ML040690107: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: MASTER RO Date: February 05, 2004                       Facility/Unit: KEWAUNEE / U1 Region:       III                             Reactor Type:     Westinghouse Start Time:                                   Finish Time:
{{#Wiki_filter:U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: MASTER RO Date: February 05, 2004 Facility/Unit: KEWAUNEE / U1 Region:
III Reactor Type: Westinghouse Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Value                                                           98.0     Points Applicants Score                                                       __________ Points Applicants Grade                                                       __________ Percent NRC Official Use Only
Applicants Signature Results Examination Value 98.0 Points Applicants Score
__________ Points Applicants Grade
__________ Percent NRC Official Use Only


APPENDIX E POLICIES AND GUIDELINES FOR TAKING NRC EXAMINATIONS Each examinee shall be briefed on the policies and guidelines applicable to the examination category (written and/or operating test) being administered. The applicants may be briefed individually or as a group. Facility licensees are encouraged to distribute a copy of this appendix to every examinee before the examinations begin. All items apply to both initial and requalification examinations, except as noted.
APPENDIX E POLICIES AND GUIDELINES FOR TAKING NRC EXAMINATIONS Each examinee shall be briefed on the policies and guidelines applicable to the examination category (written and/or operating test) being administered. The applicants may be briefed individually or as a group. Facility licensees are encouraged to distribute a copy of this appendix to every examinee before the examinations begin. All items apply to both initial and requalification examinations, except as noted.
PART A - GENERAL GUIDELINES
PART A - GENERAL GUIDELINES 1.
: 1.     [Read Verbatim] Cheating on any part of the examination will result in a denial of your application and/or action against your license.
[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.
2.
: 3.     SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e., shift supervisor, senior shift supervisor, or whatever the title of the position may be).
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.
: 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.
3.
: 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.
SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e., shift supervisor, senior shift supervisor, or whatever the title of the position may be).
PART B - WRITTEN EXAMINATION GUIDELINES
4.
: 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.
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.
: 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.
5.
: 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.
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.
: 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.
PART B - WRITTEN EXAMINATION GUIDELINES 1.
: 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.
[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.
: 6. Mark your answers on the answer sheet provided and do not leave any question blank.
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.
6.
Mark your answers on the answer sheet provided and do not leave any question blank.
Use only the paper provided and do not write on the back side of the pages. 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.
Use only the paper provided and do not write on the back side of the pages. 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.
: 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.
7.
: 8. Restroom trips are permitted, but only one applicant at a time will be allowed to leave.
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.
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 examination questions, examination aids, answer sheets, and scrap paper 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. The scrap paper will be disposed of immediately after the examination.
9.
: 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.
When you complete the examination, assemble a package including the examination questions, examination aids, answer sheets, and scrap paper 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. The scrap paper will be disposed of immediately after the examination.
: 11. Do you have any questions?
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?


REACTOR OPERATOR 001 a b c d ___  035 a b c d ___ 068 a b c d ___
REACTOR OPERATOR 001 a b c d ___
002 a b c d ___  036 a b c d ___ 069 a b c d ___
002 a b c d ___
003 a b c d ___  037 a b c d ___ 070 a b c d ___
003 a b c d ___
004 a b c d ___  038 a b c d ___ 071 a b c d ___
004 a b c d ___
005 a b c d ___  039 a b c d ___ 072 a b c d ___
005 a b c d ___
006 a b c d ___  040 a b c d ___ 073 a b c d ___
006 a b c d ___
007 a b c d ___  041 a b c d ___ 074 a b c d ___
007 a b c d ___
008 a b c d ___  042 a b c d ___ 075 a b c d ___
008 a b c d ___
009 a b c d ___  043 a b c d ___ 076 a b c d ___
009 a b c d ___
010 a b c d ___  044 a b c d ___ 077 a b c d ___
010 a b c d ___
011 a b c d ___  045 a b c d ___ 078 a b c d ___
011 a b c d ___
012 a b c d ___  046 a b c d ___ 079 a b c d ___
012 a b c d ___
013 a b c d ___  047 a b c d ___ 080 a b c d ___
013 a b c d ___
014 a b c d ___  048 a b c d ___ 081 a b c d ___
014 a b c d ___
015 a b c d ___  049 a b c d ___ 082 a b c d ___
015 a b c d ___
016 a b c d ___  050 a b c d ___ 083 a b c d ___
016 a b c d ___
017 a b c d ___  051 a b c d ___ 084 a b c d ___
017 a b c d ___
018 a b c d ___  052 a b c d ___ 085 a b c d ___
018 a b c d ___
019 a b c d ___  053 a b c d ___ 086 a b c d ___
019 a b c d ___
020 a b c d ___  054 a b c d ___ 087 a b c d ___
020 a b c d ___
021 a b c d ___  055 a b c d ___ 088 a b c d ___
021 a b c d ___
022 a b c d ___  056 a b c d ___ 089 a b c d ___
022 a b c d ___
023 a b c d ___  057 a b c d ___ 090 a b c d ___
023 a b c d ___
024 a b c d ___  058 a b c d ___ 091 a b c d ___
024 a b c d ___
025 a b c d ___  059 a b c d ___ 092 a b c d ___
025 a b c d ___
026 a b c d ___  060 a b c d ___ 093 a b c d ___
026 a b c d ___
027 a b c d ___  061 a b c d ___ 094 a b c d ___
027 a b c d ___
028 a b c d ___  062 a b c d ___ 095 a b c d ___
028 a b c d ___
029 a b c d ___  063 a b c d ___ 096 a b c d ___
029 a b c d ___
030 a b c d ___  064 a b c d ___ 097 a b c d ___
030 a b c d ___
031 a b c d ___  065 a b c d ___ 098 a b c d ___
031 a b c d ___
032 a b c d ___  066 a b c d ___ 099 a b c d ___
032 a b c d ___
033 a b c d ___  067 a b c d ___ 100 a b c d ___
033 a b c d ___
034 a b c d ___
034 a b c d ___
035 a b c d ___
036 a b c d ___
037 a b c d ___
038 a b c d ___
039 a b c d ___
040 a b c d ___
041 a b c d ___
042 a b c d ___
043 a b c d ___
044 a b c d ___
045 a b c d ___
046 a b c d ___
047 a b c d ___
048 a b c d ___
049 a b c d ___
050 a b c d ___
051 a b c d ___
052 a b c d ___
053 a b c d ___
054 a b c d ___
055 a b c d ___
056 a b c d ___
057 a b c d ___
058 a b c d ___
059 a b c d ___
060 a b c d ___
061 a b c d ___
062 a b c d ___
063 a b c d ___
064 a b c d ___
065 a b c d ___
066 a b c d ___
067 a b c d ___
068 a b c d ___
069 a b c d ___
070 a b c d ___
071 a b c d ___
072 a b c d ___
073 a b c d ___
074 a b c d ___
075 a b c d ___
076 a b c d ___
077 a b c d ___
078 a b c d ___
079 a b c d ___
080 a b c d ___
081 a b c d ___
082 a b c d ___
083 a b c d ___
084 a b c d ___
085 a b c d ___
086 a b c d ___
087 a b c d ___
088 a b c d ___
089 a b c d ___
090 a b c d ___
091 a b c d ___
092 a b c d ___
093 a b c d ___
094 a b c d ___
095 a b c d ___
096 a b c d ___
097 a b c d ___
098 a b c d ___
099 a b c d ___
100 a b c d ___


REACTOR OPERATOR                                                                   Page 5 QUESTION: 001 (1.00)
REACTOR OPERATOR Page 5 QUESTION: 001 (1.00)
All AC power has been lost and equipment is being placed in PULLOUT per ECA-0.0, LOSS OF ALL AC POWER. Which pump will be kept available, and why?
All AC power has been lost and equipment is being placed in PULLOUT per ECA-0.0, LOSS OF ALL AC POWER. Which pump will be kept available, and why?
: a. One RHR pump, to provide RCS inventory makeup.
a.
: b. One SI pump, to provide RCS inventory makeup.
One RHR pump, to provide RCS inventory makeup.
: c. One service water pump, to provide Diesel Generator cooling.
b.
: d. One charging pump, to provide RCP seal cooling.
One SI pump, to provide RCS inventory makeup.
c.
One service water pump, to provide Diesel Generator cooling.
d.
One charging pump, to provide RCP seal cooling.


REACTOR OPERATOR                                                                       Page 6 QUESTION: 002 (1.00)
REACTOR OPERATOR Page 6 QUESTION: 002 (1.00)
The controller output which automatically positions the Main Feedwater Regulating Valves (FW-7A & B) to maintain programmed level uses steam generator narrow range water level AND which of the following?
The controller output which automatically positions the Main Feedwater Regulating Valves (FW-7A & B) to maintain programmed level uses steam generator narrow range water level AND which of the following?
: a.       The setpoint established by the operator on the control station
a.
: b.       Steam flow and feedwater flow
The setpoint established by the operator on the control station b.
: c.       Steam flow, feedwater flow and Turbine impulse pressure
Steam flow and feedwater flow c.
: d.       Turbine impulse pressure
Steam flow, feedwater flow and Turbine impulse pressure d.
Turbine impulse pressure


REACTOR OPERATOR                                                                         Page 7 QUESTION: 003 (1.00)
REACTOR OPERATOR Page 7 QUESTION: 003 (1.00)
Containment temperature has increased from 100°F to 160°F due to a containment cooling malfunction. If the plant is stable at 100% power and there are negligible RCS or containment pressure changes, which one of the following describes the effect of the increase in containment temperature on the pressurizer level indicated by the pressurizer level control channels?
Containment temperature has increased from 100°F to 160°F due to a containment cooling malfunction. If the plant is stable at 100% power and there are negligible RCS or containment pressure changes, which one of the following describes the effect of the increase in containment temperature on the pressurizer level indicated by the pressurizer level control channels?
: a.     Indicated level will be HIGHER than actual level because the reference leg fluid density decreases.
a.
: b.     Indicated level will be LOWER than actual level because the reference leg fluid density decreases.
Indicated level will be HIGHER than actual level because the reference leg fluid density decreases.
: c.     Indicated level will be HIGHER than actual level because the elevated containment temperature causes increased flashing in the reference leg.
b.
: d.     Indicated level will be LOWER than actual level because of the elevated containment temperature causes increased flashing in the reference leg.
Indicated level will be LOWER than actual level because the reference leg fluid density decreases.
c.
Indicated level will be HIGHER than actual level because the elevated containment temperature causes increased flashing in the reference leg.
d.
Indicated level will be LOWER than actual level because of the elevated containment temperature causes increased flashing in the reference leg.


REACTOR OPERATOR                                                                       Page 8 QUESTION: 004 (1.00)
REACTOR OPERATOR Page 8 QUESTION: 004 (1.00)
Both Main Feedwater pumps are running when the "A" Main Feedwater pump trips. Which one of the following conditions prevents the start AND continued operation of the "A" Main Feedwater pump?
Both Main Feedwater pumps are running when the "A" Main Feedwater pump trips. Which one of the following conditions prevents the start AND continued operation of the "A" Main Feedwater pump?
: a.     Lube oil pressure is 10 psig.
a.
: b.     Suction pressure is 210 psig.
Lube oil pressure is 10 psig.
: c.     Recirculation valve is FULL open.
b.
: d.     Only one Condensate pump is running.
Suction pressure is 210 psig.
c.
Recirculation valve is FULL open.
d.
Only one Condensate pump is running.


REACTOR OPERATOR                                                                       Page 9 QUESTION: 005 (1.00)
REACTOR OPERATOR Page 9 QUESTION: 005 (1.00)
With power to 480 volt Bus 1-43 deenergized, which pressurizer heaters would be affected?
With power to 480 volt Bus 1-43 deenergized, which pressurizer heaters would be affected?
A. Backup group 1B ONLY B. Backup groups 1D AND 1E ONLY C. Backup Group 1A ONLY with transfer switch in Normal D. Backup group 1A with transfer switch in Alternate AND control group 1C ONLY
A.
Backup group 1B ONLY B.
Backup groups 1D AND 1E ONLY C.
Backup Group 1A ONLY with transfer switch in Normal D.
Backup group 1A with transfer switch in Alternate AND control group 1C ONLY


REACTOR OPERATOR                                                                       Page 10 QUESTION: 006 (1.00)
REACTOR OPERATOR Page 10 QUESTION: 006 (1.00)
Given the following:
Given the following:
      -      Station and Instrument Air System is in a normal/automatic system lineup.
Station and Instrument Air System is in a normal/automatic system lineup.
      -      The station air compressor preferred selector switch is aligned to Compressor G.
The station air compressor preferred selector switch is aligned to Compressor G.
Which of the following automatically occur when the Station and Instrument Air System air header pressure is decreasing and reaches 95 psig?
Which of the following automatically occur when the Station and Instrument Air System air header pressure is decreasing and reaches 95 psig?
: a.     Air dryers are bypassed AND Station air compressor F starts.
a.
: b.     Station air compressor F starts AND SA-400, (SA Header B Supply Valve) is fully closed.
Air dryers are bypassed AND Station air compressor F starts.
: c.     SA-200, (SA Header A Supply Valve) AND SA-400, (SA Header B Supply Valve) start to close.
b.
: d.     Instrument air compressor C starts and isolates from station air header AND SA-200, (SA Header A Supply Valve) is fully closed.
Station air compressor F starts AND SA-400, (SA Header B Supply Valve) is fully closed.
c.
SA-200, (SA Header A Supply Valve) AND SA-400, (SA Header B Supply Valve) start to close.
d.
Instrument air compressor C starts and isolates from station air header AND SA-200, (SA Header A Supply Valve) is fully closed.


REACTOR OPERATOR                                                                         Page 11 QUESTION: 007 (1.00)
REACTOR OPERATOR Page 11 QUESTION: 007 (1.00)
With the plant initially at 100% power, steady-state, which one of the following describes an effect of power range channel N-42 upper detector failing HIGH?
With the plant initially at 100% power, steady-state, which one of the following describes an effect of power range channel N-42 upper detector failing HIGH?
: a. Reactor trips on high flux.
a.
: b. Main feed regulating valves fully open.
Reactor trips on high flux.
: c. Control rods step out to high bank rod stop.
b.
: d. Over-temperature DT setpoint for one channel decreases.
Main feed regulating valves fully open.
c.
Control rods step out to high bank rod stop.
d.
Over-temperature DT setpoint for one channel decreases.


REACTOR OPERATOR                                                                     Page 12 QUESTION: 008 (1.00)
REACTOR OPERATOR Page 12 QUESTION: 008 (1.00)
The unit is at 100% power with Instrument air pressure at 115 psig. Station Air Compressor F is tagged out for preventive maintenance. What will instrument air pressure do when Station Air Compressor G is tripped.
The unit is at 100% power with Instrument air pressure at 115 psig. Station Air Compressor F is tagged out for preventive maintenance. What will instrument air pressure do when Station Air Compressor G is tripped.
: a.     decrease, then increase to a value above its previous pressure.
a.
: b.     remain unaffected.
decrease, then increase to a value above its previous pressure.
: c.     slowly decrease to a point where the unit will have to be tripped.
b.
: d.     decrease, then increase to a value below its previous pressure.
remain unaffected.
c.
slowly decrease to a point where the unit will have to be tripped.
d.
decrease, then increase to a value below its previous pressure.


REACTOR OPERATOR                                                           Page 13 QUESTION: 009 (1.00)
REACTOR OPERATOR Page 13 QUESTION: 009 (1.00)
The following plant conditions exist:
The following plant conditions exist:
        -      Reactor is Critical at 10-3 percent power
Reactor is Critical at 10-3 percent power RCS Tavg is 547°F and steady Pressurizer pressure is 2235 psig and steady Control Bank D position is 100 steps ONE Control Bank D rod drops Describe the INITIAL response of Tavg and Pressurizer pressure (PZR Press):
        -      RCS Tavg is 547°F and steady
Tavg PZR Press a.
        -      Pressurizer pressure is 2235 psig and steady
Remain the same Remain the same b.
        -      Control Bank D position is 100 steps
Increase Remain the same c.
        -      ONE Control Bank D rod drops Describe the INITIAL response of Tavg and Pressurizer pressure (PZR Press):
Remain the same Increase d.
Tavg                           PZR Press
Decrease Decrease
: a. Remain the same                 Remain the same
: b. Increase                       Remain the same
: c. Remain the same                 Increase
: d. Decrease                       Decrease


REACTOR OPERATOR                                                                       Page 14 QUESTION: 010 (1.00)
REACTOR OPERATOR Page 14 QUESTION: 010 (1.00)
The following conditions exist:
The following conditions exist:
        -      90% Reactor power.
90% Reactor power.
        -      Pressurizer Pressure control is in automatic
Pressurizer Pressure control is in automatic Backup heaters are in "AUTO".
        -      Backup heaters are in "AUTO".
Actual Pressurizer Pressure is 2235 psig.
        -      Actual Pressurizer Pressure is 2235 psig.
The Pressurizer Pressure Master Controller malfunctions and its SETPOINT drifts to 2100 psig over a 10 minute period. Which of the following describes the INITIAL automatic response of the Pressurizer Pressure Control System as this failure occurs?
The Pressurizer Pressure Master Controller malfunctions and its SETPOINT drifts to 2100 psig over a 10 minute period. Which of the following describes the INITIAL automatic response of the Pressurizer Pressure Control System as this failure occurs?
: a. Spray valves throttle closed and variable heaters go to maximum current.
a.
: b. Spray valves throttle open and variable heaters go to minimum current.
Spray valves throttle closed and variable heaters go to maximum current.
: c. Pressurizer PORVs PR-2A and PR-2B open, Spray valves throttle open, and Group C heaters go to minimum current.
b.
: d. Spray valves throttle closed, pressurizer backup heater groups go to maximum current, and backup heaters come "ON."
Spray valves throttle open and variable heaters go to minimum current.
c.
Pressurizer PORVs PR-2A and PR-2B open, Spray valves throttle open, and Group C heaters go to minimum current.
d.
Spray valves throttle closed, pressurizer backup heater groups go to maximum current, and backup heaters come "ON."


REACTOR OPERATOR                                                                           Page 15 QUESTION: 011 (1.00)
REACTOR OPERATOR Page 15 QUESTION: 011 (1.00)
Which of the following electrical interlocks prevents release of radioactive water to the RWST during transfer to Containment Sump Recirculation during a LOCA?
Which of the following electrical interlocks prevents release of radioactive water to the RWST during transfer to Containment Sump Recirculation during a LOCA?
: a. Close SI-300A/B, RWST Supply Valve to an RHR pump, before opening SI-350A/B, Containment Sump B Isolation Valve to an RHR pump.
a.
: b. Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening SI-350A/B and 351A/B, Containment Sump B Isolation Valves to an RHR pump.
Close SI-300A/B, RWST Supply Valve to an RHR pump, before opening SI-350A/B, Containment Sump B Isolation Valve to an RHR pump.
: c. Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.
b.
: d. Open SI-350A/B and 351A/B, Containment Sump B Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.
Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening SI-350A/B and 351A/B, Containment Sump B Isolation Valves to an RHR pump.
c.
Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.
d.
Open SI-350A/B and 351A/B, Containment Sump B Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.


REACTOR OPERATOR                                                                       Page 16 QUESTION: 012 (1.00)
REACTOR OPERATOR Page 16 QUESTION: 012 (1.00)
Given the following conditions:
Given the following conditions:
      -        Component Cooling Pump "A" is running
Component Cooling Pump "A" is running Component Cooling Pump "B" is in standby D/G "B" is out of service for maintenance A safety Injection signal is generated. Which one of the following describes the response of the Component Cooling Water Pumps?
      -        Component Cooling Pump "B" is in standby
Pump A Pump B a.
      -        D/G "B" is out of service for maintenance A safety Injection signal is generated. Which one of the following describes the response of the Component Cooling Water Pumps?
Runs continuously Sequences on b.
Pump A                 Pump B
Stops then sequences on Remains off c.
: a.       Runs continuously             Sequences on
Runs continuously Remains off d.
: b.       Stops then sequences on       Remains off
Stops then sequences on Sequences on
: c.       Runs continuously             Remains off
: d.       Stops then sequences on       Sequences on


REACTOR OPERATOR                                                                           Page 17 QUESTION: 013 (1.00)
REACTOR OPERATOR Page 17 QUESTION: 013 (1.00)
Given the following conditions:
Given the following conditions:
      -      The plant is operating at 18% power
The plant is operating at 18% power The high pressure piping to RCS flow instrument FT-411 on Loop A breaks What is the status of Loop A RCS flow indicators and what is the resulting plant condition (assume NO operator action is taken)?
      -      The high pressure piping to RCS flow instrument FT-411 on Loop A breaks What is the status of Loop A RCS flow indicators and what is the resulting plant condition (assume NO operator action is taken)?
a.
: a.     All Loop A flow indicators will read low, and the reactor will trip on RCS loop low flow.
All Loop A flow indicators will read low, and the reactor will trip on RCS loop low flow.
: b.     All Loop A flow indicators will read low, and the reactor will trip on low PRZR pressure.
b.
: c.     Only FI-411 RCS flow indication will read low, and no reactor trip is generated.
All Loop A flow indicators will read low, and the reactor will trip on low PRZR pressure.
: d.     Only FI-411 RCS flow indication will read low, and the reactor will trip on low PRZR pressure.
c.
Only FI-411 RCS flow indication will read low, and no reactor trip is generated.
d.
Only FI-411 RCS flow indication will read low, and the reactor will trip on low PRZR pressure.


REACTOR OPERATOR                                                                         Page 18 QUESTION: 014 (1.00)
REACTOR OPERATOR Page 18 QUESTION: 014 (1.00)
Given the following conditions:
Given the following conditions:
        -        The plant is at 15% power
The plant is at 15% power S/G B level channel LT-473 is removed from service per A-MI-87 If S/G B level channel LT-471 fails high, what would be the status of feed for the S/Gs?
        -        S/G B level channel LT-473 is removed from service per A-MI-87 If S/G B level channel LT-471 fails high, what would be the status of feed for the S/Gs?
a.
: a.       Both S/Gs are being fed from the motor-driven AFW Pumps only.
Both S/Gs are being fed from the motor-driven AFW Pumps only.
: b.       Both S/Gs are being fed from the turbine-driven AFW Pump only.
b.
: c.       S/G A is being fed from the motor-driven AFW Pump. S/G B has no feed flow.
Both S/Gs are being fed from the turbine-driven AFW Pump only.
: d.       Feed to S/G A remains normal. Feed to S/G B lowers due to throttling close of FW-7B, S/G B Main Feed valve.
c.
S/G A is being fed from the motor-driven AFW Pump. S/G B has no feed flow.
d.
Feed to S/G A remains normal. Feed to S/G B lowers due to throttling close of FW-7B, S/G B Main Feed valve.


REACTOR OPERATOR                                                                     Page 19 QUESTION: 015 (1.00)
REACTOR OPERATOR Page 19 QUESTION: 015 (1.00)
Which one of the following describes the operation of LD-13, Letdown Line Pressure Relief Valve?
Which one of the following describes the operation of LD-13, Letdown Line Pressure Relief Valve?
: a. Relieves at 200 psig to the VCT
a.
: b. Relieves at 150 psig to the PRT
Relieves at 200 psig to the VCT b.
: c. Relieves at 150 psig to the VCT
Relieves at 150 psig to the PRT c.
: d. Relieves at 200 psig to the PRT.
Relieves at 150 psig to the VCT d.
Relieves at 200 psig to the PRT.


REACTOR OPERATOR                                                                       Page 20 QUESTION: 016 (1.00)
REACTOR OPERATOR Page 20 QUESTION: 016 (1.00)
The plant is in Hot shutdown, with the following conditions:
The plant is in Hot shutdown, with the following conditions:
        -      Tave = 547°F with both RXCPs operating
Tave = 547°F with both RXCPs operating A Main Feedwater Pump is running Steam Generator A Narrow Range Level = 20%
        -      A Main Feedwater Pump is running
Steam Generator B Narrow Range Level = 15%
        -      Steam Generator A Narrow Range Level = 20%
Condensate Pump A is Hold Carded in Pullout.
        -      Steam Generator B Narrow Range Level = 15%
Condensate Pump B is running All three Auxiliary Feedwater Pumps are in Off and in Pullout All the support conditions for the Auxiliary Feedwater Pumps are met At the direction of the CRS, the BOP places all three Auxiliary Feedwater Pump control switches into the AUTO position.
        -      Condensate Pump A is Hold Carded in Pullout.
        -      Condensate Pump B is running
        -      All three Auxiliary Feedwater Pumps are in Off and in Pullout
        -      All the support conditions for the Auxiliary Feedwater Pumps are met At the direction of the CRS, the BOP places all three Auxiliary Feedwater Pump control switches into the AUTO position.
Without further operator actions, what is the status of the Auxiliary Feedwater Pumps?
Without further operator actions, what is the status of the Auxiliary Feedwater Pumps?
MDAFW Pumps           TDAFW
MDAFW Pumps TDAFW a.
: a.     Running               Running
Running Running b.
: b.     Running               Off
Running Off c.
: c.     Off                   Running
Off Running d.
: d.     Off                   Off
Off Off


REACTOR OPERATOR                                                                         Page 21 QUESTION: 017 (1.00)
REACTOR OPERATOR Page 21 QUESTION: 017 (1.00)
SP-54-086, "Turbine Stop and Governor Valve Operability," directs depressing the CLOSE SV-1 pushbutton. Which of the following statements identifies an expected response of the turbine control valves (CV-1 through CV-4) and turbine stop valve (SV-1) to this action?
SP-54-086, "Turbine Stop and Governor Valve Operability," directs depressing the CLOSE SV-1 pushbutton. Which of the following statements identifies an expected response of the turbine control valves (CV-1 through CV-4) and turbine stop valve (SV-1) to this action?
: a.     SV-1 closes, then CV-1 and CV-3 close.
a.
: b.     SV-1 closes, then CV-1 and CV-2 close.
SV-1 closes, then CV-1 and CV-3 close.
: c.     CV-1 and CV-2 close, then SV-1 closes.
b.
: d.     CV-1 and CV-3 close, then SV-1 closes.
SV-1 closes, then CV-1 and CV-2 close.
c.
CV-1 and CV-2 close, then SV-1 closes.
d.
CV-1 and CV-3 close, then SV-1 closes.


REACTOR OPERATOR                                                               Page 22 QUESTION: 018 (1.00)
REACTOR OPERATOR Page 22 QUESTION: 018 (1.00)
The following conditions exist:
The following conditions exist:
        -      A LOCA has occurred.
A LOCA has occurred.
        -      The crew is trying to reduce ECCS flow.
The crew is trying to reduce ECCS flow.
        -      All equipment is operating properly.
All equipment is operating properly.
        -      Wide Range RCS pressure is 800 psig.
Wide Range RCS pressure is 800 psig.
        -      65°F of subcooling is required to stop one of the ECCS pumps.
65°F of subcooling is required to stop one of the ECCS pumps.
What is the MAXIMUM Core Exit Thermocouple temperature at which the pump is stopped?
What is the MAXIMUM Core Exit Thermocouple temperature at which the pump is stopped?
: a. 430°F.
a.
: b. 455°F.
430°F.
: c. 480°F.
b.
: d. 505°F.
455°F.
c.
480°F.
d.
505°F.


REACTOR OPERATOR                                                                     Page 23 QUESTION: 019 (1.00)
REACTOR OPERATOR Page 23 QUESTION: 019 (1.00)
Given the following:
Given the following:
      -      The reactor is critical at 1% power.
The reactor is critical at 1% power.
      -      SI Accumulator A water volume was just found to be 1270 cubic ft (48%).
SI Accumulator A water volume was just found to be 1270 cubic ft (48%).
      -      SI Accumulator B water volume was found to be 1220 cubic ft (20%) at the same time.
SI Accumulator B water volume was found to be 1220 cubic ft (20%) at the same time.
What action is required due to these conditions, if any?
What action is required due to these conditions, if any?
: a.     No action is needed due to these conditions.
a.
: b.     SI Accumulator A water volume must be restored to limits.
No action is needed due to these conditions.
: c.     SI Accumulator B water volume must be restored to limits.
b.
: d.     Action must be initiated within 1 hour to go to HOT SHUTDOWN.
SI Accumulator A water volume must be restored to limits.
c.
SI Accumulator B water volume must be restored to limits.
d.
Action must be initiated within 1 hour to go to HOT SHUTDOWN.


REACTOR OPERATOR                                                                       Page 24 QUESTION: 020 (1.00)
REACTOR OPERATOR Page 24 QUESTION: 020 (1.00)
Given the following conditions:
Given the following conditions:
      -      Reactor Vessel Head AND Upper Internals have been removed.
Reactor Vessel Head AND Upper Internals have been removed.
      -      Residual Heat Removal boron concentration is 2458 ppm.
Residual Heat Removal boron concentration is 2458 ppm.
      -      The reactor has been shutdown for 7 days.
The reactor has been shutdown for 7 days.
      -      Spent Fuel Pool Pump "A" is operating per N-SFP-21, Spent Fuel Pool Cooling and Cleanup System. Spent Fuel Pool Pump "B" is inoperable.
Spent Fuel Pool Pump "A" is operating per N-SFP-21, Spent Fuel Pool Cooling and Cleanup System. Spent Fuel Pool Pump "B" is inoperable.
      -      Residual Heat Removal Pump "A" is operating. Residual Heat Removal Pump "B" is inoperable.
Residual Heat Removal Pump "A" is operating. Residual Heat Removal Pump "B" is inoperable.
      -      Refueling Cavity level is greater than 23 feet above the vessel flange.
Refueling Cavity level is greater than 23 feet above the vessel flange.
Based on the plant status given, determine what condition must be resolved to meet requirements for a fuel shuffle within the reactor that is NOT a full core offload.
Based on the plant status given, determine what condition must be resolved to meet requirements for a fuel shuffle within the reactor that is NOT a full core offload.
: a.     Residual Heat Removal boron concentration is too low.
a.
: b.     Spent Fuel Pool Cooling Pump "B" is required to be operable.
Residual Heat Removal boron concentration is too low.
: c.     The reactor has not been shutdown long enough.
b.
: d.     Residual Heat Removal Pump "B" is required to be operable.
Spent Fuel Pool Cooling Pump "B" is required to be operable.
c.
The reactor has not been shutdown long enough.
d.
Residual Heat Removal Pump "B" is required to be operable.


