils dry, and if an overcooling condition still exists, then establish trickle feed cooling to SG 2.
- d. isolate AFW flow to SG 1, and when SG 1 boils dry, and if an overcooling condition still exists, then isolate AFW flow to SG 2, and go to Attachment 4, Initiate MU/HPI Cooling.
SENIOR REACTOR OPERATOR Page 5 of 25 Question# 080 Fuel movement from the spent fuel pool to containment is in progress. Which of the following events would NOT require suspension of fuel movements In containment?
- a. Lowering of spent fuel pool level.
- b. Water clarity prevents visual position verification.
- c. A malfunction of one of the two fuel transfer mechanism.
- d. A discrepancy between fuel movement sheets and evolutions in progress.
SENIOR REACTOR OPERATOR Page 6 of 25 Question# 081 Given the following conditions:
- The plant was operating at 100% power with a small SG tube leak in SG 1.
- A reactor trip then occurred due a steam line break on SG 2 inside containment.
- The crew entered DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture, and was performing Section 4.0, Supplemental Actions, when a SGTR occurred on SG 1 followed by a loss of offsite power.
- RCS subcooling is 23°F.
As the HIGHEST priority, the crew is required to implement . . .
- a. Section 7.0, Overcooling.
- b. Section 8.0, Steam Generator Tube Rupture.
- c. Specific Rule 2, Actions for Loss of Subcooling Margin.
- d. Specific Rule 6, Power for C1 And D1 Buses or EDG Start.
SENIOR REACTOR OPERATOR Page 7 of 25 Question# 082 The following plant conditions exist:
- The plant is in Mode 1.
- A power ascension is in progress following a refueling outage.
- Thermal power is currently 80% RTP and four reactor coolant pumps are running.
- All rods are within alignment and insertion limits.
- QPT is 8.25 as indicated by the Incore Detector System.
- Axial Power Imbalance (API) is (+) 24 as indicated by the Excore Detector System.
Which one of the following describes the tech spec actions for these plant conditions?
SENIOR REACTOR OPERATOR Page 8 of 25 Question# 083 Given the following conditions:
- The plant is in Mode 6.
- Containment Purge is in operation and aligned to containment.
- Fuel was being removed from the reactor core.
- The Fuel Handling Director reported from containment that bubbles were observed in the vessel during the last fuel movement.
- The following annunciator was received shortly after the report:
- R320 CTMT PURGE EXH FLT RAD The CONTROLLING procedure which is expected to be used for this event is . . .
- a. DB-OP-02530, Fuel Handling Accident
- b. RA-EP-02864, Containment Evacuation
- c. Plant Services Alarm Panel 9 Annunciators
- d. DB-OP-06503, Containment Purge System Procedure
SENIOR REACTOR OPERATOR Page 9 of 25 Question# 084 An extremely serious fire in the Cable Spreading Room has required that the Control Room be evacuated.
(1) Prior to leaving the Control Room, which RCPs are to be tripped?
(2) Which of the following procedure(s), would be selected to mitigate the event?
- a. (1) No RCPs are required to be tripped.
(2) DB-OP-02519, Serious Control Room Fire ONLY.
- b. (1) Trip RCPs 1-1 and 2-2 ONLY.
(2) DB-OP-02519, Serious Control Room Fire ONLY.
- c. (1) Trip RCPs 1-1, 2-1 and 2-2 ONLY.
(2) DB-OP-02519, Serious Control Room Fire and DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
- d. (1) Trip all 4 RCPs.
(2) DB-OP-02519, Serious Control Room Fire and DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture.
SENIOR REACTOR OPERATOR Page 10 of 25 Question# 085 During the back shift the Shift Manager may authorize deviations from the requirements of the temporary modification procedure (NOP-CC-2003, Engineering Changes, Section 4.7.5, Temporary Modifications) in the event that a temporary modification is required for . . .
- a. a significant personnel hazard.
