ML042170309
| ML042170309 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/12/2004 |
| From: | Cameron R Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-456/04-301, 50-457/04-301 | |
| Download: ML042170309 (91) | |
Text
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: MASTER SRO EXAMINATION Date: 07/16/2004 Facility/Unit: BRAIDWOOD U1/U2 Region: III Reactor Type: W 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 overall, with a 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require an 80.00 percent to pass. You have eight hours to complete the combined examination, and three hours 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.
Applicants Signature Results RO / SRO-Only / Total Examination Values 75 / 25 / 100 Points Applicants Scores / / Points Applicants Grade / / Percent
SENIOR REACTOR OPERATOR Page 2 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 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 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 a 70.00 percent or better 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 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 RO examination is six hours, the 25-question, SRO-only exam is three hours, the combined RO/SRO exam is eight hours, and SRO exam limited to fuel handling is four hours; extensions will be considered under extenuating circumstances.
- 4. You may bring pens, pencils, and calculators into the examination room; programable memories must be erased. Use black ink to ensure legible copies; dark pencil should be used only if necessary 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.
SENIOR REACTOR OPERATOR Page 3
- 6. Mark your answers on the answer sheet provided and do not use ink. Use only the paper provided including your examination. If you decide to change your original answer, erase completely and enter the desired answer. If the NRC examiner is unable to determine which answer you have selected because of poor erasure, the question will be marked as incorrect.
- 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 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 including the answer sheets and examination cover 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.
- 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 or revoked.
- 11. Do you have any questions?
SENIOR REACTOR OPERATOR Page 4 QUESTION: 001 (1.00)
Unit 1 is being returned to full power following a refueling outage when the following annunciators/indications are received in the U1 Main Control Room:
- 1-14-A3 "S/G 1A FLOW MISMATCH STM FLOW LOW."
- 1-15-A9 "S/G 1A LEVEL DEVIATION HIGH LOW."
- 1-15-A8 "S/G 1A LVL HI-2 TURB TRIP P-14 ALERT."
- 1FK510, 1A S/G FW REG VLV MA station indicates 100% output.
- ALL 1A S/G NR level channels are at 89% and rising.
No other alarms are received. U1 Reactor power is 35% and RISING. The U1 Main Generator load is at 400 MWe and ramping up at 0.2 MWe/min.
The NEXT action(s) the U1 Control Room Operators should take is/are to manually:
- a. stop the power ascension by pressing "HOLD" on the U1 DEHC control panel at 1PM02J and investigate.
- b. trip the U1 MAIN FEED PUMPS by pressing the "TRIP" pushbuttons on 1PM04J.
- c. trip the U1 Reactor by placing the MAN RX TRIP switch on 1PM05J in "ACTUATE".
- d. reduce 1A S/G level by placing 1FK510 (FW REG VLV 1FW510 MA station) in "MANUAL" and "LOWER" at 1PM04J.
SENIOR REACTOR OPERATOR Page 5 QUESTION: 002 (1.00)
Given the following conditions on Unit 1:
- A Small Break RCS LOCA has occurred.
- ECCS is currently in Recirculation Mode, all pumps are running.
- RCS temperature is 320°F.
- PZR level is 10% (hot cal).
The following occurs:
- An NSO notes indications for 1CC017, UNIT 1 CC SURGE TK VENT VLV on 1PM06J going CLOSED.
Based on the above indications, a leak is occurring in the ______ Heat Exchanger.
- a. U1 CC
- b. U1 Seal Water
- c. U1 Spent Fuel Pool
- d. 1A RH QUESTION: 003 (1.00)
When a Large Break RCS LOCA occurs, ECCS injection flow is initially injected into the RCS Cold legs so that:_________________________________.
- a. boron precipitation in the core will be prevented
- b. reactor vessel boron concentration will not exceed 23.53% by diluting vessel concentration
- c. boiling can be terminated should the LOCA be due to a break in a cold leg
- d. the core can be refilled and reflooded
SENIOR REACTOR OPERATOR Page 6 QUESTION: 004 (1.00)
Given the following Unit 1 conditions:
- Reactor power is 100%.
- An inadvertent Phase B occurred from A train of SSPS at 10:00.
- During the recovery actions the following data was recorded:
1A RCP Motor 1A RCP Lower 1A RCP Seal Time Bearing Temp. Radial Bearing Temp. Outlet Temp.
10:00 178 201 211 10:03 196 218 221 10:05 202 226 231 10:06 205 229 236 Which of the following is the EARLIEST time that the 1A RCP should have been tripped per procedure?
- a. 10:00
- b. 10:03
- c. 10:05
- d. 10:06
SENIOR REACTOR OPERATOR Page 7 QUESTION: 005 (1.00)
Given the following U1 conditions:
- RCS Tavg is 587°F.
- PZR Level is at 62%.
- Normal and Excess Letdown are ISOLATED.
- MASTER PZR LEVEL CONT, 1LK-459 is in AUTOMATIC and at MINIMUM demand.
- 1FK-121, CENT CHG PMPS FLOW CONT VLV 1CV121 is in MANUAL at 5%.
- CHG HDR BACK PRESS CONTROL VLV, 1CV182 is CLOSED.
- U1 A-D RCP seal injection flows are at 8, 10, 8, and 8 gpm.
With the above conditions, if 1FK-121 is placed in automatic, U1 Charging Flow will:
- a. DROP due to U1 PZR Level being above setpoint for 100% power.
- b. RISE to ensure sufficient flow to prevent Letdown Regen HX temperature alarms with 75 gpm letdown in service.
- c. DROP due to 1LK-459, MASTER PZR LEVEL CONT being in automatic at minimum demand.
- d. RISE to ensure minimum flow is maintained to the U1 RCP seals.
SENIOR REACTOR OPERATOR Page 8 QUESTION: 006 (1.00)
Given:
- Both Units at 100% power, normal alignment.
- 0 CC Hx is aligned to Unit 1.
The following occurs:
- Unit 2 Large Break RCS LOCA.
- 2A CC pump trips on overcurrent due to motor bearing failure.
- 2B RH pump fails to start.
- All other equipment functions as designed, and the crew progresses through the appropriate procedures.
- 2BwEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, has just been entered.
Upon opening 2CC9412A, CC to RH HX 2A ISOL VLV, the 2A RH HX:
- a. will receive flow from the running Unit 1 CC pump(s).
- b. will NOT have flow, a Unit 1 CC pump must be aligned to Unit 2.
- c. will NOT have flow, the 0 CC pump must be aligned to Unit 2.
- d. will receive flow from the 2B CC pump.
SENIOR REACTOR OPERATOR Page 9 QUESTION: 007 (1.00)
Given:
- Unit 1 at 100% power.
- 1A CC pump running.
- 1B CC pump in standby.
- 0 CC pump is mechanically aligned to Unit 1 and electrically to Bus 141 (MCR 0 CC pump Bus 141 C/S is in NAT).
The following occurs:
- 10:00 1A CC pump trips.
- 10:00 1B CC pump auto starts.
- 10:01 The crew enters TS 3.7.7. Cond A "One CC flow path inoperable" for the loss of the 1A CC pump.
- 10:02 1A CC pump C/S is placed in PTL.
- 10:15 1A CC pump breaker is racked out. Control Power fuses are left installed.
Based on the above time line, TS 3.7.7 will be exited at _(1)_. The Control Power fuses for the 1A CC pump were left INSTALLED upon breaker rack out to allow the 0 CC pump to _(2)_.
__(1)__ ____________(2)___________
- b. 10:02 trip on low CC surge tank level
- d. 10:15 trip on low CC surge tank level
SENIOR REACTOR OPERATOR Page 10 QUESTION: 008 (1.00)
Given:
- Unit 2 at 100% power.
- U2 PRESS CONT CH SELECT switch is in the 457/458 position.
The following occurs:
- The U2 NSO notices PZR Variable Heater amps on 2PM05J rapidly RISING to maximum.
This is an indication that PZR PRESS transmitter 2PT_______(1)_______. Ten (10) minutes later (after manual pressure control is established and PZR Pressure is restored to normal), the following conditions are noted:
- 2PK-455A MASTER PZR PRES CONT "MAN" light is lit:
- Variable Heater AC AMPERES meter on 2PM05J indicates 260 (mid range).
If the 2PK-455A Controller "LOWER" pushbutton is depressed, indicated Unit 2 Variable Heater amps on 2PM05J will __(2)__.
_______(1)______ __(2)__
- a. 458 has failed HIGH LOWER
- b. 458 has failed LOW RISE
- c. 457 has failed HIGH LOWER
- d. 457 has failed LOW RISE
SENIOR REACTOR OPERATOR Page 11 QUESTION: 009 (1.00)
A U1 SI has occurred from 100% power. 1BwEP-0, "REACTOR TRIP OR SAFETY INJECTION", has just been implemented.
The following U1 indications are observed:
- "A" Reactor Trip Breaker (RTA) is OPEN.
- "B" Reactor Trip Breaker (RTB) is CLOSED.
- Both Reactor Trip Bypass Breakers are OPEN.
- Reactor power is 4%, with IR SUR at -0.5 dpm.
- 1 rod is stuck OUT, all others are fully INSERTED.
Both MAN RX TRIP switches on 1PM05J and 6J have been placed in "ACTUATE", however the U1 "B" Reactor Trip Breaker is still CLOSED. Based on the above conditions, the crew should:
- a. continue with 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION; Step 2.
- b. DE-energize 480V substations 134Y and 133Y.
- c. initiate Emergency Boration per 1BwOA PRI-2, EMERGENCY BORATION.
- d. transition to 1BwFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.
SENIOR REACTOR OPERATOR Page 12 QUESTION: 010 (1.00)
Unit 1 is responding to a SGTR. They have identified and isolated the ruptured S/G, cooled down, depressurized the RCS, and terminated SI.
Currently:
- U1 Core exit temperatures, S/G pressures, and RCS hot leg temperatures are ALL DROPPING.
- U1 RCS cold leg temperatures are at the saturation point for the existing S/G pressures.
- U1 RCS subcooling, per the iconic display is 35°F and white.
- NO U1 RCPs are running.
During a crew discussion, the U1 SRO states that because natural circulation is established, it is NOT necessary NOR is it desirable to establish forced reactor coolant circulation. The U1 RO states that forced reactor coolant circulation should be established, if conditions permit.
Which crew member is correct and why?
- b. The RO -- because forced circulation will minimize pressurized thermal shock and boron dilution concerns.
- c. The SRO -- because starting an RCP will result in a LOWER subcooling margin with the same heat transfer rate and PZR pressure.
- d. The RO -- because natural circulation conditions are NOT indicated (the SRO misinterpreted the indications of natural circulation).
SENIOR REACTOR OPERATOR Page 13 QUESTION: 011 (1.00)
Given the following sequence of events:
- Unit 1 at 100% power, normal alignment.
- A large steam line break occurs in the 1A/1D MSIV room.
- All U1 MSIVs fail to CLOSE.
Which MCR indications (below) are consistent with ALL Unit 1 Main Steam lines being faulted?
(Assume ALL other equipment operates as designed and that readings were taken 2 minutes after the U1 Reactor trip.)
- 1. 1TE-RC022-25B, COLD LEG TEMP RECORDERs on 1PM05J LOWERING.
- 2. 4AA122/3 and 4AD422/3, A and D MAIN STEAM LINE RAD MONITORs indicating RED on the RM-11 display.
- 3. All MAIN STEAM LINE RAD MONITORs (4AA122 through 4AD423) indicating GREEN on the RM-11 display with stable readings.
- 4. 1FI-AF011A and 18A, SG FLOWs PP 1A and 1B for 1A S/G on the Auxiliary Feedwater section of 1PM06J ALL off scale HIGH.
- a. 3, 4
- b. 2, 4
- c. 1, 2
- d. 1, 3
SENIOR REACTOR OPERATOR Page 14 QUESTION: 012 (1.00)
Given:
- Unit 2 at 100% power, normal alignment.
The following occurs:
- An inadvertent U2 FW isolation signal is generated.
- Both U2 AF pumps FAIL to start.
- All other U2 equipment functions as designed.
With the above conditions and NO operator action. IMMEDIATELY AFTER the U2 Reactor Trips, U2 RCS pressure will _____(1)_____ , and then slowly return to normal. After U2 RCS Pressure returns to normal, over the NEXT 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (and NO operator action), U2 RCS Pressure will: _________(2)__________
_(1)_ _______________________(2)__________________________
- a. RISE begin cycling at the 2RY456 PZR PORV setpoint shortly after S/G "dry out" occurs.
- b. DROP be maintained below the PZR PORV setpoints, since PZR sprays are available.
- c. RISE be maintained below the PZR PORV setpoints, since PZR sprays are available.
- d. DROP begin cycling at the 2RY456 PZR PORV setpoint shortly after S/G "dry out" occurs.
QUESTION: 013 (1.00)
Select the primary reason for rapidly depressurizing the steam generators during a Loss of All AC.
- a. To raise subcooling of the RCS.