REACTOR OPERATOR                                                                           Page 25 QUESTION: 021 (1.00)
REACTOR OPERATOR Page 25 QUESTION: 021 (1.00)
Which of the following is the purpose of NAD-02.07, Kewaunee Refueling Operations?
Which of the following is the purpose of NAD-02.07, Kewaunee Refueling Operations?
: a.       Provides step-by-step instructions to be used by fuel handlers during core offload.
a.
: b.       Provides administrative instructions for reactor engineers to follow when developing the fuel shuffle sequence to prevent inadvertent criticality during core reload.
Provides step-by-step instructions to be used by fuel handlers during core offload.
: c.       Describes the organization and responsibilities for reactor vessel disassembly, reassembly, and fuel handling operations.
b.
: d.       Provides step-by-step instructions on completing a Fuel Assembly Handling Deviation Report.
Provides administrative instructions for reactor engineers to follow when developing the fuel shuffle sequence to prevent inadvertent criticality during core reload.
c.
Describes the organization and responsibilities for reactor vessel disassembly, reassembly, and fuel handling operations.
d.
Provides step-by-step instructions on completing a Fuel Assembly Handling Deviation Report.


REACTOR OPERATOR                                                                       Page 26 QUESTION: 022 (1.00)
REACTOR OPERATOR Page 26 QUESTION: 022 (1.00)
A point source in containment is reading 300 mRem/hr at a distance of two (2) feet. Two options are available to complete a mandatory work assignment near this radiation source:
A point source in containment is reading 300 mRem/hr at a distance of two (2) feet. Two options are available to complete a mandatory work assignment near this radiation source:
Option 1 - ONE operator can perform the assignment in fifty (50) minutes working at a distance of three (3) feet from the source.
Option 1 - ONE operator can perform the assignment in fifty (50) minutes working at a distance of three (3) feet from the source.
Option 2 - THREE operators, using special extension tooling, can perform the assignment in sixty (60) minutes at a distance of six (6) feet from the source Which is the preferred option based on ALARA and the corresponding total exposure?
Option 2 - THREE operators, using special extension tooling, can perform the assignment in sixty (60) minutes at a distance of six (6) feet from the source Which is the preferred option based on ALARA and the corresponding total exposure?
: a.     Option 1, with a total exposure of 0.100 Person-REM
a.
: b.     Option 1, with a total exposure of 0.111 Person-REM
Option 1, with a total exposure of 0.100 Person-REM b.
: c.     Option 2, with a total exposure of 0.100 Person-REM
Option 1, with a total exposure of 0.111 Person-REM c.
: d.     Option 2, with a total exposure of 0.111 Person-REM
Option 2, with a total exposure of 0.100 Person-REM d.
Option 2, with a total exposure of 0.111 Person-REM


REACTOR OPERATOR                                                                         Page 27 QUESTION: 023 (1.00)
REACTOR OPERATOR Page 27 QUESTION: 023 (1.00)
Which of the following is listed in E-0, "Reactor Trip or Safety Injection," step 1 CONTINGENCY ACTIONS but is NOT in FR-S.1, "Response to a Nuclear Power Generation/ATWS," step 1 CONTINGENCY ACTIONS?
Which of the following is listed in E-0, "Reactor Trip or Safety Injection," step 1 CONTINGENCY ACTIONS but is NOT in FR-S.1, "Response to a Nuclear Power Generation/ATWS," step 1 CONTINGENCY ACTIONS?
: a.         Source range counts
a.
: b.         Intermediate range power
Source range counts b.
: c.         Reactor Trip Breakers
Intermediate range power c.
: d.         Bypass Breakers
Reactor Trip Breakers d.
Bypass Breakers


REACTOR OPERATOR                                                                         Page 28 QUESTION: 024 (1.00)
REACTOR OPERATOR Page 28 QUESTION: 024 (1.00)
Which of the following is the basis for maintaining SG Narrow Range levels between 4% and 50% during procedure ECA-0.0, "LOSS OF ALL AC POWER?"
Which of the following is the basis for maintaining SG Narrow Range levels between 4% and 50% during procedure ECA-0.0, "LOSS OF ALL AC POWER?"
: a.       Ensures the capability to cooldown the reactor only after AC power is restored.
a.
: b.       Ensures heat transfer capability exists to remove heat from the RCS.
Ensures the capability to cooldown the reactor only after AC power is restored.
: c.       Narrow Range level is the only reliable indication of SG inventory available after a loss of all AC power.
b.
: d.       Provides capability to monitor the SGs for a Steam Generator Tube Rupture.
Ensures heat transfer capability exists to remove heat from the RCS.
c.
Narrow Range level is the only reliable indication of SG inventory available after a loss of all AC power.
d.
Provides capability to monitor the SGs for a Steam Generator Tube Rupture.


REACTOR OPERATOR                                                                       Page 29 QUESTION: 025 (1.00)
REACTOR OPERATOR Page 29 QUESTION: 025 (1.00)
Which ONE of the following describes the mitigating strategies contained in ECA-1.1, "Loss of Emergency Coolant Recirculation?"
Which ONE of the following describes the mitigating strategies contained in ECA-1.1, "Loss of Emergency Coolant Recirculation?"
: a. Minimizing the depletion of the RWST, Maximizing Subcooling, determination of minimum containment spray requirements.
a.
: b. Maximizing Subcooling, minimizing the depletion of the RWST, and depressurization of the RCS to minimize break flow.
Minimizing the depletion of the RWST, Maximizing Subcooling, determination of minimum containment spray requirements.
: c. Minimizing the depletion of the RWST, determination of minimum containment spray requirements, and depressurization of the RCS to minimize break flow.
b.
: d. Maximizing subcooling, determination of minimum containment spray, and depressurization of the RCS to minimize break flow.
Maximizing Subcooling, minimizing the depletion of the RWST, and depressurization of the RCS to minimize break flow.
c.
Minimizing the depletion of the RWST, determination of minimum containment spray requirements, and depressurization of the RCS to minimize break flow.
d.
Maximizing subcooling, determination of minimum containment spray, and depressurization of the RCS to minimize break flow.


REACTOR OPERATOR                                                                 Page 30 QUESTION: 026 (1.00)
REACTOR OPERATOR Page 30 QUESTION: 026 (1.00)
Given the following CRDM coil rod motion sequence:
Given the following CRDM coil rod motion sequence:
      -      1. Stationary Gripper Energized at Low Voltage
: 1. Stationary Gripper Energized at Low Voltage
      -      2. Stationary Gripper Energizes at High Voltage
: 2. Stationary Gripper Energizes at High Voltage
      -      3. Movable Gripper Energizes
: 3. Movable Gripper Energizes
      -      4. Stationary Gripper De-energizes The next step in the sequence is __________ and the rod is being moved ____________
: 4. Stationary Gripper De-energizes The next step in the sequence is __________ and the rod is being moved ____________
: a.     Lift Coil De-energizes, Inward
a.
: b.     Lift Coil Energizes, Outward
Lift Coil De-energizes, Inward b.
: c.     Stationary Gripper Energizes at Low Voltage, Inward
Lift Coil Energizes, Outward c.
: d.     Stationary Gripper Energizes at High Voltage, Outward
Stationary Gripper Energizes at Low Voltage, Inward d.
Stationary Gripper Energizes at High Voltage, Outward


REACTOR OPERATOR                                                                     Page 31 QUESTION: 027 (1.00)
REACTOR OPERATOR Page 31 QUESTION: 027 (1.00)
With the plant in the operating mode, the reactor operator receives ROD CONTROL SYSTEM ABNORMAL annunciator and SER point 1692, "Rod Control System Non-Urgent Failure."
With the plant in the operating mode, the reactor operator receives ROD CONTROL SYSTEM ABNORMAL annunciator and SER point 1692, "Rod Control System Non-Urgent Failure."
Instrument and Control technicians narrow the problem to the Rod Control Logic Cabinet. What may have caused this condition to occur?
Instrument and Control technicians narrow the problem to the Rod Control Logic Cabinet. What may have caused this condition to occur?
: a.     Slave cycler cycles without a GO pulse
a.
: b.     A redundant power supply has been lost
Slave cycler cycles without a GO pulse b.
: c.     Oscillator fails to generate signals when called for
A redundant power supply has been lost c.
: d.     There is a loose printed circuit card in the logic circuitry
Oscillator fails to generate signals when called for d.
There is a loose printed circuit card in the logic circuitry


REACTOR OPERATOR                                                                   Page 32 QUESTION: 028 (1.00)
REACTOR OPERATOR Page 32 QUESTION: 028 (1.00)
Which of the following conditions results in a Main Steam Isolation?
Which of the following conditions results in a Main Steam Isolation?
: a.       Containment pressure of 15 psig.
a.
: b.       Steamline flow of 4X106 lb/hr AND an "SI" signal.
Containment pressure of 15 psig.
: c.       Steamline flow of 5X106 lb/hr AND Tavg of 530°F.
b.
: d.       Steamline flow of 0.8X106 lb/hr, Tavg of 530°F, AND an "SI" signal.
Steamline flow of 4X106 lb/hr AND an "SI" signal.
c.
Steamline flow of 5X106 lb/hr AND Tavg of 530°F.
d.
Steamline flow of 0.8X106 lb/hr, Tavg of 530°F, AND an "SI" signal.


REACTOR OPERATOR                                                                     Page 33 QUESTION: 029 (1.00)
REACTOR OPERATOR Page 33 QUESTION: 029 (1.00)
The unit is at 100% power with Charging pump A operating in automatic. Charging Line Flow Control valve, CVC-7, is throttled to 70%. CVC-7 then fails open. Charging pump As speed will . . . .
The unit is at 100% power with Charging pump A operating in automatic. Charging Line Flow Control valve, CVC-7, is throttled to 70%. CVC-7 then fails open. Charging pump As speed will....
: a. NOT change during this event
a.
: b. decrease at first, then returns to its initial speed
NOT change during this event b.
: c. increases at first, then remains above its initial speed
decrease at first, then returns to its initial speed c.
: d. decreases at first, then remains below its initial speed
increases at first, then remains above its initial speed d.
decreases at first, then remains below its initial speed


REACTOR OPERATOR                                                                           Page 34 QUESTION: 030 (1.00)
REACTOR OPERATOR Page 34 QUESTION: 030 (1.00)
A plant startup is in progress with power at 8 percent. Intermediate Range drawer N-36 Level Trip switch is in the BYPASS position. What is the plant response to removal of N-36 control power fuses and the reason for the plant response?
A plant startup is in progress with power at 8 percent. Intermediate Range drawer N-36 Level Trip switch is in the BYPASS position. What is the plant response to removal of N-36 control power fuses and the reason for the plant response?
: a.     A trip will occur because the Level Trip Switch bypass function will be removed.
a.
: b.     A trip will not occur because the Level Trip Switch is in the bypass position and the bypass function is not affected at any power level.
A trip will occur because the Level Trip Switch bypass function will be removed.
: c.     A trip will not occur because the Level Trip Switch is in the bypass position and power is less than P-10.
b.
: d.     A trip will occur because the Level Trip Switch bypass function is operable only above P-10.
A trip will not occur because the Level Trip Switch is in the bypass position and the bypass function is not affected at any power level.
c.
A trip will not occur because the Level Trip Switch is in the bypass position and power is less than P-10.
d.
A trip will occur because the Level Trip Switch bypass function is operable only above P-10.


REACTOR OPERATOR                                                                       Page 35 QUESTION: 031 (1.00)
REACTOR OPERATOR Page 35 QUESTION: 031 (1.00)
While operating at 100% power, Graphics Display 4 on PPCS shows the B7 CET temperature to be 592°F.
While operating at 100% power, Graphics Display 4 on PPCS shows the B7 CET temperature to be 592°F.
Which of the following sequence of actions identifies how the operator would display the B7 CET temperature value (Channel 20 on Train B) at the ICCMS panels?
Which of the following sequence of actions identifies how the operator would display the B7 CET temperature value (Channel 20 on Train B) at the ICCMS panels?
Depress the CET ID/CET TEMP pushbutton to illuminate the...
Depress the CET ID/CET TEMP pushbutton to illuminate the...
: a.     CET TEMP lamp, then depress the AVG/HOT pushbutton to display the B7 CET temperature.
a.
: b.     CET TEMP lamp, then depress the REF1/REF2 pushbutton to display the B7 CET temperature.
CET TEMP lamp, then depress the AVG/HOT pushbutton to display the B7 CET temperature.
: c.     CET ID lamp, then depress the REF1/REF2 pushbutton until "B7" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.
b.
: d.     CET ID lamp, then depress the AVG/HOT pushbutton until "20" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.
CET TEMP lamp, then depress the REF1/REF2 pushbutton to display the B7 CET temperature.
c.
CET ID lamp, then depress the REF1/REF2 pushbutton until "B7" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.
d.
CET ID lamp, then depress the AVG/HOT pushbutton until "20" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.


REACTOR OPERATOR                                                                       Page 36 QUESTION: 032 (1.00)
REACTOR OPERATOR Page 36 QUESTION: 032 (1.00)
Given the following conditions:
Given the following conditions:
      -      Four CFCUs were running prior to the event
Four CFCUs were running prior to the event A Safety Injection signal was just received Containment Pressure has increased to 3.5 psig and is currently stable What condition would you expect the CFCUs to be in at this time?
      -      A Safety Injection signal was just received
a.
      -      Containment Pressure has increased to 3.5 psig and is currently stable What condition would you expect the CFCUs to be in at this time?
All CFCUs would be running with SW return isolation valves throttled to maintain temperature b.
: a.     All CFCUs would be running with SW return isolation valves throttled to maintain temperature
All CFCUs would be running with CFCU Emergency Discharge dampers open and SW return isolation valves throttled to maintain temperature c.
: b.     All CFCUs would be running with CFCU Emergency Discharge dampers open and SW return isolation valves throttled to maintain temperature
All CFCUs would be running with SW return isolation valves fully open d.
: c.     All CFCUs would be running with SW return isolation valves fully open
All CFCUs would be running with CFCU Emergency Discharge dampers and SW return isolation valves fully open
: d.     All CFCUs would be running with CFCU Emergency Discharge dampers and SW return isolation valves fully open


REACTOR OPERATOR                                                                         Page 37 QUESTION: 033 (1.00)
REACTOR OPERATOR Page 37 QUESTION: 033 (1.00)
Given the following conditions:
Given the following conditions:
        -      The plant has tripped and a Safety Injection signal has been generated.
The plant has tripped and a Safety Injection signal has been generated.
        -      Engineered Safeguard Features Actuation System Train A relays have failed to operate ONLY the Service Water System valves.
Engineered Safeguard Features Actuation System Train A relays have failed to operate ONLY the Service Water System valves.
        -      Train B relays have operated properly.
Train B relays have operated properly.
At the completion of the SI sequence, what is the status of Service Water flow to Component Cooling Water (CCW) Heat Exchanger A, if NO operator action is taken?
At the completion of the SI sequence, what is the status of Service Water flow to Component Cooling Water (CCW) Heat Exchanger A, if NO operator action is taken?
: a. There will be NO Service Water flow through the CCW heat exchanger.
a.
: b. SW flow will be at a set constant value lower than its post-accident expected value.
There will be NO Service Water flow through the CCW heat exchanger.
: c. SW flow through the CCW heat exchanger will be at its post-accident expected value.
b.
: d. SW flow will be lower than its post-accident expected value and controlled by the CCW outlet header temperature.
SW flow will be at a set constant value lower than its post-accident expected value.
c.
SW flow through the CCW heat exchanger will be at its post-accident expected value.
d.
SW flow will be lower than its post-accident expected value and controlled by the CCW outlet header temperature.


REACTOR OPERATOR                                                                       Page 38 QUESTION: 034 (1.00)
REACTOR OPERATOR Page 38 QUESTION: 034 (1.00)
Given the following conditions:
Given the following conditions:
        -      The plant is at 55% power and steady.
The plant is at 55% power and steady.
        -      The "A" Main FW pump is in pullout.
The "A" Main FW pump is in pullout.
        -      The "B" Main FW pump is running with two condensate pumps.
The "B" Main FW pump is running with two condensate pumps.
        -      Annunciator 47062-A, "S/G A Program Level Deviation" is LIT.
Annunciator 47062-A, "S/G A Program Level Deviation" is LIT.
        -      All 3 S/G A level indicators are 38% and steady.
All 3 S/G A level indicators are 38% and steady.
Which of the following describes actions to be taken by the operator based on these conditions?
Which of the following describes actions to be taken by the operator based on these conditions?
: a. START "A" Main FW pump per N-FW-05B, Feedwater System Normal Operation AND MONITOR "A" S/G level automatic control for proper operation.
a.
: b. REDUCE load to < 50% AND MONITOR "A" S/G level automatic control for proper operation.
START "A" Main FW pump per N-FW-05B, Feedwater System Normal Operation AND MONITOR "A" S/G level automatic control for proper operation.
: c. Place Feedwater Flow Control Valve FW-7A to MANUAL AND GO to A-MI-87, Bistable Tripping for Failed Reactor Protection or Safeguards Instrumentation.
b.
: d. GO to A-FW-05A, Abnormal Feedwater System Operation, AND DETERMINE if manual feedwater control is required.
REDUCE load to < 50% AND MONITOR "A" S/G level automatic control for proper operation.
c.
Place Feedwater Flow Control Valve FW-7A to MANUAL AND GO to A-MI-87, Bistable Tripping for Failed Reactor Protection or Safeguards Instrumentation.
d.
GO to A-FW-05A, Abnormal Feedwater System Operation, AND DETERMINE if manual feedwater control is required.


REACTOR OPERATOR                                                                       Page 39 QUESTION: 035 (1.00)
REACTOR OPERATOR Page 39 QUESTION: 035 (1.00)
Given the following plant conditions:
Given the following plant conditions:
      -      The reactor is at 100% power
The reactor is at 100% power All systems are in a normal lineup Based on these conditions, which one of the following correctly states the power supply to the Reactor Coolant Pumps?
      -      All systems are in a normal lineup Based on these conditions, which one of the following correctly states the power supply to the Reactor Coolant Pumps?
RXCP A RXCP B a.
RXCP A         RXCP B
MAT MAT b.
: a.     MAT           MAT
RAT MAT c.
: b.     RAT           MAT
MAT RAT d.
: c.     MAT           RAT
RAT RAT
: d.     RAT           RAT


REACTOR OPERATOR                                                                 Page 40 QUESTION: 036 (1.00)
REACTOR OPERATOR Page 40 QUESTION: 036 (1.00)
In procedure FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, the step to check if SI can be terminated is based on which of the following parameter(s):
In procedure FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, the step to check if SI can be terminated is based on which of the following parameter(s):
: a. RCS Subcooling ONLY.
a.
: b. RCS Subcooling and RCS Cold Leg Temperatures.
RCS Subcooling ONLY.
: c. RCS Pressure ONLY.
b.
: d. RCS Pressure and RCS Cold Leg Temperatures.
RCS Subcooling and RCS Cold Leg Temperatures.
c.
RCS Pressure ONLY.
d.
RCS Pressure and RCS Cold Leg Temperatures.


REACTOR OPERATOR                                                                       Page 41 QUESTION: 037 (1.00)
REACTOR OPERATOR Page 41 QUESTION: 037 (1.00)
ECA-2.1, Uncontrolled Depressurization of Both Steam Generators, has been entered from E-2, Faulted Steam Generator Isolation. Containment pressure is 1.0 psig. Each steam generator is being fed at 100 gpm producing an RCS cooldown rate of 120&deg;F/hr. Steam generator water levels are as follows:
ECA-2.1, Uncontrolled Depressurization of Both Steam Generators, has been entered from E-2, Faulted Steam Generator Isolation. Containment pressure is 1.0 psig. Each steam generator is being fed at 100 gpm producing an RCS cooldown rate of 120&deg;F/hr. Steam generator water levels are as follows:
      -      Steam Generator A narrow range levels - 2%
Steam Generator A narrow range levels - 2%
      -      Steam Generator B narrow range levels - 8%
Steam Generator B narrow range levels - 8%
Based on the conditions above, what is the appropriate initial operator action?
Based on the conditions above, what is the appropriate initial operator action?
: a.     Decrease feed flow to each steam generator to 60 gpm.
a.
: b.     Decrease feed flow to "A" steam generator ONLY to 60 gpm.
Decrease feed flow to each steam generator to 60 gpm.
: c.     Increase feed flow as required to maintain "A" steam generator narrow range level greater than or equal to 4%.
b.
: d.     Control feed flow as required to maintain RCS hot leg temperatures stable or decreasing.
Decrease feed flow to "A" steam generator ONLY to 60 gpm.
c.
Increase feed flow as required to maintain "A" steam generator narrow range level greater than or equal to 4%.
d.
Control feed flow as required to maintain RCS hot leg temperatures stable or decreasing.


REACTOR OPERATOR                                                                       Page 42 QUESTION: 038 (1.00)
REACTOR OPERATOR Page 42 QUESTION: 038 (1.00)
The following plant conditions exist:
The following plant conditions exist:
        -      A safety injection has actuated
A safety injection has actuated A transition has been made to ES-1.1, SI Termination No charging pump is running CC flow to the RXCP thermal barrier HX has been lost since the SI actuation What action is initially taken associated with RXCP seal cooling and what is the reason for the action?
        -      A transition has been made to ES-1.1, SI Termination
a.
        -      No charging pump is running
RXCP seal injection is isolated before starting a charging pump, to avoid taking time to reestablish seal cooling since RXCP seals are already heated up.
        -      CC flow to the RXCP thermal barrier HX has been lost since the SI actuation What action is initially taken associated with RXCP seal cooling and what is the reason for the action?
b.
: a. RXCP seal injection is isolated before starting a charging pump, to avoid taking time to reestablish seal cooling since RXCP seals are already heated up.
A charging pump is started and then CC flow is established to the RXCP thermal barriers, to prevent steam binding of the CC system.
: b. A charging pump is started and then CC flow is established to the RXCP thermal barriers, to prevent steam binding of the CC system.
c.
: c. CC flow is established to the RXCP thermal barriers and then a charging pump is started, to prevent RXCP shaft warping.
CC flow is established to the RXCP thermal barriers and then a charging pump is started, to prevent RXCP shaft warping.
: d. CC flow is established to the RXCP thermal barriers, to prevent thermal shock to the RXCP seals.
d.
CC flow is established to the RXCP thermal barriers, to prevent thermal shock to the RXCP seals.


REACTOR OPERATOR                                                                       Page 43 QUESTION: 039 (1.00)
REACTOR OPERATOR Page 43 QUESTION: 039 (1.00)
Given the following plant conditions:
Given the following plant conditions:
      -      Reactor trip occurred with subsequent loss of RXCPs.
Reactor trip occurred with subsequent loss of RXCPs.
      -      RCS Pressure is 800 psig
RCS Pressure is 800 psig Operators have implemented ES-0.2, "Natural Circulation Cooldown" to go to Cold Shutdown.
      -      Operators have implemented ES-0.2, "Natural Circulation Cooldown" to go to Cold Shutdown.
A cooldown rate of 25&deg;F/hour has been established.
      -      A cooldown rate of 25&deg;F/hour has been established.
RCS depressurization has been initiated PZR level - Unexpected large variations are occurring RVLIS RXCPs OFF Indication - 90%
      -      RCS depressurization has been initiated
      -      PZR level - Unexpected large variations are occurring
      -      RVLIS RXCPs OFF Indication - 90%
The Shift Manager has determined that cooldown and depressurization shall proceed as quickly as possible. Which ONE of the following describes the appropriate actions?
The Shift Manager has determined that cooldown and depressurization shall proceed as quickly as possible. Which ONE of the following describes the appropriate actions?
: a.     Pressurize the RCS to collapse the voids, continue the cooldown and remain in ES-0.2, Natural Circulation Cooldown.
a.
: b.     Raise the cooldown rate to collapse the voids and remain in ES-0.2, Natural Circulation Cooldown.
Pressurize the RCS to collapse the voids, continue the cooldown and remain in ES-0.2, Natural Circulation Cooldown.
: c.     Pressurize the RCS to collapse the voids, continue the cooldown and transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel."
b.
: d.     Raise the cooldown rate to collapse the voids and transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel.
Raise the cooldown rate to collapse the voids and remain in ES-0.2, Natural Circulation Cooldown.
c.
Pressurize the RCS to collapse the voids, continue the cooldown and transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel."
d.
Raise the cooldown rate to collapse the voids and transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel.


REACTOR OPERATOR                                                                     Page 44 QUESTION: 040 (1.00)
REACTOR OPERATOR Page 44 QUESTION: 040 (1.00)
Given the following plant conditions:
Given the following plant conditions:
          - The unit is at 80% power.
- The unit is at 80% power.
          - Control Bank D rod K7 is stuck at 220 steps (not the most reactive rod).
- Control Bank D rod K7 is stuck at 220 steps (not the most reactive rod).
          - All other Control Bank "D" rods are at 220 steps.
- All other Control Bank "D" rods are at 220 steps.
          - Tavg = 567&deg;F.
- Tavg = 567&deg;F.
How would the shutdown margin calculation performed prior to the condition discovered above be affected?
How would the shutdown margin calculation performed prior to the condition discovered above be affected?
: a. No effect on shutdown margin.
: a. No effect on shutdown margin.
Line 449: Line 628:
: d. The effect on shutdown margin can not be determined.
: d. The effect on shutdown margin can not be determined.


REACTOR OPERATOR                                                                         Page 45 QUESTION: 041 (1.00)
REACTOR OPERATOR Page 45 QUESTION: 041 (1.00)
Which of the following indications will be inaccurate during the performance of ES-0.2, "Natural Circulation Cooldown", with RXCPs secured?
Which of the following indications will be inaccurate during the performance of ES-0.2, "Natural Circulation Cooldown", with RXCPs secured?
: a. RCS core exit TCs.
a.
: b. RCS wide range hot leg temperature.
RCS core exit TCs.
: c. RCS T-average indication.
b.
: d. RCS wide range cold leg temperature.
RCS wide range hot leg temperature.
c.
RCS T-average indication.
d.
RCS wide range cold leg temperature.


REACTOR OPERATOR                                                                   Page 46 QUESTION: 042 (1.00)
REACTOR OPERATOR Page 46 QUESTION: 042 (1.00)
The following plant conditions exist:
The following plant conditions exist:
        -      Reactor power is 80%
Reactor power is 80%
        -      Rod Control is in MANUAL
Rod Control is in MANUAL All other controls are in AUTO An inadvertent Emergency Boration was performed for two minutes. Considering steady-state to steady-state conditions, which of the following parameters will NOT change?
        -      All other controls are in AUTO An inadvertent Emergency Boration was performed for two minutes. Considering steady-state to steady-state conditions, which of the following parameters will NOT change?
a.
: a. Reactor Power
Reactor Power b.
: b. RCS Tavg
RCS Tavg c.
: c. Przr Level
Przr Level d.
: d. S/G Pressure
S/G Pressure


REACTOR OPERATOR                                                                     Page 47 QUESTION: 043 (1.00)
REACTOR OPERATOR Page 47 QUESTION: 043 (1.00)
Given the following conditions:
Given the following conditions:
      -      The plant is at 50% power
The plant is at 50% power Condensate pump A is in pullout Condensate pump B is running If condenser hot well level subsequently decreases to 10%, which one of the actions below is now required?
      -      Condensate pump A is in pullout
a.
      -      Condensate pump B is running If condenser hot well level subsequently decreases to 10%, which one of the actions below is now required?
Startup condensate pump A per N-CD-03, Condensate System.
: a.     Startup condensate pump A per N-CD-03, Condensate System.
b.
: b.     Address abnormal condensate conditions per A-CD-03, Condensate System Abnormal Operation.
Address abnormal condensate conditions per A-CD-03, Condensate System Abnormal Operation.
: c.     OPEN MU-3B, Condenser Emergency Make-up valve per N-CD-03, Condensate System.
c.
: d.     Respond to the reactor trip per E-0, Reactor Trip or Safety Injection
OPEN MU-3B, Condenser Emergency Make-up valve per N-CD-03, Condensate System.
d.
Respond to the reactor trip per E-0, Reactor Trip or Safety Injection


REACTOR OPERATOR                                                                       Page 48 QUESTION: 044 (1.00)
REACTOR OPERATOR Page 48 QUESTION: 044 (1.00)
Due to decreasing condenser vacuum, the operator performs the actions of E-AR-09, Loss of Condenser Vacuum. At one point, condenser pressure increases to 5 inches Hg absolute, and the operator must locally place the hogging jet in service.
Due to decreasing condenser vacuum, the operator performs the actions of E-AR-09, Loss of Condenser Vacuum. At one point, condenser pressure increases to 5 inches Hg absolute, and the operator must locally place the hogging jet in service.
In addition to opening MS-400, Steam Supply to Hogging Jet, and throttling MS-401, Steam to Hogging Jet, to maintain between 105-115 psig on PI-11323, four additional valves, listed below, must be aligned to place the hogging jet in service:
In addition to opening MS-400, Steam Supply to Hogging Jet, and throttling MS-401, Steam to Hogging Jet, to maintain between 105-115 psig on PI-11323, four additional valves, listed below, must be aligned to place the hogging jet in service:
        -      AR-302, Gland Steam Cdsr Exhaust to Outside
AR-302, Gland Steam Cdsr Exhaust to Outside AR-305, Gland Steam Cdsr Exhaust to Vent AR-100, Hogging Jet Air Inlet AR-2A, First Stage Ejector Inlet Which of the following is the correct valve alignment?
        -      AR-305, Gland Steam Cdsr Exhaust to Vent
AR-302 AR-305 AR-100 AR-2A a.
        -      AR-100, Hogging Jet Air Inlet
CLOSED OPEN CLOSED OPEN b.
        -      AR-2A, First Stage Ejector Inlet Which of the following is the correct valve alignment?
OPEN CLOSED OPEN CLOSED c.
AR-302         AR-305         AR-100       AR-2A
CLOSED OPEN OPEN CLOSED d.
: a.     CLOSED         OPEN           CLOSED       OPEN
OPEN CLOSED CLOSED OPEN
: b.     OPEN           CLOSED         OPEN         CLOSED
: c.     CLOSED         OPEN           OPEN         CLOSED
: d.     OPEN           CLOSED         CLOSED       OPEN


REACTOR OPERATOR                                                                     Page 49 QUESTION: 045 (1.00)
REACTOR OPERATOR Page 49 QUESTION: 045 (1.00)
The Gaseous Radioactive Waste System (WG) vent header pressure has just increased to 2 psig. Per A-GWP-32B, the AUTOMATIC ACTIONS the operator must now verify are:
The Gaseous Radioactive Waste System (WG) vent header pressure has just increased to 2 psig. Per A-GWP-32B, the AUTOMATIC ACTIONS the operator must now verify are:
: a. The start of the Waste Gas Compressors.
a.
: b. The closure of Gas Decay Tank inlet isolation valves for the tank selected for fill.
The start of the Waste Gas Compressors.
: c. The closure of Gas Decay Tanks to Holdup Tanks valve.
b.
: d. The opening of Gas Decay Tank inlet isolation valve for the tank selected for standby.
The closure of Gas Decay Tank inlet isolation valves for the tank selected for fill.
c.
The closure of Gas Decay Tanks to Holdup Tanks valve.
d.
The opening of Gas Decay Tank inlet isolation valve for the tank selected for standby.


