ML051360239
| ML051360239 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/02/2005 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-254/05-301, 50-265/05-301 | |
| Download: ML051360239 (25) | |
Text
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: May 6, 2005 Facility/Unit: Quad Cities U1/U2 Region:
III Reactor Type:
GE 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 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.
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
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; 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; and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the SRO exam limited to fuel handling. Notify the proctor if you need more time.
4.
You may bring pens, pencils, and calculators into the examination room; however, 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.
6.
Mark your answers on the answer sheet provided, and do not leave any question blank.
Use only the paper provided. If you are using ink and decide to change your original answer, draw a single line through the error, enter the desired answer, and initial the change. If you are recording your answers on a machine-gradable form that offers more than four answer choices (e.g., a through e), 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 your answer sheets 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 materials at your desk.
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?
SENIOR REACTOR OPERATOR Page 4 QUESTION: 001 (1.00)
Unit 1 is at 65% power, increasing to full load. Unit 2 is at rated power.
Moments ago, a lightning strike in the switchyard caused transformer 345 KV BUS 4 to trip.
Assuming that all automatic actions occurred, which statement below describes the procedures that should be directed. (may not list ALL procedures required) a.
Unit 1 must enter QCGP 2-3, REACTOR SCRAM.
Unit 2 must perform QCOS 0005-09, UNIT TWO ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
b.
Unit 1 must perform QOA 6100-01, LOSS OF TRANSFORMER 12(22) DURING POWER OPERATION.
Unit 2 must perform QCOS 0005-09, UNIT TWO ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
c.
Unit 1 must perform QCOS 0005-09, UNIT ONE ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Unit 2 must enter QCGP 2-3, REACTOR SCRAM.
d.
Unit 1 must perform QCOS 0005-08, UNIT ONE ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Unit 2 must perform QOA 6100-01, LOSS OF TRANSFORMER 12(22) DURING POWER OPERATION.
SENIOR REACTOR OPERATOR Page 5 QUESTION: 002 (1.00)
Unit 1 and Unit 2 were at rated power. The 1/2 250VDC Battery Charger was Out Of Service for replacement. 902-8 A10, 250 V BATTERY CHARGER 2 TRIP was received. An Operator reported that the charger feed breaker on MCC 29-2 is tripped and CANNOT be reset.
Subsequently, a LOCA occurs on Unit 2.
Regarding the loads connected to the Unit 2 250VDC battery:
(1) What action is REQUIRED to maintain voltage? (2) The REASON for maintaining voltage, is because the Unit 2 250 VDC battery _____.
a.
(1) TRIP the Emergency Hydrogen Seal Oil Pump within 30 minutes.
(2) IS REQUIRED to meet MINIMUM safety functions on Unit 2 b.
(1) TRIP the Emergency Hydrogen Seal Oil Pump within 30 minutes.
(2) MAY BE required to support safe shutdown on Unit 1 c.
(1) TRIP the Recirc MG Set Emergency Lube Oil Pumps within 30 minutes.
(2) MAY BE required to support safe shutdown on Unit 1 d.
(1) TRIP the Recirc MG Set Emergency Lube Oil Pumps within 30 minutes.
(2) IS REQUIRED to meet MINIMUM safety functions on Unit 2
SENIOR REACTOR OPERATOR Page 6 QUESTION: 003 (1.00)
Unit 2 is shutting down for a refueling outage. A manual reactor scram was inserted as planned, after the Main Turbine was taken off line. Immediately following the scram, Reactor water level dropped to -3 inches before returning to 30 inches. All EXPECTED automatic actions occurred.
A log entry describing the expected plant response was NOT MADE prior to inserting the manual scram.
Which statement describes the reportability of this event?
a.
A 1-hour ENS call IS REQUIRED, because NO LOG ENTRY was made prior to the event.
b.
An ENS call is NOT required, because the plant performed as EXPECTED.
c.
An ENS call is NOT required, because NO automatic actions occurred.
d.
A 4-hour ENS call IS REQUIRED, because NO LOG ENTRY was made prior to the event.
SENIOR REACTOR OPERATOR Page 7 QUESTION: 004 (1.00)
A Group 1 Isolation occurred with failure of the reactor to scram.