- b. a significant operator burden that is not a hazard to safe operation.
- c. forced entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or less technical specification action statement.
- d. fire protection system equipment that becomes inoperable requiring an eight hour fire watch.
SENIOR REACTOR OPERATOR Page 11 of 25 Question# 086 The following plant initial conditions exist:
- The plant is in MODE 5.
- The RCS is drained to 48".
- Loop 1 DH system is in operation.
The following indications are then received:
- Annunciator (3-1-H) LPI INJ 1 FLOW LO is lit intermittently.
- Annunciator (4-5-B) RCS LVL LO/LO-LO is lit.
Which ONE of the following sections of DB-OP-02527, Loss of Decay Heat Removal, should be performed?
- a. Loss of DH Pump
- b. Loss of Flowpath
- c. Loss of Instrument Air
- d. Loss of Inventory
SENIOR REACTOR OPERATOR Page 12 of 25 Question# 087 Given the following conditions:
- A LOCA has occurred.
- BWST level is 9 feet.
- The crew is preparing to transfer the suction of the LPI pumps to the emergency sump per Attachment 7, Transferring LPI Suction to the Emergency Sump.
When transferring the suction of the LPI and CS pumps to the emergency sump, the CS Discharge Valves CS1530 and CS1531 ___(1)___ to ensure adequate CS pump NPSH.
(2) Following transfer of the LPI and CS pumps to the emergency sump, if the LPI or CS pumps have indications of fluctuating flows or fluctuating amps, which procedure should be implemented to respond to these indications?
- a. (1) must be manually throttled closed from full open to partially open (2) DB-OP-02000, Attachment 4, Initiate MU/HPI Cooling.
- b. (1) are automatically throttled closed from full open to partially open (2) DB-OP-02000, Attachment 12, Establishing Long Term Boron Dilution.
- c. (1) must be manually throttled closed from full open to partially open (2) DB-OP-02000, Attachment 22, Cross Connect LPI Pump Discharge.
- d. (1) are automatically throttled closed from full open to partially open (2) DB-OP-02000, Attachment 27, Mitigation of Containment Emergency Sump Degradation.
SENIOR REACTOR OPERATOR Page 13 of 25 Question# 088 Given the following conditions:
- The plant is stable at 90% power.
- All ICS stations are in AUTO.
- The following Annunciator Alarms are then received:
- (4-5-C) LOOP 1 VS 2 COLD LEG T HI
- (12-3-A) SG 1 OPERATE LVL HI
- SG 1 level is rising above that level expected for plant conditions.
(1) What procedure would be entered FIRST for the above plant conditions?
(2) What are initial actions expected for the plant conditions specified above?
- a. (1) DB-OP-02526, Primary to Secondary Heat Transfer Upset (2) Place the Rod Control diamond station in MANUAL and then place BOTH Feedwater Loop Demands in HAND.
- b. (1) DB-OP-02526, Primary to Secondary Heat Transfer Upset (2) Place the Reactor Demand station in HAND and then place BOTH Feedwater Loop Demands in HAND.
- c. (1) DB-OP-06401, Integrated Control System Operating Procedure (2) Place BOTH Feedwater Loop Demands in HAND, and then, place SP7B, Startup FW Control Valve, and SP-6B, Main FW Control Valve, in HAND.
- d. (1) DB-OP-06401, Integrated Control System Operating Procedure (2) Place SP7A, Startup FW Control Valve, and SP-6A, Main FW Control Valve, in HAND, and then, place BOTH Feedwater Loop Demands in HAND.
SENIOR REACTOR OPERATOR Page 14 of 25 Question# 089 Given the following conditions:
- MUP 2 was disassembled for maintenance yesterday evening.
- The reactor had been operating at 100% power for 100 days when a reactor trip occurred due to a loss of both Main Feed Pump Turbines.
- Both auxiliary feed water pumps have tripped and attempts to restart them have been unsuccessful.
- The MDFP has also failed to start.