REACTOR OPERATOR                                                                     Page 50 QUESTION: 046 (1.00)
REACTOR OPERATOR Page 50 QUESTION: 046 (1.00)
The contents of a Gas Decay Tank is being released in accordance with the appropriate administrative controls when Gas Decay Tanks to Plant Vent, WG-36/CV-31215, closed.
The contents of a Gas Decay Tank is being released in accordance with the appropriate administrative controls when Gas Decay Tanks to Plant Vent, WG-36/CV-31215, closed.
Which of the following monitors could have caused this to occur?
Which of the following monitors could have caused this to occur?
: a.     BOTH R-13 and R-14 (Aux Building Vent Monitors)
a.
: b.     BOTH Aux. Area Monitors 03-06 and 03-08 (Beta Air Monitors Aux. Building)
BOTH R-13 and R-14 (Aux Building Vent Monitors) b.
: c.     ONLY R-13 (Aux Building Vent Monitor)
BOTH Aux. Area Monitors 03-06 and 03-08 (Beta Air Monitors Aux. Building) c.
: d.     ONLY R-14 (Aux Building Vent Monitor)
ONLY R-13 (Aux Building Vent Monitor) d.
ONLY R-14 (Aux Building Vent Monitor)


REACTOR OPERATOR                                                                       Page 51 QUESTION: 047 (1.00)
REACTOR OPERATOR Page 51 QUESTION: 047 (1.00)
Which of the following describes the detector types used in Area Radiation Monitors at Kewaunee?
Which of the following describes the detector types used in Area Radiation Monitors at Kewaunee?
: a.       ONLY GM tubes and ion chambers
a.
: b.       ONLY ion chambers
ONLY GM tubes and ion chambers b.
: c.       ONLY GM tubes
ONLY ion chambers c.
: d.       Ion chambers, GM tubes AND scintillation detectors
ONLY GM tubes d.
Ion chambers, GM tubes AND scintillation detectors


REACTOR OPERATOR                                                                       Page 52 QUESTION: 048 (1.00)
REACTOR OPERATOR Page 52 QUESTION: 048 (1.00)
Procedure A-RM-45, Abnormal Radiation Monitoring, requires the operator to determine if Post Accident Recirc must be started due to a failure of R-23, Control Room Vent Monitor, by monitoring specific process and area monitors for increasing radiation levels.
Procedure A-RM-45, Abnormal Radiation Monitoring, requires the operator to determine if Post Accident Recirc must be started due to a failure of R-23, Control Room Vent Monitor, by monitoring specific process and area monitors for increasing radiation levels.
Besides R-1, Control Room Area Monitor, what additional AREA Radiation monitor(s), if any, must be monitored and Post Accident Recirc manually started on increasing levels of radiation?
Besides R-1, Control Room Area Monitor, what additional AREA Radiation monitor(s), if any, must be monitored and Post Accident Recirc manually started on increasing levels of radiation?
: a. BOTH R-10, New Fuel Pit Area Monitor AND R-5, Fuel Handling Area Monitor.
a.
: b. NO additional Area Radiation Monitors.
BOTH R-10, New Fuel Pit Area Monitor AND R-5, Fuel Handling Area Monitor.
: c. ONLY R-10, New Fuel Pit Area Monitor.
b.
: d. ONLY R-5, Fuel Handling Area Monitor.
NO additional Area Radiation Monitors.
c.
ONLY R-10, New Fuel Pit Area Monitor.
d.
ONLY R-5, Fuel Handling Area Monitor.


REACTOR OPERATOR                                                                       Page 53 QUESTION: 049 (1.00)
REACTOR OPERATOR Page 53 QUESTION: 049 (1.00)
ES-0.2, Natural Circulation Cooldown, is being implemented. The following conditions exist:
ES-0.2, Natural Circulation Cooldown, is being implemented. The following conditions exist:
      -      RCS cold leg Temp is at 380&deg;F.
RCS cold leg Temp is at 380&deg;F.
      -      RCS Pressure is at 1450 psig.
RCS Pressure is at 1450 psig.
      -      All CRDM fans are off and CANNOT be started.
All CRDM fans are off and CANNOT be started.
      -      18 hour waiting period has begun.
18 hour waiting period has begun.
What is the basis for the 18 hour waiting period?
What is the basis for the 18 hour waiting period?
: a. Prevent damage to the CRDM coils due to overheating.
a.
: b. Ensure heat is being removed from the Steam Generator to prevent void formation in the U-tubes.
Prevent damage to the CRDM coils due to overheating.
: c. Minimize void formations in the Reactor Vessel head during subsequent RCS depressurization to place RHR in service.
b.
: d. Allow sufficient flow to the upper head region to make the upper head fluid temperature equal to the cold leg fluid temperature.
Ensure heat is being removed from the Steam Generator to prevent void formation in the U-tubes.
c.
Minimize void formations in the Reactor Vessel head during subsequent RCS depressurization to place RHR in service.
d.
Allow sufficient flow to the upper head region to make the upper head fluid temperature equal to the cold leg fluid temperature.


REACTOR OPERATOR                                                                   Page 54 QUESTION: 050 (1.00)
REACTOR OPERATOR Page 54 QUESTION: 050 (1.00)
The following plant conditions exist:
The following plant conditions exist:
        -      PZR pressure control channel selector switch is in the 4-3 position
PZR pressure control channel selector switch is in the 4-3 position PZR pressure yellow channel (PT-449 IV) has just failed low What is the effect of these conditions on the RCS?
        -      PZR pressure yellow channel (PT-449 IV) has just failed low What is the effect of these conditions on the RCS?
a.
: a. All PZR heaters will come ON; PZR PORVs PR-2A and PR-2B would not be available to open on a subsequent high RCS pressure condition.
All PZR heaters will come ON; PZR PORVs PR-2A and PR-2B would not be available to open on a subsequent high RCS pressure condition.
: b. PZR heaters are unaffected; ONLY PZR PORV PR-2A would not be available to open on a subsequent high RCS pressure condition.
b.
: c. All PZR heaters will come ON; PZR PORV PR-2A would not be available to open on a subsequent high RCS pressure condition.
PZR heaters are unaffected; ONLY PZR PORV PR-2A would not be available to open on a subsequent high RCS pressure condition.
: d. PZR heaters are unaffected; PZR PORVs PR-2A and PR-2B would not be available to open on a subsequent high RCS pressure condition.
c.
All PZR heaters will come ON; PZR PORV PR-2A would not be available to open on a subsequent high RCS pressure condition.
d.
PZR heaters are unaffected; PZR PORVs PR-2A and PR-2B would not be available to open on a subsequent high RCS pressure condition.


REACTOR OPERATOR                                                                 Page 55 QUESTION: 051 (1.00)
REACTOR OPERATOR Page 55 QUESTION: 051 (1.00)
Following an ATWS and an SI actuation from 100% power, the Reactor Trip Breakers remain closed. What effect will this have on the plant?
Following an ATWS and an SI actuation from 100% power, the Reactor Trip Breakers remain closed. What effect will this have on the plant?
: a. Automatic Turbine Trip will not occur.
a.
: b. Automatic steam line isolation will be blocked.
Automatic Turbine Trip will not occur.
: c. Automatic SI re-actuation CANNOT be blocked.
b.
: d. Feedwater isolation due to SI actuation will be blocked.
Automatic steam line isolation will be blocked.
c.
Automatic SI re-actuation CANNOT be blocked.
d.
Feedwater isolation due to SI actuation will be blocked.


REACTOR OPERATOR                                                                     Page 56 QUESTION: 052 (1.00)
REACTOR OPERATOR Page 56 QUESTION: 052 (1.00)
Which of the following parameters is monitored to determine the need to minimize DC loads while performing ECA-0.0, LOSS OF ALL AC POWER?
Which of the following parameters is monitored to determine the need to minimize DC loads while performing ECA-0.0, LOSS OF ALL AC POWER?
: a.     Battery amps
a.
: b.     Battery amp-hours
Battery amps b.
: c.     Battery volts
Battery amp-hours c.
: d.     Battery specific gravity
Battery volts d.
Battery specific gravity


REACTOR OPERATOR                                                                         Page 57 QUESTION: 053 (1.00)
REACTOR OPERATOR Page 57 QUESTION: 053 (1.00)
Given the following:
Given the following:
        -      The unit is stable at 15% power.
The unit is stable at 15% power.
        -      A failure of Instrument Bus I, BRA-113, occurs.
A failure of Instrument Bus I, BRA-113, occurs.
        -      All systems and control loops are in their NORMAL position.
All systems and control loops are in their NORMAL position.
Which of the following action(s) are required, if any, to restore pressurizer (PRZR) pressure and level conditions resulting from this failure?
Which of the following action(s) are required, if any, to restore pressurizer (PRZR) pressure and level conditions resulting from this failure?
: a. Place PRZR spray valves in MANUAL, Position PRZR Pressure Control Switch to another position, AND Then place PRZR spray valves back in AUTO.
a.
: b. Place Charging Pump Speed control to MANUAL, Position PRZR Level Control Switch to another position, AND Then place Charging Pump Speed control back to AUTO.
Place PRZR spray valves in MANUAL, Position PRZR Pressure Control Switch to another position, AND Then place PRZR spray valves back in AUTO.
: c. Position PRZR Level Control Switch to another position, AND Then restore normal letdown and PRZR heaters.
b.
: d. No actions are required to restore PRZR pressure and level.
Place Charging Pump Speed control to MANUAL, Position PRZR Level Control Switch to another position, AND Then place Charging Pump Speed control back to AUTO.
c.
Position PRZR Level Control Switch to another position, AND Then restore normal letdown and PRZR heaters.
d.
No actions are required to restore PRZR pressure and level.


REACTOR OPERATOR                                                               Page 58 QUESTION: 054 (1.00)
REACTOR OPERATOR Page 58 QUESTION: 054 (1.00)
Which one of the following would cause annunciator 47041-P, ROD BOTTOM ROD DROP, to alarm?
Which one of the following would cause annunciator 47041-P, ROD BOTTOM ROD DROP, to alarm?
: a. Control Bank B demand is 38 and a Control Bank B IRPI reads 18.
a.
: b. Control Bank A demand is 18 and a Control Bank A IRPI reads 32.
Control Bank B demand is 38 and a Control Bank B IRPI reads 18.
: c. Shutdown Bank B demand is 32 and a Shutdown Bank B IRPI reads 18.
b.
: d. Shutdown Bank A demand is 18 and a Shutdown Bank A IRPI reads 32.
Control Bank A demand is 18 and a Control Bank A IRPI reads 32.
c.
Shutdown Bank B demand is 32 and a Shutdown Bank B IRPI reads 18.
d.
Shutdown Bank A demand is 18 and a Shutdown Bank A IRPI reads 32.
Removed From Exam Because All Answers Are Correct.
Removed From Exam Because All Answers Are Correct.


REACTOR OPERATOR                                                                       Page 59 QUESTION: 055 (1.00)
REACTOR OPERATOR Page 59 QUESTION: 055 (1.00)
Given the following:
Given the following:
      -      There has been a fire necessitating the evacuation of the control room.
There has been a fire necessitating the evacuation of the control room.
      -      E-0-06, Fire in Alternate Fire Zone has been entered from E-FP-08, Emergency Operating Procedure - Fire.
E-0-06, Fire in Alternate Fire Zone has been entered from E-FP-08, Emergency Operating Procedure - Fire.
Which of the following indications is available at the Dedicated Shutdown Panel?
Which of the following indications is available at the Dedicated Shutdown Panel?
: a.     S/G 1A Narrow Range Level
a.
: b.     Charging Flow
S/G 1A Narrow Range Level b.
: c.     RWST Level
Charging Flow c.
: d.     Reactor Coolant Loop B Hot Leg Temp
RWST Level d.
Reactor Coolant Loop B Hot Leg Temp


REACTOR OPERATOR                                                                     Page 60 QUESTION: 056 (1.00)
REACTOR OPERATOR Page 60 QUESTION: 056 (1.00)
Given the following conditions:
Given the following conditions:
      -      A large break LOCA occurs.
A large break LOCA occurs.
      -      Containment pressure is observed to be 25 psig.
Containment pressure is observed to be 25 psig.
      -      Containment Spray has NOT initiated.
Containment Spray has NOT initiated.
      -      Manual actuation of Containment Spray has been unsuccessful.
Manual actuation of Containment Spray has been unsuccessful.
      -      All other ESF actuations and components have functioned normally.
All other ESF actuations and components have functioned normally.
What actions need to be taken to manually initiate Containment Spray for Train A?
What actions need to be taken to manually initiate Containment Spray for Train A?
Manual start of ICS Pump A and ...
Manual start of ICS Pump A and...
(1)     ICS-5A/MV-32066 and ICS-6A/MV32067, Ctmt Spray Pump A Discharge Isolation valves (2)     ICS-201/CV-31272 and ICS-202/CV31273, ICS Recirculation RWST valves (3)     CI-1001A/CV31393 and CI-1001B/CV-31394, Caustic Additive to Ctmt Spray valves
(1)
: a.     (1) check auto open         (2) check closed     (3) check auto open
ICS-5A/MV-32066 and ICS-6A/MV32067, Ctmt Spray Pump A Discharge Isolation valves (2)
: b.     (1) manual open             (2) check closed     (3) check auto open
ICS-201/CV-31272 and ICS-202/CV31273, ICS Recirculation RWST valves (3)
: c.     (1) manual open             (2) check closed     (3) manual open
CI-1001A/CV31393 and CI-1001B/CV-31394, Caustic Additive to Ctmt Spray valves a.
: d.     (1) manual open             (2) manual close     (3) manual open
(1) check auto open (2) check closed (3) check auto open b.
(1) manual open (2) check closed (3) check auto open c.
(1) manual open (2) check closed (3) manual open d.
(1) manual open (2) manual close (3) manual open


REACTOR OPERATOR                                                                           Page 61 QUESTION: 057 (1.00)
REACTOR OPERATOR Page 61 QUESTION: 057 (1.00)
Given the following conditions:
Given the following conditions:
      -      Radiation Monitor R-11, Containment Atmosphere, is in HIGH alarm.
Radiation Monitor R-11, Containment Atmosphere, is in HIGH alarm.
      -      All other plant conditions are normal Which of the following lists valves in the Reactor Building Ventilation System to be verified automatically CLOSED by the operator?
All other plant conditions are normal Which of the following lists valves in the Reactor Building Ventilation System to be verified automatically CLOSED by the operator?
: a.     ONLY the following valves:
a.
              -TAV-12, Cntmt Purge/Vent Supply
ONLY the following valves:
              -RBV-2, Cntmt Purge/Vent Supply B
-TAV-12, Cntmt Purge/Vent Supply
              -RBV-5, Cntmt Purge/Vent Exhaust
-RBV-2, Cntmt Purge/Vent Supply B
              -RBV-3, Cntmt Purge/Vent Exhaust B
-RBV-5, Cntmt Purge/Vent Exhaust
              -SA-7003B, Hydrogen Dilution to Cnmt
-RBV-3, Cntmt Purge/Vent Exhaust B
              -LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.
-SA-7003B, Hydrogen Dilution to Cnmt
: b.     ONLY the following valves:
-LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.
              -TAV-12, Cntmt Purge/Vent Supply
b.
              -RBV-5, Cntmt Purge/Vent Exhaust
ONLY the following valves:
              -SA-7003B, Hydrogen Dilution to Cnmt
-TAV-12, Cntmt Purge/Vent Supply
              -LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.
-RBV-5, Cntmt Purge/Vent Exhaust
: c.     ONLY the following valves:
-SA-7003B, Hydrogen Dilution to Cnmt
              -TAV-12, Cntmt Purge/Vent Supply
-LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.
              -RBV-2, Cntmt Purge/Vent Supply B
c.
              -RBV-5, Cntmt Purge/Vent Exhaust
ONLY the following valves:
              -RBV-3, Cntmt Purge/Vent Exhaust B.
-TAV-12, Cntmt Purge/Vent Supply
: d.     ONLY the following valves
-RBV-2, Cntmt Purge/Vent Supply B
              -RBV-2, Cntmt Purge/Vent Supply B
-RBV-5, Cntmt Purge/Vent Exhaust
              -RBV-3, Cntmt Purge/Vent Exhaust B
-RBV-3, Cntmt Purge/Vent Exhaust B.
              -SA-7003B, Hydrogen Dilution to Cnmt
d.
              -LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.
ONLY the following valves
-RBV-2, Cntmt Purge/Vent Supply B
-RBV-3, Cntmt Purge/Vent Exhaust B
-SA-7003B, Hydrogen Dilution to Cnmt
-LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.


REACTOR OPERATOR                                                                   Page 62 QUESTION: 058 (1.00)
REACTOR OPERATOR Page 62 QUESTION: 058 (1.00)
ECA-1.1, Loss of Emergency Coolant Recirculation, determines the required number of operating ICS pumps based on which of the following?
ECA-1.1, Loss of Emergency Coolant Recirculation, determines the required number of operating ICS pumps based on which of the following?
: a. Containment pressure, containment temperature, and sump level.
a.
: b. Containment pressure, operating CFCUs, and sump level.
Containment pressure, containment temperature, and sump level.
: c. Containment temperature, operating CFCUs, and RWST level.
b.
: d. Containment pressure, operating CFCUs, and RWST level.
Containment pressure, operating CFCUs, and sump level.
c.
Containment temperature, operating CFCUs, and RWST level.
d.
Containment pressure, operating CFCUs, and RWST level.


REACTOR OPERATOR                                                                   Page 63 QUESTION: 059 (1.00)
REACTOR OPERATOR Page 63 QUESTION: 059 (1.00)
The plant is at 100% power when control room operators receive SPENT FUEL POOL ABNORMAL Annunciator. The SFP level is decreasing AND is lower than the SFP canal level.
The plant is at 100% power when control room operators receive SPENT FUEL POOL ABNORMAL Annunciator. The SFP level is decreasing AND is lower than the SFP canal level.
The CRS instructs you to initiate makeup to the SFP. Per procedure A-SFP-21, Abnormal SFP Cooling and Cleanup System Operation, you would use. . .
The CRS instructs you to initiate makeup to the SFP. Per procedure A-SFP-21, Abnormal SFP Cooling and Cleanup System Operation, you would use...
: a.       the RWST
a.
: b.       Service Water
the RWST b.
: c.       the Reactor Makeup Control System
Service Water c.
: d.       Reactor Makeup Water through manual makeup valve
the Reactor Makeup Control System d.
Reactor Makeup Water through manual makeup valve


REACTOR OPERATOR                                                                         Page 64 QUESTION: 060 (1.00)
REACTOR OPERATOR Page 64 QUESTION: 060 (1.00)
The Unit is at 40% power in a power ascension to full power. All systems are aligned in their normal lineups for the current power level except Turbine EHC control is in MANUAL-IMP OUT.
The Unit is at 40% power in a power ascension to full power. All systems are aligned in their normal lineups for the current power level except Turbine EHC control is in MANUAL-IMP OUT.
The operator depresses the CV raise pushbutton for 2 seconds to continue the load ascension.
The operator depresses the CV raise pushbutton for 2 seconds to continue the load ascension.
Which of the following is the response of the main feedwater regulating valves to this action?
Which of the following is the response of the main feedwater regulating valves to this action?
The Main Feedwater Regulating Valves will initially throttle...
The Main Feedwater Regulating Valves will initially throttle...
: a.       CLOSED due to swell, and then throttle OPEN when level drops below 44%.
a.
: b.       OPEN due to the steam flow/feed flow mismatch, and then regulate to control level at 44%
CLOSED due to swell, and then throttle OPEN when level drops below 44%.
: c.       CLOSED due to the steam flow/feed flow mismatch, and then throttle OPEN when level drops below 44%.
b.
: d.       OPEN due to shrink, and then regulate to control level at 44%.
OPEN due to the steam flow/feed flow mismatch, and then regulate to control level at 44%
c.
CLOSED due to the steam flow/feed flow mismatch, and then throttle OPEN when level drops below 44%.
d.
OPEN due to shrink, and then regulate to control level at 44%.


REACTOR OPERATOR                                                                         Page 65 QUESTION: 061 (1.00)
REACTOR OPERATOR Page 65 QUESTION: 061 (1.00)
SP-05B-284, "Turbine Driven AFW Pump Full Flow Test - IST," was in progress. The turbine driven auxiliary feedwater pump (TDAFP) was started and had been running for 2 minutes.
SP-05B-284, "Turbine Driven AFW Pump Full Flow Test - IST," was in progress. The turbine driven auxiliary feedwater pump (TDAFP) was started and had been running for 2 minutes.
Alarm window 47062-N, "T/D AFW Pump Abnormal" then annunciates and the NAO reports the TDAFP auxiliary lube oil pump is continuously stopping and starting with lube oil pressure fluctuating between 8 and 17 psig.
Alarm window 47062-N, "T/D AFW Pump Abnormal" then annunciates and the NAO reports the TDAFP auxiliary lube oil pump is continuously stopping and starting with lube oil pressure fluctuating between 8 and 17 psig.
Which ONE of the following correctly explains the above conditions?
Which ONE of the following correctly explains the above conditions?
: a.     Conditions are normal, no operator action is required, the test should continue.
a.
: b.     Conditions are normal, the NAO should be directed to locally shutdown the auxiliary lube oil pump, the test should continue.
Conditions are normal, no operator action is required, the test should continue.
: c.     The shaft driven pump has malfunctioned, the test should be terminated.
b.
: d.     The Auxiliary Lube Oil Pump has malfunctioned, the test should be terminated.
Conditions are normal, the NAO should be directed to locally shutdown the auxiliary lube oil pump, the test should continue.
c.
The shaft driven pump has malfunctioned, the test should be terminated.
d.
The Auxiliary Lube Oil Pump has malfunctioned, the test should be terminated.


REACTOR OPERATOR                                                                   Page 66 QUESTION: 062 (1.00)
REACTOR OPERATOR Page 66 QUESTION: 062 (1.00)
Given the following conditions:
Given the following conditions:
      -      The plant is at 100% power
The plant is at 100% power S/G blowdown is in service in Mode II Condenser air removal is aligned for normal operation The NCO positions the R-19 keyswitch to the OFF position Which of the following describes the effect of the operator actions?
      -      S/G blowdown is in service in Mode II
a.
      -      Condenser air removal is aligned for normal operation
Blowdown flowpath switches to Mode I alignment.
      -      The NCO positions the R-19 keyswitch to the OFF position Which of the following describes the effect of the operator actions?
b.
: a.     Blowdown flowpath switches to Mode I alignment.
Blowdown flowpath switches to the Primary Sampling System.
: b.     Blowdown flowpath switches to the Primary Sampling System.
c.
: c.     Condenser Air Ejector discharge AR-6 (CV-31168) remains in the duct position.
Condenser Air Ejector discharge AR-6 (CV-31168) remains in the duct position.
: d.     Condenser Air Ejector discharge AR-6 (CV-31168) switches to its ATM position.
d.
Condenser Air Ejector discharge AR-6 (CV-31168) switches to its ATM position.


REACTOR OPERATOR                                                                     Page 67 QUESTION: 063 (1.00)
REACTOR OPERATOR Page 67 QUESTION: 063 (1.00)
During a liquid radwaste discharge from the Waste Condensate Tanks to the Auxiliary building standpipe, control room operators receive a Waste Disposal Panel Trouble Alarm and dispatch an operator. The operator reports from the Waste Disposal Panel (53702) that LIQUID WASTE MONITOR R-18 HIGH RADIATION" has alarmed. Radiation Monitor R-18 is verified to be alarming, but automatic action(s) do NOT occur. What automatic operation of A-RM-45, Abnormal Radiation Monitoring System must now be performed manually?
During a liquid radwaste discharge from the Waste Condensate Tanks to the Auxiliary building standpipe, control room operators receive a Waste Disposal Panel Trouble Alarm and dispatch an operator. The operator reports from the Waste Disposal Panel (53702) that LIQUID WASTE MONITOR R-18 HIGH RADIATION" has alarmed. Radiation Monitor R-18 is verified to be alarming, but automatic action(s) do NOT occur. What automatic operation of A-RM-45, Abnormal Radiation Monitoring System must now be performed manually?
: a. Manually close WD-19, Waste Liquid Discharge Isolation Valve .
a.
: b. Manually close WD-17, Waste Condensate Pumps Discharge Valve.
Manually close WD-19, Waste Liquid Discharge Isolation Valve.
: c. Manually close WD-22, Waste Condensate Pumps to Auxiliary Building Standpipe.
b.
: d. Stop Waste Condensate Pump 1A.
Manually close WD-17, Waste Condensate Pumps Discharge Valve.
c.
Manually close WD-22, Waste Condensate Pumps to Auxiliary Building Standpipe.
d.
Stop Waste Condensate Pump 1A.


REACTOR OPERATOR                                                                   Page 68 QUESTION: 064 (1.00)
REACTOR OPERATOR Page 68 QUESTION: 064 (1.00)
When the RHR system is placed in the shutdown cooling mode of operation, component cooling is __(1)__ aligned to the associated RHR heat exchanger prior to RHR pump start AND component cooling flows through the __(2)__ side of the RHR heat exchanger.
When the RHR system is placed in the shutdown cooling mode of operation, component cooling is __(1)__ aligned to the associated RHR heat exchanger prior to RHR pump start AND component cooling flows through the __(2)__ side of the RHR heat exchanger.
(1)                   (2)
(1)
: a.     Automatically         Tube
(2) a.
: b.     Manually               Tube
Automatically Tube b.
: c.     Automatically         Shell
Manually Tube c.
: d.     Manually               Shell
Automatically Shell d.
Manually Shell


REACTOR OPERATOR                                                                 Page 69 QUESTION: 065 (1.00)
REACTOR OPERATOR Page 69 QUESTION: 065 (1.00)
A LOCA has occurred. Post-LOCA containment hydrogen concentration is 7%. What method is available to address hydrogen control in the containment?
A LOCA has occurred. Post-LOCA containment hydrogen concentration is 7%. What method is available to address hydrogen control in the containment?
: a.     dilute the containment atmosphere.
a.
: b.     place the Hydrogen Recombiner in service.
dilute the containment atmosphere.
: c.     vent containment through the Shield Building Ventilation System.
b.
: d.     spray containment using the containment spray pumps.
place the Hydrogen Recombiner in service.
c.
vent containment through the Shield Building Ventilation System.
d.
spray containment using the containment spray pumps.
Removed From Exam Because There Are No Correct Answers.
Removed From Exam Because There Are No Correct Answers.


REACTOR OPERATOR                                                                         Page 70 QUESTION: 066 (1.00)
REACTOR OPERATOR Page 70 QUESTION: 066 (1.00)
During refueling operations, an irradiated fuel assembly is dropped in the reactor vessel. A fuel handler reports to the control room that gas bubbles are emanating from the dropped assembly.
During refueling operations, an irradiated fuel assembly is dropped in the reactor vessel. A fuel handler reports to the control room that gas bubbles are emanating from the dropped assembly.
Shortly afterwards, R-11 alarms on high radiation. The control room operator enters E-FH-53A, "Dropped or Damaged Fuel Assembly" procedure and ____(1)_____. Controls for the R11 alarm ____(2)_____.
Shortly afterwards, R-11 alarms on high radiation. The control room operator enters E-FH-53A, "Dropped or Damaged Fuel Assembly" procedure and ____(1)_____. Controls for the R11 alarm ____(2)_____.
: a.     (1) verifies that the Auxiliary Building Special Vent system starts (2) automatically stops upward movement of the manipulator hoist
a.
: b.     (1) verifies that the Containment Vent Isolation occurred (2) do NOT affect the fuel handling system
(1) verifies that the Auxiliary Building Special Vent system starts (2) automatically stops upward movement of the manipulator hoist b.
: c.     (1) actuates the containment evacuation alarm (2) automatically stops movement of the manipulator trolley and bridge
(1) verifies that the Containment Vent Isolation occurred (2) do NOT affect the fuel handling system c.
: d.     (1) orders the affected area evacuated (2) automatically stops upward movement of the manipulator hoist
(1) actuates the containment evacuation alarm (2) automatically stops movement of the manipulator trolley and bridge d.
(1) orders the affected area evacuated (2) automatically stops upward movement of the manipulator hoist


REACTOR OPERATOR                                                                           Page 71 QUESTION: 067 (1.00)
REACTOR OPERATOR Page 71 QUESTION: 067 (1.00)
In the event that access to an area with radiation levels in excess of 1000 mrem/hour CANNOT be prevented using a locked door, Technical Specification 6.13 requires the area to be roped off and conspicuously posted.
In the event that access to an area with radiation levels in excess of 1000 mrem/hour CANNOT be prevented using a locked door, Technical Specification 6.13 requires the area to be roped off and conspicuously posted.
Which one of the following lists the additional measure that fulfills the requirements of Technical Specifications for the entrance to this area?
Which one of the following lists the additional measure that fulfills the requirements of Technical Specifications for the entrance to this area?
: a. Install an audible alarm.
a.
: b. Setup a control point.
Install an audible alarm.
: c. Install a flashing light.
b.
: d. Setup a dose rate indicating device.
Setup a control point.
c.
Install a flashing light.
d.
Setup a dose rate indicating device.