- b. To enhance restoration of S/G level from the diesel driven AF pump.
- c. To provide maximum core cooling until power can be restored.
SENIOR REACTOR OPERATOR Page 15 QUESTION: 014 (1.00)
Given the following:
- Unit 2 at 100% power, normal alignment.
- 211 Battery Charger voltage: 131 Vdc
- 211 Battery Charger amps: 35A If the 211 BATTERY BREAKER, AF-2 is OPENED inadvertently, DC bus 211 will:
- a. remain energized. Locally, 211 Battery Charger amps and voltage will remain approximately the same.
- b. DE-energize. Locally, 211 Battery Charger amps will DROP and Charger voltage will remain approximately the same.
- c. remain energized. Locally, 211 Battery Charger amps will RISE and voltage will remain approximately the same.
- d. DE-energize. Locally, 211 Battery Charger amps and Charger voltage will DROP.
QUESTION: 015 (1.00)
Given the following:
- Unit 2 is at 100% power.
- 2A SX pump trips.
An attempt is made to start the 2B SX pump but, it does NOT start. Which of the following could be preventing the 2B SX pump start?
- a. 2B SX pump suction pressure locally indicates 6 psig.
SENIOR REACTOR OPERATOR Page 16 QUESTION: 016 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
- Instrument Air to Unit 1 Containment is inadvertently lost.
The loss of Instrument Air to Unit 1 Containment can be confirmed at 1PM05J by checking that:
- b. both 1CV8146 and 1CV8147, CHG TO RC LOOPs 1A and 1B ISOL VLVS indicate OPEN.
QUESTION: 017 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
An event occurs and the following indications are noted:
- Aux building radiation monitors show RISING trends.
- U1 PZR pressure and PZR level begin LOWERING.
- Both U1 RH pump discharge pressure indicators in the MCR are pegged HIGH.
The crew decides to attempt to isolate the leak by closing 1SI8809A, RH to COLD legs 1A & 1D to isolate the leak. To ALLOW 1SI8809A to close using the MCR handswitch at 1PM06J, the crew must first ______________________________________ on 1PM06J.
- a. place the 1A RH PP C/S to PULL OUT
- b. fully OPEN 1SI8840, RH TO HOT LEGS 1A & 1D using the C/S
- c. place the 480V FEED TO BUS 131X1A/X2A C/S to CLOSE
- d. fully OPEN 1RH8716A, 1A RH PP DISCH XTIE using the C/S
SENIOR REACTOR OPERATOR Page 17 QUESTION: 018 (1.00)
Given the following conditions on Unit 1:
- 1BwCA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION is in progress.
- Annunciator 1-6-A7, RWST LEVEL LO-3 has just alarmed.
Based on the above conditions, U1 RWST level is currently__________________, the crew must immediately place ALL pumps taking suction from the U1 RWST in PULL OUT unless a flow path exists from the Containment Sump.
- a. 7%
- b. 12%, when U1 RWST level drops to 7%
- c. 17%
- d. 46%, when U1 RWST level drops to 17%
SENIOR REACTOR OPERATOR Page 18 QUESTION: 019 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
- A Turbine Generator problem forces a Unit 1 reactor trip.
Immediately after the Unit 1 trip, the following conditions are noted:
- A 1A S/G safety has failed partially OPEN and will NOT reseat.
- 1FW039B, 1B S/G LOW FLOW ISOL VLV is indicating mid position and will NOT close.
- AF has auto started due to low S/G level.
- ALL other components function as designed.
15 minutes after the Unit 1 trip, 1BwEP ES-0.1, REACTOR TRIP RESPONSE is in progress and the following U1 conditions are noted:
- SI has NOT been actuated.
- All MSIVs are CLOSED.
- RCS pressure is stable at 2235 psig.
- PZR level is currently being maintained at program with CV Letdown isolated.
- VCT level is being maintained with Auto Makeup.
- RCS average temperature is 544°F and drifting LOWER slowly.
- AF flow has been reduced as necessary to maintain S/G levels.
Based on the above conditions and using the appropriate switches on 1PM05J/6J, the RO must:
- a. ACTUATE SI.
- b. ACTUATE FWI.
- c. EMERGENCY BORATE.
- d. REDUCE RCS pressure using AUX SPRAY.
SENIOR REACTOR OPERATOR Page 19 QUESTION: 020 (1.00)
Given:
- Unit 1 startup in progress, reactor power at 7x10-11 amps and stable.
The following occurs:
- Unit 1 IR Channel N35 fails low.
- Unit 1 IR Channel N36 is checked and indicates 7x10-11 amps.
- LOSS OF DETECTOR VOLT light is lit on N35 drawer.
Referring to the attached pages (9-10) of 1BwOA INST-1, NUCLEAR INSTRUMENTATION MALFUNCTION, the crew must:
- a. trip U1 immediately, an ATWS has occurred.
- b. maintain Rx power <1x10-10 amps until N35 is repaired.
- c. place both IR MAN BLOCK switches to BLOCK.
- d. RAISE U1 Reactor power to greater than 10% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
SENIOR REACTOR OPERATOR Page 20 QUESTION: 021 (1.00)
Given:
- Unit 2 CW chlorination is being performed.
- BwOP WX-501T1, LIQUID RELEASE TANK 0WX01T RELEASE FORM using 0WX896, RELEASE TANK DISCHARGE ISOLATION VALVE is in progress. All actions associated with starting the release have been performed correctly.
The following occurs:
- 0FT-CW040 CW Blowdown flow indication on 0PM01J drops to below the minimum required due to 1B CW pump tripping.
With the above conditions, the NSO should _______(1)________. The NSO ____(2)____
verify that 0WX896 has CLOSED by checking the RM-11 0PR01J, LIQ RADWASTE Process Rad Monitor indications for loss of sample flow.
_____________(1)____________ _(2)_
- a. call radwaste to ensure that the WX can NOT release is terminated
- b. verify 1B CW pp discharge valve CLOSES can
- c. restore CW Blowdown flow from Unit 2 can NOT
- d. inform the U1 Unit Supervisor can
SENIOR REACTOR OPERATOR Page 21 QUESTION: 022 (1.00)
Given:
- Both Units at 100% power.
The following occurs:
- RM-11 panel alarms.
- An NSO investigating finds that 0RE-AR001, ELEV 346 Area Rad Monitor (3AS101) indicates RED.
Per the associated BwAR the required actions are to ______(1)_____ the Charcoal Booster Fans for the in service Non-Accessible VA plenums to limit potential offsite dose due to radioactive _(2)_.
_____(1)_____ _(2)_
- a. verify running Iodine
- b. consider starting Xenon
- c. verify running Argon
- d. consider starting Iodine
SENIOR REACTOR OPERATOR Page 22 QUESTION: 023 (1.00)
Given:
- A fire has occurred in the Div 11 ESF switchgear room.
- The fire is out.
- The fire brigade chief has requested the Div 11 Supply Fan be placed in PURGE mode.
- The Div 11 Supply Fan is currently shutdown.
- The PURGE C/S for the DIV 11 SUPPLY Fan on 1VX01J has been placed in PURGE.
With the PURGE C/S for the DIV 11 SUPPLY Fan on 1VX01J in PURGE, the Div 11 Supply Fan Suction and Recirc dampers __(1)__ reposition (from their shutdown positions) when the Div 11 Supply Fan is started. If a reflash of the fire occurs during purge operations, the DIV 11 SUPPLY FAN: _______________(2)_______________.
__(1)__ ___________________(2)____________________
- a. will must be manually shutdown by placing the fan C/S on 1VX01J to STOP
- b. will NOT must be manually shutdown by placing the fan C/S on 1VX01J to STOP
- c. will will automatically shutdown due to high ionization
- d. will NOT will automatically shutdown due to high ionization
SENIOR REACTOR OPERATOR Page 23 QUESTION: 024 (1.00)
With Unit 1 initially at 100%, normal alignment, the following occurs:
- 1B RCP trips.
- 5 minutes after the RCP trip, SI auto actuates and all MSIVs are manually closed.
- Upon MSIV closure 1C S/G PORV sticks open. This is found 10 minutes later and the valve closes when the 1PM04J C/S is taken to close.
- All other equipment functions as designed.
- S/G levels are as follows when all AF flows are throttled back to 50 gpm. No other adjustments are made before or after):
1A S/G NR level is 15% 1B S/G NR level is 35%
1C S/G NR level is 12% 1D S/G NR level is 25%
- The crew transitions from 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION to 1BwEP-1 LOSS OF REACTOR OR SECONDARY COOLANT.
- Unsure that this is the correct procedure, the US enters 1BwEP ES-0.0, REDIAGNOSIS.
- At step 3, the US asks the RO if any SG level is "increasing in an uncontrolled manner".
- The RO observes the following indications:
1A S/G NR level is 22% Pressure is 1050 psig 1B S/G NR level is 41% Pressure is 1050 psig 1C S/G NR level is 17% Pressure is 1050 psig 1D S/G NR level is 41% Pressure is 1090 psig Based on the above conditions, the RO will state that "____S/G(s) is/are RISING in an uncontrolled manner."
- a. 1A
- b. 1B
- c. NO
- d. 1D
SENIOR REACTOR OPERATOR Page 24 QUESTION: 025 (1.00)
Given:
- Unit 1 has recently recovered from a Steam Generator Overpressure transient.
Currently:
- Unit 1 at 85% power, normal alignment.
- Post transient engineering reviews show that 1A S/G safeties lifted at the following setpoints:
1MS013A lifted at 1284 psig 1MS014A lifted at 1159 psig 1MS015A lifted at 1211 psig 1MS016A lifted at 1232 psig 1MS017A lifted at 1171 psig Based on the above conditions, and referring to the attached TS pages (3.7.1-1 through 4), the crew must ______________________ hours.
- a. reduce power to < or = to 56% within 4
- b. reduce power to < or = to 39% within 4
- c. reduce power to < or = to 23% within 4
- d. be in MODE 3 within 6
SENIOR REACTOR OPERATOR Page 25 QUESTION: 026 (1.00)
With Unit 1 initially at 100% power, normal alignment:
- A small break RCS LOCA occurs.
- All equipment functions as designed.
- The crew transitions through the appropriate procedures.
Currently:
- 1BwEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, is in progress.
- U1 RCS temperature is 390°F.
- U1 RCS Pressure is 850 psig.
- Annunciator 1-3-A7 AF PUMP SUCTION PRESSURE LOW ALARM has just come in.
- The computer points for U-1 AF pump suction pressure both indicate 20.0 psia.
In accordance with the operator action summary page of 1BwEP ES-1.2, the crew should__(1)__ the U1 RCS cooldown rate or :_______(2)________.
__(1)__ _______(2)________
- b. LOWER crosstie CSTs
- c. RAISE crosstie CSTs
SENIOR REACTOR OPERATOR Page 26 QUESTION: 027 (1.00)
Given:
- Unit 1 at 100%, normal alignment.
- A grid problem causes a Unit trip and loss of offsite power.
- 1BwEP ES-0.2, NATURAL CIRCULATION COOLDOWN, has just been entered.
Per design, RCS natural circulation capability for Unit 1 will provide sufficient flow to:
- a. prevent head voiding with NO CRDM fans running during cooldown with 5°F subcooling.
- b. prevent core T from exceeding 10°F with NR S/G levels >10% during cooldown.
- d. cooldown the RCS at 5°F/HR with design basis decay heat to MODE 4.
QUESTION: 028 (1.00)
Given:
- Unit 2 at 35% power.
- Normal "at power" electrical alignment exists.
2A RCP trips due to a loss of its associated 6.9 Kv bus. With the above conditions, the U2 "Red" FIRST OUT annunciator that will be generated is:
- a. RCP BUS UNDER FREQ RX TRIP.
- d. RCP BUS UNDERVOLT RX TRIP.
SENIOR REACTOR OPERATOR Page 27 QUESTION: 029 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
- 1LT-112 VCT Level transmitter is failed "as is" at 43%.
With the above conditions, if 1LT-185 VCT LEVEL Transmitter fails to 97%, VCT LVL CONT, 1LK-112 will ___________(1)___________. With both VCT level transmitters failed, taking control switch 1CVLCV112A, LTDWN TO VCT OR HUT DIVERT VLV out of AUTO to the VCT position ___(2)___ reposition the valve.
_______________(1)________________ __(2)__
- a. Fully OPEN to direct letdown flow to the HUT will
- b. Fully OPEN to direct letdown flow to the HUT will NOT
- c. remain in its current position will
- d. Partially OPEN to direct letdown flow to the HUT will NOT
SENIOR REACTOR OPERATOR Page 28 QUESTION: 030 (1.00)
Given:
- Unit 1 RCS temp stable at 260°F.
- Unit 0 CC HX is aligned to Unit 1.
- 1A RH pump is running in shutdown cooling mode.
- 1B RH pump aligned for ECCS injection.
- ALL Unit 1 Steam Dumps and S/G PORVs are closed.
- HX 1A FLOW CONT VLV (1RH606) Controller on 1PM06J output is indicating 50%.