The Command SRO should direct MU/HPI cooling be initiated . . ..
- a. IMMEDIATELY.
- b. when Thot exceeds 600°F if feedwater is NOT restored.
- c. when Thot exceeds 600°F even if feedwater is restored.
- d. when the check for heat transfer step is reached in DB-OP-02000.
SENIOR REACTOR OPERATOR Page 15 of 25 Question# 090 Which one of the following describes the operation you should direct for the LPI, HPI, and MU pumps during a loss of Component Cooling Water?
You should direct the control room operators to. . .
- b. IMMEDIATELY trip the LPI and HPI pumps. Start a timer for the MU pumps; they may be operated for up to one hour.
- c. IMMEDIATELY trip the MU pumps. Monitor ECCS Room Coolers. As long as they are in service, LPI and HPI pumps can be operated.
- d. start a timer for the LPI and HPI pumps. They may be operated for up to an hour. The MU pumps can be operated as long as the MU Pump Room HVAC unit is in service.
SENIOR REACTOR OPERATOR Page 16 of 25 Question# 091 Given the following conditions:
- The plant was at 100% power.
- RC 2, PZR Spray Valve, then failed open and RC10, PZR Spray Block Valve, could not be closed.
- RCS pressure is lowering.
Under these plant conditions and in accordance with DB-OP-02513, Pressurizer System Abnormal Operation, you should direct the operators to . . .
- b. implement DB-OP-02504, Rapid Shutdown, and reduce reactor power to 72%; shutdown RCP 2-1.
- c. implement DB-OP-02504, Rapid Shutdown, and reduce reactor power to 72%; shutdown RCP 2-2.
- d. enter either DB-OP-02504, Rapid Shutdown, or DB-OP-06902, Power Operations, and shutdown the plant. Then stop RCPs 2-1 and RCPs 2-2 after the reactor is shutdown.
SENIOR REACTOR OPERATOR Page 17 of 25 Question# 092 Given that the plant was operating at 100% power with a small tube leak on SG 2 with AFPT 2 out of service.
A reactor trip occurred followed by:
- SG 1 was isolated after the reactor trip due to an overcooling event.
- A SGTR then occurred on SG 2.
- Trickle Feed cooling using AFPT 1 was established to SG 1 and then SG 2 was isolated due to the SGTR.
(1) Compliance with Specific Rule 4, Steam Generator Control, for SG level and feedwater flow is ___(1)___ when utilizing Trickle feed Cooling.
AFPT 1 then trips and can NOT be re-started.
(2) What action is required to be taken per DB-OP-02000?
(1) (2)
- a. required Establish Trickle Feed cooling to SG 1 using the MDFP.
- b. required Establish MU/HPI Cooling.
- c. not required Establish Trickle Feed cooling to SG 2 using the MDFP.
- d. not required Establish MU/HPI Cooling.
SENIOR REACTOR OPERATOR Page 18 of 25 Question# 093 The unit was in Mode 6 with the equipment hatch installed with core alterations in progress.
- A new fuel bundle was placed in the core.
- The fuel handling bridge was then moved back to the transfer mechanism for the next bundle.
- The reactor operator in the control room reported rising counts on his source range indications.
- It was then determined that the last bundle was placed in the wrong core location.
Under these conditions you should. . .
- a. direct operators to begin an immediate boration of the reactor vessel via the decay heat removal system.
- b. direct operators to begin an immediate boration of the reactor vessel via the high pressure injection system.
- c. direct the operators on the fuel handling bridge to immediately retrieve the mis-placed bundle and return it to the transfer mechanism.
- d. direct the operators on the fuel handling bridge to immediately retrieve the mis-placed bundle and place it in its correct location.
SENIOR REACTOR OPERATOR Page 19 of 25 Question# 094 During implementation of an Abnormal Procedure, what is REQUIRED to allow a deviation from a step sequence?
- a. The Shift Manager has concurred with the deviation.