The following conditions are observed:
RPV water level is being maintained -142 to -166 inches ADS Valves are being used to maintain RPV pressure 800-1000 psig Reactor power is 5%, LOWERING SBLC is injecting and tank level has dropped from 85 to 60%
Drywell pressure is 17 psig, STEADY Torus pressure is 15 psig, STEADY Drywell temperature is 290/F, RISING Torus water level is 14.5 feet, RISING Torus water temperature is 160/F, LOWERING NO QGA 200 actions have been ordered.
WHICH of the following is the NEXT action to take per the QGAs?
a.
Lower the RPV pressure band to stay within the Heat Capacity Limit.
b.
Raise RPV level to ensure core cooling.
c.
Blowdown the RPV to stay within the Pressure Suppression Pressure limit.
d.
Spray the Drywell to lower Drywell temperature.
SENIOR REACTOR OPERATOR Page 8 QUESTION: 005 (1.00)
In the Tech Spec Bases, the Reactor Vessel Steam Dome Pressure-High scram ________.
a.
is assumed in the Reactor overpressurization analysis, to occur AFTER Reactor power reaches the APRM Fixed Neutron Flux-High scram setpoint b.
is assumed in the Reactor overpressurization analysis, to occur BEFORE Reactor power reaches the APRM Fixed Neutron Flux-High scram setpoint c.
is credited in the control rod drop accident analysis, for causing the Reactor scram.
d.
is credited in the Reactor Recirc controller failure analysis, for causing the Reactor scram.
QUESTION: 006 (1.00)
Unit 2 was operating at 100% power when a transient occurred causing RPV water level to decrease.
Which of the following is the HIGHEST RPV water level that would REQUIRE a site assembly?
a.
0" b.
-59" c.
-142" d.
-191"
SENIOR REACTOR OPERATOR Page 9 QUESTION: 007 (1.00)
Given:
Unit 2 has experienced a reactor scram and a loss of off-site power.
There is a fire ?15 feet north of the 2A TBCCW pump.
The Unit 2 Supervisor has determined that normal and emergency plant procedures are insufficient to control the event.
Using the information provided, DETERMINE which QCARP Procedure (if any) should be used?
a.
0030-02 b.
0030-03 c.
0030-04 d.
NO QCARP procedure is required
SENIOR REACTOR OPERATOR Page 10 QUESTION: 008 (1.00)
Unit 2 was operating at 75% power when a leak developed on the Main Condenser Boot. Five minutes ago, backpressure reached 6.5" Hg. and a manual Reactor scram was inserted.
Conditions are now:
Reactor power is 15% and LOWERING slowly Reactor pressure is 930 psig and STEADY Four Turbine Bypass valves are OPEN Reactor Level is 0" and LOWERING Reactor Recirc Pumps are TRIPPED Drywell pressure is 1.3 psig and STEADY Reactor Relief Valves are ALL CLOSED Main Condenser Backpressure is 7.0" Hg and RISING MSIVs are ALL OPEN With regards to reactor pressure control, what are the INITIAL actions that should be directed?
a.
DO NOT BYPASS the RPV low level isolations and control reactor pressure 800-1000 psig with Turbine Bypass valves.
b.
BYPASS the RPV low level isolations and control reactor pressure 800-1000 psig with Turbine Bypass valves.
c.
DO NOT BYPASS the RPV low level isolations and control reactor pressure 700-900 psig with Relief valves.
d.
BYPASS the RPV low level isolations and control reactor pressure 700-900 psig with Relief valves.
SENIOR REACTOR OPERATOR Page 11 QUESTION: 009 (1.00)
Unit 2 is starting up following a refueling outage. HPCI periodic flow-rate testing is in progress.
Reactor Power 16%
Drywell Pressure 1.25 psig Torus Pressure 0.10 psig Torus Water Avg Temp 98/F Drywell Avg Temp 155/F Based upon the above conditions, which Parameter listed below requires a Tech Spec Action Statement to be entered?
a.
Torus Water Temperature b.
Drywell to Torus D/P c.
Drywell Temperature d.
Drywell Pressure QUESTION: 010 (1.00)
Which of the following unisolable leaks, with offsite radiation release rates approaching the General Emergency level, would require you to select QGA 500-01 as the appropriate procedure to protect the general public?
a.
Fuel pool cooling discharging into Radwaste Valve-Alley b.
RWCU piping discharging into the RWCU demin room c.