- 1TI-674 HX 1 OUTLT TEMP (Unit 1 CC HX CC Outlet) on 1PM06J is 80°F and stable.
If the output on the 1RH606 Controller on 1PM06J is RAISED to 60%, (assume NO other operator actions occur at this time) Unit 1 CC HX CC outlet temperature will __(1)__. Following 1RH606 adjustment, a constant U1 RCS heatup/cooldown rate can be maintained over the next hour if ______(2)______
__(1)__ ________________(2)_____________
SENIOR REACTOR OPERATOR Page 29 QUESTION: 031 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
The following occurs:
- An earthquake results in a Small Break RCS LOCA on U1.
- A U1 SI signal is actuated.
- Loose debris in the MCC for 1SI8821A, PP 1A TO COLD LEGS ISOL VLV causes 1SI8821A to fully CLOSE and prevents it from being re-opened from the MCR.
- 1A SI pump fails to start.
- All other U1 equipment functions as designed.
- Unit 1 RCS pressure is currently 2050 psig and LOWERING.
With NO operator action and assuming U1 RCS pressure continues to lower, 1B SI pump flow will be initiated to: ______________________.
- a. ALL four U1 RCS cold legs
- b. 1C & 1D RCS cold legs ONLY
- c. 1B & 1D RCS cold legs ONLY
- d. 1B & 1C RCS cold legs ONLY QUESTION: 032 (1.00)
Given the following:
- Unit 1 at 100%, normal alignment.
Which one of the following would cause the GREATEST rate of change in PRT pressure?
- a. 1CV8117 LETDOWN RELIEF fails open.
- b. U1 Reactor Vessel Inner O-ring fails.
- c. A U1 RCS Loop Drain valve fails open.
- d. 1RY8010A, PZR SAFETY fails open.
SENIOR REACTOR OPERATOR Page 30 QUESTION: 033 (1.00)
Given:
- Unit 2 at 100% power, normal alignment.
- An inadvertent U2 Containment Isolation Phase A has occurred.
- All equipment has functioned as designed, NO operator action has been taken.
With the above conditions and referring to the attached print (20E-2-4030RY11), if the C/S for 2RY8028 PW to PRT (outside) CNMT ISOL VLV on 2PM05J is taken to OPEN, 2RY8028 will:
- a. NOT OPEN due to the active Unit 2 Containment Isolation Phase A signal.
- b. OPEN and will remain open if the C/S is released due to the lack of spring return on the C/S in the OPEN position.
- c. OPEN and immediately reclose as soon as the full open limit is reached due to the active Unit 2 Containment Isolation Phase A signal.
- d. OPEN and will remain open as long as the C/S is being held in the OPEN position.
SENIOR REACTOR OPERATOR Page 31 QUESTION: 034 (1.00)
Given:
- Unit 2 at 100% power, normal alignment.
- Unit 0 CC Hx aligned to Unit 1.
- 2A CC pump running.
- 2B CC pump in standby.
- 2PI-CC107, CC PUMP DISCH PRESS on 2PM06J indicates 140 psig.
With the above conditions, inadvertently isolating CC to the Unit 2 FC HX will cause indicated CC pressure on 2PI-CC107 to RISE to approximately _(1)_ psig. At this point, 2LI-670/2LI-676, SRGE TK LVL 2A/2B (Unit 2 CC Surge Tank Level indicators) on 2PM06J may BEGIN being LOWERING, due to the U2 RCP ________(2)________ CC relief(s) lifting.
_(1)_ ________(2)________
- a. 150 Thermal Barrier
- b. 175 Thermal Barrier
- c. 150 Motor Bearing Return Header
- d. 175 Motor Bearing Return Header QUESTION: 035 (1.00)
The Unit 1 PZR Spray Nozzle is kept warm during normal ops by:
(1RY455B and C are PZR SPRAY valves)
- a. bypass holes in the disks of BOTH 1RY455B and C. Bypasses are drilled to achieve approx. 1 GPM (each) when the valves indicate fully closed.
- b. manual throttle valves which bypass approx. 1 GPM (each) around BOTH 1RY455B and C.
- c. a bypass hole in the disk of 1RY455B. Bypass is drilled to achieve approx. 2 GPM when 1RY455B indicates fully closed. 1RY455C does NOT have a drilled bypass.
- d. a SINGLE manual throttle valve which bypasses approx. 2 GPM around 1RY455B. 1RY455C does NOT have a bypass.
SENIOR REACTOR OPERATOR Page 32 QUESTION: 036 (1.00)
Given:
- 1RY456, PZR PORV C/S is in AUTO.
- U1 RCS pressure is approaching the 1RY456 lift setpoint.
- U1 PZR level is 74% with a steam bubble.
- U1 PRT Pressure is 3 psig.
With the conditions above, the expected initial U1 PZR PORV Tail Pipe temperature once 1RY456 OPENs is _(1)_ °F. If NEITHER U1 PZR PORV lifts, and U1 RCS pressure reaches the U1 PZR Safety setpoint, the expected INITIAL U1 PZR SAFETY Tail Pipe temperatures will be ____(2)___ the expected U1 PZR PORV Tail Pipe temperature above.
_(1)_ ____(2)___
- a. 222 the same as
- b. 308 the same as
- c. 308 HIGHER than
- d. 653 HIGHER than QUESTION: 037 (1.00)
Which of the following describes the type of core protection afforded by the Reactor Protection System "Over Temperature Delta T" trip?
- a. KW per linear foot
- b. Departure from nucleate boiling
- c. RCS Integrity
- d. Loss of heat sink
SENIOR REACTOR OPERATOR Page 33 QUESTION: 038 (1.00)
Given the following U1 initial conditions:
- MODE 3.
- RCS temp at 557°F.
- Shutdown banks withdrawn.
- S/G NR levels all at 60%.
- ALL RCPs running.
- NO Tech Specifications currently entered.
With the above conditions, which of the following scenarios would require Tech Specs to be entered?
- a. A U1 Reactor trip is initiated, RTA fails to OPEN and Rod N9 indicates 18 steps.
- c. 1B RCP TRIPs.
- d. U1 CST level is determined to be 72%.
QUESTION: 039 (1.00)
Given the following conditions:
- Unit 1 RCS pressure being RAISED following an outage.
As U1 RCS pressure rises, U1 PZR LOW PRESS SI BLOCK PERMISSIVE P11, Bypass Permissive Light on1PM05J is expected to initially reset (DE-energize), when indicated U1 PZR pressure on PZR pressure channels 455 and _(1)_ on 1PM05J reach _(2)_ psig.
_(1)_ _(2)_
- a. 456 1885
- b. 458 1885
- c. 457 1930
- d. 458 1930
SENIOR REACTOR OPERATOR Page 34 QUESTION: 040 (1.00)
Given:
- U1 at 100%, normal alignment.
- A loss of U1 Containment Cooling occurs.
With the above conditions, which ONE of the following U1 components will begin to give an inaccurate HIGH indication?
- a. RCS wide range pressures
- b. PRT pressure
- c. S/G pressures
- d. Pressurizer Hot Cal levels
SENIOR REACTOR OPERATOR Page 35 QUESTION: 041 (1.00)
Given the following conditions on Unit 2:
- A Large Break RCS LOCA has occurred.
- All equipment up to this point has functioned as designed.
- Annunciator 2-6-B7, RWST LEVEL LO-2 has just alarmed.
If 2SI8811A, CNMT SUMP ISOL VLV fails to automatically OPEN and NO operator action is taken, the FIRST abnormal indication the U2 NSO will observe will be 2A CS pump
________(1)_______. To deal with the failure of 2SI8811A above, 2BwEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION Attachment A, MANUAL OPERATION OF CONTAINMENT SUMP ISOLATION VALVES _(2)_ direct the 2A CS pump C/S on 2PM06J be placed in "Pull Out" before performing the valve alignments necessary to manually OPEN 2SI8811A from the MCR.
________(1)_______ _(2)_
- a. amps pegged HIGH will
- b. runout will NOT
- c. flow oscillating will
- d. discharge pressure oscillating will NOT
SENIOR REACTOR OPERATOR Page 36 QUESTION: 042 (1.00)
Given:
- Unit 1 at 17% power, preparing to synchronize U1 Main Generator.
- All systems are in their normal alignment for the above situation.
If 1PT507, Main Steam Header Press fails HIGH, U1 Steam dumps will _(1)_ OPEN
________(2)__________.
_(1)_ _________________(2)___________________
- a. NOT due to the lack of an "actuation" signal
- b. fully then fully CLOSE as soon as RCS Tavg drops below 550°F
- c. fully then fully CLOSE as soon as RCS Tavg drops below 557°F
- d. NOT due to the lack of an "arming" signal
SENIOR REACTOR OPERATOR Page 37 QUESTION: 043 (1.00)
Given conditions:
- Unit 2 at 95% power.
- 2D Cond/Cond Booster pump is tagged out.
If the 2B Cond/Cond Booster pump TRIPS and annunciator 2-16-E1 FW PUMP NPSH LOW illuminates "RED" as a result, the _______(1)_______, will automatically OPEN (when NPSH falls below the actuation setpoint), and the crew should immediately (Per 2BwOA SEC-1, SECONDARY PUMP TRIP) _______(2)_________.
- a. 1) 2CB025, LOW PRESS HTR 2) Initiate a U2 Reactor Trip STRING BYP VLV
- b. 1) 2CD157A/B, COND GS 2) Initiate a U2 Reactor Trip COND 2A/B BYP VLVs
SENIOR REACTOR OPERATOR Page 38 QUESTION: 044 (1.00)
Given the following sequence of events:
- A Unit 1 Reactor trip from 100% power has occurred due to 1C MSIV failing closed.
- Upon exit of 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, 1C S/G pressure is noted to be 1240 psig and 1C NR S/G level is >95%.
- 1BwFR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE is entered, followed by 1BwFR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL.
With the above conditions, which of the following lists mitigation strategies in 1BwFR-H.2/H.3 that will be used to reduce 1C S/G pressure and/or level?
- a. Attempt to release steam from 1C S/G by opening the 1C S/G PORV. Attempt to place S/G Blowdown in service to the 1C S/G.
- b. Attempt to release steam from 1C S/G by opening the 1C S/G PORV. Reduce AF flow (to a minimum of) 45 gpm to the 1C S/G.
- d. Verify FW isolated to 1C S/G. Attempt to place S/G Blowdown in service to the 1C S/G.
SENIOR REACTOR OPERATOR Page 39 QUESTION: 045 (1.00)
Given:
- Unit 2 at 100% power, normal alignment.
The following sequence of events occur:
- Unit 2 Reactor trips.
- Both Unit 2 AF pumps automatically start
- Instrument bus 214 is lost 5 minutes later.
- No operator actions are taken.
When Instrument Bus 214 was lost, the 2AF005E-H, S/G FLOW CONT valves failed
________(1)_______ due the loss of power to their controllers. Following the loss of Instrument Bus 214, if Instrument Air is subsequently lost to the 2AF005E-H positioners and valve actuators, the 2AF005E-H valves will ____(2)____.
________(1)_______ ____(2)____
- a. CLOSED OPEN fully
- b. CLOSED remain CLOSED
- c. to approximately 70% open fully CLOSE
- d. to approximately 70% open OPEN fully
SENIOR REACTOR OPERATOR Page 40 QUESTION: 046 (1.00)
While time stroking 1AF013A, S/G 1A ISOL VLV closed, for a surveillance, an Assist NSO notes that the control switch does not spring back to the mid position once the control switch is released. With the above conditions, the Assist NSO is required to:
- a. continue on with the surveillance. This feature is normal and is used during unit shutdowns to isolate AF to the steam generator to prevent gravity feeding.
- b. immediately direct the 480v breaker for 1AF013A be opened locally. The valve will continue to attempt to stoke closed as long as the C/S is in the close position.
- c. attempt to correct the switch problem by cycling the switch to open and close at least twice.
- d. stop performing the surveillance, inform the Unit 1 US and Unit 1 NSO immediately, and write an Issue.
QUESTION: 047 (1.00)
Given the following conditions on Unit 1:
- 17% Reactor power, PREPARING TO SYNCHRONIZE the Main Generator.
- Main Generator voltage regulator C/S is in "ON".
- Main Generator output voltage is 23.2 Kv.
- "BUS ALIVE" lights are lit on the 1PM01J mimic for the 6.9 Kv feeds from the U1 UATs.
The following occurs:
- Breaker 1592, 6.9 Kv bus feed from SAT 142-1 is inadvertently locally tripped.
Assuming NO operator actions, 1 minute later, the 1D:
- b. CD/CB booster pump will be receiving power from UAT 141-1.
- c. CD/CB booster pump will be tripped due to bus UV.
SENIOR REACTOR OPERATOR Page 41 QUESTION: 048 (1.00)
Given the following sequence of events:
- Unit 1 at 100% power, normal alignment.
- An event occurs.
- A manual Unit 1 Reactor trip is initiated due to feed flow problems.