- b. A Condition Report is written prior to taking the actions.
- c. The reason for the deviation is noted in a copy of the procedure.
- d. A Peer Check of the actions is conducted by any licensed operator.
SENIOR REACTOR OPERATOR Page 20 of 25 Question# 095 Given the following conditions:
- Power is being lowered from 100%.
- AFPT 1 was out of service.
The following event then occurred:
- A reactor trip from 10% power occurred.
- SG startup levels are at 40 inches.
- SG pressures are at 900 psig.
- RCS Hot Leg temperatures are at 550°F due to an overcooling transient that occurred following the reactor trip.
- RCS pressure is 1750 psig.
- The running MFW Pump tripped, however both MFW Pumps are available.
- AFPT 2 just tripped and is not available.
Of the following, what is the PREFERRED method of restoring feedwater flow to the SGs per DB-OP-02000, Attachment 5, Guidelines For Restoring Feedwater?
- a. Using the SUFP at 300 gpm.
- b. Using a Main FW Pump at 900 gpm.
SENIOR REACTOR OPERATOR Page 21 of 25 Question# 096 According to NOP-WM-1001, Order Planning Process, an Operations SRO is responsible for which ONE of the following in regards to Order processing?
- a. Verifying proper RWPs are filled out.
- b. Assuring proper job priorities are assigned.
- c. Planning and scheduling of maintenance work activities.
- d. Determine need for reactivity impact review by Reactor Engineering.
SENIOR REACTOR OPERATOR Page 22 of 25 Question# 097 The following plant conditions exist:
- The reactor was at 65% power ramping to 100% RTP.
- Control Rod Group 3 then dropped into the core.
- Reactor power dropped to 48% RTP as a result of the rods dropping.
You should GO TO . . .
- a. DB-OP-02504, Rapid Shutdown, and commence a RAPID SHUTDOWN to HOT STANDBY.
- b. DB-OP-02516, CRD Malfunctions, and direct the operators to maintain reactor power less than 50%.
- c. DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture, and direct the operators to TRIP the reactor.
- d. DB-OP-06902, Power Operations, after verifying SHUTDOWN MARGIN. If power operation to 100% is permitted, restore Group 3 and return to the power ramp.
SENIOR REACTOR OPERATOR Page 23 of 25 Question# 098 A Liquid Radwaste Release is needed to be performed from the Miscellaneous Waste Monitor Tank. However, Radiation Monitors RE-1878A and B are both currently inoperable. To perform the Liquid Release from the Miscellaneous Waste Monitor Tank what actions must be taken in accordance with the ODCM, Offsite Dose Calculation Manual, and DB-OP-03011, Radioactive Liquid Batch Release, to accomplish this?
- a. Pull and analyze two independent samples ONLY.
- b. Pull and analyze two independent samples AND perform two independent verifications of the release rate calculations ONLY.
- c. Pull and analyze two independent samples AND perform two independent verifications of the release rate calculations AND two independent verifications of the discharge valve lineup ONLY.
- d. Pull and analyze two independent tank samples AND perform two independent verifications of the release rate calculations AND two independent verifications of the discharge valve lineup AND one of the Radiation Monitors RE-1878A or B must be returned to service prior to the release.
SENIOR REACTOR OPERATOR Page 24 of 25 Question# 099 Given the following conditions:
- A SGTR has occurred that results in loss of subcooled margin.
- A lockout of D1 has occurred.
- Pressurizer level is 8 inches.
The use of both makeup injection lines is . . .
- a. allowed because of the low pressurizer level.
- b. allowed because of a loss of subcooled margin.
- c. NOT allowed because both makeup pumps are NOT available.
- d. NOT allowed because both low pressure injection pumps are NOT available.
SENIOR REACTOR OPERATOR Page 25 of 25 Question# 100 An Alert has been declared. Security was notified to activate CANS. Ten minutes later the Shift Manager noted that his pager had not activated. Which of the following is the first alternative method available to the Shift Manager to activate the pager system on the proper event code?