HPCI steam inlet piping discharging into the Torus area d.
The Main Turbine Bypass Valves discharging into the Turbine Building
SENIOR REACTOR OPERATOR Page 12 QUESTION: 011 (1.00)
Unit 1 is at rated power. The 1B Core Spray Pump was taken OOS service earlier this shift for motor bearing repair. All appropriate Tech Spec action statements were entered.
At 15:30 the Unit NLO reports from the 2201-7 rack that the Core Spray Header High D/P switches indicate:
A + 1.3 psid B - 1.2 psid What is causing this indication and what Tech Spec action is required?
a.
The B Core Spray discharge line is broken inside the reactor. RESTORE B Core Spray loop to operable status within 7 days.
b.
The A Core Spray discharge line is broken inside the reactor. RESTORE A Core Spray loop to operable status within 7 days.
c.
The B Core Spray discharge line is broken inside the reactor. Be in MODE 3 by 0430 tomorrow.
d.
The A Core Spray discharge line is broken inside the reactor. Be in MODE 3 by 0430 tomorrow.
SENIOR REACTOR OPERATOR Page 13 QUESTION: 012 (1.00)
Given:
Unit 1 is in the process of off loading the reactor core Unit 2 is operating at 100% power The 1/2 A SBGT operability surveillance has just been completed with the following results:
4400 scfm flow 6.13 inches of water pressure drop across the HEPA filters and charcoal adsorbers The 1/2 B SBGT train is now running for an upcoming RB vent OOS Five minutes later an electrical fault causes the 1/2-7504B, TURB BLDG CLG AIR DMPR, to OPEN. What actions are required by Tech Specs?
a.
Unit 1: Restore one SBGT subsystem to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Unit 2: Enter Tech Spec LCO 3.0.3 b.
Unit 1: Suspend movement of irradiated fuel in the secondary containment, suspend core alterations and initiate action to suspend OPDRVs immediately.
Unit 2: Restore one SBGT subsystem to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
c.
Unit 1: Restore SBGT subsystem to operable status within 7 days.
Unit 2: Restore SBGT subsystem to operable status within 7 days.
d.
Unit 1: Place the operable SBGT subsystem in operation immediately.
Unit 2: Enter Tech Spec LCO 3.0.3
SENIOR REACTOR OPERATOR Page 14 QUESTION: 013 (1.00)
Unit 1 was operating at rated power when the following scenario occurs.
0000 LOOP on Unit 1 0001 1/2 EDG fails to start, cause unknown 0003 U1 EDG output breaker trips on overload 0007 Bus 13-1 to Bus 23-1 crosstie breaker fails to close, cause unknown 0012 U1 SBO DG fails to start due to starting air failure 0020 1/2 EDG is manually started and loads to 13-1 0022 Busses 14-1 and 24-1 are crosstied 0035 Off-Site power is restored.
Which one of the following most correctly describes the reportability for this event?
a.
This event IS reportable as an Unusual Event.
b.
This event IS reportable as an ALERT.
c.
This event IS reportable as a Site Area Emergency.
d.
This event is NOT reportable.
QUESTION: 014 (1.00)
Unit 1 is operating at full power. At 0900 the ANSO notes no light indication for the MO 1-3702, U1 RBCCW SPLY VLV. Investigation reveals an electrical short has damaged breaker components and the breaker requires extensive repairs which will take 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Which of the following is correct regarding the situation?
a.
No action is required because the MO 1-3702 does NOT have a required stroke time.
b.
RBCCW flow must be isolated to the drywell by 1300.
c.
RBCCW flow must be isolated to the drywell by 1700.
d.
No actions are required since the in-line check valve is operable.
SENIOR REACTOR OPERATOR Page 15 QUESTION: 015 (1.00)
Both Units are at rated power.
A Laborer reported that inside the SSMP room, he had "bumped" valve 1/2-2999-11, causing it to break off and spray water.
You dispatched the Field Supervisor and an NLO who CLOSED valves 1/2-2999-7 AND 1/2-2901-25 to STOP the leak (see below).
Assume NO additional equipment is damaged AND an IR has been generated, what is the IMPACT on the SSMP system, AND what should be done to correct it?
a.
SSMP is INOPERABLE. Valve in the Fire Header to the SSMP suction.
b.
SSMP is OPERABLE. No additional actions are required.
c.