Two minutes after the Reactor trip the following Unit 1 conditions are noted:
- 41-BRKR, "PMG OUTPUT BRKR" indicates OPEN on 1PM01J.
- Position indicating lights for several DC operated valves have been lost on 1PM05J.
- 1E1-DC001 "DC BUS 111 VOLTAGE", and 1EI-DC002 "DC BUS 112 VOLTAGE" on 1PM01J both indicate 132 volts.
With the above conditions, the Unit 1 Assist NSO should expect to see annunciator
"_____(1)_____" fast flashing, it can then be positively determined that: _____(2)_____.
- a. 1) 1-22-E6, 125V DC BATT 112 MAIN BRKR TRIP
- 2) DC 112 Battery Breaker AF-2 has tripped
- b. 1) 1-21-E6, 125V DC BATT 111 MAIN BRKR TRIP
- 2) DC 111 Battery Breaker AF-2 has tripped
- 2) the DC bus 112/114 bus tie fuses have blown
- 2) the DC bus 111/113 bus tie fuses have blown
SENIOR REACTOR OPERATOR Page 42 QUESTION: 049 (1.00)
Given Unit 1 at 100% power, normal alignment with the following exception:
- Following satisfactory completion (and shutdown) of the last surveillance run of the 1A DG, BOTH manual discharge valves for 1A DG Fuel Oil Storage Tank Transfer pumps were inadvertently CLOSED.
With the above conditions, the following occurs:
- 1A DG is started and immediately fully loaded.
If the 1A DG is burning fuel at 6.7 gpm, it should be expected to run out of fuel in approximately:
- a. 45 to 60 seconds.
- b. 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- c. 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- d. 24 to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
QUESTION: 050 (1.00)
Given:
- Unit 2 at 100% power, normal alignment.
- A SAT 242-1 lockout occurs.
Proper 2B D/G and sequencer operation can be verified if the:
- a. 2B CV pump breaker CLOSED light on 2PM05J is lit within 10 seconds.
- b. 0B VC Chill Water pump RUN light on 0PM02J is lit after 25 seconds.
- c. 2B and 2D RCFC High Speed breaker CLOSED lights are lit on 2PM06J after 30 seconds.
- d. 2B AF pp RUN light is lit on 2PM05J within 45 seconds.
SENIOR REACTOR OPERATOR Page 43 QUESTION: 051 (1.00)
Given:
- Both Units at 100%, normal alignment.
- 0A VC running.
The following occurs:
- 0PR31J Control Room Outside Air Intake (Train A) is inadvertently shutdown.
The crew initiates actions to restore.
If while 0PR31J is shutdown, a 0PR32J, Control Room Outside Air Intake (Train A) detector fails its Check Source test, the RM-11 monitor indication for the affected 0PR32J channel will turn from Green to ____(1)____. In addition, per the associated BwAR for 0PR32J, the NSO must verify the ____________(2)__________.
_________(1)_______ ______________(2)_____________
- a. BLUE (Operate Failure) 0A VC Makeup Fan is RUNNING
- b. CYAN (Equipment Failure) 0A VC Normal Supply Fan is SHUTDOWN
- c. BLUE (Operate Failure) MCR Office Fans 0VV01CA and CB are RUNNING
SENIOR REACTOR OPERATOR Page 44 QUESTION: 052 (1.00)
Given:
- Unit 1 in MODE 3.
- Unit 2 at 100% power, normal alignment.
- OC WS pump is OOS.
Which of the following events will result in TOTAL loss of WS flow?
- a. SAT 142-1 Lockout.
- b. 4Kv Buses 143 and 244 feed BRKRs Trip and Lockout.
- c. SAT 242-1 Lockout.
- d. 4Kv Buses 144 and 243 feed BRKRs Trip and Lockout.
QUESTION: 053 (1.00)
Unit 1 SAC is fed from 4 KV Bus __(1)__. Unit 2 SAC is fed from 4 KV Bus __(2)__.
__(1)__ __(2)__
- a. 144 243
- b. 143 244
- c. 144 244
- d. 143 243
SENIOR REACTOR OPERATOR Page 45 QUESTION: 054 (1.00)
The BwAR for Annunciator 1-1-B2, CNMT HATCH DOOR SEAL TROUBLE lists the 3 alarm inputs as coming from:
- SUPPLY AIR PRESSURE HIGH.
- SUPPLY AIR PRESSURE LOW.
- SUPPLY AIR FLOW HIGH.
If the CNMT HATCH DOOR SEAL TROUBLE annunciator came in due to high air FLOW and low air PRESSURE, then cleared 8 minutes later, which of the following should be considered valid?
- a. Containment Hatch Air Lock Door interlock has failed.
- b. The Containment Overall Leakage Rate has increased.
- c. Personnel have just passed through the Air Lock Doors.
- d. A Containment Hatch Air Lock is INOPERABLE.
QUESTION: 055 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
- Running SX pump suction temperature is 95°F.
- The CNMT ISOL PHASE A switch on 1PM06J is inadvertently placed in the "ACTUATE" position.
- All equipment functions as designed.
With the above conditions and NO operator actions over the next 10 minutes, the Unit 1 NSO should expect to see Unit 1:
- b. PZR level LOWERING.
- c. CV letdown flow RISING.
- d. Containment pressure RISING.
SENIOR REACTOR OPERATOR Page 46 QUESTION: 056 (1.00)
Given the following on Unit 2:
- RCS pressure is 1485 psig, CETCs are 525°F.
- All RCPs are running.
- RVLIS Head level is indicating 31%.
- RVLIS Plenum level is indicating 81%.
With the above conditions, actual Unit 2 RVLIS HEAD level is between ___(1)___ , Unit 2 RVLIS PLENUM level ___(2)___ accurate.
__(1)__ ___(2)___
- a. 31-100% is
- b. 31-100% is NOT
- c. 0-31% is NOT
- d. 0-31% is
SENIOR REACTOR OPERATOR Page 47 QUESTION: 057 (1.00)
Given the following conditions on Unit 1:
- 100% power, EOL.
- PDMS is INOPERABLE.
The following occurs:
- A Unit 1 Main Turbine load reduction is initiated due to problems with the 1C FW pump recirc valve.
- Upon completion of the U1 Main Turbine load reduction the following conditions are noted:
Unit 1 power (Thermal) is 90%.
Annunciator 1-10-B6 ROD BANK LOW INSERTION LIMIT is fast flashing.
Annunciator 1-10-C6 ROD BANK LO-2 INSERTION LIMIT is clear.
AFDs indication for N41-N44 are -22.0, -22.2, -18.5, -18.5 (respectively).
Boration is in progress.
Currently, with the above conditions, per Technical Specifications, and referring to attached COLR Figure 2.8.1, the crew must enter TS:__(1)__.
- TS 3.1.6 CONTROL BANK INSERTION LIMITS for control bank insertion limits NOT met.
- TS 3.2.3 AXIAL FLUX DIFFERENCE for AFD NOT within limits.
This action statement currently require(s) that the crew:__________(2)__________.
__(1)__ _______________(2)_____________
- a. 3.1.6 continue to borate, restore rods above the RIL immediately
- b. 3.2.3 reduce power to less than 50% immediately
- c. 3.2.3 reduce power to less than 50% within 30 minutes
- d. 3.1.6 continue to borate, restore rods above the RIL within 30 minutes
SENIOR REACTOR OPERATOR Page 48 QUESTION: 058 (1.00)
Given the following conditions on Unit 2:
- CORE EXIT THERMOCOUPLES (2TI-IT001/2) on 2PM05J both indicate 350°F.
If a CETC Hot Junction Thermocouple begins to fail "OPEN", the applicable CETC display on 2PM05J will begin ___(1)___. As the failed "OPEN" Hot Junction Thermocouple
_____(2)_____, the CETC display will flash and return to 350°F as the circuit ignores the bad input.
___(1)___ _____(2)_____
- a. DROPPING approaches 50F
- b. DROPPING drops below 35F
- c. RISING exceeds 2300F
- d. RISING approaches 1200F QUESTION: 059 (1.00)
Given:
- A Unit 1 RCS LOCA and Containment Spray Actuation have occurred.
- ALL U1 ESF equipment has functioned as designed.
- NO U1 ESF signals have been reset.
The MINIMUM action(s) the crew must perform in order to allow 1CS019A, EDUC 1A SPRAY ADD VLV to CLOSE and remain CLOSED, is/are to reset the U1 Train A:
- a. SI Signal, and then reset the U1 Train A Containment Spray Actuation Signal.
- b. Containment Spray Actuation Signal, only.
- c. Containment Isolation Phase B Signal, only.
- d. SI Signal, and then the U1 Train A Containment Isolation Phase B Signal.
SENIOR REACTOR OPERATOR Page 49 QUESTION: 060 (1.00)
The Containment Hydrogen Recombiners, in conjunction with the _______(1)_______are designed to maintain Containment Hydrogen concentration below _(2)_ % following a design basis accident.
________(1)_______ _(2)_
- a. Reactor Cavity vent fans 2
- b. RCFCs 4
- c. CRDM vent fans 5
- d. CNMT Spray system 8 QUESTION: 061 (1.00)
Given the following conditions on Unit 1:
- Reactor power at 100%, normal alignment.
- Post LOCA Purge is being used to reduce Unit 1 Containment pressure.
The following occurs:
- Annunciator 0-33-E3, POST LOCA PURGE EXH FAN TRIP DP/FLOW LOW alarms.
- 1VQ03C, U1 POST LOCA PURGE EXHAUST FAN is verified to still be running.
Adjustment of 1VQ03C flowrate is accomplished by throttling 1VQ013Y, POST LOCA PURGE FAN EXHAUST DISCH DAMPER ___(1)____. If 1AR011, CONTAINMENT FUEL HANDLING INCIDENT (Train A) Rad Monitor fails HIGH, the crew should expect to find 1VQ03C __(2)__.
___(1)___ ___(2)___
- a. locally RUNNING
- b. at 0PM02J TRIPPED
- c. at 0PM01J RUNNING
- d. locally TRIPPED
SENIOR REACTOR OPERATOR Page 50 QUESTION: 062 (1.00)
Given:
- The Fuel Handling Building Crane area radiation monitor, 0RE-AR039, is alarming at 150 mrem/hr.
Based on the above indications (ONLY), the:
- a. Spent fuel pit bridge crane hoist will stop upward motion.
- b. Fuel Handling Building crane hoist will stop upward motion.
- c. Charcoal Booster fan for the in-service FHB plenum will start.
- d. Fuel Handling Building ventilation will isolate.
SENIOR REACTOR OPERATOR Page 51 QUESTION: 063 (1.00)
With Unit 2 initially at 100%, normal alignment, the following occurs:
- 2A S/G faults outside containment upstream of the 2A MSIV.
- An automatic SI occurs.
- All equipment functions as designed and the crew progresses through the appropriate procedures.
Currently:
- 2A S/G pressure is DROPPING (currently at 300 psig).
- U2 RCS pressure is 1930 psig and RISING.
- The crew is performing the steps necessary to terminate SI.
The automatic U2 SI was caused by actuation of (as indicated on the appropriate 2PM04J TSLB status lights) "S/G 2A _____(1)_____" bistables. An indication that the 2A SG has RUPTURED (in addition to the fault), would be indicated by U2 ECCS High head flow
____(2)____ .
_____(1)_____ ____(2)____
- a. LO PRESS LOWERING
- b. LO PRESS STABILIZING
- c. HI PRESS RATE LOWERING
- d. HI PRESS RATE STABILIZING
SENIOR REACTOR OPERATOR Page 52 QUESTION: 064 (1.00)
Given the following initial conditions:
- Unit 1 at 100% power, normal alignment.
Consider the following two cases SEPARATELY:
A) Unit 1 Main Turbine/Generator Bearing Oil pressure falls to 5 psig.
B) Unit 1 Main Turbine/Generator Thrust Bearing Wear pressure reaches 85 psig.
With the above conditions, the Unit 1 NSO can expect that the indications on 1PM01J for OCBs 1-8 and 7-8, MAIN TRANSFORMER FEEDs to 345Kv SWYD will change from CLOSED to OPEN in approximately _(1)_ second(s) in Case "A)" and approximately _(2)_ second(s) in Case "B)".
_(1)_ _(2)_
- a. 1 1
- b. 30 1
- c. 1 30
- d. 30 30
SENIOR REACTOR OPERATOR Page 53 QUESTION: 065 (1.00)
Given:
- Both Units at 100% power.
- Both the CC and SX sides of the "0" CC Hx are aligned to Unit 1.
- 2A SX pump is tagged out for cleaning of the 2A SX Strainer.
The following occurs:
- Grid problems cause both Main Generators to trip and a loss of ALL Off Site power on BOTH units.
- 2B Diesel Generator starts but, mechanically fails before its output breaker closes.
- All other equipment on BOTH units function as designed.
With the above conditions, and assuming ONLY the action(s) listed in ONE of the choices below is/are taken, Unit 2 SX flow can be re-initiated by:
SENIOR REACTOR OPERATOR Page 54 QUESTION: 066 (1.00)
Given the following Unit 1 conditions:
- Startup in progress.