- a. Activation of the Backup CANS.
- b. Manual activation of the group page.
- c. individual contact of emergency responders.
- d. Manual activation of Emergency Notification System (ENS).
- END OF EXAM ********************
Reference Section Page 1 of 18 Question# 001 Question# 006 K/A 073K501 K/A 000022K103 Answer: d. Answer: d.
Reference:
Reference:
Q 38229 Bank Bank Higher Fundamental Question# 007 Question# 002 K/A 002A204 K/A 076A201 Answer: c.
Answer: d.
Reference:
Reference:
76241; OPS-GOP-437-K; ITS; UHS -
DB-OP-02511 Mode Change Modified New Higher Higher Question# 003 Question# 008 K/A 078K302 K/A 000026K304 Answer: a. Answer: a.
Reference:
Reference:
OPS-GOP-128-02K New ORQ-0824, 37548; Loss of Air Higher BANK FUNDAMENTAL Question# 009 K/A 000029A108 Question# 004 Answer: d.
K/A 000011K303
Reference:
Answer: d New
Reference:
Fundamental Bank Fundamental Question# 010 K/A 000038EA2.16 Question# 005 Answer: c.
K/A 103A404 REFERENCE Answer: d. DB-OP-02000, Revision 20 - Steps 8.34
Reference:
and 8.35 OPS-SYS-I506.04, Section 12, page 27 New DB-OP-02000, Attachment 9 Higher New Higher Question# 011 K/A 016K301 Answer: a.
Reference:
New Higher
Reference Section Page 2 of 18 Question# 012 Question# 017 K/A 000054 2.3.14 K/A 2.1.25 Answer: b. Answer: d.
Reference:
Reference:
OPS-GOP-131-11K Question 3 DB-OP-06703, Curves CC6.3c and DB-OP-02531 CC6.3d Bank Provide Pages 56 through 60 of DB-OP-Higher 06703, Miscellaneous Operation Curves.
New Question# 013 Higher K/A 041K201 Answer: b.
Reference:
Question# 018 OPS-SYS-524-04K; Loss of ICS power K/A BW/E04K2.1 on MFP Answer: b.
Bank
Reference:
Higher OPS-SYS-517-05K: 62166; MFP trip effects on cross limits BANK Question# 014 HIGHER K/A 000056A204 Answer: b.
Reference:
Question# 019 36847: OPS-GOP-111-03K (ORQ- K/A 2.2.35 0107): C1 L/O SW response Answer: b.
New
Reference:
Higher 39189, OPS-GOP-127-03K; OLE-4619; Loss of DH in Mode 5 Bank Question# 015 Higher K/A 000057A112 Answer: a.
Reference:
Question# 020 DB-OP-02532 K/A 000028 AA1.02 New Answer: b.
Fundamental
Reference:
DB-OP-02512 09-07-05 Question# 016 New K/A 000058K301 Higher Answer: c.
Reference:
37801 OPS-GOP-137-01K Question# 021 37801 ORQ-1085; Effects of D2P loss K/A 000051K301 BANK Answer: c.
FUNDAMENTAL
Reference:
New Fundamental
Reference Section Page 3 of 18 Question# 022 Question# 027 K/A 000061A101 K/A E03A2.2 Answer: d. Answer: a.
Reference:
Reference:
New DB-OP-02000, Attachment 7 (and Fundamental Bases for Attachment 7)
New Higher Question# 023 K/A 2.4.1 Answer: a. Question# 028
Reference:
K/A 003 2.2.44 63036; OPS-GOP-302-01K: OPS-GOP- Answer: b.
420-01K: ATWS (OLE-48152)
Reference:
BANK DB-OP-06005, RC Pump Operation, HIGHER Revision 21 DB-SD-039A, RCS System Description, Revision 5 Question# 024 New K/A (B&W) A03 AK1.3 Higher Answer: d.