REACTOR OPERATOR                                                                     Page 72 QUESTION: 068 (1.00)
REACTOR OPERATOR Page 72 QUESTION: 068 (1.00)
Air Compressor A is operating when cooling water to the compressor is inadvertently isolated.
Air Compressor A is operating when cooling water to the compressor is inadvertently isolated.
The air compressor will trip...
The air compressor will trip...
: a. due to low jacket water pressure.
a.
: b. when the limit for oil temperature is exceeded.
due to low jacket water pressure.
: c. when the limit for air outlet temperature is exceeded.
b.
: d. due to seal leakage resulting in low air discharge pressure.
when the limit for oil temperature is exceeded.
c.
when the limit for air outlet temperature is exceeded.
d.
due to seal leakage resulting in low air discharge pressure.


REACTOR OPERATOR                                                                       Page 73 QUESTION: 069 (1.00)
REACTOR OPERATOR Page 73 QUESTION: 069 (1.00)
Given the following:
Given the following:
      -      RCS Average Temperature = 547&deg;F.
RCS Average Temperature = 547&deg;F.
      -      The reactor is critical at approximately 3% power.
The reactor is critical at approximately 3% power.
      -      The "B" Diesel Generator is inoperable.
The "B" Diesel Generator is inoperable.
      -      The NORMAL power supply for pressurizer heater control group "A" was taken out of service to repair a breaker fault.
The NORMAL power supply for pressurizer heater control group "A" was taken out of service to repair a breaker fault.
Which of the following describes the Technical Specification operability and required actions for the pressurizer heaters, if any?
Which of the following describes the Technical Specification operability and required actions for the pressurizer heaters, if any?
: a.     Technical Specifications requirements are MET and no action is required.
a.
: b.     Technical Specifications requirements are NOT met, and within 1 hour action is required to go to at least HOT STANDBY within the next 6 hours.
Technical Specifications requirements are MET and no action is required.
: c.     Technical Specifications requirements are NOT met, and within 1 hour action is required to go to at least HOT SHUTDOWN within the next 6 hours.
b.
: d.     Technical Specifications requirements are NOT met, and within 1 hour action is required to go to at least COLD SHUTDOWN within the next 36 hours.
Technical Specifications requirements are NOT met, and within 1 hour action is required to go to at least HOT STANDBY within the next 6 hours.
c.
Technical Specifications requirements are NOT met, and within 1 hour action is required to go to at least HOT SHUTDOWN within the next 6 hours.
d.
Technical Specifications requirements are NOT met, and within 1 hour action is required to go to at least COLD SHUTDOWN within the next 36 hours.


REACTOR OPERATOR                                                               Page 74 QUESTION: 070 (1.00)
REACTOR OPERATOR Page 74 QUESTION: 070 (1.00)
Which of the following uses Safeguard 125 VDC power as the NORMAL power supply?
Which of the following uses Safeguard 125 VDC power as the NORMAL power supply?
: a.       Bus 4 Circuit Breaker Control
a.
: b.       7.5 KVA Inverter BRA-111
Bus 4 Circuit Breaker Control b.
: c.       Reactor Trip Breaker shunt trip coil
7.5 KVA Inverter BRA-111 c.
: d.       Non-interruptible Bus BRD-115
Reactor Trip Breaker shunt trip coil d.
Non-interruptible Bus BRD-115


REACTOR OPERATOR                                                                   Page 75 QUESTION: 071 (1.00)
REACTOR OPERATOR Page 75 QUESTION: 071 (1.00)
Power is lost to BRB-104. Which component(s) associated with the 1B EDG will be affected by this condition?
Power is lost to BRB-104. Which component(s) associated with the 1B EDG will be affected by this condition?
A.     Field flash circuit AND jacket water pumps ONLY B.     Field flash circuit AND fuel oil priming pump ONLY C.     Jacket water pumps AND immersion heaters ONLY D.     Fuel oil priming pump AND starting air compressors ONLY
A.
Field flash circuit AND jacket water pumps ONLY B.
Field flash circuit AND fuel oil priming pump ONLY C.
Jacket water pumps AND immersion heaters ONLY D.
Fuel oil priming pump AND starting air compressors ONLY


REACTOR OPERATOR                                                                           Page 76 QUESTION: 072 (1.00)
REACTOR OPERATOR Page 76 QUESTION: 072 (1.00)
Which of the following correctly describes the effect of a failure (HIGH) of R-15, Air Ejector Exhaust Monitor during a release?
Which of the following correctly describes the effect of a failure (HIGH) of R-15, Air Ejector Exhaust Monitor during a release?
(1)     Air Ejector Discharge Vent. AR-6/CV-31168 positions to DUCT (2)     S/G Blowdown Isolation valves CLOSE (3)     S/G Sample Isolation valves CLOSE (4)     Humidification Steam Inlet CV HS-17-1/CV31770 CLOSES
(1)
: a.       ONLY (1), (2) AND (3) occur
Air Ejector Discharge Vent. AR-6/CV-31168 positions to DUCT (2)
: b.       ONLY (2) AND (3) occur
S/G Blowdown Isolation valves CLOSE (3)
: c.       (1), (2), (3) AND (4) occur
S/G Sample Isolation valves CLOSE (4)
: d.       ONLY (2), (3) AND (4) occur
Humidification Steam Inlet CV HS-17-1/CV31770 CLOSES a.
ONLY (1), (2) AND (3) occur b.
ONLY (2) AND (3) occur c.
(1), (2), (3) AND (4) occur d.
ONLY (2), (3) AND (4) occur


REACTOR OPERATOR                                                                       Page 77 QUESTION: 073 (1.00)
REACTOR OPERATOR Page 77 QUESTION: 073 (1.00)
Which of the following describes the CW condition(s) that would provide an interlock to PREVENT starting a CW pump?
Which of the following describes the CW condition(s) that would provide an interlock to PREVENT starting a CW pump?
(I)     Seal Water Flow < 2 gpm (II)     "Forebay Level Low Low" (566 or 42%)
(I)
(III)   Thrust Bearing Cooler Flow < 4 gpm
Seal Water Flow < 2 gpm (II)
: a.       ONLY (II)
"Forebay Level Low Low" (566 or 42%)
: b.       ONLY (I) and (III)
(III)
: c.       ONLY (II) and (III)
Thrust Bearing Cooler Flow < 4 gpm a.
: d.       (I), (II) and (III)
ONLY (II) b.
ONLY (I) and (III) c.
ONLY (II) and (III) d.
(I), (II) and (III)


REACTOR OPERATOR                                                                           Page 78 QUESTION: 074 (1.00)
REACTOR OPERATOR Page 78 QUESTION: 074 (1.00)
A malfunction of ONE of the "A" Diesel Generator Room CO2 temperature switches occurs, causing it to fail HIGH. Which of the following describes the response of the CO2 system to the "A" Diesel Generator Room?
A malfunction of ONE of the "A" Diesel Generator Room CO2 temperature switches occurs, causing it to fail HIGH. Which of the following describes the response of the CO2 system to the "A" Diesel Generator Room?
: a.       The CO2 actuation sequence will not begin until a second switch actuation occurs.
a.
: b.       The CO2 actuation sequence will sound a local horn, but will not discharge.
The CO2 actuation sequence will not begin until a second switch actuation occurs.
: c.       The CO2 actuation sequence will sound a local horn and then discharge.
b.
: d.       The CO2 actuation sequence will start a local, flashing red light, sound a local horn and then discharge.
The CO2 actuation sequence will sound a local horn, but will not discharge.
c.
The CO2 actuation sequence will sound a local horn and then discharge.
d.
The CO2 actuation sequence will start a local, flashing red light, sound a local horn and then discharge.


REACTOR OPERATOR                                                                 Page 79 QUESTION: 075 (1.00)
REACTOR OPERATOR Page 79 QUESTION: 075 (1.00)
Given the following conditions:
Given the following conditions:
      -      The plant is at 100% power.
The plant is at 100% power.
      -      All lineups/switch positions are in their NORMAL position.
All lineups/switch positions are in their NORMAL position.
      -      Pressurizer Level Channel LT-426 (Channel I) fails LOW What is the status of the following BEFORE any operator actions are taken?
Pressurizer Level Channel LT-426 (Channel I) fails LOW What is the status of the following BEFORE any operator actions are taken?
Letdown Flow Indication       "Pressurizer Level Low" Annunciator
Letdown Flow Indication "Pressurizer Level Low" Annunciator a.
: a.         Normal                             LIT
Normal LIT b.
: b.         Normal                             Not LIT
Normal Not LIT c.
: c.         Zero                               LIT
Zero LIT d.
: d.         Zero                               Not Lit
Zero Not Lit


REACTOR OPERATOR                                                                 Page 80 QUESTION: 076 (1.00)
REACTOR OPERATOR Page 80 QUESTION: 076 (1.00)
Given the following conditions:
Given the following conditions:
      -      Steam Generator NR Levels are 88%
Steam Generator NR Levels are 88%
      -      MSIVs are CLOSED Per Procedure FR-H.2, "Response to Steam Generator Overpressure," which of the methods given below has PRIORITY for decreasing S/G pressure?
MSIVs are CLOSED Per Procedure FR-H.2, "Response to Steam Generator Overpressure," which of the methods given below has PRIORITY for decreasing S/G pressure?
: a.     Dump steam using SG PORVs
a.
: b.     Isolate AFW to the S/Gs
Dump steam using SG PORVs b.
: c.     Dump steam using Steam Supply to Turbine-Driven AFW Pump
Isolate AFW to the S/Gs c.
: d.     Dump steam using Main Steam Isolation Bypass Valves
Dump steam using Steam Supply to Turbine-Driven AFW Pump d.
Dump steam using Main Steam Isolation Bypass Valves


REACTOR OPERATOR                                                                       Page 81 QUESTION: 077 (1.00)
REACTOR OPERATOR Page 81 QUESTION: 077 (1.00)
In addressing a PRZR relief valve (PORV) that is stuck open, the associated block valve must be closed. Which of the following indication(s) can be used to identify which PORV is stuck open?
In addressing a PRZR relief valve (PORV) that is stuck open, the associated block valve must be closed. Which of the following indication(s) can be used to identify which PORV is stuck open?
(I)   PR-2A(B) indicating lights on the Mechanical Console C (II)   Acoustic monitor indicating lights on the Mechanical Console C (III) Outlet temperatures for each PORV
(I)
: a.         ONLY (I)
PR-2A(B) indicating lights on the Mechanical Console C (II)
: b.         ONLY (I) OR (III)
Acoustic monitor indicating lights on the Mechanical Console C (III)
: c.         ONLY (II) OR (III)
Outlet temperatures for each PORV a.
: d.         (I), (II) OR (III)
ONLY (I) b.
ONLY (I) OR (III) c.
ONLY (II) OR (III) d.
(I), (II) OR (III)


REACTOR OPERATOR                                                                 Page 82 QUESTION: 078 (1.00)
REACTOR OPERATOR Page 82 QUESTION: 078 (1.00)
A LOCA has occurred and a controlled RCS cooldown and depressurization per ES-1.2, "Post LOCA Cooldown and Depressurization" is in progress. ALL ECCS equipment is OPERABLE.
A LOCA has occurred and a controlled RCS cooldown and depressurization per ES-1.2, "Post LOCA Cooldown and Depressurization" is in progress. ALL ECCS equipment is OPERABLE.
RCS Pressure and Temperature is 1500 psig / 480&deg;F. After SI pump A is secured as part of the RCS cooldown and depressurization, the following alarms occur:
RCS Pressure and Temperature is 1500 psig / 480&deg;F. After SI pump A is secured as part of the RCS cooldown and depressurization, the following alarms occur:
      -      47022-D, "CONTAINMENT HIGH PRESSURE SI"
47022-D, "CONTAINMENT HIGH PRESSURE SI" 47024-A, "ACCUMULATOR A PRESSURE HIGH/LOW" 47024-B, "ACCUMULATOR A LEVEL HIGH/LOW" What action(s) must be taken, if any, based on these conditions:
      -      47024-A, "ACCUMULATOR A PRESSURE HIGH/LOW"
a.
      -      47024-B, "ACCUMULATOR A LEVEL HIGH/LOW" What action(s) must be taken, if any, based on these conditions:
Trip both RCPs.
: a.     Trip both RCPs.
b.
: b.     Restart SI pump A.
Restart SI pump A.
: c.     Trip both RCPs AND Restart SI pump A.
c.
: d.     No action required.
Trip both RCPs AND Restart SI pump A.
d.
No action required.


REACTOR OPERATOR                                                                         Page 83 QUESTION: 079 (1.00)
REACTOR OPERATOR Page 83 QUESTION: 079 (1.00)
Which of the following systems is considered to be the most likely location for a rupture or break outside containment, and therefore is the system of primary concern during ECA-1.2, "LOCA Outside Containment?"
Which of the following systems is considered to be the most likely location for a rupture or break outside containment, and therefore is the system of primary concern during ECA-1.2, "LOCA Outside Containment?"
: a.     Safety Injection
a.
: b.     Residual Heat Removal
Safety Injection b.
: c.     Component Cooling
Residual Heat Removal c.
: d.     Chemical and Volume Control
Component Cooling d.
Chemical and Volume Control


REACTOR OPERATOR                                                                       Page 84 QUESTION: 080 (1.00)
REACTOR OPERATOR Page 84 QUESTION: 080 (1.00)
Given the following conditions:
Given the following conditions:
        -        A loss of normal feedwater flow has occurred.
A loss of normal feedwater flow has occurred.
        -        The actions of FR-S.1 "Response to Nuclear Power Generation/ATWS" must be performed due to a failure of the plant to trip Which of the following describes the proper sequence of steps to be taken with a failure of the reactor to trip, AFTER beginning to manually insert the Control Rods?
The actions of FR-S.1 "Response to Nuclear Power Generation/ATWS" must be performed due to a failure of the plant to trip Which of the following describes the proper sequence of steps to be taken with a failure of the reactor to trip, AFTER beginning to manually insert the Control Rods?
(I)     -   Locally Open Reactor Trip Breakers (II)     -   Open Bus 33 and Bus 43 supply breakers (III)   -   TRIP Rod Drive MG Set Motor & Generator Circuit Breaker Control Switches
(I)
: a.       (I), (II), and THEN (III).
- Locally Open Reactor Trip Breakers (II)
: b.       (II), (I), and THEN (III).
- Open Bus 33 and Bus 43 supply breakers (III)
: c.       (II), (III), and THEN (I).
- TRIP Rod Drive MG Set Motor & Generator Circuit Breaker Control Switches a.
: d.       (III), (II), and THEN (I).
(I), (II), and THEN (III).
b.
(II), (I), and THEN (III).
c.
(II), (III), and THEN (I).
d.
(III), (II), and THEN (I).


REACTOR OPERATOR                                                                       Page 85 QUESTION: 081 (1.00)
REACTOR OPERATOR Page 85 QUESTION: 081 (1.00)
Given the following conditions:
Given the following conditions:
      -      Reactor power is 100%
Reactor power is 100%
      -      VCT level transmitter LT-112 (24015) fails high (100%)
VCT level transmitter LT-112 (24015) fails high (100%)
Which of the following describes what occurs if NO operator action is taken?
Which of the following describes what occurs if NO operator action is taken?
VCT level decreases __________.
VCT level decreases __________.
: a.     because auto makeup capacity is not able to maintain VCT level with letdown diverted
a.
: b.     with NO auto makeup capability causing charging suction to shift to the RWST
because auto makeup capacity is not able to maintain VCT level with letdown diverted b.
: c.     until charging pumps lose suction and start to cavitate
with NO auto makeup capability causing charging suction to shift to the RWST c.
: d.     until auto makeup starts and maintains VCT level
until charging pumps lose suction and start to cavitate d.
until auto makeup starts and maintains VCT level


REACTOR OPERATOR                                                                     Page 86 QUESTION: 082 (1.00)
REACTOR OPERATOR Page 86 QUESTION: 082 (1.00)
Given the following conditions:
Given the following conditions:
      -      The plant is at 255&deg;F, cooling down to Cold Shutdown with RHR Train A.
The plant is at 255&deg;F, cooling down to Cold Shutdown with RHR Train A.
      -      RHR Train B is out of service for testing.
RHR Train B is out of service for testing.
      -      Annunciator 47024-H, CC SURGE TANK LEVEL HIGH/LOW is LIT.
Annunciator 47024-H, CC SURGE TANK LEVEL HIGH/LOW is LIT.
      -      CC Surge Tank Level is 53% and INCREASING.
CC Surge Tank Level is 53% and INCREASING.
      -      R-17, Component Cooling Liquid Rad Monitor, is in HIGH ALARM.
R-17, Component Cooling Liquid Rad Monitor, is in HIGH ALARM.
      -      VCT level is DECREASING.
VCT level is DECREASING.
      -      All other indications are NORMAL.
All other indications are NORMAL.
Which of the following is the location of the leak?
Which of the following is the location of the leak?
: a.     RHR system.
a.
: b.     SFP heat exchanger.
RHR system.
: c.     Seal Water heat exchanger.
b.
: d.     SW system.
SFP heat exchanger.
c.
Seal Water heat exchanger.
d.
SW system.


REACTOR OPERATOR                                                                       Page 87 QUESTION: 083 (1.00)
REACTOR OPERATOR Page 87 QUESTION: 083 (1.00)
Complete the following statement:
Complete the following statement:
Source Range neutron detectors operate in the ____(1)_____ region, so decreasing the detector voltage beyond calibration limits would result in a _____(2)_____ indicated power level.
Source Range neutron detectors operate in the ____(1)_____ region, so decreasing the detector voltage beyond calibration limits would result in a _____(2)_____ indicated power level.
: a.     (1) Ionization,       (2) higher
a.
: b.     (1) Proportional,     (2) higher
(1) Ionization, (2) higher b.
: c.     (1) Ionization,       (2) lower
(1) Proportional, (2) higher c.
: d.     (1) Proportional,     (2) lower
(1) Ionization, (2) lower d.
(1) Proportional, (2) lower


REACTOR OPERATOR                                                                       Page 88 QUESTION: 084 (1.00)
REACTOR OPERATOR Page 88 QUESTION: 084 (1.00)
The following conditions exist:
The following conditions exist:
        -      A reactor startup has been completed per N-CRD-49B, "Reactor Startup."
A reactor startup has been completed per N-CRD-49B, "Reactor Startup."
        -      The Source Range trip is blocked.
The Source Range trip is blocked.
        -      The N35 Intermediate Range channel is failed LOW with the level trip bypassed.
The N35 Intermediate Range channel is failed LOW with the level trip bypassed.
        -      The N36 Intermediate Range channel is reading ERRATICALLY.
The N36 Intermediate Range channel is reading ERRATICALLY.
        -      Source Range counts have just reached 106 CPS What is the expected indication on the intermediate range nuclear instruments for this condition?
Source Range counts have just reached 106 CPS What is the expected indication on the intermediate range nuclear instruments for this condition?
: a. 10-3 % Power (IR)
a.
: b. 10-2 % Power (IR)
10-3 % Power (IR) b.
: c. 10-1 % Power (IR)
10-2 % Power (IR) c.
: d. 100 or 1% Power (IR)
10-1 % Power (IR) d.
100 or 1% Power (IR)


REACTOR OPERATOR                                                                       Page 89 QUESTION: 085 (1.00)
REACTOR OPERATOR Page 89 QUESTION: 085 (1.00)
The plant is at 100% power. TLA-15, RMS ABOVE NORMAL is in alarm due to increasing radiation level on R-19, S/G Blowdown Liquid Monitor. What action(s) must be taken based on these conditions?
The plant is at 100% power. TLA-15, RMS ABOVE NORMAL is in alarm due to increasing radiation level on R-19, S/G Blowdown Liquid Monitor. What action(s) must be taken based on these conditions?
: a.     IF the radiation level on R-19, S/G Blowdown Liquid Monitor increases to HIGH alarm, THEN go to E-0-14, "Steam Generator Tube Leak."
a.
: b.     Go to E-0-14, "Steam Generator Tube Leak" and perform Operator immediate actions.
IF the radiation level on R-19, S/G Blowdown Liquid Monitor increases to HIGH alarm, THEN go to E-0-14, "Steam Generator Tube Leak."
: c.     Go to A-RM-45, "Abnormal Radiation Monitoring System" and verify the automatic actions occur as listed for R-19, S/G Blowdown Liquid Monitor.
b.
: d.     Per A-RM-45, "Abnormal Radiation Monitoring System" determine primary-to-secondary leak rate using "R-19 to Leakage Rate Conversion Graph."
Go to E-0-14, "Steam Generator Tube Leak" and perform Operator immediate actions.
c.
Go to A-RM-45, "Abnormal Radiation Monitoring System" and verify the automatic actions occur as listed for R-19, S/G Blowdown Liquid Monitor.
d.
Per A-RM-45, "Abnormal Radiation Monitoring System" determine primary-to-secondary leak rate using "R-19 to Leakage Rate Conversion Graph."


REACTOR OPERATOR                                                                         Page 90 QUESTION: 086 (1.00)
REACTOR OPERATOR Page 90 QUESTION: 086 (1.00)
Which of the following describes the reason for tripping both RXCPs, if required, per step 1 of E-3, "Steam Generator Tube Rupture?"
Which of the following describes the reason for tripping both RXCPs, if required, per step 1 of E-3, "Steam Generator Tube Rupture?"
: a.     To minimize the potential for RCP damage when an RCS depressurization is initiated.
a.
: b.     To minimize the heat input when a controlled RCS cooldown is initiated.
To minimize the potential for RCP damage when an RCS depressurization is initiated.
: c.     To prevent the automatic opening of a pressurizer PORV.
b.
: d.     To prevent unnecessary RCS water depletion.
To minimize the heat input when a controlled RCS cooldown is initiated.
c.
To prevent the automatic opening of a pressurizer PORV.
d.
To prevent unnecessary RCS water depletion.


REACTOR OPERATOR                                                                       Page 91 QUESTION: 087 (1.00)
REACTOR OPERATOR Page 91 QUESTION: 087 (1.00)
The following plant conditions exist:
The following plant conditions exist:
        -      FR-H.1, Response to Loss of Secondary Heat Sink is in progress.
FR-H.1, Response to Loss of Secondary Heat Sink is in progress.
        -      The CST is unavailable.
The CST is unavailable.
        -      Yarway wide range S/G levels are at 20%.
Yarway wide range S/G levels are at 20%.
        -      RCS pressure is at 2200 psig.
RCS pressure is at 2200 psig.
        -      Containment pressure is 1 psig.
Containment pressure is 1 psig.
Which of the following heat removal methods is available, if any, before RCS bleed and feed is required AND what is the preferred sequence for establishing flow to at least one S/G?
Which of the following heat removal methods is available, if any, before RCS bleed and feed is required AND what is the preferred sequence for establishing flow to at least one S/G?
(1)   Depressurize SG and establish Condensate flow (2)   Establish AFW flow using Service Water (3)   Establish Main Feedwater flow
(1)
: a.     (2), (3), (1)
Depressurize SG and establish Condensate flow (2)
: b.     (3), (2), (1)
Establish AFW flow using Service Water (3)
: c.     (3), (1), (2)
Establish Main Feedwater flow a.
: d. No S/G heat removal method is available; RCS bleed and feed is required immediately.
(2), (3), (1) b.
(3), (2), (1) c.
(3), (1), (2) d.
No S/G heat removal method is available; RCS bleed and feed is required immediately.


REACTOR OPERATOR                                                                         Page 92 QUESTION: 088 (1.00)
REACTOR OPERATOR Page 92 QUESTION: 088 (1.00)
Which of the following places the plant in a 1 hour Limiting Condition of Operation per Technical Specifications?
Which of the following places the plant in a 1 hour Limiting Condition of Operation per Technical Specifications?
: a. BRA-101, Station Battery A, fuse blows.
a.
: b. BRA-108, Battery Charger A, damaged due to fire.
BRA-101, Station Battery A, fuse blows.
: c. BRA-102, DC DIstribution Train A, damaged bus bar.
b.
: d. BRA-111, Instrument Bus 1 Inverter, damaged rectifier.
BRA-108, Battery Charger A, damaged due to fire.
c.
BRA-102, DC DIstribution Train A, damaged bus bar.
d.
BRA-111, Instrument Bus 1 Inverter, damaged rectifier.


REACTOR OPERATOR                                                                     Page 93 QUESTION: 089 (1.00)
REACTOR OPERATOR Page 93 QUESTION: 089 (1.00)
The following plant conditions exist:
The following plant conditions exist:
        -      An accidental gaseous release has occurred.
An accidental gaseous release has occurred.
        -      The derived air concentration (DAC) of this release is 4 DAC.
The derived air concentration (DAC) of this release is 4 DAC.
Which of the following is the expected exposure to the whole body of a worker breathing air in this area for 30 minutes?
Which of the following is the expected exposure to the whole body of a worker breathing air in this area for 30 minutes?
: a.     2 mrem
a.
: b.     5 mrem
2 mrem b.
: c.     8 mrem
5 mrem c.
: d.     10 mrem
8 mrem d.
10 mrem


REACTOR OPERATOR                                                                         Page 94 QUESTION: 090 (1.00)
REACTOR OPERATOR Page 94 QUESTION: 090 (1.00)
The plant is operating at 100% power. Annunciator 47033-35, TLA-15, RMS ABOVE NORMAL, alarms due to rising count rate on R-42, S/G A N16 Monitor.
The plant is operating at 100% power. Annunciator 47033-35, TLA-15, RMS ABOVE NORMAL, alarms due to rising count rate on R-42, S/G A N16 Monitor.
Plant conditions:
Plant conditions:
Pressurizer level:             47%, stable.
Pressurizer level:
Pressurizer pressure:         2235 psig.
47%, stable.
Pressurizer pressure:
2235 psig.
Which of the following describes the action or actions required for this situation?
Which of the following describes the action or actions required for this situation?
: a.     Enter E-0-14, Steam Generator Tube Leak.
a.
: b.     Manually trip the reactor and enter E-0, Reactor Trip or Safety Injection.
Enter E-0-14, Steam Generator Tube Leak.
: c.     Contact Health Physics to assist in identifying the radiation source.
b.
: d.     Evacuate the reactor building.
Manually trip the reactor and enter E-0, Reactor Trip or Safety Injection.
c.
Contact Health Physics to assist in identifying the radiation source.
d.
Evacuate the reactor building.


REACTOR OPERATOR                                                                     Page 95 QUESTION: 091 (1.00)
REACTOR OPERATOR Page 95 QUESTION: 091 (1.00)
Given the following conditions:
Given the following conditions:
      -      A LOCA has occurred
A LOCA has occurred The crew is performing a cooldown per ES-1.2 " Post LOCA Cooldown and Depressurization" Two Containment Cooling Fan Coil Units are running Containment pressure is stable at 2.2 psig A transition to FR-Z.3 "Response to High Containment Radiation Level" is made on a YELLOW path condition Why does FR-Z.3 start idle Containment Cooling Fan Coil Units?
      -      The crew is performing a cooldown per ES-1.2 " Post LOCA Cooldown and Depressurization"
a.
      -      Two Containment Cooling Fan Coil Units are running
To remove radioactive particulates during condensation of water vapor.
      -      Containment pressure is stable at 2.2 psig
b.
      -      A transition to FR-Z.3 "Response to High Containment Radiation Level" is made on a YELLOW path condition Why does FR-Z.3 start idle Containment Cooling Fan Coil Units?
To remove radioactive gases during condensation of water vapor.
: a.     To remove radioactive particulates during condensation of water vapor.
c.
: b.     To remove radioactive gases during condensation of water vapor.
To support Containment Purge and Vent Subsystem Exhaust filtration.
: c.     To support Containment Purge and Vent Subsystem Exhaust filtration.
d.
: d.     To support Containment Purge and Vent Subsystem Purge filtration.
To support Containment Purge and Vent Subsystem Purge filtration.


REACTOR OPERATOR                                                                     Page 96 QUESTION: 092 (1.00)
REACTOR OPERATOR Page 96 QUESTION: 092 (1.00)
Given the following conditions:
Given the following conditions:
      -      A fire has occurred on site.
A fire has occurred on site.
      -      E-0-06, "Fire in Alternate Fire Zone" is being implemented.
E-0-06, "Fire in Alternate Fire Zone" is being implemented.
Complete the following statement:
Complete the following statement:
During implementation of E-0-06, only ____(1)____ equipment is being controlled from the Dedicated Shutdown Panel and offsite power is considered to be ____(2)____.
During implementation of E-0-06, only ____(1)____ equipment is being controlled from the Dedicated Shutdown Panel and offsite power is considered to be ____(2)____.
____(1)____           ____(2)____
____(1)____
: a.     Train A               available
____(2)____
: b.     Train A               NOT available
a.
: c.     Train B               available
Train A available b.
: d.     Train B               NOT available
Train A NOT available c.
Train B available d.
Train B NOT available


REACTOR OPERATOR                                                                         Page 97 QUESTION: 093 (1.00)
REACTOR OPERATOR Page 97 QUESTION: 093 (1.00)
The plant was operating at 100% power when the following events occurred:
The plant was operating at 100% power when the following events occurred:
      -      0100: RC-413, Pressurizer Liquid Sampling Isolation valve is determined to be INOPERABLE.
0100: RC-413, Pressurizer Liquid Sampling Isolation valve is determined to be INOPERABLE.
      -      0200: RC-412, Pressurizer Liquid Sampling Isolation valve is determined to be INOPERABLE.
0200: RC-412, Pressurizer Liquid Sampling Isolation valve is determined to be INOPERABLE.
What log entry or entries need to be made to track these inoperable valves?
What log entry or entries need to be made to track these inoperable valves?
: a. An entry for each valve in the Shift Managers Log AND in the Shift Managers LCO Tracking Log at the time they became INOPERABLE.
a.
: b. An entry for each valve in the Control Room Log AND in the Shift Managers LCO Tracking Log at the time the valves were discovered to be INOPERABLE.
An entry for each valve in the Shift Managers Log AND in the Shift Managers LCO Tracking Log at the time they became INOPERABLE.
: c. An entry in the Shift Managers Log AND the Control Room Log for each valve at the time they became INOPERABLE, AND an entry in the Control Room Shift Turnover Checklist at shift turnover.
b.
: d. One log entry for both valves in the Control Room Shift Turnover Checklist at shift turnover AND an entry for each valve in the Periodic Daily Log at the time each valve became INOPERABLE.
An entry for each valve in the Control Room Log AND in the Shift Managers LCO Tracking Log at the time the valves were discovered to be INOPERABLE.
c.
An entry in the Shift Managers Log AND the Control Room Log for each valve at the time they became INOPERABLE, AND an entry in the Control Room Shift Turnover Checklist at shift turnover.
d.
One log entry for both valves in the Control Room Shift Turnover Checklist at shift turnover AND an entry for each valve in the Periodic Daily Log at the time each valve became INOPERABLE.