- Core Burnup 3590.7 EFPH.
- 8 fold count rate has just been reached.
- Control Bank C is at 180 steps.
The U1 US has requested that the Unit Assist NSO determine the Estimated Critical Bank Position. If the NSO obtains BwCB-1 Fig 9, ESTIMATED CRITICAL POSITION from the "Curve Book" at the U1 NSO desk, per RM-AA-102, CONTROL OF DOCUMENTS, a "revision check" of this figure __(1)__ be required. Referring to the attached copy of BwCB-1 Fig 9 and the conditions above, the Assist NSO should report that U1 will go critical when CB D reaches _(2)_ steps.
__(1)__ _(2)_
- a. will 125
- b. will 105
- c. will NOT 105
- d. will NOT 125 QUESTION: 067 (1.00)
With Unit 1 in MODE 1, which of the following U1 conditions would require LCO entry?
- a. Pressurizer Level at 82%.
- b. RCS Tavg at 594°F.
- c. Containment Pressure at 0.85 psig.
- d. Pressurizer Pressure at 2215 psig.
SENIOR REACTOR OPERATOR Page 55 QUESTION: 068 (1.00)
Given:
- Unit 2 at 20% power.
- The U2 US has directed the 2FW009s be OPENED.
When opening 2FW009A, LOOP 2A (FW Isolation Valve) the operator MUST hold the C/S on 2PM06J in OPEN:
- a. until the WHITE light between the position indicators is OUT. If the switch is released before the WHITE light is OUT, the valve will return to the CLOSED position.
- b. until the CLOSED indicator light is OUT. If the switch is released before the CLOSED indicator is OUT, the valve will return to the CLOSED position.
- c. just until the OPEN indicator light is lit, the switch may then be released and the valve will travel fully OPEN.
- d. just until the WHITE light between the position indicators is lit, the switch may then be released and the valve will travel fully OPEN.
QUESTION: 069 (1.00)
Which of the following jobs would require submittal of Temporary Configuration Change Paperwork prior to the work being performed?
- a. A gag is required to be installed on the U1 CV Letdown Relief to stop spurious lifting during normal operations.
- b. A clamp on ammeter is to be installed to monitor pump amps during pump start as part of troubleshooting for a WR.
- c. Tygon tubing is required to be attached to the U2 RH pump suction piping per the RH system drain procedure.
- d. An electrical jumper is to be placed in a components start circuit as part of a surveillance procedure to prevent inadvertent auto start.
SENIOR REACTOR OPERATOR Page 56 QUESTION: 070 (1.00)
A final clear of a Clearance Order on the 1B CW pump is to be processed. Which of the following cards must be removed FIRST?
- a. Master clearance tag.
- b. Personal protection tag(s).
- c. Power supply danger tag(s).
- d. Control switch danger tag(s).
QUESTION: 071 (1.00)
The Exelon Administrative dose guideline for TEDE is __(1)__ mRem/yr. When exiting a contaminated area an operator should: ______________(2)________________.
_(1)_ ______________(2)________________
- a. 2000 use the closest contamination monitor
- b. 3000 remove gloves first then rubber shoe covers
- c. 3000 use the closest contamination monitor
- d. 2000 remove gloves first then rubber shoe covers
SENIOR REACTOR OPERATOR Page 57 QUESTION: 072 (1.00)
Due to lowering Oxygen levels in Unit 1 Containment, RP has requested Mini Purge Supply and Exhaust be placed in service. Before placing U1 Mini Purge Exhaust in service, a ____(1)____
Exhaust Fan must be running. When starting the U1 Mini Purge Supply Fan, the fan C/S must be held in "start" until the ___________(2)___________ fully OPEN or the fan will NOT start.
____(1)_____ _______________(2)_____________
- a. Lab HVAC Purge Supply containment isolation valves
- b. Aux Bldg (for U1 Vent Stack) fan suction damper locally indicates
- d. Rad Waste Bldg Purge Supply containment isolation valves
SENIOR REACTOR OPERATOR Page 58 QUESTION: 073 (1.00)
Given the following U1 conditions:
- 1SI8801A and B (CHG PMPS TO COLD LEGS INJ ISOL) are CLOSED. Action has been initiated to attempt to open the valves.
- All other equipment has functioned as designed.
- 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT has just been entered.
- Following the transition brief, the NSO notes that annunciator 1-5-A7, CNMT PHASE B ISOLATION is fast flashing.
- SPDS Iconic indication for U1 Containment pressure indicates 18 psig.
Based on the above conditions, the NSO can verify that the U1 Phase B Isolation occurred at the appropriate setpoint by checking the Containment Pressure recorder on __(1)__. Following verification that the Phase B actions have occurred, the NSO must: __________(2)_________
__(1)__ ___________________(2)________________________
- a. 1PM05J leave ALL RCPS RUNNING due to the lack of High Head Injection flow
- d. 1PM04J leave ALL RCPS RUNNING due to the lack of High Head Injection flow
SENIOR REACTOR OPERATOR Page 59 QUESTION: 074 (1.00)
The following U1 indications are observed after a U1 reactor trip from 100% power, normal alignment:
Time after trip 1Min 2Min 3Min 4Min PZR level % 30 10.8 0 0 RCS pressure psig 1964 1808 1708 1627 S/G levels % (WR) (all) 54 52 50 48 S/G pressures psig (all) 950 770 610 500 Containment pressure psig 10.6 18.1 23.0 25.1 RCP flow % (all) 100 0 0 0 Assuming that Emergency Operating procedure operator actions were performed ONLY when required and that ALL ECCS equipment functioned as designed, based on the above indications, the transient(s) that has/have occurred is/are:
- c. four S/Gs have faulted inside Containment followed by a Loss of Offsite power
- d. four S/Gs have faulted inside Containment ONLY
SENIOR REACTOR OPERATOR Page 60 QUESTION: 075 (1.00)
The intent of the major action steps performed in 1BwFR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION are to:
QUESTION: 076 (1.00)
Given the following sequence of events on Unit 1:
- 100% power, normal alignment.
- An SI occurs due to Low PZR pressure.
- 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION has been entered.
2 minutes later, the following U1 conditions are noted:
- PZR pressure is continuing to LOWER.
- PZR Level is RISING.
- RCS Tavg is 560°F.
- Containment pressure is stable.
Based on the above conditions, the US should direct an NSO to check _______(1)_______.
The NEXT procedure required to be entered in response to this event is ______(2)_______.
_________(1)_________ _______(2)______
- b. Aux Building Rad levels 1BwCA-1.1, LOSS OF EMERGENCY on RM-11 COOLANT RECIRCULATION
SENIOR REACTOR OPERATOR Page 61 QUESTION: 077 (1.00)
Given the following Unit 1 conditions:
- RCS temp stable at 305°F.
- PZR Level stable at 35%.
- 1D RCP is running.
- All U1 NR S/G levels are 50%.
- 1A RH pump running in Shutdown Cooling mode.
- 1B RH pump in standby (ECCS Injection mode).
- All Steam Dumps and S/G PORVs are closed.
The following occurs:
- 1TI-604, RH HX 1A RTRN TEMP indicator on 1PM06J begins RISING.
- Followed by indication that 1TE-0612, (1A RH) PP DSCH TEMP recorder indicator on 1PM06J is also RISING.
- 1RH606, HX 1A FLOW CONT VLV controller is adjusted, but NO effect is noticed on 1A RH system temperatures. Based on the above conditions
_____(1)____. The NEXT procedure that should be entered is ____(2)___ .
________(1)________ ____________________(2)_________________
- b. CC flow has been lost BwOP RH-6, PLACING THE RH SYSTEM IN to the 1A RH HX SHUTDOWN COOLING to place the 1B RH pump in service
- c. IA has been lost BwOP RH-6, PLACING THE RH SYSTEM IN to 1RH606 SHUTDOWN COOLING to place the 1B RH pump in service.
- d. IA has been lost 1BwOA PRI-10, LOSS OF RH COOLING to 1RH606
SENIOR REACTOR OPERATOR Page 62 QUESTION: 078 (1.00)
Given:
- Both Units at 100% power, normal alignment.
- Unit 0 CC HX aligned to Unit 1.
- 0 CC pump is mechanically and electrically aligned to U1.
A large break U1 RCS LOCA occurs.
- All U1 equipment initially functions as designed.
- Steps necessary to place both trains of ECCS equipment in Recirc Mode have been completed.
- A leak in the CC piping upstream of the inlet valve to the 1A RH Heat Exchanger is identified.
With the above conditions:
- BwOP _____(1)_____ (ONLY) should be performed to recover/maintain 1 Train of Unit 1 CC Surge Tank level.
- Following U1 CC train separation, repair of the leak, and the 1A and 0 CC pumps running, the 0 CC pump will have __(2)__ portion of the U1 CC surge tank aligned.
__________(1)__________________ ____(2)____
- a. CC-8, ISOLATION OF CC BETWEEN the A Train UNITS 1 AND 2.
- d. CC-8, ISOLATION OF CC BETWEEN the B Train UNITS 1 AND 2.
SENIOR REACTOR OPERATOR Page 63 QUESTION: 079 (1.00)
Given the following sequence of events:
- Unit 2 initially at 100% power.
- PZR PORV, 2RY455A fails OPEN.
- An ATWS condition is identified.
- The immediate actions of 2BwFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS have been performed and the crew is continuing on in the procedure.
- Closure of 2RY455A and 2RY8000A, PZR PORV BLOCK VALVE is attempted by the RO with NO change in status.
With the above conditions, step 10 of 2BwFR-S.1, Verify All Dilution Paths Isolated _(1)_ be performed with Main Control Room Actions ONLY. Assuming that 2RY455A CANNOT be isolated and that the U2 Reactor is locally tripped, the NEXT procedure that will be entered is:
_________(2)_________.
_(1)_ ___________________(2)_______________________
- a. can 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION
- b. can NOT 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION
SENIOR REACTOR OPERATOR Page 64 QUESTION: 080 (1.00)
Which of the following events meets the requirements to perform a Site Assembly?
(EP-AA-1001, Braidwood Annex, is available)
- a. U2 in MODE 5, when a loss of Unit 2 Offsite Power occurs followed by the inability to energize 241 or 242 for 65 minutes.
- b. U1 is stable in MODE 3, when both RH pumps are determined to be INOPERABLE.
- c. U2 in MODE 2, when the reactor fails to automatically trip, manual trip is successful.
- d. U1 in MODE 2, when a loss of Unit 1 offsite power occurs followed by the inability to energize 141 or 142 for 20 minutes.
SENIOR REACTOR OPERATOR Page 65 QUESTION: 081 (1.00)
Given:
- Unit 1 at 100% power, normal alignment.
An event occurs:
- Power Range NI N41, Intermediate Range NI N35 and Source Range NI N31 are ALL determined to be DE-energized.
- ALL other NI Channels are energized.
- ALL S/G levels are verified stable.
- Multiple annunciators are present and several recorders are DE-energized.
Based on the above conditions, 1BwOA _______(1)______ should be entered. Power should be restored to Intermediate NI Channel, N35 when:________(2)_______.
_____________(1)___________ _________(2)_______________
- a. ELEC-1, LOSS OF DC BUS DC Bus 111 is crosstied to DC Bus 211 by closing the Cross Tie Breakers in the 111 and 211 Battery rooms
- b. ELEC-2, LOSS OF INSTRUMENT BUS Instrument Bus 111 panel in the AEER is transferred to the Reserve Feed and the 111 CVT is energized
- c. ELEC-2, LOSS OF INSTRUMENT BUS Instrument Bus 113 panel in the AEER is transferred to the Reserve Feed and the 113 CVT is energized
- d. ELEC-1, LOSS OF DC BUS DC Bus 112 is crosstied to DC Bus 212 by closing the Cross Tie Breakers in the 112 and 212 Battery rooms
SENIOR REACTOR OPERATOR Page 66 QUESTION: 082 (1.00)
Given:
- An event has occurred on Unit 1.
- The crew is currently in 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
The STA notes the following Unit 1 conditions:
- RCS subcooling is 0°F.
- CETCs indicate 1050°F.
- IR SUR + 0.1 dpm.
- PR NIs all at 1%.
- ALL NR S/G levels at 4%.
- Max attainable AF flow: 300 gpm.
- Containment Pressure is 52 psig.
Based on the above, the US should immediately enter:
- a. 1BwFR-S.1, RESPONSE TO NUCLEAR GENERATION/ATWS.
- b. 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
- c. 1BwFR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE.
- d. 1BwFR-C.1, RESPONSE TO INADEQUATE CORE COOLING.
SENIOR REACTOR OPERATOR Page 67 QUESTION: 083 (1.00)
Given the following conditions on Unit 1:
- 90% power, normal alignment.
- Control Bank D rods are at 215 steps.
An event occurs and the following Unit 1 indications are noted:
- Control Bank D Rods are automatically stepping OUT.