Reference:
DB-OP-02532 Question# 029 New K/A 064K402 Fundamental Answer: c.
Reference:
OPS-SYS-506-07K Question# 025 Modified K/A A04K1.3 Higher Answer: b.
Reference:
36841, OPS-GOP-305-02K, Question# 030 ORQ-0101; SG Level after regain AFW. K/A 004A401 MODIFIED Answer: b.
HIGHER
Reference:
DB-OP-02504, Rapid Shutdown, Revision 14 Question# 026 New K/A B&WA05 AK2.02 Higher Answer: d.
Reference:
DB-OP-02521, DB-OP-02527 Question# 031 New K/A 013K303 Fundamental Answer: c.
Reference:
OPS-SYS-1506.05, SFAS Lesson Plan NEW HIGHER
Reference Section Page 4 of 18 Question# 032 Question# 037 K/A 006K605 K/A 010K502 Answer: d. Answer: c.
Reference:
Reference:
37079; OPS-GOP-304-04K Steam Tables ORQ-0343; SBLOCA, 9 ft in BWST Bank BANK Higher HIGHER Question# 038 Question# 033 K/A 012A306 K/A 006A302 Answer: b.
Answer: b.
Reference:
Reference:
76866; OPS-SYS-504-11K: RPS OPS-SYS-302-02K; (OLC-36940): Ch 1 indication for RCP with low amps Sequence Removed with LOOP and BANK SA2 HIGHER Bank 1008 NRC Exam Higher Question# 039 Question# 034 K/A 012K606 K/A 007A101 Answer: d.
Answer: b.
Reference:
Reference:
New OPS-SYS-104-03K Fundamental BANK HIGHER 2008 NRC Exam Question# 040 K/A 013A402 Answer: b.
Question# 035
Reference:
K/A 008K402 OPS-SYS-506-08K Answer: b. BANK
Reference:
HIGHER DB-OP-02523, SD-016 Bank Higher Question# 041 K/A 005A203 Answer: d.
Question# 036
Reference:
K/A 010 EA1.01 New Answer: c. Fundamental
Reference:
DB-OP-06003, OPSYSSI104.06 New Higher
Reference Section Page 5 of 18 Question# 042 Question# 047 K/A 022K201 K/A 062K302 Answer: c. Answer: d.
Reference:
Reference:
OPS SYS-1306.05, SFAS Lesson Plan DB-SC-03070, DB-OP-06316 NEW New HIGHER Fundamental Question# 043 Question# 048 K/A 026K102 K/A 063K402 Answer: b. Answer: b.
Reference:
Reference:
System Description 022A, Revision 3, 36465; OPS-GOP-137-04K, OPS-GOP-Containment Spray System, TABLE 2.5- 137-08K; Loss of D2P and DBP actions.
3 Bank BASES FOR SETPOINTS (p. T2.5-3-1) Higher New Fundamental Question# 049 K/A 004 2.1.28 Question# 044 Answer: c.
K/A 039K107
Reference:
Answer: d. System Question Review Bank, 07
Reference:
02 OPS-SYS-I207.05, Section H Bank New Fundamental Higher Question# 050 Question# 045 K/A 064A108 K/A 059K102 Answer: a.
Answer: c.
Reference:
Reference:
DB-SC-03070, DB-OP-06316 SD-014, System Description for Main Bank Feedwater System, Rev. 5, page 2-6 Fundamental Bank Fundamental Question# 051 K/A 000007 2.1.7 Question# 046 Answer: b.
K/A 061K201
Reference:
Answer: b. Bank
Reference:
Higher DB-OP-02537, Attachment 2 New Higher
Reference Section Page 6 of 18 Question# 052 Question# 057 K/A 000008A201 K/A 000025K101 Answer: d. Answer: d.
Reference:
Reference:
DB-OP-02513 Pressurizer Abnormal Bank AB, Section 4.4 Higher Bank Higher Question# 058 K/A 011A303 Question# 053 Answer: d.