REACTOR OPERATOR                                                                   Page 98 QUESTION: 094 (1.00)
REACTOR OPERATOR Page 98 QUESTION: 094 (1.00)
Given the following:
Given the following:
      -      A LOCA has occurred.
A LOCA has occurred.
      -      Containment Pressure is 6 psig.
Containment Pressure is 6 psig.
      -      Core Exit Thermocouples are at 600&deg;F.
Core Exit Thermocouples are at 600&deg;F.
      -      RCS pressure is 200 psig.
RCS pressure is 200 psig.
      -      RHR is in its at-power lineup.
RHR is in its at-power lineup.
      -      FR-C.3, Response to Saturated Core Cooling, is being implemented.
FR-C.3, Response to Saturated Core Cooling, is being implemented.
What flows to the RCS must be verified per FR-C.3, Response to Saturated Core Cooling?
What flows to the RCS must be verified per FR-C.3, Response to Saturated Core Cooling?
: a.     Charging pump flow ONLY.
a.
: b.     RHR and SI pump flows ONLY.
Charging pump flow ONLY.
: c.     SI pump flow ONLY.
b.
: d.     Charging and SI pump flows ONLY.
RHR and SI pump flows ONLY.
c.
SI pump flow ONLY.
d.
Charging and SI pump flows ONLY.


REACTOR OPERATOR                                                                     Page 99 QUESTION: 095 (1.00)
REACTOR OPERATOR Page 99 QUESTION: 095 (1.00)
The following conditions exist:
The following conditions exist:
        -      A runback from 80% to 60% power occurred 2 hours ago.
A runback from 80% to 60% power occurred 2 hours ago.
        -      Chemistry samples of the RCS indicate high dose-equivalent I-131.
Chemistry samples of the RCS indicate high dose-equivalent I-131.
Why is it desirable to increase letdown flow through the CVC mixed bed demineralizers to 80 gpm under these conditions?
Why is it desirable to increase letdown flow through the CVC mixed bed demineralizers to 80 gpm under these conditions?
: a. To reduce RCS activity.
a.
: b. To control RCS pH.
To reduce RCS activity.
: c. To reduce RCS corrosion products.
b.
: d. To control RCS boron concentration.
To control RCS pH.
c.
To reduce RCS corrosion products.
d.
To control RCS boron concentration.


REACTOR OPERATOR                                                                       Page 100 QUESTION: 096 (1.00)
REACTOR OPERATOR Page 100 QUESTION: 096 (1.00)
While performing ECA-1.1, Loss of Emergency Coolant Recirculation, the "RHR Pump A Supply to ICS Pump A", valve RHR-400A could not be operated from the control room. The steps contingency action states "Locally open valve". On which elevation of the auxiliary building is this valve located?
While performing ECA-1.1, Loss of Emergency Coolant Recirculation, the "RHR Pump A Supply to ICS Pump A", valve RHR-400A could not be operated from the control room. The steps contingency action states "Locally open valve". On which elevation of the auxiliary building is this valve located?
: a.       572
a.
: b.       586
572 b.
: c.       606
586 c.
: d.       626
606 d.
626


REACTOR OPERATOR                                                                   Page 101 QUESTION: 097 (1.00)
REACTOR OPERATOR Page 101 QUESTION: 097 (1.00)
In order to establish a Containment Purge in HOT SHUTDOWN, which of the following is required?
In order to establish a Containment Purge in HOT SHUTDOWN, which of the following is required?
: 1.       Notify NRC prior to opening 36" RBV valves.
1.
: 2.       Obtain a Gaseous Waste Discharge Permit.
Notify NRC prior to opening 36" RBV valves.
: 3.       Verify Annunciator 47051-B, "Containment Vent High Radiation Disabled" is CLEAR.
2.
: a.       ONLY 1 and 2.
Obtain a Gaseous Waste Discharge Permit.
: b.       ONLY 1 and 3.
3.
: c.       ONLY 2 and 3.
Verify Annunciator 47051-B, "Containment Vent High Radiation Disabled" is CLEAR.
: d.       1, 2 and 3.
a.
ONLY 1 and 2.
b.
ONLY 1 and 3.
c.
ONLY 2 and 3.
d.
1, 2 and 3.


REACTOR OPERATOR                                                                         Page 102 QUESTION: 098 (1.00)
REACTOR OPERATOR Page 102 QUESTION: 098 (1.00)
For a Steam Line Break of a given size and location, which of the following initial conditions results in the smallest reactivity rate of change immediately after the break?
For a Steam Line Break of a given size and location, which of the following initial conditions results in the smallest reactivity rate of change immediately after the break?
CORE BURNUP (MWD/MTU)               RCS Tavg
CORE BURNUP (MWD/MTU)
: a.       9000                               450&deg;F
RCS Tavg a.
: b.       9000                               547&deg;F
9000 450&deg;F b.
: c.       5000                               450&deg;F
9000 547&deg;F c.
: d.       5000                               547&deg;F
5000 450&deg;F d.
5000 547&deg;F


REACTOR OPERATOR                                                                     Page 103 QUESTION: 099 (1.00)
REACTOR OPERATOR Page 103 QUESTION: 099 (1.00)
Given the following:
Given the following:
      -      Reactor power is stabilized at the eight-fold power level.
Reactor power is stabilized at the eight-fold power level.
      -      The Eight-Fold Critical Rod Position is determined to be 65 steps on Control Bank C.
The Eight-Fold Critical Rod Position is determined to be 65 steps on Control Bank C.
Which action is required in this situation?
Which action is required in this situation?
: a.     Emergency Borate 300 gallons.
a.
: b.     SHUT DOWN the reactor per N-CRD-49C, "Reactor Shutdown"
Emergency Borate 300 gallons.
: c.     Get permission from Station Nuclear Engineer to continue with the startup.
b.
: d.     Verify the Eight-fold Critical Rod Position is within +400pcm of ECP
SHUT DOWN the reactor per N-CRD-49C, "Reactor Shutdown" c.
Get permission from Station Nuclear Engineer to continue with the startup.
d.
Verify the Eight-fold Critical Rod Position is within +400pcm of ECP


REACTOR OPERATOR                                                             Page 104 QUESTION: 100 (1.00)
REACTOR OPERATOR Page 104 QUESTION: 100 (1.00)
Given the following:
Given the following:
      -      The plant is in normal 100% power operations.
The plant is in normal 100% power operations.
      -      Containment Fan Coil Units Emergency Discharge Dampers RBV-150 A and B both fail OPEN.
Containment Fan Coil Units Emergency Discharge Dampers RBV-150 A and B both fail OPEN.
What is the major concern at this time?
What is the major concern at this time?
: a.     Damage to the Nuclear Instrumentation.
a.
: b.     Damage to the Reactor Vessel Gap.
Damage to the Nuclear Instrumentation.
: c.     RXCP A motor stator overheating.
b.
: d.     RXCP B motor stator overheating.
Damage to the Reactor Vessel Gap.
c.
RXCP A motor stator overheating.
d.
RXCP B motor stator overheating.
(********** END OF EXAMINATION **********)
(********** END OF EXAMINATION **********)


Line 1,029: Line 1,373:


==REFERENCES:==
==REFERENCES:==
 
Page 105 ANSWER: 001 C
ANSWER: 001 C            ANSWER: 034 D            ANSWER: 067 C


==REFERENCE:==
==REFERENCE:==
ECA-0.0, CAUTION prior to Step 6; BYRON1 10/29/2001 Exam Bank Higher 000062K303..(KAs)
ANSWER: 034 D


==REFERENCE:==
==REFERENCE:==
A-FW-05A, Abnormal FW Operation, step 4.4.
New Higher 059000 2.2.2..(KAs)
ANSWER: 067 C


==REFERENCE:==
==REFERENCE:==
 
LO R01-01-LPTS4.010; Tech Spec 6.1; KNPP EQB Bank Memory 2.1.10..(KAs)
ECA-0.0, CAUTION prior to A-FW-05A, Abnormal FW    LO R01-01-LPTS4.010; Step 6;                  Operation, step 4.4.      Tech Spec 6.1; BYRON1 10/29/2001 Exam                              KNPP EQB New Bank                      Higher                    Bank Higher                    059000 2.2.2    ..(KAs) Memory 000062K303  ..(KAs)                              2.1.10     ..(KAs)
ANSWER: 002 B
ANSWER: 002 B             ANSWER: 035 A            ANSWER: 068 C


==REFERENCE:==
==REFERENCE:==
LP RO2-02-LP05A, Main Feedwater; SD 05A, Feedwater New Higher 059000K408..(KAs)
ANSWER: 035 A


==REFERENCE:==
==REFERENCE:==
SD 39, 4160 V System; SD 36, RCS New Memory 003000K201..(KAs)
ANSWER: 068 C


==REFERENCE:==
==REFERENCE:==
 
OP A-AS-1, Abnormal Station/
LP RO2-02-LP05A, Main    SD 39, 4160 V System;    OP A-AS-1, Abnormal Station/
Instrument Air System Operation; SD #1, Station/Instrument Air, Pg 9.
Feedwater;                SD 36, RCS                Instrument Air System SD 05A, Feedwater                                  Operation; New                      SD #1, Station/Instrument Air, New                      Memory                    Pg 9.
Bank Memory 078000K403..(KAs)
Higher                    003000K201      ..(KAs) 059000K408  ..(KAs)                              Bank Memory 078000K403     ..(KAs)
ANSWER: 003 A
ANSWER: 003 A             ANSWER: 036 A            ANSWER: 069 B


==REFERENCE:==
==REFERENCE:==
NRC EQB; KNPP 02/21/1994 Exam; ADV-SYS-LP-36D, p. 11; ADV-SYS-LP-36D, EO-RO4.a Bank Higher 022000K302..(KAs)
ANSWER: 036 A


==REFERENCE:==
==REFERENCE:==
IPEOP Background Document for FR-P.1; LP RO4-04-LP-016, Response to Imminent Pressurized Thermal Shock Condition New Memory E08EA202..(KAs)
ANSWER: 069 B


==REFERENCE:==
==REFERENCE:==
 
LP RO2-01-LP-36B, PZR and PRT; Tech Spec 3.1.a.6 and its basis; SD 38, DC and Emergency AC Power New Higher 062000 2.1.12..(KAs)
NRC EQB;                  IPEOP Background          LP RO2-01-LP-36B, PZR and KNPP 02/21/1994 Exam;    Document for FR-P.1;      PRT; ADV-SYS-LP-36D, p. 11;    LP RO4-04-LP-016,        Tech Spec 3.1.a.6 and its ADV-SYS-LP-36D,          Response to Imminent      basis; EO-RO4.a                  Pressurized Thermal Shock SD 38, DC and Emergency Condition                AC Power Bank Higher                    New                       New 022000K302  ..(KAs)    Memory                    Higher E08EA202      ..(KAs)    062000 2.1.12     ..(KAs)
Page 105


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 106 ANSWER: 004 D
ANSWER: 004 D             ANSWER: 037 A              ANSWER: 070 C


==REFERENCE:==
==REFERENCE:==
NRC EQB; Prairie Island 1 and 2 05/09/1994 Exam.
Modified Memory 056000K103..(KAs)
ANSWER: 037 A


==REFERENCE:==
==REFERENCE:==
ECA-2.1, Uncontrolled Depressurization of Both S/Gs New Higher E12EA13..(KAs)
ANSWER: 070 C


==REFERENCE:==
==REFERENCE:==
 
SD 38, DC and Emergency AC Electrical Distribution.
NRC EQB;                  ECA-2.1, Uncontrolled      SD 38, DC and Emergency Prairie Island 1 and 2    Depressurization of Both    AC Electrical Distribution.
New Memory 063000K201..(KAs)
05/09/1994 Exam.          S/Gs New Modified                  New                        Memory Memory                    Higher                      063000K201     ..(KAs) 056000K103      ..(KAs) E12EA13      ..(KAs)
ANSWER: 005 B
ANSWER: 005 B            ANSWER: 038 A              ANSWER: 071 B


==REFERENCE:==
==REFERENCE:==
E-240 Rev. AQ; Adv System LP Objective R02-05-LP36D.003 ("N/A).
New Memory 011000K202..(KAs)
ANSWER: 038 A


==REFERENCE:==
==REFERENCE:==
ES-1.1, SI Termination and Background Document; LP RO4-04-LP-005 New Memory 000026K303..(KAs)
ANSWER: 071 B


==REFERENCE:==
==REFERENCE:==
 
SD 38, DC and Emergency AC Power; LP RO2-03-LP-042A, D/Gs New Memory 064000K202..(KAs)
E-240 Rev. AQ;            ES-1.1, SI Termination and  SD 38, DC and Emergency Adv System LP Objective  Background Document;        AC Power; R02-05-LP36D.003 ("N/A). LP RO4-04-LP-005            LP RO2-03-LP-042A, D/Gs New                       New                        New Memory                    Memory                      Memory 011000K202      ..(KAs) 000026K303      ..(KAs)  064000K202     ..(KAs)
ANSWER: 006 C
ANSWER: 006 C            ANSWER: 039 C              ANSWER: 072 C


==REFERENCE:==
==REFERENCE:==
KNPP SD 1, Rev 1, p 6; LP O-RO-LP-2.11.1, EO 3; NRC EQB; KNPP 1993 Exam Modified Higher 079000K101..(KAs)
ANSWER: 039 C


==REFERENCE:==
==REFERENCE:==
ES-0.2, Natural Circulation Cooldown Modified Higher 2.4.4..(KAs)
ANSWER: 072 C


==REFERENCE:==
==REFERENCE:==
 
SD 45, Radiation Monitors; A-RM-45, Abnormal Radiation Monitoring; E-3748, PRM Integrated Logic Diagram New Memory 073000K301..(KAs)
KNPP SD 1, Rev 1, p 6;    ES-0.2, Natural Circulation SD 45, Radiation Monitors; LP O-RO-LP-2.11.1, EO 3;  Cooldown                    A-RM-45, Abnormal Radiation NRC EQB;                  Modified                    Monitoring; KNPP 1993 Exam            Higher                      E-3748, PRM Integrated Logic 2.4.4      ..(KAs)        Diagram Modified Higher                                                New 079000K101      ..(KAs)                            Memory 073000K301     ..(KAs)
Page 106


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 107 ANSWER: 007 D
ANSWER: 007 D             ANSWER: 040 C              ANSWER: 073 C


==REFERENCE:==
==REFERENCE:==
NRC EQB; V. C. Summer 1 1992/05/18 Exam Bank Higher 015000K101..(KAs)
ANSWER: 040 C


==REFERENCE:==
==REFERENCE:==
SD 49 Rod Control and RPI; Tech Specs New Higher 000005K105..(KAs)
ANSWER: 073 C


==REFERENCE:==
==REFERENCE:==
 
SD 4, CW System; ARP 47051-N, Forebay Level Low; LP RO2-02-LP-004, CW New Memory 075000K401..(KAs)
NRC EQB;                  SD 49 Rod Control and RPI; SD 4, CW System; V. C. Summer 1 1992/05/18 Tech Specs                ARP 47051-N, Forebay Level Exam                                                Low; Bank                      New                        LP RO2-02-LP-004, CW Higher                    Higher 015000K101 ..(KAs)      000005K105      ..(KAs)  New Memory 075000K401     ..(KAs)
ANSWER: 008 D
ANSWER: 008 D             ANSWER: 041 C              ANSWER: 074 C


==REFERENCE:==
==REFERENCE:==
NRC EQB; North Anna 1 01/26/1996 Exam.
Bank Higher 000065K304..(KAs)
ANSWER: 041 C


==REFERENCE:==
==REFERENCE:==
ES-0.2, Rev 0, Caution before step 1, p 2.;
NRC EQB; Point Beach 04/29/1991.
Bank Memory 000015A109..(KAs)
ANSWER: 074 C


==REFERENCE:==
==REFERENCE:==
 
SD 8, Fire Protection System; RO2-02-LP-008, Fire Protection System; New Memory 086000K604..(KAs)
NRC EQB;                  ES-0.2, Rev 0, Caution    SD 8, Fire Protection System; North Anna 1 01/26/1996  before step 1, p 2.;      RO2-02-LP-008, Fire Exam.                    NRC EQB;                  Protection System; Point Beach 04/29/1991.
ANSWER: 009 A
Bank                                                New Higher                    Bank                      Memory 000065K304      ..(KAs) Memory                     086000K604     ..(KAs) 000015A109      ..(KAs)
ANSWER: 009 A            ANSWER: 042 A              ANSWER: 075 A


==REFERENCE:==
==REFERENCE:==
NRC EQB; Prairie Island 1 and 2 09/28/1992 Exam.
Bank Higher 000003K103..(KAs)
ANSWER: 042 A


==REFERENCE:==
==REFERENCE:==
PWR Fundamentals; Braidwood 4/1/1996 Exam Bank Memory 000024K102..(KAs)
ANSWER: 075 A


==REFERENCE:==
==REFERENCE:==
 
SD 36, Reactor Coolant System; ARP 47043-F, PRZR Level Low; A-MI-87, B/S Tripping for Failed RP or Safeguards Inst.
NRC EQB;                  PWR Fundamentals;          SD 36, Reactor Coolant Prairie Island 1 and 2    Braidwood 4/1/1996 Exam    System; 09/28/1992 Exam.                                    ARP 47043-F, PRZR Level Bank                      Low; Bank                      Memory                    A-MI-87, B/S Tripping for Higher                    000024K102      ..(KAs)  Failed RP or Safeguards Inst.
New Memory 000028A206..(KAs)
000003K103      ..(KAs)
New Memory 000028A206     ..(KAs)
Page 107


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 108 ANSWER: 010 B
ANSWER: 010 B               ANSWER: 043 D              ANSWER: 076 A


==REFERENCE:==
==REFERENCE:==
BYRON1 10/29/2001 Exam.
Modified Higher 000027K203..(KAs)
ANSWER: 043 D


==REFERENCE:==
==REFERENCE:==
LP RO2-02-LP-003, Condensate and Air Removal System; New Higher 056000A204..(KAs)
ANSWER: 076 A


==REFERENCE:==
==REFERENCE:==
 
LP RO4-04-LP-036; FR-H.2, Response to S/G Overpressure; IPEOP Background Document New Memory E13EK11..(KAs)
BYRON1 10/29/2001 Exam.      LP RO2-02-LP-003,          LP RO4-04-LP-036; Condensate and Air          FR-H.2, Response to S/G Modified                    Removal System;            Overpressure; Higher                                                  IPEOP Background 000027K203    ..(KAs)      New                        Document Higher 056000A204    ..(KAs)    New Memory E13EK11     ..(KAs)
ANSWER: 011 B
ANSWER: 011 B               ANSWER: 044 B              ANSWER: 077 A


==REFERENCE:==
==REFERENCE:==
ES-1.3, Transfer to Cntnmt Sump Recirc; SD 33, SI System.
New Memory 006000 2.3.11..(KAs)
ANSWER: 044 B


==REFERENCE:==
==REFERENCE:==
RO2-02-LP-003.004; O-AOP-LP-D8; E-AR-09, Loss of Condenser Vacuum New Higher 000051 2.1.30..(KAs)
ANSWER: 077 A


==REFERENCE:==
==REFERENCE:==
 
LP RO4-04-LP-36B ARP 47042-A, PZR PORV Open; ARP 47042-B, PZR PORV Discharge Temperature High; New Higher 000008A203..(KAs)
ES-1.3, Transfer to Cntnmt  RO2-02-LP-003.004;          LP RO4-04-LP-36B Sump Recirc;                O-AOP-LP-D8;                ARP 47042-A, PZR PORV SD 33, SI System.            E-AR-09, Loss of            Open; Condenser Vacuum            ARP 47042-B, PZR PORV New                                                      Discharge Temperature High; Memory                      New 006000 2.3.11      ..(KAs) Higher                      New 000051 2.1.30      ..(KAs) Higher 000008A203     ..(KAs)
ANSWER: 012 A
ANSWER: 012 A               ANSWER: 045 A              ANSWER: 078 B


==REFERENCE:==
==REFERENCE:==
KNPP EQB; LP Obj RO2-01-LP31.004; CCW SD 31.
Bank Higher 008000A308..(KAs)
ANSWER: 045 A


==REFERENCE:==
==REFERENCE:==
SD 32B, Gaseous Radioactive Waste Disposal; New Memory 071000A302..(KAs)
ANSWER: 078 B


==REFERENCE:==
==REFERENCE:==
 
ES-1.2, Post LOCA Cooldown and Depressurization, Step 16a (Contingency Actions)
KNPP EQB;                    SD 32B, Gaseous            ES-1.2, Post LOCA Cooldown LP Obj RO2-01-LP31.004;      Radioactive Waste Disposal; and Depressurization, Step CCW SD 31.                                              16a (Contingency Actions)
New Higher 000009 2.4.45..(KAs)
New Bank                        Memory                      New Higher                       071000A302    ..(KAs)    Higher 008000A308    ..(KAs)                                  000009 2.4.45       ..(KAs)
Page 108


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 109 ANSWER: 013 A
ANSWER: 013 A               ANSWER: 046 A                ANSWER: 079 B


==REFERENCE:==
==REFERENCE:==
LP RO2-02-LP362; SD 36, RCS; KNPP 12/2000 Exam.
Bank Higher 003000A304..(KAs)
ANSWER: 046 A


==REFERENCE:==
==REFERENCE:==
SD 32B, Gaseous Radioactive Waste Disposal; SD 45, Radiation Monitoring New Memory 071000A409..(KAs)
ANSWER: 079 B


==REFERENCE:==
==REFERENCE:==
 
ECA-1.2, LOCA Outside Containment; IPEOP Background Document; Prairie Island 05/15/2000 Exam; LP RO4-04-LP-020, LOCA Outside Containment Modified Memory E04EK22..(KAs)
LP RO2-02-LP362;            SD 32B, Gaseous              ECA-1.2, LOCA Outside SD 36, RCS;                Radioactive Waste Disposal;  Containment; KNPP 12/2000 Exam.          SD 45, Radiation Monitoring  IPEOP Background Document; Bank                        New                          Prairie Island 05/15/2000 Higher                      Memory                      Exam; 003000A304    ..(KAs)    071000A409    ..(KAs)      LP RO4-04-LP-020, LOCA Outside Containment Modified Memory E04EK22         ..(KAs)
ANSWER: 014 A
ANSWER: 014 A               ANSWER: 047 A                ANSWER: 080 B


==REFERENCE:==
==REFERENCE:==
SD 05A, Feedwater System; SD 05B, Auxiliary Feedwater System; KNPP EQB.
Bank Higher 061000K101..(KAs)
ANSWER: 047 A


==REFERENCE:==
==REFERENCE:==
SD 45, Radiation Monitoring; RO2-01-LP045, Radiation Monitoring New Memory 072000K501..(KAs)
ANSWER: 080 B


==REFERENCE:==
==REFERENCE:==
 
FR-S.1, Response to Nuclear Power Generation/ATWS; IPEOP Background Document; New Memory 000029 2.4.49..(KAs)
SD 05A, Feedwater System;  SD 45, Radiation Monitoring; FR-S.1, Response to Nuclear SD 05B, Auxiliary Feedwater RO2-01-LP045, Radiation      Power Generation/ATWS; System;                    Monitoring                  IPEOP Background KNPP EQB.                                                Document; New Bank                        Memory                       New Higher                      072000K501    ..(KAs)      Memory 061000K101    ..(KAs)                                  000029 2.4.49       ..(KAs)
ANSWER: 015 A
ANSWER: 015 A               ANSWER: 048 D                ANSWER: 081 C


==REFERENCE:==
==REFERENCE:==
KNPP Exam 12/18/1997; SD 035, CVCS.
Bank Memory 004000A405..(KAs)
ANSWER: 048 D


==REFERENCE:==
==REFERENCE:==
SD 45, Radiation Monitoring; A-RM-45, Abnormal Radiation Monitoring New Memory 072000 2.3.10..(KAs)
ANSWER: 081 C


==REFERENCE:==
==REFERENCE:==
 
KNPP NRC Exam 10/24/2000 ARP 47043-L, VCT Level High/Low SD 35, CVCS Bank Memory 000022A108..(KAs)
KNPP Exam 12/18/1997;      SD 45, Radiation Monitoring; KNPP NRC Exam 10/24/2000 SD 035, CVCS.              A-RM-45, Abnormal            ARP 47043-L, VCT Level Bank                        Radiation Monitoring        High/Low Memory                                                  SD 35, CVCS 004000A405 ..(KAs)        New Memory                      Bank 072000 2.3.10      ..(KAs) Memory 000022A108       ..(KAs)
Page 109


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 110 ANSWER: 016 B
ANSWER: 016 B                 ANSWER: 049 C              ANSWER: 082 A


==REFERENCE:==
==REFERENCE:==
LP RO2-05-LP05B, Aux Feedwater; KNPP EQB Bank Higher 061000A101..(KAs)
ANSWER: 049 C


==REFERENCE:==
==REFERENCE:==
ES-0.2, Natural Circulation Cooldown; ES-0.2 Background Document; Bank Memory 002000A203..(KAs)
ANSWER: 082 A


==REFERENCE:==
==REFERENCE:==
 
A-CC-31, Abnormal CCW Operations; ARP 47024-H, CC Surge Tank Level High/Low; A-RHR-34, Abnormal RHR Operations; A-RM-45, Abnormal Rad Monitoring New Higher 000025A202..(KAs)
LP RO2-05-LP05B, Aux          ES-0.2, Natural Circulation A-CC-31, Abnormal CCW Feedwater;                    Cooldown;                  Operations; KNPP EQB                      ES-0.2 Background          ARP 47024-H, CC Surge Document;                  Tank Level High/Low; Bank                                                      A-RHR-34, Abnormal RHR Higher                        Bank                        Operations; 061000A101        ..(KAs)    Memory                      A-RM-45, Abnormal Rad 002000A203      ..(KAs)    Monitoring New Higher 000025A202     ..(KAs)
ANSWER: 017 D
ANSWER: 017 D                 ANSWER: 050 D              ANSWER: 083 C


==REFERENCE:==
==REFERENCE:==
SP-54-086, TSV and GV Operability Test, Pg 3 of 17.
New Memory 045A401..(KAs)
ANSWER: 050 D


==REFERENCE:==
==REFERENCE:==
RO2-05-LP-36C, Pressurizer Pressure Control New Higher 010000K103..(KAs)
ANSWER: 083 C


==REFERENCE:==
==REFERENCE:==
 
LP RO2-05-LP048, Excore Nuclear Instrumentation System; SD 48, Excore Nuclear Instrumentation New Memory 000032K101..(KAs)
SP-54-086, TSV and GV        RO2-05-LP-36C,              LP RO2-05-LP048, Excore Operability Test, Pg 3 of 17. Pressurizer Pressure        Nuclear Instrumentation Control                    System; New                                                      SD 48, Excore Nuclear Memory                        New                        Instrumentation 045A401        ..(KAs)      Higher 010000K103      ..(KAs)    New Memory 000032K101     ..(KAs)
ANSWER: 018 B
ANSWER: 018 B                 ANSWER: 051 C              ANSWER: 084 A


==REFERENCE:==
==REFERENCE:==
Byron 10/29/2001 Exam Bank Higher 2.1.25..(KAs)
ANSWER: 051 C


==REFERENCE:==
==REFERENCE:==
RO2-05-LP472, Reactor Protection New Higher 012000K304..(KAs)
ANSWER: 084 A


==REFERENCE:==
==REFERENCE:==
 
LP RO2-05-LP048, Excore Nuclear Instrumentation System; SD 48, Excore Nuclear Instrumentation New Memory 000033A201..(KAs)
Byron 10/29/2001 Exam        RO2-05-LP472, Reactor      LP RO2-05-LP048, Excore Protection                  Nuclear Instrumentation Bank                                                      System; Higher                        New                        SD 48, Excore Nuclear 2.1.25      ..(KAs)          Higher                      Instrumentation 012000K304      ..(KAs)
New Memory 000033A201     ..(KAs)
Page 110


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 111 ANSWER: 019 C
ANSWER: 019 C             ANSWER: 052 C              ANSWER: 085 B


==REFERENCE:==
==REFERENCE:==
LP R02-05-LP-033; TS 3.3.a. Accumulators New Higher 2.1.11..(KAs)
ANSWER: 052 C


==REFERENCE:==
==REFERENCE:==
LP RO4-04-LP040, Loss of all AC Power; Comanche Peak 11/26/90; ECA-0.0, Loss of all AC Power Bank Memory 000055K101..(KAs)
ANSWER: 085 B


==REFERENCE:==
==REFERENCE:==
 
A-RM-45, Abnormal Radiation Monitoring System; E-0-14, Steam Generator Tube Leak New Memory 000037A113..(KAs)
LP R02-05-LP-033;        LP RO4-04-LP040, Loss of    A-RM-45, Abnormal Radiation TS 3.3.a. Accumulators    all AC Power;              Monitoring System; Comanche Peak 11/26/90;    E-0-14, Steam Generator New                      ECA-0.0, Loss of all AC    Tube Leak Higher                    Power 2.1.11      ..(KAs)                                  New Bank                        Memory Memory                     000037A113     ..(KAs) 000055K101      ..(KAs)
ANSWER: 020 A
ANSWER: 020 A             ANSWER: 053 D              ANSWER: 086 D


==REFERENCE:==
==REFERENCE:==
LP R02-05-LP-053; N-FH-53-CLC, Pre-Refueling Checklist; RF-01.00, KNPP Refueling Procedure; New Higher 2.2.27..(KAs)
ANSWER: 053 D


==REFERENCE:==
==REFERENCE:==
LP RO2-05-36C, Pzr Pressure Control; SD 36, RCS; A-MI-87, Bistable Tripping for Failed RP or Safeguards Inst.
New Higher 000057A102..(KAs)
ANSWER: 086 D