- T-ref indication on 1TR-412 on 1PM05J is failed HIGH at 592°F.
- ALL other MCB indications are normal.
With the above conditions and NO operator action, Unit 1 Control Bank D rods will step until
_(1)_ is reached. The US should enter 1BwOA _____________(2)_____________.
_(1)_ __________________(2)__________________
- a. C-3 INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL
- b. C-4 ROD-1, UNCONTROLLED ROD MOTION
- c. C-5 INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL
- d. C-11 ROD-1, UNCONTROLLED ROD MOTION
SENIOR REACTOR OPERATOR Page 68 QUESTION: 084 (1.00)
Given:
- Unit 2 in MODE 3.
- Instrument Bus 212 is being powered from its CVT.
- SAT 242-1 faults.
- 2A DG fails to start.
- All other equipment functions as designed.
With the above conditions and assuming NO operator action, 5 minutes later, U2 Source Range indication at 2PM05J will be available from:___(1)___. The US should enter ______(2)_____.
____(1)____ _______________(2)________________
- b. N32 ONLY 2BwOA ELEC-4, LOSS OF OFFSITE POWER
- d. N32 ONLY 2BwOA INST-1, NUCLEAR INSTRUMENTATION MALFUNCTION
SENIOR REACTOR OPERATOR Page 69 QUESTION: 085 (1.00)
Given the following sequence of events:
- Unit 1 is in a refueling outage.
- While lifting an assembly out of the U1 Reactor Vessel into the manipulator crane, a fault in the manipulator crane controller causes it to continue lifting the assembly past the upper limit until the cables break.
- Upon hitting the lower core support plate, the assembly falls over into the sides of several other assemblies.
- A large amount of bubbles are seen coming from the dropped assembly and the damaged (in place) assemblies.
The NEXT action the Fuel Handling SRO should take is to:
- a. notify RP to monitor U1 Containment Radiation levels.
- b. direct the placement of any fuel assembly in the U1 Containment Upender be placed in the RCCA change fixture.
- c. inform the MCR to initiate Unit 1 Containment closure.
- d. inform the MCR to evacuate Unit 1 Containment.
SENIOR REACTOR OPERATOR Page 70 QUESTION: 086 (1.00)
Given:
- Both units at 100% power, normal alignment.
The following occurs:
- Annunciator 0-33-D7, MCR IONIZATION alarms.
- Annunciator 0-37-A4, UNIT 1 AREA FIRE alarms.
- Visible smoke is seen in the Unit 1 end of the Main Control Room.
Based on the above conditions, the FIRST procedure to be immediately entered is: _(1)_ BwOA PRI-5 CONTROL ROOM INACCESSIBILITY. BwAR 0-37-A4, UNIT 1 AREA FIRE will direct actions to prevent losing U1 ______(2)_________ , IF the fire is in an affected area.
_(1)_ __________________(2)___________________
- b. 1 CV pump suction due to inadvertent VCT Outlet Valve CLOSURE
- d. 0 CV pump suction due to inadvertent VCT Outlet Valve CLOSURE
SENIOR REACTOR OPERATOR Page 71 QUESTION: 087 (1.00)
Given:
- An RCS LOCA has occurred on Unit 2.
Currently, the U2 US is briefing the crew that per 2BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT step 12b, they are transitioning to 2BwEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION. During the brief, the U2 Admin NSO reports that annunciator 2-6-B7, RWST LEVEL LO-2 has just alarmed and the STA reports an ORANGE path on Core Cooling exists. Based on the above information, the US should implement step 1 of _____________ immediately.
- b. 2BwFR-C.2, RESPONSE TO DEGRADED CORE COOLING
- c. 2BwEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION
- d. 2BwFR-C.1, RESPONSE TO INADEQUATE CORE COOLING QUESTION: 088 (1.00)
Given:
- Unit 1 RCS at 557°F, 2235 psig.
- Preparations are being performed for a U1 Reactor Start-up.
- An NLO performing rounds has found that 1RH618, 1A RH HX FLOW CONTROL BYPASS VALVE has a broken Instrument Air supply line.
Per Technical Specification Bases and with the above conditions, Unit 1 A train ECCS is:
- a. OPERABLE, 1RH618 fails CLOSED on a loss of air and this position is proper for all modes of ECCS operation.
- b. INOPERABLE, 1RH618 fails CLOSED and must be able to be opened for proper flow during ECCS injection.
- c. OPERABLE, 1RH618 fails OPEN on a loss of air to ensure a flow path is available during ECCS injection.
- d. INOPERABLE, 1RH618 fails OPEN on a loss of air and must be able to be closed to ensure core cooling during ECCS recirculation phase.
SENIOR REACTOR OPERATOR Page 72 QUESTION: 089 (1.00)
Given:
- Unit 1 has recently entered MODE 3 from MODE 4.
- U1 RCS pressure is 2235 psig, temperature is 557°F.
- Due to an error, both U1 SI pump control switches were inadvertently left in "Pull Out" following the mode change.
With the above conditions, and NO operator action, if an intermediate break U1 RCS LOCA and subsequent SI occurred, actual U1 High Head Injection flow would be expected to be ___(1)___
(than if the SI pumps were available) when RCS pressure initially stabilizes. For certain intermediate size RCS LOCAs where neither SI pump can be restored ______(2)______ would be expected to be entered.
__(1)__ _________________(2)___________________
- b. LOWER 1BwCA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION
- c. HIGHER 1BwFR-C.2, RESPONSE TO DEGRADED CORE COOLING
- d. LOWER 1BwFR-C.2, RESPONSE TO DEGRADED CORE COOLING
SENIOR REACTOR OPERATOR Page 73 QUESTION: 090 (1.00)
Given:
- Both Units at 100% power, normal alignment.
- 1A DG is in synchronized to the grid for a monthly surveillance run.
During a board walk down, the on-coming U1 Unit Supervisor notes the following switch positions/indications on 1PM01J:
- DG 1A FEED TO 4KV BUS 141 control switch is in NAC.
- DG 1A ACB 1413 AUTO RE-CLOSE CIRCUIT ARM selector switch is in NORMAL.
- DG 1A EMER MODE SPEED/VOLT CONTROL selector switch is in AUTO.
- DIESEL GEN 1A START control switch is in NAC.
- 1JI-DG002, DIESEL GEN 1A OUTPUT WATTS are 5450 Kw.
- 1VI-DG004, DIESEL GEN 1A OUTPUT VARS are 450 Kvar OUT.
- 1II-DG001, DIESEL GEN 1A OUTPUT CURRENT is 766 amps.
Based on the above indications, the on-coming U1 Unit Supervisor should:
- a. direct the Unit 1 NSO to LOWER 1A DG voltage, the 1A DG continuous amp rating limit is being exceeded.
- b. direct the Unit 1 NSO to LOWER 1A DG frequency, the 1A DG continuous amp rating limit is being exceeded.
- c. declare the 1A DG INOPERABLE, 1A DG speed and volt control will NOT transfer to isochronous if a U1 SI and loss of offsite power occur.
- d. declare the 1A DG INOPERABLE, the 1A DG output breaker will NOT reclose if a U1 SI and loss of offsite power occur.
SENIOR REACTOR OPERATOR Page 74 QUESTION: 091 (1.00)
Per TS bases, if an RCS leak develops and slowly increases in size, the process radiation detectors used for Containment atmosphere monitoring at Braidwood must be able to INITIALLY detect the leak (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) when the leakrate is GREATER than or equal to _(1)_ gpm. With Unit 1 at 100% power, normal alignment, if a spurious HIGH alarm is received on the 1PR11J, CONTAINMENT ATMOSPHERE process radiation monitor gaseous channel, TS 3.4.15, RCS Leakage Detection Instrumentation __(2)__ required to be entered.
(Assume all equipment functions as designed.)
_(1)_ __(2)__
- a. 1 is
- b. 0.5 is
- c. 0.5 is NOT
- d. 1 is NOT QUESTION: 092 (1.00)
Given:
- Unit 2 plant startup in progress.
- U2 Reactor power at 8%.
- U2 Main Turbine speed 250 rpm and rising.
- All conditions normal for this point in the startup.
If a loss of offsite power occurs, the NEXT procedure the U2 Unit Supervisor should implement is:
- a. 2BwGP 100-5, PLANT SHUTDOWN AND COOLDOWN.
- b. 2BwOA TG-8, TURBINE TRIP BELOW P8.
- c. 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
- d. 2BwOA ELEC-4, LOSS OF OFFSITE POWER.
SENIOR REACTOR OPERATOR Page 75 QUESTION: 093 (1.00)
Given:
- A 600 gpm steam generator tube rupture has occurred on the 1A S/G.
- NO other U1 equipment has malfunctioned.
- The crew has progressed through the appropriate procedures and is currently about to initiate the cooldown step in 1BwEP-3, STEAM GENERATOR TUBE RUPTURE.
With the above conditions, if the U1 RCS cooldown is initiated using the intact S/G PORVs (instead of the Steam Dumps) the ________(1)________ will be GREATER. While performing the 1BwEP-3 cooldown with Steam Dumps, as RCS Tavg approaches 552°F, the operators should place and hold both BYPASS INTERLOCK switches on 1PM02J in ___(2)___ until RCS Tavg on 2 loops is LESS than annunciator 1-14-C1, TAVE LO-2 ALERT setpoint.
_______(1)_______ ___(2)__
- a. RCS cooldown rate OFF/RESET
- b. potential off site dose BYPASS
- c. RCS cooldown rate BYPASS
- d. potential off site dose OFF/RESET
SENIOR REACTOR OPERATOR Page 76 QUESTION: 094 (1.00)
Given the following Unit 1 conditions:
- RCS temperature is 195°F, cooling down.
- 1B CV pump is running.
- RWST level 87%.
- RWST boron concentration is 2320 ppm.
The following components are Danger Tagged in the positions described for Low Temperature Overpressure (LTOP). Assume ALL other associated equipment is in its normal MODE 5 alignment.
- 1A CV pump C/S in PTL, 1SI8801A, CHG PMPS TO COLD LEGS INJ ISOL VLV is CLOSED.
- 1A SI pump C/S in PTL, 1SI8921A, 1A SI PUMP MANUAL DISCHARGE valve is CLOSED.
- 1B SI pump C/S in PTL, 1B SI pump Breaker is RACKED OUT.
- ALL U1 Accumulator outlet valves CLOSED with power removed.
- U1 PDP C/S is in PTL, U1 PDP pump Breaker is RACKED OUT.
With the above conditions, the U1 Unit Supervisor should enter Technical Specification:
- a. 3.4.12, LTOP, due to 1A CV pump/1SI8801A status.
SENIOR REACTOR OPERATOR Page 77 QUESTION: 095 (1.00)
A Licensed SRO must be present to directly supervise which of the following evolutions?
- 1. Reactor Vessel Head lift.
- 2. Control Rod Drive unlatching.
- 3. Upper Internals lifting.
- 4. When beginning core reload, a NEW assembly is lowered below the Vessel flange.
- a. 3&4
- b. 1&2
- c. 2&4
- d. 1&3 QUESTION: 096 (1.00)
Given:
- Unit 2 is in a refueling outage with core ON-load in progress.
Consider each situation below separately. Assume all other plant equipment is OPERABLE (where applicable). Which of the following situations would require U2 Core Alterations be STOPPED?
- a. Instrument buses 213 and 214 are being powered by their respective CVTs.
Instrument Inverters 213 and 214 are declared INOPERABLE.
- b. SR Channel N-31 unexpectedly rises from 3 counts/second to 12 counts/second following loading of the 15th fuel assembly.
- c. 0A and 0B Control Room Ventilation Makeup Filtration trains have been declared INOPERABLE.
- d. All SR NIs unexpectedly rise from 10 counts/second to 17 counts/second following loading of the 15th fuel assembly.
SENIOR REACTOR OPERATOR Page 78 QUESTION: 097 (1.00)
Given the following sequence of events:
- The Temperature Control Valve (TCV) for the U1 Hydrogen Seal Oil System Air Side Seal Heat Exchanger fails OPEN due to a controller malfunction.
- The TCV Bypass is throttled OPEN and the TCV upstream isolation is CLOSED to return Air Side Seal Oil temperatures to normal.
Tracking of the U1 Hydrogen Seal Oil system Air Side Seal Heat Exchanger TCV Bypass and Upstream isolation valve status will be accomplished by:
- a. "Temporary Modification" tags hung on the TCV Inlet Isolation and Bypass valves.
- b. a "Deficiency Tag" hung on the TCV that will direct the Bypass and Inlet valves be returned to their normal positions when the TCV is repaired.
- c. "Equipment Status Tags" hung on the Bypass and Inlet valves explaining the status and listing the requesting individual.
- d. "Danger Tags" hung on the TCV Inlet and Bypass Valve under an Admin Clearance.
SENIOR REACTOR OPERATOR Page 79 QUESTION: 098 (1.00)
Per BwOP WX501T1, LIQUID RELEASE TANK 0WX01T RELEASE FORM, which of ONE of the following actions must be PERFORMED by a Shift Manager or Senior Reactor Operator prior to the release of 0WX01T, Liquid Release Tank?