SSMP is INOPERABLE. Valve in Service Water to the room cooler.
d.
SSMP is INOPERABLE. Valve in the Fire Header to the room cooler.
SENIOR REACTOR OPERATOR Page 16 QUESTION: 016 (1.00)
A LOCA has occurred on Unit 2, concurrently with a LOOP.
Reactor Pressure is 300 psig and LOWERING.
RCIC and SBLC are the ONLY high pressure systems available AND injecting into the Reactor.
Reactor Water Level is -193" and LOWERING.
The RHR System is in operation per QCOP 1000-30.
BOTH loops of Torus Sprays are in operation.
BOTH loops of Torus Cooling are in operation.
Drywell sprays are NOT in operation due to valve binding on both loops.
Drywell Pressure is 19 psig and RISING.
Torus Pressure is 17 psig and RISING.
Torus Level is 14 feet and STABLE.
Complete the following statements.
QGA 500-1, RPV BLOWDOWN is required based upon __(1)__. The 901-3 Panel Operator should be directed to __(2)__.
a.
(1) Reactor Water Level AND Torus Pressure (2) STOP Torus Cooling AND Torus Sprays b.
(1) Reactor Water Level ONLY (2) STOP Torus Cooling AND Torus Sprays c.
(1) Reactor Water Level AND Torus Pressure (2) CONTINUE to operate Torus Cooling AND Torus Sprays d.
(1) Torus Pressure ONLY (2) CONTINUE to operate Torus Cooling AND Torus Sprays
SENIOR REACTOR OPERATOR Page 17 QUESTION: 017 (1.00)
What is the TS bases for the high level RFP and Turbine trips?
a.
To ensure that the fuel cladding integrity Safety Limit and the cladding 1% plastic strain limit are not violated during the feedwater controller failure, maximum demand event.
b.
To ensure that the fuel design limits are not exceeded anywhere in the core during normal operation, including anticipated operational occurrences.
c.
To ensure that the Safety Limit MCPR is not violated during a slow recirc flow increase event that does not terminate in a scram.
d.
To prevent overflow into the Main Steam Lines.
SENIOR REACTOR OPERATOR Page 18 QUESTION: 018 (1.00)
Unit 1 has experienced a transient. The following lists the current conditions.
RPV pressure 800 psig and LOWERING RPV water level 30" and STEADY, maintained with feedwater Torus area water level is 3" and RISING Second floor RB radiation reading is 3.5 R/hr and RISING B RWCU pump room temperature is 250/F and RISING RWCU heat exchanger room temperature is 210/F and RISING The breakers for the RWCU isolation valves have TRIPPED and will NOT reset Which of the following is the correct action to take and the basis for that action?
a.
Blowdown the RPV per QGA 500-1. This will maintain HPCI and RCIC availability for core submergence.
b.
Cooldown the RPV per QCGP 2-1. This will maintain habitability in accessible portions of the secondary containment.
c.
Blowdown the RPV per QGA 500-1. This will maintain habitability in accessible portions of the secondary containment.
d.
Cooldown the RPV per QCGP 2-1. This will maintain HPCI and RCIC availability for core submergence.
SENIOR REACTOR OPERATOR Page 19 QUESTION: 019 (1.00)
Both units are operating at full reactor power. On midnight shift the Unit 1 ANSO becomes very ill and at 0400 leaves the site to seek medical attention. The day shift ANSO is expected to be in at 0630.
As the US you locate the QAP binder in the control room and find that the Shift Manning procedure is missing. When you attempt to access EDMS you find it is down for server maintenance.
Where could you locate the most current revision of the procedure and what actions are required in this case?
a.
In Passport OR In the WEC. Immediately take action to replace the missing ANSO.
b.
In Passport ONLY. Immediately take action to replace the missing ANSO.
c.
In Passport OR in the WEC. No action to INCREASE shift manning is required.
d.
In the WEC ONLY. No action to INCREASE shift manning is required.
QUESTION: 020 (1.00)
You are the Unit Supervisor. An activity that will cause the Shutdown Risk status change from GREEN to YELLOW requires a Heightened Level of Awareness (HLA) briefing on your shift.
Which of the following lists your responsibilities per HU-AA-1211, BRIEFINGS - PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY AND POST-JOB BRIEFINGS?
a.