==REFERENCE:==
==REFERENCE:==
 
BKG E-3, Steam Generator Tube Rupture; IPEOP Background Document; E-3, Steam Generator Tube Rupture New Memory 000038K308..(KAs)
LP R02-05-LP-053;        LP RO2-05-36C, Pzr          BKG E-3, Steam Generator N-FH-53-CLC,              Pressure Control;          Tube Rupture; Pre-Refueling Checklist;  SD 36, RCS;                IPEOP Background RF-01.00, KNPP Refueling  A-MI-87, Bistable Tripping  Document; Procedure;                for Failed RP or Safeguards E-3, Steam Generator Tube Inst.                      Rupture New Higher                    New                        New 2.2.27      ..(KAs)      Higher                      Memory 000057A102      ..(KAs)    000038K308     ..(KAs)
ANSWER: 021 C
ANSWER: 021 C            ANSWER: 054 C              ANSWER: 087 C


==REFERENCE:==
==REFERENCE:==
LP R02-05-LP-053; NAD-02.07, KNPP Refueling Operations New Memory 2.2.26..(KAs)
ANSWER: 054 C


==REFERENCE:==
==REFERENCE:==
KNPP SD 49, Rod Control and RPI; KNPP EQB RO2-05-LP049.004 010; LP RO2-05-LP049, Rod Control and RPI.
Bank Higher 014000K502..(KAs)
ANSWER: 087 C


==REFERENCE:==
==REFERENCE:==
 
A-FW-05B, Abnormal AFW System Operation; FR-H.1, Response to Loss of Secondary Heat Sink; BKG FR-H.1, Loss of Secondary Heat Sink; IPEOP Background Document New Higher E05EK22..(KAs)
LP R02-05-LP-053;        KNPP SD 49, Rod Control    A-FW-05B, Abnormal AFW NAD-02.07, KNPP Refueling and RPI;                    System Operation; Operations                KNPP EQB                    FR-H.1, Response to Loss of RO2-05-LP049.004 010;      Secondary Heat Sink; New                      LP RO2-05-LP049, Rod        BKG FR-H.1, Loss of Memory                    Control and RPI.            Secondary Heat Sink; 2.2.26      ..(KAs)                                  IPEOP Background Document Bank Higher                      New 014000K502      ..(KAs)    Higher E05EK22     ..(KAs)
Page 111


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 112 ANSWER: 022 C
ANSWER: 022 C              ANSWER: 055 C                  ANSWER: 088 C


==REFERENCE:==
==REFERENCE:==
12/11/2000 KNPP Exam.
Modified Higher 2.3.2..(KAs)
ANSWER: 055 C


==REFERENCE:==
==REFERENCE:==
Fire Protection Program Plan, Appendix D; E-0-06, Fire in Alternate Fire Zone; E-FP-08, EOP - Fire.
New Memory 016000K401..(KAs)
ANSWER: 088 C


==REFERENCE:==
==REFERENCE:==
 
Tech Spec and Bases; A-EDC-38, Abnormal DC Supply and Distribution System; SD 38, "DC and Emergency AC Distribution; LP RO2-03-LP 038, DC and Emergency AC Distribution New Memory 000058 2.2.22..(KAs)
12/11/2000 KNPP Exam.      Fire Protection Program        Tech Spec and Bases; Plan, Appendix D;              A-EDC-38, Abnormal DC Modified                    E-0-06, Fire in Alternate Fire Supply and Distribution Higher                      Zone;                          System; 2.3.2      ..(KAs)        E-FP-08, EOP - Fire.          SD 38, "DC and Emergency AC Distribution; New                            LP RO2-03-LP 038, DC and Memory                        Emergency AC Distribution 016000K401      ..(KAs)
ANSWER: 023 B
New Memory 000058 2.2.22       ..(KAs)
ANSWER: 023 B              ANSWER: 056 C                  ANSWER: 089 B


==REFERENCE:==
==REFERENCE:==
FR-S.1, Response to a Nuclear Power Generation/ATWS; E-0, Reactor Trip or Safety Injection.
New Higher 2.4.1..(KAs)
ANSWER: 056 C


==REFERENCE:==
==REFERENCE:==
FR-Z.1, Response to High Ctnmt Pressure, Step 3, pgs 3-4; CS Integrated Logic Diag E-1604; System Integrated Logic Diagram ICS E-2012.
Bank Memory 026000A301..(KAs)
ANSWER: 089 B


==REFERENCE:==
==REFERENCE:==
 
10CFR20, definitions and part 1204; SD 32B, Gaseous Radioactive Waste Disposal; New Higher 000060K102..(KAs)
FR-S.1, Response to a      FR-Z.1, Response to High      10CFR20, definitions and part Nuclear Power              Ctnmt Pressure, Step 3, pgs    1204; Generation/ATWS;            3-4;                          SD 32B, Gaseous Radioactive E-0, Reactor Trip or Safety CS Integrated Logic Diag      Waste Disposal; Injection.                  E-1604; System Integrated Logic        New New                         Diagram ICS E-2012.            Higher Higher                                                     000060K102       ..(KAs) 2.4.1      ..(KAs)        Bank Memory 026000A301      ..(KAs)
ANSWER: 024 B
ANSWER: 024 B               ANSWER: 057 A                  ANSWER: 090 A


==REFERENCE:==
==REFERENCE:==
Byron Exam 10/20/2000; ECA-0.0, LOSS OF ALL AC POWER and Background Document.
New Higher 2.4.7..(KAs)
ANSWER: 057 A


==REFERENCE:==
==REFERENCE:==
A-RM-45, Abnormal Radiation Monitoring System.
New Memory 029000A102..(KAs)
ANSWER: 090 A


==REFERENCE:==
==REFERENCE:==
 
ARP 47033-35, TLA-15, RMS ABOVE NORMAL; New Memory 000061AK30..(KAs)
Byron Exam 10/20/2000;      A-RM-45, Abnormal              ARP 47033-35, TLA-15, RMS ECA-0.0, LOSS OF ALL AC    Radiation Monitoring          ABOVE NORMAL; POWER and Background        System.
Document.                                                  New New                            Memory New                         Memory                         000061AK30       ..(KAs)
Higher                      029000A102      ..(KAs) 2.4.7      ..(KAs)
Page 112


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 113 ANSWER: 025 C
ANSWER: 025 C             ANSWER: 058 D          ANSWER: 091 A


==REFERENCE:==
==REFERENCE:==
FR-C.2, Response to Degraded Core Cooling.
Bank Memory E11EK32..(KAs)
ANSWER: 058 D


==REFERENCE:==
==REFERENCE:==
Byron Exam 06/29/2000.
Bank Memory 103000A101..(KAs)
ANSWER: 091 A


==REFERENCE:==
==REFERENCE:==
 
FR-Z.3, Response to High Containment Radiation Level; BKG FR-Z.3,Response to High Containment Radiation Level; IPEOP Background Document; KNPP NRC Exam 12/11/2000 Modified Higher E16EK33..(KAs)
FR-C.2, Response to        Byron Exam 06/29/2000. FR-Z.3, Response to High Degraded Core Cooling.                            Containment Radiation Level; Bank                    BKG FR-Z.3,Response to Bank                      Memory                  High Containment Radiation Memory                    103000A101    ..(KAs) Level; E11EK32    ..(KAs)                              IPEOP Background Document; KNPP NRC Exam 12/11/2000 Modified Higher E16EK33     ..(KAs)
ANSWER: 026 B
ANSWER: 026 B              ANSWER: 059 B          ANSWER: 092 B


==REFERENCE:==
==REFERENCE:==
LP RO2-05-LP 049, Rod Control and RPI; SD-49, Section 3.3.2.
New Higher 001000K103..(KAs)
ANSWER: 059 B


==REFERENCE:==
==REFERENCE:==
KNPP Exam 02/24/1997 Modified Memory 033000A203..(KAs)
ANSWER: 092 B


==REFERENCE:==
==REFERENCE:==
 
E-0-06, Fire in Alternate Fire Zone; Byron Exam 06/29/2000 New Higher 000067A217..(KAs)
LP RO2-05-LP 049, Rod      KNPP Exam 02/24/1997    E-0-06, Fire in Alternate Fire Control and RPI;                                  Zone; SD-49, Section 3.3.2.      Modified                Byron Exam 06/29/2000 Memory New                        033000A203    ..(KAs) New Higher                                             Higher 001000K103      ..(KAs)                          000067A217       ..(KAs)
ANSWER: 027 B
ANSWER: 027 B             ANSWER: 060 B          ANSWER: 093 C


==REFERENCE:==
==REFERENCE:==
RO2-05-LP 049, Rod Control and RPI, pg 43 and 44; ARP 47043-R, Rod Control System Abnormal New Memory 001000K611..(KAs)
ANSWER: 060 B


==REFERENCE:==
==REFERENCE:==
Beaver Valley 2 Exam 03/17/1997; Modified Higher 035000A301..(KAs)
ANSWER: 093 C


==REFERENCE:==
==REFERENCE:==
 
LO R02-04-LP056.007; Tech Spec 3.6.b.3.B, Containment System New Memory 000069 2.2.23..(KAs)
RO2-05-LP 049, Rod        Beaver Valley 2 Exam    LO R02-04-LP056.007; Control and RPI, pg 43 and 03/17/1997;            Tech Spec 3.6.b.3.B, 44;                                                Containment System ARP 47043-R, Rod Control  Modified System Abnormal            Higher                  New 035000A301    ..(KAs) Memory New                                                000069 2.2.23         ..(KAs)
Memory 001000K611      ..(KAs)
Page 113


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 114 ANSWER: 028 D
ANSWER: 028 D           ANSWER: 061 C            ANSWER: 094 C


==REFERENCE:==
==REFERENCE:==
KNPP SD 55, ESF Bank Memory 013000K403..(KAs)
ANSWER: 061 C


==REFERENCE:==
==REFERENCE:==
KNPP SD 05B, AFW System; ARP 47062-N Bank Higher 039000A404..(KAs)
ANSWER: 094 C


==REFERENCE:==
==REFERENCE:==
 
FR-C.3, Response to Saturated Core Cooling; New Higher E07EK13..(KAs)
KNPP SD 55, ESF        KNPP SD 05B, AFW          FR-C.3, Response to System;                  Saturated Core Cooling; Bank                    ARP 47062-N Memory                                            New 013000K403    ..(KAs) Bank                      Higher Higher                    E07EK13         ..(KAs) 039000A404    ..(KAs)
ANSWER: 029 A
ANSWER: 029 A          ANSWER: 062 C            ANSWER: 095 A


==REFERENCE:==
==REFERENCE:==
LP RO2-05-035, CVCS; SD 35, CVCS.
New Higher 004000K305..(KAs)
ANSWER: 062 C


==REFERENCE:==
==REFERENCE:==
KNPP 12/11/00 NRC Exam; SD 09, Air Removal System Bank Higher 055000K106..(KAs)
ANSWER: 095 A


==REFERENCE:==
==REFERENCE:==
 
A-RC-36A, High Reactor Coolant Activity; KNPP NRC Exam 12/18/1997 Bank Higher 000076K305..(KAs)
LP RO2-05-035, CVCS;    KNPP 12/11/00 NRC Exam;  A-RC-36A, High Reactor SD 35, CVCS.            SD 09, Air Removal System Coolant Activity; KNPP NRC Exam 12/18/1997 New                    Bank Higher                  Higher                    Bank 004000K305    ..(KAs) 055000K106    ..(KAs)  Higher 000076K305       ..(KAs)
ANSWER: 030 A
ANSWER: 030 A           ANSWER: 063 A            ANSWER: 096 B


==REFERENCE:==
==REFERENCE:==
LP RO2-05-048, NIS; SD 48, NIS; 11/13/1990 Millstone 3 Exam.
Bank Higher 015000K603..(KAs)
ANSWER: 063 A


==REFERENCE:==
==REFERENCE:==
A-RM-45, Abnormal Radiation Monitoring System; LP Obj RO2-01-LP045.004; Dwg XK-100-131; FD Waste Disposal System.
New Memory 068000A204..(KAs)
ANSWER: 096 B


==REFERENCE:==
==REFERENCE:==
 
SD 23, ICS System; Dwg A-204, A-210, OPERXK-100-18; Dwg OPERM-217; New Memory 026000 2.4.34..(KAs)
LP RO2-05-048, NIS;    A-RM-45, Abnormal        SD 23, ICS System; SD 48, NIS;            Radiation Monitoring      Dwg A-204, A-210, 11/13/1990 Millstone 3  System;                  OPERXK-100-18; Exam.                  LP Obj RO2-01-LP045.004;  Dwg OPERM-217; Dwg XK-100-131; Bank                    FD Waste Disposal System. New Higher                                            Memory 015000K603    ..(KAs) New                      026000 2.4.34       ..(KAs)
Memory 068000A204    ..(KAs)
Page 114


REACTOR OPERATOR  
REACTOR OPERATOR  


==REFERENCES:==
==REFERENCES:==
 
Page 115 ANSWER: 031 D
ANSWER: 031 D             ANSWER: 064 D            ANSWER: 097 C


==REFERENCE:==
==REFERENCE:==
SD 50, Incore Instrumentation; Inadequate Core Cooling Monitor, Sect. 1.4, CET Operation, and 3.4.3, CET Instrumentation.
New Memory 017000A401..(KAs)
ANSWER: 064 D


==REFERENCE:==
==REFERENCE:==
 
SD RHR pg 16; Dwgs OPERXK-100-18, -19.
SD 50, Incore           
New Memory 005000K101..(KAs)
ANSWER: 097 C


==REFERENCE:==
==REFERENCE:==
SD 18, Reactor Building Instrumentation;          SD RHR pg 16;            Ventilation; Inadequate Core Cooling  Dwgs OPERXK-100-18, -19. ARP 47051-B, Containment Monitor, Sect. 1.4, CET                            Vent High Radiation Disabled; Operation, and 3.4.3, CET New                      N-RBV-18B, Reactor Bldg Instrumentation.          Memory                  Vent System Cold Operation 005000K101    ..(KAs)  and Releases New                                               New Memory                                            Higher 017000A401      ..(KAs)                          029000 2.3.9           ..(KAs)
SD 18, Reactor Building Ventilation; ARP 47051-B, Containment Vent High Radiation Disabled; N-RBV-18B, Reactor Bldg Vent System Cold Operation and Releases New Higher 029000 2.3.9..(KAs)
ANSWER: 032 C            ANSWER: 065 A            ANSWER: 098 C
ANSWER: 032 C


==REFERENCE:==
==REFERENCE:==
SD 18, RBV; Hydrogen Control; LP RO2-04-LP 18, RBV System.
New Higher 022000A301..(KAs)
ANSWER: 065 A


==REFERENCE:==
==REFERENCE:==
N-RBV-18C, POST-LOCA Hydrogen Control.
New Memory 028000K502..(KAs)
ANSWER: 098 C


==REFERENCE:==
==REFERENCE:==
 
KNPP Exam 12/18/97; Reactor Data Manual Bank Higher 000040 2.2.34..(KAs)
SD 18, RBV;              N-RBV-18C, POST-LOCA    KNPP Exam 12/18/97; Hydrogen Control;        Hydrogen Control.        Reactor Data Manual LP RO2-04-LP 18, RBV System.                  New                      Bank New                      Memory                  Higher Higher                    028000K502    ..(KAs)  000040 2.2.34           ..(KAs) 022000A301 ..(KAs)
ANSWER: 033 D
ANSWER: 033 D             ANSWER: 066 B            ANSWER: 099 B


==REFERENCE:==
==REFERENCE:==
SD 2, Service Water; KNPP EQB.
Bank Higher 076000K307..(KAs)
ANSWER: 066 B


==REFERENCE:==
==REFERENCE:==
E-RH-53A, "Dropped or Damaged FA,8/17/2001; SD Rad Mon, pgs 12-13; SD FH, pgs 13,16, 28.
New Higher 034000A201..(KAs)
ANSWER: 099 B


==REFERENCE:==
==REFERENCE:==
 
N-CRD-49B, Reactor Startup; N-CRD-49C, Reactor Shutdown; New Higher 2.2.1..(KAs)
SD 2, Service Water;      E-RH-53A, "Dropped or    N-CRD-49B, Reactor Startup; KNPP EQB.                Damaged FA,8/17/2001;    N-CRD-49C, Reactor SD Rad Mon, pgs 12-13;  Shutdown; Bank                      SD FH, pgs 13,16, 28.
Higher                    New                     New 076000K307      ..(KAs)  Higher                   Higher 034000A201 ..(KAs)      2.2.1       ..(KAs)
ANSWER: 100 D
ANSWER: 100 D


==REFERENCE:==
==REFERENCE:==
KNPP Exam 12/11/2000; SD 18, Reactor Building Vent Bank Higher 2.1.32..(KAs)


KNPP Exam 12/11/2000; SD 18, Reactor Building Vent Bank Higher 2.1.32        ..(KAs)
Page 116 A N S W E R K E Y MULTIPLE CHOICE 001 c 002 b 003 a 004 d 005 b 006 c 007 d 008 d 009 a 010 b 011 b 012 a 013 a 014 a 015 a 016 b 017 d 018 b 019 c 020 a 021 c 022 c 023 b 024 b 025 c 026 b 027 b 028 d 029 a 030 a 031 d 032 c 033 d 034 d 035 a 036 a 037 a 038 a 039 c 040 c 041 c 042 a 043 d 044 b 045 a 046 a 047 a 048 d 049 c 050 d 051 c 052 c 053 d 054 c 055 c 056 c 057 a 058 d 059 b 060 b 061 c 062 c 063 a 064 d 065 a 066 b 067 c 068 c 069 b 070 c 071 b 072 c 073 c 074 c 075 a 076 a 077 a 078 b 079 b 080 b 081 c 082 a 083 c 084 a 085 b 086 d 087 c 088 c 089 b 090 a 091 a 092 b 093 c 094 c 095 a 096 b 097 c 098 c 099 b 100 d}}
Page 115
 
ANSWER KEY MULTIPLE CHOICE 001 c 021 c  041 c          061 c 081 c 002 b 022 c  042 a          062 c 082 a 003 a 023 b 043 d         063 a 083 c 004 d 024 b 044 b         064 d 084 a 005 b 025 c 045 a         065 a 085 b 006 c 026 b 046 a          066 b 086 d 007 d 027 b 047 a          067 c 087 c 008 d 028 d 048 d          068 c 088 c 009 a 029 a 049 c          069 b 089 b 010 b 030 a 050 d         070 c 090 a 011 b 031 d  051 c          071 b 091 a 012 a 032 c 052 c         072 c 092 b 013 a 033 d 053 d         073 c 093 c 014 a 034 d 054 c         074 c 094 c 015 a 035 a 055 c         075 a 095 a 016 b 036 a 056 c         076 a 096 b 017 d 037 a 057 a         077 a 097 c 018 b 038 a  058 d          078 b 098 c 019 c 039 c  059 b          079 b 099 b 020 a 040 c  060 b          080 b 100 d Page 116}}

Latest revision as of 04:31, 16 January 2025

Initial RO Examination 02/05/2004
ML040690107
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 02/05/2004
From:
NRC/RGN-III
To:
Nuclear Management Co
References
50-305/OL04-301
Download: ML040690107 (116)
v • d • e


Text

U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: MASTER RO Date: February 05, 2004 Facility/Unit: KEWAUNEE / U1 Region:

III Reactor Type: Westinghouse Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results Examination Value 98.0 Points Applicants Score

__________ Points Applicants Grade

__________ Percent NRC Official Use Only

APPENDIX E POLICIES AND GUIDELINES FOR TAKING NRC EXAMINATIONS Each examinee shall be briefed on the policies and guidelines applicable to the examination category (written and/or operating test) being administered. The applicants may be briefed individually or as a group. Facility licensees are encouraged to distribute a copy of this appendix to every examinee before the examinations begin. All items apply to both initial and requalification examinations, except as noted.

PART A - GENERAL GUIDELINES 1.

[Read Verbatim] Cheating on any part of the examination will result in a denial of your application and/or action against your license.

2.

If you have any questions concerning the administration of any part of the examination, do not hesitate asking them before starting that part of the test.

3.

SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e., shift supervisor, senior shift supervisor, or whatever the title of the position may be).

4.

You must pass every part of the examination to receive a license 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.

6.

Mark your answers on the answer sheet provided and do not leave any question blank.

Use only the paper provided and do not write on the back side of the pages. 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.

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 examination questions, examination aids, answer sheets, and scrap paper 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. The scrap paper will be disposed of immediately after 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?

REACTOR OPERATOR 001 a b c d ___

002 a b c d ___

003 a b c d ___

004 a b c d ___

005 a b c d ___

006 a b c d ___

007 a b c d ___

008 a b c d ___

009 a b c d ___

010 a b c d ___

011 a b c d ___

012 a b c d ___

013 a b c d ___

014 a b c d ___

015 a b c d ___

016 a b c d ___

017 a b c d ___

018 a b c d ___

019 a b c d ___

020 a b c d ___

021 a b c d ___

022 a b c d ___

023 a b c d ___

024 a b c d ___

025 a b c d ___

026 a b c d ___

027 a b c d ___

028 a b c d ___

029 a b c d ___

030 a b c d ___

031 a b c d ___

032 a b c d ___

033 a b c d ___

034 a b c d ___

035 a b c d ___

036 a b c d ___

037 a b c d ___

038 a b c d ___

039 a b c d ___

040 a b c d ___

041 a b c d ___

042 a b c d ___

043 a b c d ___

044 a b c d ___

045 a b c d ___

046 a b c d ___

047 a b c d ___

048 a b c d ___

049 a b c d ___

050 a b c d ___

051 a b c d ___

052 a b c d ___

053 a b c d ___

054 a b c d ___

055 a b c d ___

056 a b c d ___

057 a b c d ___

058 a b c d ___

059 a b c d ___

060 a b c d ___

061 a b c d ___

062 a b c d ___

063 a b c d ___

064 a b c d ___

065 a b c d ___

066 a b c d ___

067 a b c d ___

068 a b c d ___

069 a b c d ___

070 a b c d ___

071 a b c d ___

072 a b c d ___

073 a b c d ___

074 a b c d ___

075 a b c d ___

076 a b c d ___

077 a b c d ___

078 a b c d ___

079 a b c d ___

080 a b c d ___

081 a b c d ___

082 a b c d ___

083 a b c d ___

084 a b c d ___

085 a b c d ___

086 a b c d ___

087 a b c d ___

088 a b c d ___

089 a b c d ___

090 a b c d ___

091 a b c d ___

092 a b c d ___

093 a b c d ___

094 a b c d ___

095 a b c d ___

096 a b c d ___

097 a b c d ___

098 a b c d ___

099 a b c d ___

100 a b c d ___

REACTOR OPERATOR Page 5 QUESTION: 001 (1.00)

All AC power has been lost and equipment is being placed in PULLOUT per ECA-0.0, LOSS OF ALL AC POWER. Which pump will be kept available, and why?

a.

One RHR pump, to provide RCS inventory makeup.

b.

One SI pump, to provide RCS inventory makeup.

c.

One service water pump, to provide Diesel Generator cooling.

d.

One charging pump, to provide RCP seal cooling.

REACTOR OPERATOR Page 6 QUESTION: 002 (1.00)

The controller output which automatically positions the Main Feedwater Regulating Valves (FW-7A & B) to maintain programmed level uses steam generator narrow range water level AND which of the following?

a.

The setpoint established by the operator on the control station b.

Steam flow and feedwater flow c.

Steam flow, feedwater flow and Turbine impulse pressure d.

Turbine impulse pressure

REACTOR OPERATOR Page 7 QUESTION: 003 (1.00)

Containment temperature has increased from 100°F to 160°F due to a containment cooling malfunction. If the plant is stable at 100% power and there are negligible RCS or containment pressure changes, which one of the following describes the effect of the increase in containment temperature on the pressurizer level indicated by the pressurizer level control channels?

a.

Indicated level will be HIGHER than actual level because the reference leg fluid density decreases.

b.

Indicated level will be LOWER than actual level because the reference leg fluid density decreases.

c.

Indicated level will be HIGHER than actual level because the elevated containment temperature causes increased flashing in the reference leg.

d.

Indicated level will be LOWER than actual level because of the elevated containment temperature causes increased flashing in the reference leg.

REACTOR OPERATOR Page 8 QUESTION: 004 (1.00)

Both Main Feedwater pumps are running when the "A" Main Feedwater pump trips. Which one of the following conditions prevents the start AND continued operation of the "A" Main Feedwater pump?

a.

Lube oil pressure is 10 psig.

b.

Suction pressure is 210 psig.

c.

Recirculation valve is FULL open.

d.

Only one Condensate pump is running.

REACTOR OPERATOR Page 9 QUESTION: 005 (1.00)

With power to 480 volt Bus 1-43 deenergized, which pressurizer heaters would be affected?

A.

Backup group 1B ONLY B.

Backup groups 1D AND 1E ONLY C.

Backup Group 1A ONLY with transfer switch in Normal D.

Backup group 1A with transfer switch in Alternate AND control group 1C ONLY

REACTOR OPERATOR Page 10 QUESTION: 006 (1.00)

Given the following:

Station and Instrument Air System is in a normal/automatic system lineup.

The station air compressor preferred selector switch is aligned to Compressor G.

Which of the following automatically occur when the Station and Instrument Air System air header pressure is decreasing and reaches 95 psig?

a.

Air dryers are bypassed AND Station air compressor F starts.

b.

Station air compressor F starts AND SA-400, (SA Header B Supply Valve) is fully closed.

c.

SA-200, (SA Header A Supply Valve) AND SA-400, (SA Header B Supply Valve) start to close.

d.

Instrument air compressor C starts and isolates from station air header AND SA-200, (SA Header A Supply Valve) is fully closed.

REACTOR OPERATOR Page 11 QUESTION: 007 (1.00)

With the plant initially at 100% power, steady-state, which one of the following describes an effect of power range channel N-42 upper detector failing HIGH?

a.

Reactor trips on high flux.

b.

Main feed regulating valves fully open.

c.

Control rods step out to high bank rod stop.

d.

Over-temperature DT setpoint for one channel decreases.

REACTOR OPERATOR Page 12 QUESTION: 008 (1.00)

The unit is at 100% power with Instrument air pressure at 115 psig. Station Air Compressor F is tagged out for preventive maintenance. What will instrument air pressure do when Station Air Compressor G is tripped.

a.

decrease, then increase to a value above its previous pressure.

b.

remain unaffected.

c.

slowly decrease to a point where the unit will have to be tripped.

d.

decrease, then increase to a value below its previous pressure.

REACTOR OPERATOR Page 13 QUESTION: 009 (1.00)

The following plant conditions exist:

Reactor is Critical at 10-3 percent power RCS Tavg is 547°F and steady Pressurizer pressure is 2235 psig and steady Control Bank D position is 100 steps ONE Control Bank D rod drops Describe the INITIAL response of Tavg and Pressurizer pressure (PZR Press):

Tavg PZR Press a.

Remain the same Remain the same b.

Increase Remain the same c.

Remain the same Increase d.

Decrease Decrease

REACTOR OPERATOR Page 14 QUESTION: 010 (1.00)

The following conditions exist:

90% Reactor power.

Pressurizer Pressure control is in automatic Backup heaters are in "AUTO".

Actual Pressurizer Pressure is 2235 psig.

The Pressurizer Pressure Master Controller malfunctions and its SETPOINT drifts to 2100 psig over a 10 minute period. Which of the following describes the INITIAL automatic response of the Pressurizer Pressure Control System as this failure occurs?

a.

Spray valves throttle closed and variable heaters go to maximum current.

b.

Spray valves throttle open and variable heaters go to minimum current.

c.

Pressurizer PORVs PR-2A and PR-2B open, Spray valves throttle open, and Group C heaters go to minimum current.

d.

Spray valves throttle closed, pressurizer backup heater groups go to maximum current, and backup heaters come "ON."

REACTOR OPERATOR Page 15 QUESTION: 011 (1.00)

Which of the following electrical interlocks prevents release of radioactive water to the RWST during transfer to Containment Sump Recirculation during a LOCA?

a.

Close SI-300A/B, RWST Supply Valve to an RHR pump, before opening SI-350A/B, Containment Sump B Isolation Valve to an RHR pump.

b.

Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening SI-350A/B and 351A/B, Containment Sump B Isolation Valves to an RHR pump.

c.

Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.

d.

Open SI-350A/B and 351A/B, Containment Sump B Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.

REACTOR OPERATOR Page 16 QUESTION: 012 (1.00)

Given the following conditions:

Component Cooling Pump "A" is running Component Cooling Pump "B" is in standby D/G "B" is out of service for maintenance A safety Injection signal is generated. Which one of the following describes the response of the Component Cooling Water Pumps?

Pump A Pump B a.

Runs continuously Sequences on b.

Stops then sequences on Remains off c.

Runs continuously Remains off d.

Stops then sequences on Sequences on

REACTOR OPERATOR Page 17 QUESTION: 013 (1.00)

Given the following conditions:

The plant is operating at 18% power The high pressure piping to RCS flow instrument FT-411 on Loop A breaks What is the status of Loop A RCS flow indicators and what is the resulting plant condition (assume NO operator action is taken)?

a.

All Loop A flow indicators will read low, and the reactor will trip on RCS loop low flow.

b.

All Loop A flow indicators will read low, and the reactor will trip on low PRZR pressure.

c.

Only FI-411 RCS flow indication will read low, and no reactor trip is generated.

d.

Only FI-411 RCS flow indication will read low, and the reactor will trip on low PRZR pressure.

REACTOR OPERATOR Page 18 QUESTION: 014 (1.00)

Given the following conditions:

The plant is at 15% power S/G B level channel LT-473 is removed from service per A-MI-87 If S/G B level channel LT-471 fails high, what would be the status of feed for the S/Gs?

a.

Both S/Gs are being fed from the motor-driven AFW Pumps only.

b.

Both S/Gs are being fed from the turbine-driven AFW Pump only.

c.

S/G A is being fed from the motor-driven AFW Pump. S/G B has no feed flow.

d.

Feed to S/G A remains normal. Feed to S/G B lowers due to throttling close of FW-7B, S/G B Main Feed valve.

REACTOR OPERATOR Page 19 QUESTION: 015 (1.00)

Which one of the following describes the operation of LD-13, Letdown Line Pressure Relief Valve?

a.

Relieves at 200 psig to the VCT b.

Relieves at 150 psig to the PRT c.

Relieves at 150 psig to the VCT d.

Relieves at 200 psig to the PRT.

REACTOR OPERATOR Page 20 QUESTION: 016 (1.00)

The plant is in Hot shutdown, with the following conditions:

Tave = 547°F with both RXCPs operating A Main Feedwater Pump is running Steam Generator A Narrow Range Level = 20%

Steam Generator B Narrow Range Level = 15%

Condensate Pump A is Hold Carded in Pullout.