- a. Verify that the actual circulating water blowdown rate is equal to or GREATER than 8000 gpm using the computer point or recorder on 0PM01J.
- b. Independently verify that the release tank INLET valve for the tank to be released is CLOSED.
- c. Calculate the initial MAXIMUM liquid release rate based on Chemistry and Rad Protection sample analysis.
- d. Independently verify at the RM-11 panel that 0RE-PR001, LIQUID RELEASE MONITOR Alert and High setpoints were adjusted per Rad Protection instructions in the release package.
QUESTION: 099 (1.00)
Which of the following events would require informing the NRC "immediately by ENS after notification of state and local agencies, but within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />"? (EP-AA-1001, Braidwood Annex, is available.)
- a. Unit 1 in MODE 3 when an unplanned loss of annunciators on the 1PM01J, 5J and 6J panels occurs for >15 minutes.
- b. Unit 2 in MODE 1 when a manual Reactor trip is initiated due to a loss of DC bus 212 for >15 minutes.
- c. Unit 2 in MODE 1, Unit 1 DEFUELED, when a Tornado/water spout is seen over the Braidwood lake.
- d. Both Units in MODE 1, an inadvertent gas release results in a 5.5x103 µCi/sec release for 72 minutes.
SENIOR REACTOR OPERATOR Page 80 QUESTION: 100 (1.00)
Given:
- An event has occurred on Unit 2.
Currently, the crew is transitioning out of 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
At the transition brief, the STA reports the highest critical safety function is a yellow path on Heat Sink. With the above conditions, the STA is required to scan status trees______(1)_____.
The U2 Unit Supervisor MUST transition to the ____________(2)____________.
______(1)_____ ____________________(2)__________________
- a. continuously Yellow Heat Sink Functional Restoration procedure
- b. every 10-20 minutes Yellow Heat Sink Functional Restoration procedure
- c. every 10-20 minutes Optimal Recovery Guideline specified by 2BwEP-0
- d. continuously Optimal Recovery Guideline specified by 2BwEP-0
(********** END OF EXAMINATION **********)
SENIOR REACTOR OPERATOR Page 81 Braidwood 2004 License Exam List of Student
References:
Question Number 20 Response to Nuclear Instrument Malfunction, 1BwOA INST-1 pages 9,10 (ONLY) REV 102 Question Number 25 TS 3.7.1-1 through -4 Question Number 33 Electrical Schematic Diagram for Pressurizer Relief Tank Primary Water & Nitrogen Supply Isolation Valves - 2RY8028& 2RY8033; Pressurizer Relief TNK. VENT. To Gas Analyzer Isolation Valves -2RY8025 &2RY8026. 20E-2-4030RY11 Question Number 36 Steam Tables/Mollier Diagram Question Number 57 U1 COLR Figure 2.8.1 Axial Flux Difference Limits with PDMS Inoperable Question Number 66 BwCB-1 Fig 9 Rev 15. Estimated Critical Position ( 4 pages)
Question Numbers 80, & 99 Radiological Emergency Plan Annex for Braidwood Station- EP-AA-1001 (entire annex)
SENIOR REACTOR OPERATOR Page 82 ANSWER: 001 (1.00) ANSWER: 005 (1.00) ANSWER: 010 (1.00)
- c. d. b.
REFERENCE:
REFERENCE:
REFERENCE:
1BwEP-0 rev 102: REACTOR ILT Lesson plan I1-CV-XL-01 1BwEP-3 Rev 100 ILT lesson TRIP OR SI CVCS page 29 plan I1-EP-XL-04 Rev 17 Big Note EF-1 Rev 10: HIGHER WOG Rev 1C Reactor Trip setpoints NEW HIGHER OP-AA-300 rev 0: Reactivity 000022AK104 ..(KAs) BANK Management Controls 000038EK103 ..(KAs)
HIGHER BANK ANSWER: 006 (1.00) 000007 2.4.49 ..(KAs) a. ANSWER: 011 (1.00)
REFERENCE:
c.
Big Note CC-1, Rev 7
REFERENCE:
ANSWER: 002 (1.00) HIGHER 1BwEP 2 Rev 1A Big Note
- d. NEW AF-1 Rev 6
REFERENCE:
000025AK203 ..(KAs) HIGHER ILT Lesson plan I1-CC-XL-01 NEW Rev 2 00WE12EA1.2 ..(KAs)
Big Note CV-1 Rev 5 ANSWER: 007 (1.00)
HIGHER b.
NEW
REFERENCE:
ANSWER: 012 (1.00) 000009EA207 ..(KAs) ILT Lesson plan I1-CC-XL-01 d.
rev 2
REFERENCE:
TS 3.7.7 amend 98 ILT lesson plans I1-MI-XL-08 ANSWER: 003 (1.00) HIGHER rev 15. I1-EP-XL-01 Rev 15.
- d. NEW HIGHER
REFERENCE:
2.2.22 000026 ..(KAs) NEW ILT lesson plans I1-EC-XL-01 000054AK305 ..(KAs)
Rev 3. I1-EP-XL-02 Rev 14.
MEMORY ANSWER: 008 (1.00)
NEW d. ANSWER: 013 (1.00) 000011EK305 ..(KAs)
REFERENCE:
d.
Big Note RY-2 rev 5
REFERENCE:
HIGHER ILT Lesson plan I1-CA-XL-01 ANSWER: 004 (1.00) NEW Rev 06
- b. 000027AA102 ..(KAs) MEMORY
REFERENCE:
BANK 1BwOA PRI-6 REV 101 000055EK302 ..(KAs)
MEMORY ANSWER: 009 (1.00)
BANK a. ANSWER: 014 (1.00) 000015AA208 ..(KAs)
REFERENCE:
b.
1BwEP-0 REV 102 step 1
REFERENCE:
1BwFR-S.1 REV 1A step 8 BwOP DC-7-211 Rev 3 Big 1BwEP ES-0.1 REV 103 step Note DC-1 Rev 5. 2BwOA 5 ELEC-1 Rev 100 HIGHER HIGHER MODIFIED NEW 000029EK206 ..(KAs) 000058AK101 ..(KAs)
SENIOR REACTOR OPERATOR Page 83 ANSWER: 015 (1.00) ANSWER: 020 (1.00) ANSWER: 025 (1.00)
- b. b. c.
REFERENCE:
REFERENCE:
REFERENCE:
BWD ILT Lesson plan 1BwOA INST-1 REV 102 TS 3.7.1 Amendment 128 I1-SX-XL-01. Big Note NI-3 rev 7 HIGHER MEMORY HIGHER MODIFIED BANK NEW 00WE13EA2.2 ..(KAs) 000062AA102 ..(KAs) 2.1.23 000033 ..(KAs)
ANSWER: 026 (1.00)
ANSWER: 016 (1.00) ANSWER: 021 (1.00) b.
- b. a.
REFERENCE:
REFERENCE:
REFERENCE:
OAS page for 1BwEP ES-1.2 BWD ILT LESSON Plan ILT Lesson plan I1-AR-XL-01 rev 103 I1-SA-XL-01 table 53-1 Rev 3 ILT Lesson plan BwAR 1-3-A7 Rev 8E4 P&ID M-64 Sheet 2 I1-WX-XL-01 Rev 1 BwOP HIGHER MEMORY CW-12 Rev 25 NEW NEW HIGHER 00WE03EK1.3 ..(KAs) 000065AA208 ..(KAs) NEW 000059AA103 ..(KAs)
ANSWER: 027 (1.00)
ANSWER: 017 (1.00) d.
- c. ANSWER: 022 (1.00)
REFERENCE:
REFERENCE:
- d. BWD ILT Lesson Plan Big Notes ECCS-2 Rev 6,
REFERENCE:
I1-EP-XL-01 Rev 15 WOG EF-2 Rev 8 BwAR 4-0AR057J Rev 2 Background ES 0.2 MEMORY MEMORY MEMORY NEW NEW NEW 00WE04EK2.1 ..(KAs) 000061AK302 ..(KAs) 2.1.27 00WE09 ..(KAs)
ANSWER: 018 (1.00) ANSWER: 023 (1.00) ANSWER: 028 (1.00)
- b. b. c.
REFERENCE:
REFERENCE:
REFERENCE:
1BwCA-1.1 Rev 102 ILT Lesson plan I1-VX-XL-01 2BwAR 2-11-A5 (Rev 5E2),
BwAR 1-6-A7 Rev 9 rev 2 BwOP VX-7 Rev 52 B5 (Rev 5E1), C5 (Rev 5E1),
MEMORY MEMORY D5 (Rev 5E1).
NEW NEW HIGHER 2.4.50 00WE11 ..(KAs) 000067AA103 ..(KAs) NEW 003000K304 ..(KAs)
ANSWER: 019 (1.00) ANSWER: 024 (1.00) ANSWER: 029 (1.00)
- c. d. a.
REFERENCE:
REFERENCE:
REFERENCE:
1BwOA PRI-2 Rev 100 BWD ILT Lesson Plan 1BwAR 1-9-A2 Rev 10 Big 1BwEP ES-0.1 Rev 100 I1-EP-XL-01 Rev 14 NOTE CV-3 Rev 6 HIGHER HIGHER HIGHER NEW NEW NEW 000024AA202 ..(KAs) 00WE01EK2.2 ..(KAs) 004000K404 ..(KAs)
SENIOR REACTOR OPERATOR Page 84 ANSWER: 030 (1.00) ANSWER: 035 (1.00) ANSWER: 039 (1.00)
- a. b. c.
REFERENCE:
REFERENCE:
REFERENCE:
P&ID M-62 Rev BN Big Note RY-1 Rev 7 Big Note EF-1 Rev 10 HIGHER MEMORY MEMORY NEW NEW MODIFIED 005000A103 ..(KAs) 010000K401 ..(KAs) 013000A402 ..(KAs)
ANSWER: 031 (1.00) ANSWER: 036 (1.00) ANSWER: 040 (1.00)
- a. a. d.
REFERENCE:
REFERENCE:
REFERENCE:
Big Note ECCS-1 Rev 6 Steam tables BWD ILT lesson plan HIGHER HIGHER I1-RY-XL-01 rev 4.
NEW NEW Big Note RH-4 Rev 7 006000K603 ..(KAs) 010000K502 ..(KAs) HIGHER BANK 022000K302 ..(KAs)
ANSWER: 032 (1.00) ANSWER: 037 (1.00)
- d. b.
REFERENCE:
REFERENCE:
ANSWER: 041 (1.00)
Big Notes RY-1 Rev 7, RY-4 BWD ILT Lesson Plan c.
Rev 7 I1-RP-XL-02 Rev 1
REFERENCE:
MEMORY MEMORY 2BwEP ES-1.3 Rev 102 NEW MODIFIED BWD ILT lesson plan 007000K103 ..(KAs) 012000K501 ..(KAs) I1-CA-XL-02 Rev 11 HIGHER NEW ANSWER: 033 (1.00) ANSWER: 038 (1.00) 026000A202 ..(KAs)
- d. a.
REFERENCE:
REFERENCE:
20E-2-4030RY11 rev K TS 3.7.6 amend 98, 3.4.16 ANSWER: 042 (1.00)
MEMORY amend 98, 3.4.5 amend 98, b.
NEW 3.3.1 cond C, pages 2 and 16
REFERENCE:
007000A401 ..(KAs) amend 110. 0BwOSR 0.1-0 Big Note MS-4 Rev 8 Rev 13 1BwGP 100-1 Rev 19 Unit Common All Modes 1BwGP 100-3 Rev 27 ANSWER: 034 (1.00) Shiftly and Daily Operating HIGHER
- c. Surveillance Data Sheet. NEW
REFERENCE:
MEMORY 039000K306 ..(KAs)
BwOP CC-15 rev 12 Big Note NEW CC-2 Rev 5 2.1.33 012000 ..(KAs) ANSWER: 043 (1.00)
HIGHER c.
NEW
REFERENCE:
008000A103 ..(KAs) 2BwOA SEC-1 REV 102 Big Note FW-1 Rev 8 MEMORY NEW 056000A204 ..(KAs)
SENIOR REACTOR OPERATOR Page 85 ANSWER: 044 (1.00) ANSWER: 048 (1.00) ANSWER: 052 (1.00)
- d. c. a.
REFERENCE:
REFERENCE:
REFERENCE:
1BwFR H.2 Rev 1A 1BwOA ELEC-1 Rev 100 Big Note WS-1 Rev 1 1BwFR H.3 Rev 1A 1-22-E10, 125V DC HIGHER HIGHER DIST.PNL 112/114 VOLT NEW NEW LOW 076000K201 ..(KAs) 059000 2.4.6 ..(KAs) Big Note DC-1 Rev 5 HIGHER NEW ANSWER: 053 (1.00)
ANSWER: 045 (1.00) 063000A301 ..(KAs) c.
- a.