K/A 000009K203
Reference:
Answer: d. OPS-SYS-I106.07
Reference:
Bank Bank Fundamental Higher Question# 059 Question# 054 K/A 014A402 K/A 078A301 Answer: b.
ANSWER: d.
Reference:
REFERENCE:
Modified 08-04-20 Fundamental BANK Fundamental Question# 060 K/A 015K101 Question# 055 Answer: d.
K/A 000015/17K207
Reference:
Answer: b. New
Reference:
Fundamental Bank Fundamental Question# 061 K/A 000040 2.2.37 Question# 056 Answer: a.
K/A 001A104
Reference:
Answer: c. DB-OP-02000, Step 7.37 Bases
Reference:
New 58881 Higher DB-OP-06901, Plant Startup; Revision 31 Bank Question# 062 Higher K/A 035K401 Answer: b.
Reference:
OPS-SYS-516-04K: 70963; SG level transmitter failure Bank Higher
Reference Section Page 7 of 18 Question# 063 Question# 068 K/A 000055K102 K/A 2.2.12 Answer: d. Answer: d.
Reference:
Reference:
DB-OP-02521, DB-OP-06903 DB-OP-06911 p.41, Note 7.16.2-5 New Bank Fundamental Fundamental Question# 064 Question# 069 K/A 068K610 K/A 000001 AK206 Answer: c. Answer: a.
Reference
Reference:
38338 DB-OP-02516 DB-OP-03011, Radioactive Liquid Batch New Release Fundamental Bank Fundamental Question# 070 K/A 2.2.42 Question# 065 Answer: a.
K/A 072K501
Reference:
Answer: c. ITS 3.8.7
Reference:
Modified Lesson Plan OPS-SYS-I508.06, Higher Process and Area Rad Monitoring.
New Higher Question# 071 K/A 2.3.4 Answer: b.
Question# 066
Reference:
K/A 2.1.4 10 CFR 20 Answer: d. Modified
Reference:
Higher NT-OT-07001 Modified Higher Question# 072 K/A 2.3.15 Answer: b.
Question# 067
Reference:
K/A 000065A103 BANK Answer: d. Fundamental
Reference:
32642 DB-OP-02528 Bank Fundamental
Reference Section Page 8 of 18 Question# 073 Question# 077 K/A 000076 2.2.22 K/A 017A202 Answer: a. Answer: a.
Reference:
Reference:
76040; OPS-GOP-420-01K; OLE; What DB-OP-02000, Figure 2, Incore T/C parameters affect DNB Temperature vs RC Pressure for TS 3.4.1 Inadequate Core Cooling, and Section BANK 9.0 FUNDAMENTAL Provide DB-OP-02000, Figure 2 New Higher Question# 074 K/A 2.4.31 Answer: a. Question# 078
Reference:
K/A 028 2.1.20 Lesson Plan OP-SYS-I509, Station Answer: d.
Annunciator; Revision 6
Reference:
New DB-OP-06502 Fundamental New Higher Question# 075 K/A 2.4.34 Question# 079 Answer: a. K/A B&W E05 2.4.6
Reference:
Answer: c.
DB-OP-2508, Control Room Evacuation;
Reference:
Revision 8 DB-OP-02000, Section 7.0 New New Fundamental Higher Question# 076 Question# 080 K/A 063A201 K/A 2.1.40 Answer: c. Answer: c.
Reference:
Reference:
DB-0P-02538, LOSS OF D2P AND DB-OP-00030, Fuel Handling DBP, Revision 13 Operations, Section 6.3 & Section 6.9 DB-0P-02537, LOSS OF D1P AND New DAP, Revision 14 Higher New Higher Question# 081 K/A 000056AA2.46 Answer: d.
Reference:
DB-OP-02000 Bases Document on Prioritization, DB-OP-02000, Specific Rule 6 New Higher
Reference Section Page 9 of 18 Question# 082 Question# 087 K/A 2.2.22 K/A 026A207 Answer: c. Answer: d.