Condensate Pump B is running All three Auxiliary Feedwater Pumps are in Off and in Pullout All the support conditions for the Auxiliary Feedwater Pumps are met At the direction of the CRS, the BOP places all three Auxiliary Feedwater Pump control switches into the AUTO position.

Without further operator actions, what is the status of the Auxiliary Feedwater Pumps?

MDAFW Pumps TDAFW a.

Running Running b.

Running Off c.

Off Running d.

Off Off

REACTOR OPERATOR Page 21 QUESTION: 017 (1.00)

SP-54-086, "Turbine Stop and Governor Valve Operability," directs depressing the CLOSE SV-1 pushbutton. Which of the following statements identifies an expected response of the turbine control valves (CV-1 through CV-4) and turbine stop valve (SV-1) to this action?

a.

SV-1 closes, then CV-1 and CV-3 close.

b.

SV-1 closes, then CV-1 and CV-2 close.

c.

CV-1 and CV-2 close, then SV-1 closes.

d.

CV-1 and CV-3 close, then SV-1 closes.

REACTOR OPERATOR Page 22 QUESTION: 018 (1.00)

The following conditions exist:

A LOCA has occurred.

The crew is trying to reduce ECCS flow.

All equipment is operating properly.

Wide Range RCS pressure is 800 psig.

65°F of subcooling is required to stop one of the ECCS pumps.

What is the MAXIMUM Core Exit Thermocouple temperature at which the pump is stopped?

a.

430°F.

b.

455°F.

c.

480°F.

d.

505°F.

REACTOR OPERATOR Page 23 QUESTION: 019 (1.00)

Given the following:

The reactor is critical at 1% power.

SI Accumulator A water volume was just found to be 1270 cubic ft (48%).

SI Accumulator B water volume was found to be 1220 cubic ft (20%) at the same time.

What action is required due to these conditions, if any?

a.

No action is needed due to these conditions.

b.

SI Accumulator A water volume must be restored to limits.

c.

SI Accumulator B water volume must be restored to limits.

d.

Action must be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to go to HOT SHUTDOWN.

REACTOR OPERATOR Page 24 QUESTION: 020 (1.00)

Given the following conditions:

Reactor Vessel Head AND Upper Internals have been removed.

Residual Heat Removal boron concentration is 2458 ppm.

The reactor has been shutdown for 7 days.

Spent Fuel Pool Pump "A" is operating per N-SFP-21, Spent Fuel Pool Cooling and Cleanup System. Spent Fuel Pool Pump "B" is inoperable.

Residual Heat Removal Pump "A" is operating. Residual Heat Removal Pump "B" is inoperable.

Refueling Cavity level is greater than 23 feet above the vessel flange.

Based on the plant status given, determine what condition must be resolved to meet requirements for a fuel shuffle within the reactor that is NOT a full core offload.

a.

Residual Heat Removal boron concentration is too low.

b.

Spent Fuel Pool Cooling Pump "B" is required to be operable.

c.

The reactor has not been shutdown long enough.

d.

Residual Heat Removal Pump "B" is required to be operable.

REACTOR OPERATOR Page 25 QUESTION: 021 (1.00)

Which of the following is the purpose of NAD-02.07, Kewaunee Refueling Operations?

a.

Provides step-by-step instructions to be used by fuel handlers during core offload.

b.

Provides administrative instructions for reactor engineers to follow when developing the fuel shuffle sequence to prevent inadvertent criticality during core reload.

c.

Describes the organization and responsibilities for reactor vessel disassembly, reassembly, and fuel handling operations.

d.

Provides step-by-step instructions on completing a Fuel Assembly Handling Deviation Report.

REACTOR OPERATOR Page 26 QUESTION: 022 (1.00)

A point source in containment is reading 300 mRem/hr at a distance of two (2) feet. Two options are available to complete a mandatory work assignment near this radiation source:

Option 1 - ONE operator can perform the assignment in fifty (50) minutes working at a distance of three (3) feet from the source.

Option 2 - THREE operators, using special extension tooling, can perform the assignment in sixty (60) minutes at a distance of six (6) feet from the source Which is the preferred option based on ALARA and the corresponding total exposure?

a.

Option 1, with a total exposure of 0.100 Person-REM b.

Option 1, with a total exposure of 0.111 Person-REM c.

Option 2, with a total exposure of 0.100 Person-REM d.

Option 2, with a total exposure of 0.111 Person-REM

REACTOR OPERATOR Page 27 QUESTION: 023 (1.00)

Which of the following is listed in E-0, "Reactor Trip or Safety Injection," step 1 CONTINGENCY ACTIONS but is NOT in FR-S.1, "Response to a Nuclear Power Generation/ATWS," step 1 CONTINGENCY ACTIONS?

a.

Source range counts b.

Intermediate range power c.

Reactor Trip Breakers d.

Bypass Breakers

REACTOR OPERATOR Page 28 QUESTION: 024 (1.00)

Which of the following is the basis for maintaining SG Narrow Range levels between 4% and 50% during procedure ECA-0.0, "LOSS OF ALL AC POWER?"

a.

Ensures the capability to cooldown the reactor only after AC power is restored.

b.

Ensures heat transfer capability exists to remove heat from the RCS.

c.

Narrow Range level is the only reliable indication of SG inventory available after a loss of all AC power.

d.

Provides capability to monitor the SGs for a Steam Generator Tube Rupture.

REACTOR OPERATOR Page 29 QUESTION: 025 (1.00)

Which ONE of the following describes the mitigating strategies contained in ECA-1.1, "Loss of Emergency Coolant Recirculation?"

a.

Minimizing the depletion of the RWST, Maximizing Subcooling, determination of minimum containment spray requirements.

b.

Maximizing Subcooling, minimizing the depletion of the RWST, and depressurization of the RCS to minimize break flow.

c.

Minimizing the depletion of the RWST, determination of minimum containment spray requirements, and depressurization of the RCS to minimize break flow.

d.

Maximizing subcooling, determination of minimum containment spray, and depressurization of the RCS to minimize break flow.

REACTOR OPERATOR Page 30 QUESTION: 026 (1.00)

Given the following CRDM coil rod motion sequence:

1. Stationary Gripper Energized at Low Voltage
2. Stationary Gripper Energizes at High Voltage
3. Movable Gripper Energizes
4. Stationary Gripper De-energizes The next step in the sequence is __________ and the rod is being moved ____________

a.

Lift Coil De-energizes, Inward b.

Lift Coil Energizes, Outward c.

Stationary Gripper Energizes at Low Voltage, Inward d.

Stationary Gripper Energizes at High Voltage, Outward

REACTOR OPERATOR Page 31 QUESTION: 027 (1.00)

With the plant in the operating mode, the reactor operator receives ROD CONTROL SYSTEM ABNORMAL annunciator and SER point 1692, "Rod Control System Non-Urgent Failure."

Instrument and Control technicians narrow the problem to the Rod Control Logic Cabinet. What may have caused this condition to occur?

a.

Slave cycler cycles without a GO pulse b.

A redundant power supply has been lost c.

Oscillator fails to generate signals when called for d.

There is a loose printed circuit card in the logic circuitry

REACTOR OPERATOR Page 32 QUESTION: 028 (1.00)

Which of the following conditions results in a Main Steam Isolation?

a.

Containment pressure of 15 psig.

b.

Steamline flow of 4X106 lb/hr AND an "SI" signal.

c.

Steamline flow of 5X106 lb/hr AND Tavg of 530°F.

d.

Steamline flow of 0.8X106 lb/hr, Tavg of 530°F, AND an "SI" signal.

REACTOR OPERATOR Page 33 QUESTION: 029 (1.00)

The unit is at 100% power with Charging pump A operating in automatic. Charging Line Flow Control valve, CVC-7, is throttled to 70%. CVC-7 then fails open. Charging pump As speed will....

a.

NOT change during this event b.

decrease at first, then returns to its initial speed c.

increases at first, then remains above its initial speed d.

decreases at first, then remains below its initial speed

REACTOR OPERATOR Page 34 QUESTION: 030 (1.00)

A plant startup is in progress with power at 8 percent. Intermediate Range drawer N-36 Level Trip switch is in the BYPASS position. What is the plant response to removal of N-36 control power fuses and the reason for the plant response?

a.

A trip will occur because the Level Trip Switch bypass function will be removed.

b.

A trip will not occur because the Level Trip Switch is in the bypass position and the bypass function is not affected at any power level.

c.

A trip will not occur because the Level Trip Switch is in the bypass position and power is less than P-10.

d.

A trip will occur because the Level Trip Switch bypass function is operable only above P-10.

REACTOR OPERATOR Page 35 QUESTION: 031 (1.00)

While operating at 100% power, Graphics Display 4 on PPCS shows the B7 CET temperature to be 592°F.

Which of the following sequence of actions identifies how the operator would display the B7 CET temperature value (Channel 20 on Train B) at the ICCMS panels?

Depress the CET ID/CET TEMP pushbutton to illuminate the...

a.

CET TEMP lamp, then depress the AVG/HOT pushbutton to display the B7 CET temperature.

b.

CET TEMP lamp, then depress the REF1/REF2 pushbutton to display the B7 CET temperature.

c.

CET ID lamp, then depress the REF1/REF2 pushbutton until "B7" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.

d.

CET ID lamp, then depress the AVG/HOT pushbutton until "20" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.

REACTOR OPERATOR Page 36 QUESTION: 032 (1.00)

Given the following conditions:

Four CFCUs were running prior to the event A Safety Injection signal was just received Containment Pressure has increased to 3.5 psig and is currently stable What condition would you expect the CFCUs to be in at this time?

a.

All CFCUs would be running with SW return isolation valves throttled to maintain temperature b.

All CFCUs would be running with CFCU Emergency Discharge dampers open and SW return isolation valves throttled to maintain temperature c.

All CFCUs would be running with SW return isolation valves fully open d.

All CFCUs would be running with CFCU Emergency Discharge dampers and SW return isolation valves fully open

REACTOR OPERATOR Page 37 QUESTION: 033 (1.00)

Given the following conditions:

The plant has tripped and a Safety Injection signal has been generated.

Engineered Safeguard Features Actuation System Train A relays have failed to operate ONLY the Service Water System valves.

Train B relays have operated properly.

At the completion of the SI sequence, what is the status of Service Water flow to Component Cooling Water (CCW) Heat Exchanger A, if NO operator action is taken?

a.

There will be NO Service Water flow through the CCW heat exchanger.

b.

SW flow will be at a set constant value lower than its post-accident expected value.

c.

SW flow through the CCW heat exchanger will be at its post-accident expected value.

d.

SW flow will be lower than its post-accident expected value and controlled by the CCW outlet header temperature.

REACTOR OPERATOR Page 38 QUESTION: 034 (1.00)

Given the following conditions:

The plant is at 55% power and steady.

The "A" Main FW pump is in pullout.

The "B" Main FW pump is running with two condensate pumps.

Annunciator 47062-A, "S/G A Program Level Deviation" is LIT.

All 3 S/G A level indicators are 38% and steady.

Which of the following describes actions to be taken by the operator based on these conditions?

a.

START "A" Main FW pump per N-FW-05B, Feedwater System Normal Operation AND MONITOR "A" S/G level automatic control for proper operation.

b.

REDUCE load to < 50% AND MONITOR "A" S/G level automatic control for proper operation.

c.

Place Feedwater Flow Control Valve FW-7A to MANUAL AND GO to A-MI-87, Bistable Tripping for Failed Reactor Protection or Safeguards Instrumentation.

d.

GO to A-FW-05A, Abnormal Feedwater System Operation, AND DETERMINE if manual feedwater control is required.

REACTOR OPERATOR Page 39 QUESTION: 035 (1.00)

Given the following plant conditions:

The reactor is at 100% power All systems are in a normal lineup Based on these conditions, which one of the following correctly states the power supply to the Reactor Coolant Pumps?

RXCP A RXCP B a.

MAT MAT b.

RAT MAT c.

MAT RAT d.

RAT RAT

REACTOR OPERATOR Page 40 QUESTION: 036 (1.00)

In procedure FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, the step to check if SI can be terminated is based on which of the following parameter(s):

a.

RCS Subcooling ONLY.

b.

RCS Subcooling and RCS Cold Leg Temperatures.

c.

RCS Pressure ONLY.

d.

RCS Pressure and RCS Cold Leg Temperatures.

REACTOR OPERATOR Page 41 QUESTION: 037 (1.00)

ECA-2.1, Uncontrolled Depressurization of Both Steam Generators, has been entered from E-2, Faulted Steam Generator Isolation. Containment pressure is 1.0 psig. Each steam generator is being fed at 100 gpm producing an RCS cooldown rate of 120°F/hr. Steam generator water levels are as follows:

Steam Generator A narrow range levels - 2%

Steam Generator B narrow range levels - 8%

Based on the conditions above, what is the appropriate initial operator action?

a.

Decrease feed flow to each steam generator to 60 gpm.

b.

Decrease feed flow to "A" steam generator ONLY to 60 gpm.

c.

Increase feed flow as required to maintain "A" steam generator narrow range level greater than or equal to 4%.

d.

Control feed flow as required to maintain RCS hot leg temperatures stable or decreasing.

REACTOR OPERATOR Page 42 QUESTION: 038 (1.00)

The following plant conditions exist:

A safety injection has actuated A transition has been made to ES-1.1, SI Termination No charging pump is running CC flow to the RXCP thermal barrier HX has been lost since the SI actuation What action is initially taken associated with RXCP seal cooling and what is the reason for the action?

a.

RXCP seal injection is isolated before starting a charging pump, to avoid taking time to reestablish seal cooling since RXCP seals are already heated up.

b.

A charging pump is started and then CC flow is established to the RXCP thermal barriers, to prevent steam binding of the CC system.

c.

CC flow is established to the RXCP thermal barriers and then a charging pump is started, to prevent RXCP shaft warping.

d.

CC flow is established to the RXCP thermal barriers, to prevent thermal shock to the RXCP seals.

REACTOR OPERATOR Page 43 QUESTION: 039 (1.00)

Given the following plant conditions:

Reactor trip occurred with subsequent loss of RXCPs.

RCS Pressure is 800 psig Operators have implemented ES-0.2, "Natural Circulation Cooldown" to go to Cold Shutdown.

A cooldown rate of 25°F/hour has been established.

RCS depressurization has been initiated PZR level - Unexpected large variations are occurring RVLIS RXCPs OFF Indication - 90%

The Shift Manager has determined that cooldown and depressurization shall proceed as quickly as possible. Which ONE of the following describes the appropriate actions?

a.

Pressurize the RCS to collapse the voids, continue the cooldown and remain in ES-0.2, Natural Circulation Cooldown.

b.

Raise the cooldown rate to collapse the voids and remain in ES-0.2, Natural Circulation Cooldown.

c.

Pressurize the RCS to collapse the voids, continue the cooldown and transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel."

d.

Raise the cooldown rate to collapse the voids and transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel.

REACTOR OPERATOR Page 44 QUESTION: 040 (1.00)

Given the following plant conditions:

- The unit is at 80% power.

- Control Bank D rod K7 is stuck at 220 steps (not the most reactive rod).

- All other Control Bank "D" rods are at 220 steps.

- Tavg = 567°F.

How would the shutdown margin calculation performed prior to the condition discovered above be affected?

a. No effect on shutdown margin.
b. Shutdown margin would be more conservative.
c. Shutdown margin would be less conservative.
d. The effect on shutdown margin can not be determined.

REACTOR OPERATOR Page 45 QUESTION: 041 (1.00)

Which of the following indications will be inaccurate during the performance of ES-0.2, "Natural Circulation Cooldown", with RXCPs secured?

a.

RCS core exit TCs.

b.

RCS wide range hot leg temperature.

c.

RCS T-average indication.

d.

RCS wide range cold leg temperature.

REACTOR OPERATOR Page 46 QUESTION: 042 (1.00)

The following plant conditions exist:

Reactor power is 80%

Rod Control is in MANUAL All other controls are in AUTO An inadvertent Emergency Boration was performed for two minutes. Considering steady-state to steady-state conditions, which of the following parameters will NOT change?

a.

Reactor Power b.

RCS Tavg c.

Przr Level d.

S/G Pressure

REACTOR OPERATOR Page 47 QUESTION: 043 (1.00)

Given the following conditions:

The plant is at 50% power Condensate pump A is in pullout Condensate pump B is running If condenser hot well level subsequently decreases to 10%, which one of the actions below is now required?

a.

Startup condensate pump A per N-CD-03, Condensate System.

b.

Address abnormal condensate conditions per A-CD-03, Condensate System Abnormal Operation.

c.

OPEN MU-3B, Condenser Emergency Make-up valve per N-CD-03, Condensate System.

d.

Respond to the reactor trip per E-0, Reactor Trip or Safety Injection

REACTOR OPERATOR Page 48 QUESTION: 044 (1.00)

Due to decreasing condenser vacuum, the operator performs the actions of E-AR-09, Loss of Condenser Vacuum. At one point, condenser pressure increases to 5 inches Hg absolute, and the operator must locally place the hogging jet in service.

In addition to opening MS-400, Steam Supply to Hogging Jet, and throttling MS-401, Steam to Hogging Jet, to maintain between 105-115 psig on PI-11323, four additional valves, listed below, must be aligned to place the hogging jet in service:

AR-302, Gland Steam Cdsr Exhaust to Outside AR-305, Gland Steam Cdsr Exhaust to Vent AR-100, Hogging Jet Air Inlet AR-2A, First Stage Ejector Inlet Which of the following is the correct valve alignment?

AR-302 AR-305 AR-100 AR-2A a.

CLOSED OPEN CLOSED OPEN b.

OPEN CLOSED OPEN CLOSED c.

CLOSED OPEN OPEN CLOSED d.

OPEN CLOSED CLOSED OPEN

REACTOR OPERATOR Page 49 QUESTION: 045 (1.00)

The Gaseous Radioactive Waste System (WG) vent header pressure has just increased to 2 psig. Per A-GWP-32B, the AUTOMATIC ACTIONS the operator must now verify are:

a.

The start of the Waste Gas Compressors.

b.

The closure of Gas Decay Tank inlet isolation valves for the tank selected for fill.

c.

The closure of Gas Decay Tanks to Holdup Tanks valve.

d.

The opening of Gas Decay Tank inlet isolation valve for the tank selected for standby.

REACTOR OPERATOR Page 50 QUESTION: 046 (1.00)

The contents of a Gas Decay Tank is being released in accordance with the appropriate administrative controls when Gas Decay Tanks to Plant Vent, WG-36/CV-31215, closed.

Which of the following monitors could have caused this to occur?

a.

BOTH R-13 and R-14 (Aux Building Vent Monitors) b.

BOTH Aux. Area Monitors 03-06 and 03-08 (Beta Air Monitors Aux. Building) c.

ONLY R-13 (Aux Building Vent Monitor) d.

ONLY R-14 (Aux Building Vent Monitor)

REACTOR OPERATOR Page 51 QUESTION: 047 (1.00)

Which of the following describes the detector types used in Area Radiation Monitors at Kewaunee?

a.

ONLY GM tubes and ion chambers b.

ONLY ion chambers c.

ONLY GM tubes d.

Ion chambers, GM tubes AND scintillation detectors

REACTOR OPERATOR Page 52 QUESTION: 048 (1.00)

Procedure A-RM-45, Abnormal Radiation Monitoring, requires the operator to determine if Post Accident Recirc must be started due to a failure of R-23, Control Room Vent Monitor, by monitoring specific process and area monitors for increasing radiation levels.

Besides R-1, Control Room Area Monitor, what additional AREA Radiation monitor(s), if any, must be monitored and Post Accident Recirc manually started on increasing levels of radiation?

a.

BOTH R-10, New Fuel Pit Area Monitor AND R-5, Fuel Handling Area Monitor.

b.

NO additional Area Radiation Monitors.

c.

ONLY R-10, New Fuel Pit Area Monitor.

d.

ONLY R-5, Fuel Handling Area Monitor.

REACTOR OPERATOR Page 53 QUESTION: 049 (1.00)

ES-0.2, Natural Circulation Cooldown, is being implemented. The following conditions exist:

RCS cold leg Temp is at 380°F.

RCS Pressure is at 1450 psig.

All CRDM fans are off and CANNOT be started.

18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> waiting period has begun.

What is the basis for the 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> waiting period?

a.

Prevent damage to the CRDM coils due to overheating.

b.

Ensure heat is being removed from the Steam Generator to prevent void formation in the U-tubes.

c.

Minimize void formations in the Reactor Vessel head during subsequent RCS depressurization to place RHR in service.

d.

Allow sufficient flow to the upper head region to make the upper head fluid temperature equal to the cold leg fluid temperature.

REACTOR OPERATOR Page 54 QUESTION: 050 (1.00)

The following plant conditions exist:

PZR pressure control channel selector switch is in the 4-3 position PZR pressure yellow channel (PT-449 IV) has just failed low What is the effect of these conditions on the RCS?

a.

All PZR heaters will come ON; PZR PORVs PR-2A and PR-2B would not be available to open on a subsequent high RCS pressure condition.

b.

PZR heaters are unaffected; ONLY PZR PORV PR-2A would not be available to open on a subsequent high RCS pressure condition.

c.

All PZR heaters will come ON; PZR PORV PR-2A would not be available to open on a subsequent high RCS pressure condition.

d.

PZR heaters are unaffected; PZR PORVs PR-2A and PR-2B would not be available to open on a subsequent high RCS pressure condition.

REACTOR OPERATOR Page 55 QUESTION: 051 (1.00)

Following an ATWS and an SI actuation from 100% power, the Reactor Trip Breakers remain closed. What effect will this have on the plant?

a.

Automatic Turbine Trip will not occur.

b.

Automatic steam line isolation will be blocked.

c.

Automatic SI re-actuation CANNOT be blocked.

d.

Feedwater isolation due to SI actuation will be blocked.

REACTOR OPERATOR Page 56 QUESTION: 052 (1.00)

Which of the following parameters is monitored to determine the need to minimize DC loads while performing ECA-0.0, LOSS OF ALL AC POWER?

a.

Battery amps b.

Battery amp-hours c.

Battery volts d.

Battery specific gravity

REACTOR OPERATOR Page 57 QUESTION: 053 (1.00)

Given the following:

The unit is stable at 15% power.

A failure of Instrument Bus I, BRA-113, occurs.

All systems and control loops are in their NORMAL position.

Which of the following action(s) are required, if any, to restore pressurizer (PRZR) pressure and level conditions resulting from this failure?

a.

Place PRZR spray valves in MANUAL, Position PRZR Pressure Control Switch to another position, AND Then place PRZR spray valves back in AUTO.

b.

Place Charging Pump Speed control to MANUAL, Position PRZR Level Control Switch to another position, AND Then place Charging Pump Speed control back to AUTO.

c.

Position PRZR Level Control Switch to another position, AND Then restore normal letdown and PRZR heaters.

d.

No actions are required to restore PRZR pressure and level.

REACTOR OPERATOR Page 58 QUESTION: 054 (1.00)

Which one of the following would cause annunciator 47041-P, ROD BOTTOM ROD DROP, to alarm?

a.

Control Bank B demand is 38 and a Control Bank B IRPI reads 18.

b.

Control Bank A demand is 18 and a Control Bank A IRPI reads 32.

c.

Shutdown Bank B demand is 32 and a Shutdown Bank B IRPI reads 18.

d.

Shutdown Bank A demand is 18 and a Shutdown Bank A IRPI reads 32.

Removed From Exam Because All Answers Are Correct.

REACTOR OPERATOR Page 59 QUESTION: 055 (1.00)

Given the following:

There has been a fire necessitating the evacuation of the control room.

E-0-06, Fire in Alternate Fire Zone has been entered from E-FP-08, Emergency Operating Procedure - Fire.

Which of the following indications is available at the Dedicated Shutdown Panel?

a.

S/G 1A Narrow Range Level b.

Charging Flow c.

RWST Level d.

Reactor Coolant Loop B Hot Leg Temp

REACTOR OPERATOR Page 60 QUESTION: 056 (1.00)

Given the following conditions:

A large break LOCA occurs.

Containment pressure is observed to be 25 psig.

Containment Spray has NOT initiated.

Manual actuation of Containment Spray has been unsuccessful.

All other ESF actuations and components have functioned normally.

What actions need to be taken to manually initiate Containment Spray for Train A?

Manual start of ICS Pump A and...

(1)

ICS-5A/MV-32066 and ICS-6A/MV32067, Ctmt Spray Pump A Discharge Isolation valves (2)

ICS-201/CV-31272 and ICS-202/CV31273, ICS Recirculation RWST valves (3)

CI-1001A/CV31393 and CI-1001B/CV-31394, Caustic Additive to Ctmt Spray valves a.

(1) check auto open (2) check closed (3) check auto open b.

(1) manual open (2) check closed (3) check auto open c.

(1) manual open (2) check closed (3) manual open d.

(1) manual open (2) manual close (3) manual open

REACTOR OPERATOR Page 61 QUESTION: 057 (1.00)

Given the following conditions:

Radiation Monitor R-11, Containment Atmosphere, is in HIGH alarm.

All other plant conditions are normal Which of the following lists valves in the Reactor Building Ventilation System to be verified automatically CLOSED by the operator?

a.

ONLY the following valves:

-TAV-12, Cntmt Purge/Vent Supply

-RBV-2, Cntmt Purge/Vent Supply B

-RBV-5, Cntmt Purge/Vent Exhaust

-RBV-3, Cntmt Purge/Vent Exhaust B

-SA-7003B, Hydrogen Dilution to Cnmt

-LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.

b.

ONLY the following valves:

-TAV-12, Cntmt Purge/Vent Supply

-RBV-5, Cntmt Purge/Vent Exhaust

-SA-7003B, Hydrogen Dilution to Cnmt

-LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.

c.

ONLY the following valves:

-TAV-12, Cntmt Purge/Vent Supply

-RBV-2, Cntmt Purge/Vent Supply B

-RBV-5, Cntmt Purge/Vent Exhaust

-RBV-3, Cntmt Purge/Vent Exhaust B.

d.

ONLY the following valves

-RBV-2, Cntmt Purge/Vent Supply B

-RBV-3, Cntmt Purge/Vent Exhaust B

-SA-7003B, Hydrogen Dilution to Cnmt

-LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.

REACTOR OPERATOR Page 62 QUESTION: 058 (1.00)

ECA-1.1, Loss of Emergency Coolant Recirculation, determines the required number of operating ICS pumps based on which of the following?

a.

Containment pressure, containment temperature, and sump level.

b.

Containment pressure, operating CFCUs, and sump level.

c.

Containment temperature, operating CFCUs, and RWST level.

d.

Containment pressure, operating CFCUs, and RWST level.

REACTOR OPERATOR Page 63 QUESTION: 059 (1.00)

The plant is at 100% power when control room operators receive SPENT FUEL POOL ABNORMAL Annunciator. The SFP level is decreasing AND is lower than the SFP canal level.

The CRS instructs you to initiate makeup to the SFP. Per procedure A-SFP-21, Abnormal SFP Cooling and Cleanup System Operation, you would use...

a.

the RWST b.

Service Water c.

the Reactor Makeup Control System d.

Reactor Makeup Water through manual makeup valve

REACTOR OPERATOR Page 64 QUESTION: 060 (1.00)

The Unit is at 40% power in a power ascension to full power. All systems are aligned in their normal lineups for the current power level except Turbine EHC control is in MANUAL-IMP OUT.

The operator depresses the CV raise pushbutton for 2 seconds to continue the load ascension.

Which of the following is the response of the main feedwater regulating valves to this action?

The Main Feedwater Regulating Valves will initially throttle...

a.

CLOSED due to swell, and then throttle OPEN when level drops below 44%.

b.

OPEN due to the steam flow/feed flow mismatch, and then regulate to control level at 44%

c.

CLOSED due to the steam flow/feed flow mismatch, and then throttle OPEN when level drops below 44%.

d.

OPEN due to shrink, and then regulate to control level at 44%.

REACTOR OPERATOR Page 65 QUESTION: 061 (1.00)

SP-05B-284, "Turbine Driven AFW Pump Full Flow Test - IST," was in progress. The turbine driven auxiliary feedwater pump (TDAFP) was started and had been running for 2 minutes.

Alarm window 47062-N, "T/D AFW Pump Abnormal" then annunciates and the NAO reports the TDAFP auxiliary lube oil pump is continuously stopping and starting with lube oil pressure fluctuating between 8 and 17 psig.

Which ONE of the following correctly explains the above conditions?

a.

Conditions are normal, no operator action is required, the test should continue.

b.

Conditions are normal, the NAO should be directed to locally shutdown the auxiliary lube oil pump, the test should continue.

c.

The shaft driven pump has malfunctioned, the test should be terminated.

d.

The Auxiliary Lube Oil Pump has malfunctioned, the test should be terminated.

REACTOR OPERATOR Page 66 QUESTION: 062 (1.00)

Given the following conditions:

The plant is at 100% power S/G blowdown is in service in Mode II Condenser air removal is aligned for normal operation The NCO positions the R-19 keyswitch to the OFF position Which of the following describes the effect of the operator actions?

a.

Blowdown flowpath switches to Mode I alignment.

b.

Blowdown flowpath switches to the Primary Sampling System.

c.

Condenser Air Ejector discharge AR-6 (CV-31168) remains in the duct position.

d.

Condenser Air Ejector discharge AR-6 (CV-31168) switches to its ATM position.

REACTOR OPERATOR Page 67 QUESTION: 063 (1.00)

During a liquid radwaste discharge from the Waste Condensate Tanks to the Auxiliary building standpipe, control room operators receive a Waste Disposal Panel Trouble Alarm and dispatch an operator. The operator reports from the Waste Disposal Panel (53702) that LIQUID WASTE MONITOR R-18 HIGH RADIATION" has alarmed. Radiation Monitor R-18 is verified to be alarming, but automatic action(s) do NOT occur. What automatic operation of A-RM-45, Abnormal Radiation Monitoring System must now be performed manually?

a.

Manually close WD-19, Waste Liquid Discharge Isolation Valve.

b.

Manually close WD-17, Waste Condensate Pumps Discharge Valve.

c.

Manually close WD-22, Waste Condensate Pumps to Auxiliary Building Standpipe.

d.

Stop Waste Condensate Pump 1A.