REFERENCE:
REFERENCE:
BWD ILT Lesson plan 2BwOA ELEC-2 Rev 100 ANSWER: 049 (1.00) I1-SA-XL-01 rev 4 BWD ILT Lesson plan b. MEMORY I1-AF-XL-01 Rev 3
REFERENCE:
NEW HIGHER Big note DG-9 rev 6 078000K201 ..(KAs)
NEW SR 3.8.1.4 amend 108 061000K601 ..(KAs) HIGHER NEW ANSWER: 054 (1.00) 064000K608 ..(KAs) c.
ANSWER: 046 (1.00)
REFERENCE:
- d. BwAR 1-1-B2 Rev 3E3
REFERENCE:
ANSWER: 050 (1.00) SR 3.6.2.1 Note 1 amend 98 OP-AA-108-105 Rev 1: a. HIGHER Equipment Deficiency
REFERENCE:
BANK Identification and Big Notes: DG-2 Rev 4, AF-1 103000K105 ..(KAs) documentation Rev 6 20E-1-4030AF07 Rev T: BWD ILT Lesson plan Schematic diagram 1A I1-DG-XL-01 Rev 3 ANSWER: 055 (1.00)
Auxiliary Feedwater Isolation BWD ILT Lesson plan d.
Valves 1AF013A From Pump I1-WO-XL-01 Rev 3
REFERENCE:
1A AND 1AF013E FROM Print 20E-2-4030VP04 Rev H 1BwOA PRI-13 rev 55 PUMP1B HIGHER Big Note CV-1 Rev 5 MEMORY NEW HIGHER NEW 064000A302 ..(KAs) NEW 2.1.2 061000 ..(KAs) 103000A101 ..(KAs)
ANSWER: 051 (1.00)
ANSWER: 047 (1.00) a. ANSWER: 056 (1.00)
- a.
REFERENCE:
c.
REFERENCE:
BwAR 2-0PR032J rev 5
REFERENCE:
Big Notes AC-6 rev 7 and BWD ILT Lesson plan BWD ILT Lesson plan AC-7 rev 3. I1-AR-XL-01 rev 3 I1-IC-XL-01 Rev 2 HIGHER HIGHER Big Note CORE-2 Rev 2 NEW NEW MEMORY 062000K201 ..(KAs) 073000A202 ..(KAs) NEW 002000K402 ..(KAs)
SENIOR REACTOR OPERATOR Page 86 ANSWER: 057 (1.00) ANSWER: 062 (1.00) ANSWER: 066 (1.00)
- c. b. d.
REFERENCE:
REFERENCE:
REFERENCE:
1BwAR 1-10-A6 rev. 7E1 BWD ILT Lesson plans BwCB-1 Fig 9 Rev 15.
TS 3.1.6 amend 98 I1-FH-XL-01 rev 2, RM-AA-102 rev 3 TS 3.2.3 amend 110 I1-AR-XL-01 Rev 3. HIGHER U1 COLR Figure 2.5.1 MEMORY NEW U1 COLR Figure 2.8.1 rev 1. BANK 194001 2.1.25 ..(KAs)
HIGHER 034000K602 ..(KAs)
NEW 015000K513 ..(KAs) ANSWER: 067 (1.00)
ANSWER: 063 (1.00) b.
- b.
REFERENCE:
ANSWER: 058 (1.00)
REFERENCE:
U1 COLR CAD-03-89, Rev 1
- c. Big Note EF-1 Rev 10. Page 17
REFERENCE:
BWD ILT Lesson Plan TS 3.4.9 Amend 98 Big Note CORE-2 rev 2 I1-EP-XL-02B Rev 6. TS 3.6.4 Amend 98 MEMORY HIGHER MEMORY NEW NEW BANK 017000A101 ..(KAs) 035000K302 ..(KAs) 2.1.33 194001 ..(KAs)
ANSWER: 059 (1.00) ANSWER: 064 (1.00) ANSWER: 068 (1.00)
- b. b. c.
REFERENCE:
REFERENCE:
REFERENCE:
Big Note CS-1 Rev 7 BWD ILT Lesson plan 1BwGP 100-3 Rev 27 MEMORY I1-MP-XL-01 Rev 3 MEMORY NEW Big Note EHC-2 NEW 027000K101 ..(KAs) MEMORY 2.2.2 194001 ..(KAs)
NEW ANSWER: 060 (1.00) 045000A311 ..(KAs)
- b. ANSWER: 069 (1.00)
REFERENCE:
a.
BWD ILT lesson plan ANSWER: 065 (1.00)
REFERENCE:
I1-HG-XL-01 rev 1 a. CC-AA-112 Rev 7 MEMORY
REFERENCE:
MEMORY NEW Big Note SX -1 Rev 5 BANK 2.1.28 028000 ..(KAs) Big Note AC-6 Rev 7 194001 2.2.11 ..(KAs)
HIGHER ANSWER: 061 (1.00) NEW
- d. 075000K203 ..(KAs) ANSWER: 070 (1.00)
REFERENCE:
b.
BWD ILT Lesson plan
REFERENCE:
I1-VP-XL-01 rev 1 OP-MW-109-101 Rev 2 BwOP VQ-7 rev 12 MEMORY BwAR 0-33-E3 rev 6. BANK MEMORY 2.2.13 194001 ..(KAs)
NEW 029000A401 ..(KAs)
SENIOR REACTOR OPERATOR Page 87 ANSWER: 071 (1.00) ANSWER: 076 (1.00) ANSWER: 080 (1.00)
- a. d. d.
REFERENCE:
REFERENCE:
REFERENCE:
NGET Study guide Rev 28 BWD ILT lesson plan EP-AA-1001 Rev 13 MEMORY I1-MI-XL-04 Rev 3. EP-MW-113-100 Rev 100 NEW 1BwEP-0 Rev 102 HIGHER 194001 2.3.4 ..(KAs) 1BwEP ES-0.1 Rev 103 NEW HIGHER 000056 2.1.14 ..(KAs)
NEW ANSWER: 072 (1.00) 000008AA203 ..(KAs) b ANSWER: 081 (1.00)
REFERENCE:
b.
BwOP VQ-6 Rev 15 ANSWER: 077 (1.00)
REFERENCE:
MEMORY a. 1BwOA ELEC-2, Rev 100 NEW
REFERENCE:
BwOP IP-2 Rev 10 2.3.9 194001 ..(KAs) 1BwOA PRI-10 Rev 101 HIGHER BWD ILT Lesson plan NEW I1-RH-XL-01 Rev 3 2.1.30 000057 ..(KAs)
ANSWER: 073 (1.00) BwOP RH-6 Rev 30
- b. HIGHER
REFERENCE:
NEW ANSWER: 082 (1.00) 1BwEP-1 Rev 105 OAS page 000025AA108 ..(KAs) b.
BwAR 1-5-A7 Rev 5
REFERENCE:
HIGHER 1BwST-1, 2, 3, 5 Rev 1B NEW ANSWER: 078 (1.00) BwAP 340-1 Rev 15 194001 2.4.50 ..(KAs) c. HIGHER
REFERENCE:
NEW BwOP CC-14 Rev 9 00WE05EA2.1 ..(KAs)
ANSWER: 074 (1.00) BwOP CC-8 Rev 16
- c. Big Note CC-1 Rev 7
REFERENCE:
HIGHER ANSWER: 083 (1.00)
BWD ILT Lesson Plan NEW d.
I1-CA-XL-03 Rev 10 000026AA203 ..(KAs)
REFERENCE:
HIGHER 1BwOA ROD-1 Rev 54a NEW 1BwOA INST-2 Rev 101 194001 2.4.47 ..(KAs) ANSWER: 079 (1.00) Big Note EF-1 Rev 10
- b. HIGHER
REFERENCE:
NEW ANSWER: 075 (1.00) 2BwFR-S.1 Rev 1A 2.1.32 000001 ..(KAs)
- b. MEMORY
REFERENCE:
NEW BWD ILT Lesson plan 2.1.14 000029 ..(KAs) ANSWER: 084 (1.00)
I1-FR-XL-04 Rev 7 a.
MEMORY
REFERENCE:
BANK 2BwOA ELEC-4 Rev 100 194001 2.4.18 ..(KAs) Big Note I&C-2 Rev 3 HIGHER NEW 000032AA201 ..(KAs)
SENIOR REACTOR OPERATOR Page 88 ANSWER: 085 (1.00) ANSWER: 090 (1.00) ANSWER: 094 (1.00)
- d. d. a.
REFERENCE:
REFERENCE:
REFERENCE:
1BwOA Refuel-1 Rev 54 TS bases 3.8.1 page 5 Rev TS Bases 3.4.12-14 Rev 0 MEMORY 0 TS 3.5.4 Amend 98 NEW Big Note DG-1 Rev 8 TS 3.4.12 Amend 98 000036AK101 ..(KAs) Big Note DG-3 Rev 8 HIGHER BWD ILT Lesson plan NEW I1-DG-XL-01 Rev 3. 2.1.12 194001 ..(KAs)
ANSWER: 086 (1.00) HIGHER
- d. NEW
REFERENCE:
062000A305 ..(KAs) ANSWER: 095 (1.00) 0BwOA PRI-5 Rev 101 c.
BwAR 0-37-A4 Rev 13
REFERENCE:
MEMORY ANSWER: 091 (1.00) 1BwGP 100-6 rev 18 page NEW a. 17, 20, 24 2.4.31 000068 ..(KAs)
REFERENCE:
BwAP 320-1 rev 15 TS bases 3.4.15 page 3 Rev MEMORY 32 NEW ANSWER: 087 (1.00) BWD ILT Lesson plan 2.1.1 194001 ..(KAs)
- c. I1-AR-XL-01 Rev 3.
REFERENCE:
MEMORY 2BwEP ES-1.3 Rev 102 NEW ANSWER: 096 (1.00) 2BwFR-C.2 Rev 100 073000 2.1.28 ..(KAs) c.
BwAP 340-1 Rev 15
REFERENCE:
BwAR 2-6-B7 Rev 7E2 BwAP 370-3, Rev 28 MEMORY ANSWER: 092 (1.00) TS 3.7.10 Amend 98 NEW c. TS 3.8.8 Amend 124 00WE06EA2.1 ..(KAs)
REFERENCE:
MEMORY 2BwEP-0 Rev 104 NEW Big Note RD-4 rev 5 2.2.31 194001 ..(KAs)
ANSWER: 088 (1.00) HIGHER
- a. NEW
REFERENCE:
001000A202 ..(KAs) ANSWER: 097 (1.00)
TS 3.5.2 Bases c.
Big Note RH-1 Rev 5
REFERENCE:
HIGHER ANSWER: 093 (1.00) OP-AA-108-101 Rev 1 MODIFIED b. MEMORY 005000K305 ..(KAs)
REFERENCE:
NEW BWD ILT Lesson plans 194001 2.2.16 ..(KAs)
I1-MS-XL-01 Rev 2, ANSWER: 089 (1.00) I1-DU-XL-01 Rev 3,
- c. I1-EP-XL-04 Rev 17 ANSWER: 098 (1.00)
REFERENCE:
BwAR 1-14-C1 Rev 6E1 a.
Big note ECCS-1 Rev 6 MEMORY
REFERENCE:
1BwCA-1.1 Rev 102 NEW BwOP WX-501T1 HIGHER 041000 2.4.50 ..(KAs) MEMORY NEW NEW 006000A202 ..(KAs) 2.3.3 194001 ..(KAs)
SENIOR REACTOR OPERATOR Page 89 ANSWER: 099 (1.00) ANSWER: 100 (1.00)
- a. c.
REFERENCE:
REFERENCE:
EP-AA-1001 Rev 13 BwAP 340-1 Rev 15 MEMORY BWD ILT Lesson Plan NEW I1-EP-XL-01 Rev 15 2.4.33 194001 ..(KAs) MEMORY NEW 2.4.13 194001 ..(KAs)
(********** END OF EXAMINATION **********)
SENIOR REACTOR OPERATOR Page 90 ANSWER KEY MULTIPLE CHOICE 001 c 021 a 041 c 061 d 081 b 002 d 022 d 042 b 062 b 082 b 003 d 023 b 043 c 063 b 083 d 004 b 024 d 044 d 064 b 084 a 005 d 025 c 045 a 065 a 085 d 006 a 026 b 046 d 066 d 086 d 007 b 027 d 047 a 067 b 087 c 008 d 028 c 048 c 068 c 088 a 009 a 029 a 049 b 069 a 089 c 010 b 030 a 050 a 070 b 090 d 011 c 031 a 051 a 071 a 091 a 012 d 032 d 052 a 072 b 092 c 013 d 033 d 053 c 073 b 093 b 014 b 034 c 054 c 074 c 094 a 015 b 035 b 055 d 075 b 095 c 016 b 036 a 056 c 076 d 096 c 017 c 037 b 057 c 077 a 097 c 018 b 038 a 058 c 078 c 098 a 019 c 039 c 059 b 079 b 099 a 020 b 040 d 060 b 080 d 100 c
(********** END OF EXAMINATION **********)