Reference:
Reference:
Provide COLR with this question. DB-OP-02000, Attachments 7 and 27, 76231; OPS-GOP-431-K and SD-022A ITS; QPT/API Actions New BANK Higher HIGHER Question# 088 Question# 083 K/A 059 2.1.20 K/A 000036A203 Answer: a.
Answer: a.
Reference:
Reference:
DB-OP-02526 DB-OP-02530 New Bank Higher Fundamental Question# 089 Question# 084 K/A 061 2.4.22 K/A 000068 2.4.25 Answer: a.
Answer: b.
Reference:
Reference:
36838 DB-OP-02519 DB-OP-02000, Rev 23 New Specific Rule 4 Fundamental New Fundamental Question# 085 K/A BW/A01 2.1.1 Question# 090 Answer: a. K/A 000007 2.2.12
Reference:
Answer: a.
37680
Reference:
NOP-CC-2003, Engineering Changes 20-6-08 Bank Bank Fundamental Higher Question# 086 Question# 091 K/A 005A203 K/A 000008A201 Answer: d. Answer: c.
Reference:
Reference:
DB-OP-02527, Loss of Decay Heat DB-OP-02513 Removal, Revision 12 New 23-4-03 Higher Bank Higher
Reference Section Page 10 of 18 Question# 092 Question# 096 K/A 000038A210 K/A 2.2.19 Answer: d. Answer: d.
Reference:
Reference:
DB-OP-02000, Section 8.0 NOP-WM-1001 New Modified Higher Fundamental Question# 093 Question# 097 K/A 034A203 K/A 000005A203 Answer: a. Answer: a.
Reference:
Reference:
DB-OP-00030, Fuel Handling 13-6-21 Operations Bank NEW Higher HIGHER Question# 098 Question# 094 K/A 2.3.6 K/A 2.1.20 Answer: c.
Answer: deleted.
Reference:
Reference:
New DB-OP-01003, Step 6.1.5 Higher Bank Fundamental Question# 099 K/A 2.4.6 Question# 095 Answer: c.
K/A 000054 2.3.14
Reference:
Answer: c. DB-OP-02000, Specific Rule 3
Reference:
78726 DB-OP-02000, Attachment 5 Bank New Higher Higher Question# 100 K/A 2.4.30 Answer: a.
Reference:
OPS-GOP-603-04K (38755, ORQ-2061)
All methods to CANS BANK FUNDAMENTAL
- END OF EXAMINATION ******************
ANSWER KEY Page 1 of 1 001 d. 021 c. 041 d. 061 a. 081 d.
002 d. 022 d. 042 c. 062 b. 082 c.
003 a. 023 a. 043 b. 063 d. 083 a.
004 d 024 d. 044 d. 064 c. 084 b.
005 d. 025 b. 045 c. 065 c. 085 a.
006 d. 026 d. 046 b. 066 d. 086 d.
007 c. 027 a. 047 d. 067 d. 087 d.
008 a. 028 b. 048 b. 068 d. 088 a.
009 d. 029 c. 049 c. 069 a. 089 a.
010 c. 030 b. 050 a. 070 a. 090 a.
011 a. 031 c. 051 b. 071 b. 091 c.
012 b. 032 d. 052 d. 072 b. 092 d.
013 b. 033 b. 053 d. 073 a. 093 a.
014 b. 034 b. 054 d. 074 a. 094 deleted 015 a. 035 b. 055 b. 075 a. 095 c.
016 c. 036 c. 056 c. 076 c. 096 d.
017 d. 037 c. 057 d. 077 a. 097 a.
018 b. 038 b. 058 d. 078 d. 098 c.
019 b. 039 d. 059 b. 079 c. 099 c.
020 b. 040 b. 060 d. 080 c. 100 a.
- END OF EXAMINATION ********************