Acting as the Test Coordinator for the evolution and granting permission to begin the evolution.
b.
Deciding who needs to monitor the brief and acting as Test Coordinator for the evolution.
c.
Deciding who needs to monitor the brief and setting abort criteria for the evolution.
d.
Granting permission to perform the evolution and setting abort criteria for the evolution.
SENIOR REACTOR OPERATOR Page 20 QUESTION: 021 (1.00)
You have been assigned to SUPERVISE fuel moves on the refuel floor during a FULL-CORE OFFLOAD.
Which of the following activities is required EVERY SHIFT, before fuel moves can begin?
a.
Sign on as a HOLDER of the Clearance Order that is placed to prevent cavity draining.
b.
INSPECT the refueling bridge and the area around the cavity for loose materials.
c.
ANNOUNCE over the Public Address system that fuel moves are ABOUT TO COMMENCE.
d.
VERIFY with the QNE that Shutdown Margin is MET.
QUESTION: 022 (1.00)
Under which of the following circumstances would an INTERIM Procedure Change be appropriate as opposed to a TEMPORARY procedure change?
a.
The proposed procedure change will NOT change the intent of the original procedure and will be used MANY TIMES over the upcoming refuel cycle.
b.
The proposed procedure change will NOT change the intent of the original procedure and will be used only ONCE.
c.
When the Shift Manager determines there is NOT sufficient time to perform reviews, REGARDLESS of change of intent status.
d.
The proposed procedure change WILL change the intent of the original procedure and will be used only ONCE.
SENIOR REACTOR OPERATOR Page 21 QUESTION: 023 (1.00)
According to Tech Specs, what is the lowest level of authority responsible for the administrative control of keys to locked high radiation areas?
a.
The Shift Manager on duty OR ANY Radiation Protection Technician b.
ANY LICENSED Operator on duty OR the Radiation Protection ALARA Coordinator c.
The Shift Manager on duty OR Radiation Protection Supervision d.
ANY Senior Reactor Operator on duty OR Radiation Protection Supervision QUESTION: 024 (1.00)
Complete the following statement regarding EMERGENCY usage of safety systems included in Tech Specs during plant emergencies.
Tech Spec required safety systems...
a.
can be disabled ONLY AFTER notifying the NRC of entry into 10 CFR 50.54(x).
b.
are NEVER intentionally disabled.
c.
are procedurally REQUIRED to be disabled, WHEN doing so is a necessary part of a mitigation strategy.
d.
can be disabled ONLY AFTER receiving approval from the Site Emergency Director.
SENIOR REACTOR OPERATOR Page 22 QUESTION: 025 (1.00)
Which of the following is unacceptable, when a HOLD point is reached during QGA execution?
a.
CONTINUE to review and complete subsequent step(s) PRIOR to meeting the conditions listed in the HOLD point.
b.
CONTINUE to review and complete PARALLEL QGA LEGS step(s) PRIOR to meeting the conditions in the HOLD point.
c.
CONTINUE to review and complete prior step(s) until the conditions in the HOLD point have been met.
d.
CONTINUE to review and complete override(s) applicable to prior step(s) PRIOR to meeting the conditions in the HOLD point.
(********** END OF EXAMINATION **********)
SENIOR REACTOR OPERATOR Page 23 ANSWER: 001 (1.00) b.
REFERENCE:
QOA 912-2 B4 BUS 4 TRIP XFMR 12 TRIP, QOA 6100-01 LOSS OF TRANSFORMER 12(22)
DURING POWER OPERATION.
HIGHER NEW 295003.2.4..(KA's)
ANSWER: 002 (1.00) c.
REFERENCE:
QCOA 6900-05 LOSS OF SAFETY RELATED 250VDC BATTERY CHARGERS CONCURRENT WITH A DESIGN BASIS ACCIDENT.
TS Bases B 3.8.4-2 and B3.8.4-4 MEMORY NEW 295004A204..(KA's)
ANSWER: 003 (1.00) b.
REFERENCE:
QCGP 2-3 Precaution D.7 MEMORY NEW 295006.2.1..(KA's)
ANSWER: 004 (1.00) d.
REFERENCE:
QGA 200, QGA 101, Strategies document, Rev 11 HIGHER MODIFIED QGA Procedures with entry conditions blanked provided to applicants 295028.2.4..(KA's)
ANSWER: 005 (1.00) a.
REFERENCE:
TS B 3.3.1.1-11 B 3.3.1.1-13, B 3.3.1.1-14 MEMORY NEW 295025A202..(KA's)
ANSWER: 006 (1.00) c.
REFERENCE:
Emergency Action Level Wallboard EP-AA-1006 App.
3 Quad Cities Annex HIGHER NEW Emergency Action Level Wallboard EP-AA-1006 App. 3 Quad Cities Annex provided 295031.2.1..(KA's)
ANSWER: 007 (1.00) c.
REFERENCE:
QCOA 0010-12 Attachment C HIGHER MODIFIED QCOA 0010-12 provided to applicants 600000A213..(KA's)
ANSWER: 008 (1.00) b.
REFERENCE:
Strategies for successful transient mitigation HIGHER BANK 295002.2.4..(KA's)
ANSWER: 009 (1.00) c.
REFERENCE:
TS 3.6.2.1 HIGHER NEW 295012A201..(KA's)
ANSWER: 010 (1.00) d.
REFERENCE:
QGA 400 MEMORY BANK QGA 300 and 400 provided with entry conditions blanked out.
295017A204..(KA's)
ANSWER: 011 (1.00) d.
REFERENCE:
QCAN 901(2)-3 F5, Core Spray Lesson Plan HIGHER NEW 209001205..(KA's)
ANSWER: 012 (1.00) b.
REFERENCE:
Tech Spec 3.6.4.3 and its Bases. TS 5.5.7.d HIGHER BANK Tech Spec 5.5.7 provided 261000.2.1..(KA's)
SENIOR REACTOR OPERATOR Page 24 ANSWER: 013 (1.00) c.
REFERENCE:
EP-AA-1006r19e App 3.
Quad Cities Annex HIGHER NEW EP-AA-1006r19e App
- 3. Quad Cities Annex provided.
264000.2.4..(KA's)
ANSWER: 014 (1.00) b.
REFERENCE:
TS 3.6.1.3 TRM Appendix A page A1-3 HIGHER NEW TS 3.6.1.3 TRM Appendix A pages A1-1 through A1-14 provided 400000.2.1..(KA's)
ANSWER: 015 (1.00) d.
REFERENCE:
QCOP 2900-01 HIGHER NEW No KA exists for the SSMP system. System was added to random selection process, following discussion with lead examiner, in accordance with ES 401-1, note 3.
ANSWER: 016 (1.00) a.
REFERENCE:
QGA 100, QGA 200 HIGHER NEW QGAs provided as discussed with Lead Examiner 230000A215..(KA's)
ANSWER: 017 (1.00) a.
REFERENCE:
TS B 3.3.2.2 MEMORY NEW 259001.2.2..(KA's)
ANSWER: 018 (1.00) c.
REFERENCE:
QGA 300 and EPG page B-8-12 HIGHER NEW QGA 300 and 400 with entry conditions blanked out.
290001A205..(KA's)
ANSWER: 019 (1.00) a.
REFERENCE:
QAP 0300-03 MEMORY NEW 2.1.5..(KA's)
ANSWER: 020 (1.00) d.
REFERENCE:
From HU-AA-1211 MEMORY NEW 2.1.9..(KA's)
ANSWER: 021 (1.00) b.
REFERENCE:
QCFHP 0100-01, QCFHP 0300-01 MEMORY NEW 2.2.29..(KA's)
ANSWER: 022 (1.00) d.
REFERENCE:
AD-AA-101 MEMORY BANK 2.2.16..(KA's)
ANSWER: 023 (1.00) c.
REFERENCE:
TS 5.7.2.a MEMORY BANK 2.3.1..(KA's)
ANSWER: 024 (1.00) c.
REFERENCE:
QGA Bases page I-3 MEMORY NEW 2.4.22..(KA's)
ANSWER: 025 (1.00) a.
REFERENCE:
QGA Lesson Plan MEMORY BANK 2.4.7..(KA's)
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SENIOR REACTOR OPERATOR Page 25 A N S W E R K E Y MULTIPLE CHOICE 001 b 002 c 003 b 004 d 005 a 006 c 007 c 008 b 009 c 010 d 011 d 012 b 013 c 014 b 015 d 016 a 017 a 018 c 019 a 020 d 021 b 022 d 023 c 024 c 025 a
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