REACTOR OPERATOR Page 68 QUESTION: 064 (1.00)

When the RHR system is placed in the shutdown cooling mode of operation, component cooling is __(1)__ aligned to the associated RHR heat exchanger prior to RHR pump start AND component cooling flows through the __(2)__ side of the RHR heat exchanger.

(1)

(2) a.

Automatically Tube b.

Manually Tube c.

Automatically Shell d.

Manually Shell

REACTOR OPERATOR Page 69 QUESTION: 065 (1.00)

A LOCA has occurred. Post-LOCA containment hydrogen concentration is 7%. What method is available to address hydrogen control in the containment?

a.

dilute the containment atmosphere.

b.

place the Hydrogen Recombiner in service.

c.

vent containment through the Shield Building Ventilation System.

d.

spray containment using the containment spray pumps.

Removed From Exam Because There Are No Correct Answers.

REACTOR OPERATOR Page 70 QUESTION: 066 (1.00)

During refueling operations, an irradiated fuel assembly is dropped in the reactor vessel. A fuel handler reports to the control room that gas bubbles are emanating from the dropped assembly.

Shortly afterwards, R-11 alarms on high radiation. The control room operator enters E-FH-53A, "Dropped or Damaged Fuel Assembly" procedure and ____(1)_____. Controls for the R11 alarm ____(2)_____.

a.

(1) verifies that the Auxiliary Building Special Vent system starts (2) automatically stops upward movement of the manipulator hoist b.

(1) verifies that the Containment Vent Isolation occurred (2) do NOT affect the fuel handling system c.

(1) actuates the containment evacuation alarm (2) automatically stops movement of the manipulator trolley and bridge d.

(1) orders the affected area evacuated (2) automatically stops upward movement of the manipulator hoist

REACTOR OPERATOR Page 71 QUESTION: 067 (1.00)

In the event that access to an area with radiation levels in excess of 1000 mrem/hour CANNOT be prevented using a locked door, Technical Specification 6.13 requires the area to be roped off and conspicuously posted.

Which one of the following lists the additional measure that fulfills the requirements of Technical Specifications for the entrance to this area?

a.

Install an audible alarm.

b.

Setup a control point.

c.

Install a flashing light.

d.

Setup a dose rate indicating device.

REACTOR OPERATOR Page 72 QUESTION: 068 (1.00)

Air Compressor A is operating when cooling water to the compressor is inadvertently isolated.

The air compressor will trip...

a.

due to low jacket water pressure.

b.

when the limit for oil temperature is exceeded.

c.

when the limit for air outlet temperature is exceeded.

d.

due to seal leakage resulting in low air discharge pressure.

REACTOR OPERATOR Page 73 QUESTION: 069 (1.00)

Given the following:

RCS Average Temperature = 547°F.

The reactor is critical at approximately 3% power.

The "B" Diesel Generator is inoperable.

The NORMAL power supply for pressurizer heater control group "A" was taken out of service to repair a breaker fault.

Which of the following describes the Technical Specification operability and required actions for the pressurizer heaters, if any?

a.

Technical Specifications requirements are MET and no action is required.

b.

Technical Specifications requirements are NOT met, and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action is required to go to at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

Technical Specifications requirements are NOT met, and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action is required to go to at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d.

Technical Specifications requirements are NOT met, and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action is required to go to at least COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

REACTOR OPERATOR Page 74 QUESTION: 070 (1.00)

Which of the following uses Safeguard 125 VDC power as the NORMAL power supply?

a.

Bus 4 Circuit Breaker Control b.

7.5 KVA Inverter BRA-111 c.

Reactor Trip Breaker shunt trip coil d.

Non-interruptible Bus BRD-115

REACTOR OPERATOR Page 75 QUESTION: 071 (1.00)

Power is lost to BRB-104. Which component(s) associated with the 1B EDG will be affected by this condition?

A.

Field flash circuit AND jacket water pumps ONLY B.

Field flash circuit AND fuel oil priming pump ONLY C.

Jacket water pumps AND immersion heaters ONLY D.

Fuel oil priming pump AND starting air compressors ONLY

REACTOR OPERATOR Page 76 QUESTION: 072 (1.00)

Which of the following correctly describes the effect of a failure (HIGH) of R-15, Air Ejector Exhaust Monitor during a release?

(1)

Air Ejector Discharge Vent. AR-6/CV-31168 positions to DUCT (2)

S/G Blowdown Isolation valves CLOSE (3)

S/G Sample Isolation valves CLOSE (4)

Humidification Steam Inlet CV HS-17-1/CV31770 CLOSES a.

ONLY (1), (2) AND (3) occur b.

ONLY (2) AND (3) occur c.

(1), (2), (3) AND (4) occur d.

ONLY (2), (3) AND (4) occur

REACTOR OPERATOR Page 77 QUESTION: 073 (1.00)

Which of the following describes the CW condition(s) that would provide an interlock to PREVENT starting a CW pump?

(I)

Seal Water Flow < 2 gpm (II)

"Forebay Level Low Low" (566 or 42%)

(III)

Thrust Bearing Cooler Flow < 4 gpm a.

ONLY (II) b.

ONLY (I) and (III) c.

ONLY (II) and (III) d.

(I), (II) and (III)

REACTOR OPERATOR Page 78 QUESTION: 074 (1.00)

A malfunction of ONE of the "A" Diesel Generator Room CO2 temperature switches occurs, causing it to fail HIGH. Which of the following describes the response of the CO2 system to the "A" Diesel Generator Room?

a.

The CO2 actuation sequence will not begin until a second switch actuation occurs.

b.

The CO2 actuation sequence will sound a local horn, but will not discharge.

c.

The CO2 actuation sequence will sound a local horn and then discharge.

d.

The CO2 actuation sequence will start a local, flashing red light, sound a local horn and then discharge.

REACTOR OPERATOR Page 79 QUESTION: 075 (1.00)

Given the following conditions:

The plant is at 100% power.

All lineups/switch positions are in their NORMAL position.

Pressurizer Level Channel LT-426 (Channel I) fails LOW What is the status of the following BEFORE any operator actions are taken?

Letdown Flow Indication "Pressurizer Level Low" Annunciator a.

Normal LIT b.

Normal Not LIT c.

Zero LIT d.

Zero Not Lit

REACTOR OPERATOR Page 80 QUESTION: 076 (1.00)

Given the following conditions:

Steam Generator NR Levels are 88%

MSIVs are CLOSED Per Procedure FR-H.2, "Response to Steam Generator Overpressure," which of the methods given below has PRIORITY for decreasing S/G pressure?

a.

Dump steam using SG PORVs b.

Isolate AFW to the S/Gs c.

Dump steam using Steam Supply to Turbine-Driven AFW Pump d.

Dump steam using Main Steam Isolation Bypass Valves

REACTOR OPERATOR Page 81 QUESTION: 077 (1.00)

In addressing a PRZR relief valve (PORV) that is stuck open, the associated block valve must be closed. Which of the following indication(s) can be used to identify which PORV is stuck open?

(I)

PR-2A(B) indicating lights on the Mechanical Console C (II)

Acoustic monitor indicating lights on the Mechanical Console C (III)

Outlet temperatures for each PORV a.

ONLY (I) b.

ONLY (I) OR (III) c.

ONLY (II) OR (III) d.

(I), (II) OR (III)

REACTOR OPERATOR Page 82 QUESTION: 078 (1.00)

A LOCA has occurred and a controlled RCS cooldown and depressurization per ES-1.2, "Post LOCA Cooldown and Depressurization" is in progress. ALL ECCS equipment is OPERABLE.

RCS Pressure and Temperature is 1500 psig / 480°F. After SI pump A is secured as part of the RCS cooldown and depressurization, the following alarms occur:

47022-D, "CONTAINMENT HIGH PRESSURE SI" 47024-A, "ACCUMULATOR A PRESSURE HIGH/LOW" 47024-B, "ACCUMULATOR A LEVEL HIGH/LOW" What action(s) must be taken, if any, based on these conditions:

a.

Trip both RCPs.

b.

Restart SI pump A.

c.

Trip both RCPs AND Restart SI pump A.

d.

No action required.

REACTOR OPERATOR Page 83 QUESTION: 079 (1.00)

Which of the following systems is considered to be the most likely location for a rupture or break outside containment, and therefore is the system of primary concern during ECA-1.2, "LOCA Outside Containment?"

a.

Safety Injection b.

Residual Heat Removal c.

Component Cooling d.

Chemical and Volume Control

REACTOR OPERATOR Page 84 QUESTION: 080 (1.00)

Given the following conditions:

A loss of normal feedwater flow has occurred.

The actions of FR-S.1 "Response to Nuclear Power Generation/ATWS" must be performed due to a failure of the plant to trip Which of the following describes the proper sequence of steps to be taken with a failure of the reactor to trip, AFTER beginning to manually insert the Control Rods?

(I)

- Locally Open Reactor Trip Breakers (II)

- Open Bus 33 and Bus 43 supply breakers (III)

- TRIP Rod Drive MG Set Motor & Generator Circuit Breaker Control Switches a.

(I), (II), and THEN (III).

b.

(II), (I), and THEN (III).

c.

(II), (III), and THEN (I).

d.

(III), (II), and THEN (I).

REACTOR OPERATOR Page 85 QUESTION: 081 (1.00)

Given the following conditions:

Reactor power is 100%

VCT level transmitter LT-112 (24015) fails high (100%)

Which of the following describes what occurs if NO operator action is taken?

VCT level decreases __________.

a.

because auto makeup capacity is not able to maintain VCT level with letdown diverted b.

with NO auto makeup capability causing charging suction to shift to the RWST c.

until charging pumps lose suction and start to cavitate d.

until auto makeup starts and maintains VCT level

REACTOR OPERATOR Page 86 QUESTION: 082 (1.00)

Given the following conditions:

The plant is at 255°F, cooling down to Cold Shutdown with RHR Train A.

RHR Train B is out of service for testing.

Annunciator 47024-H, CC SURGE TANK LEVEL HIGH/LOW is LIT.

CC Surge Tank Level is 53% and INCREASING.

R-17, Component Cooling Liquid Rad Monitor, is in HIGH ALARM.

VCT level is DECREASING.

All other indications are NORMAL.

Which of the following is the location of the leak?

a.

RHR system.

b.

SFP heat exchanger.

c.

Seal Water heat exchanger.

d.

SW system.

REACTOR OPERATOR Page 87 QUESTION: 083 (1.00)

Complete the following statement:

Source Range neutron detectors operate in the ____(1)_____ region, so decreasing the detector voltage beyond calibration limits would result in a _____(2)_____ indicated power level.

a.

(1) Ionization, (2) higher b.

(1) Proportional, (2) higher c.

(1) Ionization, (2) lower d.

(1) Proportional, (2) lower

REACTOR OPERATOR Page 88 QUESTION: 084 (1.00)

The following conditions exist:

A reactor startup has been completed per N-CRD-49B, "Reactor Startup."

The Source Range trip is blocked.

The N35 Intermediate Range channel is failed LOW with the level trip bypassed.

The N36 Intermediate Range channel is reading ERRATICALLY.

Source Range counts have just reached 106 CPS What is the expected indication on the intermediate range nuclear instruments for this condition?

a.

10-3 % Power (IR) b.

10-2 % Power (IR) c.

10-1 % Power (IR) d.

100 or 1% Power (IR)

REACTOR OPERATOR Page 89 QUESTION: 085 (1.00)

The plant is at 100% power. TLA-15, RMS ABOVE NORMAL is in alarm due to increasing radiation level on R-19, S/G Blowdown Liquid Monitor. What action(s) must be taken based on these conditions?

a.

IF the radiation level on R-19, S/G Blowdown Liquid Monitor increases to HIGH alarm, THEN go to E-0-14, "Steam Generator Tube Leak."

b.

Go to E-0-14, "Steam Generator Tube Leak" and perform Operator immediate actions.

c.

Go to A-RM-45, "Abnormal Radiation Monitoring System" and verify the automatic actions occur as listed for R-19, S/G Blowdown Liquid Monitor.

d.

Per A-RM-45, "Abnormal Radiation Monitoring System" determine primary-to-secondary leak rate using "R-19 to Leakage Rate Conversion Graph."

REACTOR OPERATOR Page 90 QUESTION: 086 (1.00)

Which of the following describes the reason for tripping both RXCPs, if required, per step 1 of E-3, "Steam Generator Tube Rupture?"

a.

To minimize the potential for RCP damage when an RCS depressurization is initiated.

b.

To minimize the heat input when a controlled RCS cooldown is initiated.

c.

To prevent the automatic opening of a pressurizer PORV.

d.

To prevent unnecessary RCS water depletion.

REACTOR OPERATOR Page 91 QUESTION: 087 (1.00)

The following plant conditions exist:

FR-H.1, Response to Loss of Secondary Heat Sink is in progress.

The CST is unavailable.

Yarway wide range S/G levels are at 20%.

RCS pressure is at 2200 psig.

Containment pressure is 1 psig.

Which of the following heat removal methods is available, if any, before RCS bleed and feed is required AND what is the preferred sequence for establishing flow to at least one S/G?

(1)

Depressurize SG and establish Condensate flow (2)

Establish AFW flow using Service Water (3)

Establish Main Feedwater flow a.

(2), (3), (1) b.

(3), (2), (1) c.

(3), (1), (2) d.

No S/G heat removal method is available; RCS bleed and feed is required immediately.

REACTOR OPERATOR Page 92 QUESTION: 088 (1.00)

Which of the following places the plant in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Limiting Condition of Operation per Technical Specifications?

a.

BRA-101, Station Battery A, fuse blows.

b.

BRA-108, Battery Charger A, damaged due to fire.

c.

BRA-102, DC DIstribution Train A, damaged bus bar.

d.

BRA-111, Instrument Bus 1 Inverter, damaged rectifier.

REACTOR OPERATOR Page 93 QUESTION: 089 (1.00)

The following plant conditions exist:

An accidental gaseous release has occurred.

The derived air concentration (DAC) of this release is 4 DAC.

Which of the following is the expected exposure to the whole body of a worker breathing air in this area for 30 minutes?

a.

2 mrem b.

5 mrem c.

8 mrem d.

10 mrem

REACTOR OPERATOR Page 94 QUESTION: 090 (1.00)

The plant is operating at 100% power. Annunciator 47033-35, TLA-15, RMS ABOVE NORMAL, alarms due to rising count rate on R-42, S/G A N16 Monitor.

Plant conditions:

Pressurizer level:

47%, stable.

Pressurizer pressure:

2235 psig.

Which of the following describes the action or actions required for this situation?

a.

Enter E-0-14, Steam Generator Tube Leak.

b.

Manually trip the reactor and enter E-0, Reactor Trip or Safety Injection.

c.

Contact Health Physics to assist in identifying the radiation source.

d.

Evacuate the reactor building.

REACTOR OPERATOR Page 95 QUESTION: 091 (1.00)

Given the following conditions:

A LOCA has occurred The crew is performing a cooldown per ES-1.2 " Post LOCA Cooldown and Depressurization" Two Containment Cooling Fan Coil Units are running Containment pressure is stable at 2.2 psig A transition to FR-Z.3 "Response to High Containment Radiation Level" is made on a YELLOW path condition Why does FR-Z.3 start idle Containment Cooling Fan Coil Units?

a.

To remove radioactive particulates during condensation of water vapor.

b.

To remove radioactive gases during condensation of water vapor.

c.

To support Containment Purge and Vent Subsystem Exhaust filtration.

d.

To support Containment Purge and Vent Subsystem Purge filtration.

REACTOR OPERATOR Page 96 QUESTION: 092 (1.00)

Given the following conditions:

A fire has occurred on site.

E-0-06, "Fire in Alternate Fire Zone" is being implemented.

Complete the following statement:

During implementation of E-0-06, only ____(1)____ equipment is being controlled from the Dedicated Shutdown Panel and offsite power is considered to be ____(2)____.

____(1)____

____(2)____

a.

Train A available b.

Train A NOT available c.

Train B available d.

Train B NOT available

REACTOR OPERATOR Page 97 QUESTION: 093 (1.00)

The plant was operating at 100% power when the following events occurred:

0100: RC-413, Pressurizer Liquid Sampling Isolation valve is determined to be INOPERABLE.

0200: RC-412, Pressurizer Liquid Sampling Isolation valve is determined to be INOPERABLE.

What log entry or entries need to be made to track these inoperable valves?

a.

An entry for each valve in the Shift Managers Log AND in the Shift Managers LCO Tracking Log at the time they became INOPERABLE.

b.

An entry for each valve in the Control Room Log AND in the Shift Managers LCO Tracking Log at the time the valves were discovered to be INOPERABLE.

c.

An entry in the Shift Managers Log AND the Control Room Log for each valve at the time they became INOPERABLE, AND an entry in the Control Room Shift Turnover Checklist at shift turnover.

d.

One log entry for both valves in the Control Room Shift Turnover Checklist at shift turnover AND an entry for each valve in the Periodic Daily Log at the time each valve became INOPERABLE.

REACTOR OPERATOR Page 98 QUESTION: 094 (1.00)

Given the following:

A LOCA has occurred.

Containment Pressure is 6 psig.

Core Exit Thermocouples are at 600°F.

RCS pressure is 200 psig.

RHR is in its at-power lineup.

FR-C.3, Response to Saturated Core Cooling, is being implemented.

What flows to the RCS must be verified per FR-C.3, Response to Saturated Core Cooling?

a.

Charging pump flow ONLY.

b.

RHR and SI pump flows ONLY.

c.

SI pump flow ONLY.

d.

Charging and SI pump flows ONLY.

REACTOR OPERATOR Page 99 QUESTION: 095 (1.00)

The following conditions exist:

A runback from 80% to 60% power occurred 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.

Chemistry samples of the RCS indicate high dose-equivalent I-131.

Why is it desirable to increase letdown flow through the CVC mixed bed demineralizers to 80 gpm under these conditions?

a.

To reduce RCS activity.

b.

To control RCS pH.

c.

To reduce RCS corrosion products.

d.

To control RCS boron concentration.

REACTOR OPERATOR Page 100 QUESTION: 096 (1.00)

While performing ECA-1.1, Loss of Emergency Coolant Recirculation, the "RHR Pump A Supply to ICS Pump A", valve RHR-400A could not be operated from the control room. The steps contingency action states "Locally open valve". On which elevation of the auxiliary building is this valve located?

a.

572 b.

586 c.

606 d.

626

REACTOR OPERATOR Page 101 QUESTION: 097 (1.00)

In order to establish a Containment Purge in HOT SHUTDOWN, which of the following is required?

1.

Notify NRC prior to opening 36" RBV valves.

2.

Obtain a Gaseous Waste Discharge Permit.

3.

Verify Annunciator 47051-B, "Containment Vent High Radiation Disabled" is CLEAR.

a.

ONLY 1 and 2.

b.

ONLY 1 and 3.

c.

ONLY 2 and 3.

d.

1, 2 and 3.

REACTOR OPERATOR Page 102 QUESTION: 098 (1.00)

For a Steam Line Break of a given size and location, which of the following initial conditions results in the smallest reactivity rate of change immediately after the break?

CORE BURNUP (MWD/MTU)

RCS Tavg a.

9000 450°F b.

9000 547°F c.

5000 450°F d.

5000 547°F

REACTOR OPERATOR Page 103 QUESTION: 099 (1.00)

Given the following:

Reactor power is stabilized at the eight-fold power level.

The Eight-Fold Critical Rod Position is determined to be 65 steps on Control Bank C.

Which action is required in this situation?

a.

Emergency Borate 300 gallons.

b.

SHUT DOWN the reactor per N-CRD-49C, "Reactor Shutdown" c.

Get permission from Station Nuclear Engineer to continue with the startup.

d.

Verify the Eight-fold Critical Rod Position is within +400pcm of ECP

REACTOR OPERATOR Page 104 QUESTION: 100 (1.00)

Given the following:

The plant is in normal 100% power operations.

Containment Fan Coil Units Emergency Discharge Dampers RBV-150 A and B both fail OPEN.

What is the major concern at this time?

a.

Damage to the Nuclear Instrumentation.

b.

Damage to the Reactor Vessel Gap.

c.

RXCP A motor stator overheating.

d.

RXCP B motor stator overheating.

(********** END OF EXAMINATION **********)

REACTOR OPERATOR

REFERENCES:

Page 105 ANSWER: 001 C

REFERENCE:

ECA-0.0, CAUTION prior to Step 6; BYRON1 10/29/2001 Exam Bank Higher 000062K303..(KAs)

ANSWER: 034 D

REFERENCE:

A-FW-05A, Abnormal FW Operation, step 4.4.

New Higher 059000 2.2.2..(KAs)

ANSWER: 067 C

REFERENCE:

LO R01-01-LPTS4.010; Tech Spec 6.1; KNPP EQB Bank Memory 2.1.10..(KAs)

ANSWER: 002 B

REFERENCE:

LP RO2-02-LP05A, Main Feedwater; SD 05A, Feedwater New Higher 059000K408..(KAs)

ANSWER: 035 A

REFERENCE:

SD 39, 4160 V System; SD 36, RCS New Memory 003000K201..(KAs)

ANSWER: 068 C

REFERENCE:

OP A-AS-1, Abnormal Station/

Instrument Air System Operation; SD #1, Station/Instrument Air, Pg 9.

Bank Memory 078000K403..(KAs)

ANSWER: 003 A

REFERENCE:

NRC EQB; KNPP 02/21/1994 Exam; ADV-SYS-LP-36D, p. 11; ADV-SYS-LP-36D, EO-RO4.a Bank Higher 022000K302..(KAs)

ANSWER: 036 A

REFERENCE:

IPEOP Background Document for FR-P.1; LP RO4-04-LP-016, Response to Imminent Pressurized Thermal Shock Condition New Memory E08EA202..(KAs)

ANSWER: 069 B

REFERENCE:

LP RO2-01-LP-36B, PZR and PRT; Tech Spec 3.1.a.6 and its basis; SD 38, DC and Emergency AC Power New Higher 062000 2.1.12..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 106 ANSWER: 004 D

REFERENCE:

NRC EQB; Prairie Island 1 and 2 05/09/1994 Exam.

Modified Memory 056000K103..(KAs)

ANSWER: 037 A

REFERENCE:

ECA-2.1, Uncontrolled Depressurization of Both S/Gs New Higher E12EA13..(KAs)

ANSWER: 070 C

REFERENCE:

SD 38, DC and Emergency AC Electrical Distribution.

New Memory 063000K201..(KAs)

ANSWER: 005 B

REFERENCE:

E-240 Rev. AQ; Adv System LP Objective R02-05-LP36D.003 ("N/A).

New Memory 011000K202..(KAs)

ANSWER: 038 A

REFERENCE:

ES-1.1, SI Termination and Background Document; LP RO4-04-LP-005 New Memory 000026K303..(KAs)

ANSWER: 071 B

REFERENCE:

SD 38, DC and Emergency AC Power; LP RO2-03-LP-042A, D/Gs New Memory 064000K202..(KAs)

ANSWER: 006 C

REFERENCE:

KNPP SD 1, Rev 1, p 6; LP O-RO-LP-2.11.1, EO 3; NRC EQB; KNPP 1993 Exam Modified Higher 079000K101..(KAs)

ANSWER: 039 C

REFERENCE:

ES-0.2, Natural Circulation Cooldown Modified Higher 2.4.4..(KAs)

ANSWER: 072 C

REFERENCE:

SD 45, Radiation Monitors; A-RM-45, Abnormal Radiation Monitoring; E-3748, PRM Integrated Logic Diagram New Memory 073000K301..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 107 ANSWER: 007 D

REFERENCE:

NRC EQB; V. C. Summer 1 1992/05/18 Exam Bank Higher 015000K101..(KAs)

ANSWER: 040 C

REFERENCE:

SD 49 Rod Control and RPI; Tech Specs New Higher 000005K105..(KAs)

ANSWER: 073 C

REFERENCE:

SD 4, CW System; ARP 47051-N, Forebay Level Low; LP RO2-02-LP-004, CW New Memory 075000K401..(KAs)

ANSWER: 008 D

REFERENCE:

NRC EQB; North Anna 1 01/26/1996 Exam.

Bank Higher 000065K304..(KAs)

ANSWER: 041 C

REFERENCE:

ES-0.2, Rev 0, Caution before step 1, p 2.;

NRC EQB; Point Beach 04/29/1991.

Bank Memory 000015A109..(KAs)

ANSWER: 074 C

REFERENCE:

SD 8, Fire Protection System; RO2-02-LP-008, Fire Protection System; New Memory 086000K604..(KAs)

ANSWER: 009 A

REFERENCE:

NRC EQB; Prairie Island 1 and 2 09/28/1992 Exam.

Bank Higher 000003K103..(KAs)

ANSWER: 042 A

REFERENCE:

PWR Fundamentals; Braidwood 4/1/1996 Exam Bank Memory 000024K102..(KAs)

ANSWER: 075 A

REFERENCE:

SD 36, Reactor Coolant System; ARP 47043-F, PRZR Level Low; A-MI-87, B/S Tripping for Failed RP or Safeguards Inst.

New Memory 000028A206..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 108 ANSWER: 010 B

REFERENCE:

BYRON1 10/29/2001 Exam.

Modified Higher 000027K203..(KAs)

ANSWER: 043 D

REFERENCE:

LP RO2-02-LP-003, Condensate and Air Removal System; New Higher 056000A204..(KAs)

ANSWER: 076 A

REFERENCE:

LP RO4-04-LP-036; FR-H.2, Response to S/G Overpressure; IPEOP Background Document New Memory E13EK11..(KAs)

ANSWER: 011 B

REFERENCE:

ES-1.3, Transfer to Cntnmt Sump Recirc; SD 33, SI System.

New Memory 006000 2.3.11..(KAs)

ANSWER: 044 B

REFERENCE:

RO2-02-LP-003.004; O-AOP-LP-D8; E-AR-09, Loss of Condenser Vacuum New Higher 000051 2.1.30..(KAs)

ANSWER: 077 A

REFERENCE:

LP RO4-04-LP-36B ARP 47042-A, PZR PORV Open; ARP 47042-B, PZR PORV Discharge Temperature High; New Higher 000008A203..(KAs)

ANSWER: 012 A

REFERENCE:

KNPP EQB; LP Obj RO2-01-LP31.004; CCW SD 31.

Bank Higher 008000A308..(KAs)

ANSWER: 045 A

REFERENCE:

SD 32B, Gaseous Radioactive Waste Disposal; New Memory 071000A302..(KAs)

ANSWER: 078 B

REFERENCE:

ES-1.2, Post LOCA Cooldown and Depressurization, Step 16a (Contingency Actions)

New Higher 000009 2.4.45..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 109 ANSWER: 013 A

REFERENCE:

LP RO2-02-LP362; SD 36, RCS; KNPP 12/2000 Exam.

Bank Higher 003000A304..(KAs)

ANSWER: 046 A

REFERENCE:

SD 32B, Gaseous Radioactive Waste Disposal; SD 45, Radiation Monitoring New Memory 071000A409..(KAs)

ANSWER: 079 B

REFERENCE:

ECA-1.2, LOCA Outside Containment; IPEOP Background Document; Prairie Island 05/15/2000 Exam; LP RO4-04-LP-020, LOCA Outside Containment Modified Memory E04EK22..(KAs)

ANSWER: 014 A

REFERENCE:

SD 05A, Feedwater System; SD 05B, Auxiliary Feedwater System; KNPP EQB.

Bank Higher 061000K101..(KAs)

ANSWER: 047 A

REFERENCE:

SD 45, Radiation Monitoring; RO2-01-LP045, Radiation Monitoring New Memory 072000K501..(KAs)

ANSWER: 080 B

REFERENCE:

FR-S.1, Response to Nuclear Power Generation/ATWS; IPEOP Background Document; New Memory 000029 2.4.49..(KAs)

ANSWER: 015 A

REFERENCE:

KNPP Exam 12/18/1997; SD 035, CVCS.

Bank Memory 004000A405..(KAs)

ANSWER: 048 D

REFERENCE:

SD 45, Radiation Monitoring; A-RM-45, Abnormal Radiation Monitoring New Memory 072000 2.3.10..(KAs)

ANSWER: 081 C

REFERENCE:

KNPP NRC Exam 10/24/2000 ARP 47043-L, VCT Level High/Low SD 35, CVCS Bank Memory 000022A108..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 110 ANSWER: 016 B

REFERENCE:

LP RO2-05-LP05B, Aux Feedwater; KNPP EQB Bank Higher 061000A101..(KAs)

ANSWER: 049 C

REFERENCE:

ES-0.2, Natural Circulation Cooldown; ES-0.2 Background Document; Bank Memory 002000A203..(KAs)

ANSWER: 082 A

REFERENCE:

A-CC-31, Abnormal CCW Operations; ARP 47024-H, CC Surge Tank Level High/Low; A-RHR-34, Abnormal RHR Operations; A-RM-45, Abnormal Rad Monitoring New Higher 000025A202..(KAs)

ANSWER: 017 D

REFERENCE:

SP-54-086, TSV and GV Operability Test, Pg 3 of 17.

New Memory 045A401..(KAs)

ANSWER: 050 D

REFERENCE:

RO2-05-LP-36C, Pressurizer Pressure Control New Higher 010000K103..(KAs)

ANSWER: 083 C

REFERENCE:

LP RO2-05-LP048, Excore Nuclear Instrumentation System; SD 48, Excore Nuclear Instrumentation New Memory 000032K101..(KAs)

ANSWER: 018 B

REFERENCE:

Byron 10/29/2001 Exam Bank Higher 2.1.25..(KAs)

ANSWER: 051 C

REFERENCE:

RO2-05-LP472, Reactor Protection New Higher 012000K304..(KAs)

ANSWER: 084 A

REFERENCE:

LP RO2-05-LP048, Excore Nuclear Instrumentation System; SD 48, Excore Nuclear Instrumentation New Memory 000033A201..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 111 ANSWER: 019 C

REFERENCE:

LP R02-05-LP-033; TS 3.3.a. Accumulators New Higher 2.1.11..(KAs)

ANSWER: 052 C

REFERENCE:

LP RO4-04-LP040, Loss of all AC Power; Comanche Peak 11/26/90; ECA-0.0, Loss of all AC Power Bank Memory 000055K101..(KAs)

ANSWER: 085 B

REFERENCE:

A-RM-45, Abnormal Radiation Monitoring System; E-0-14, Steam Generator Tube Leak New Memory 000037A113..(KAs)

ANSWER: 020 A

REFERENCE:

LP R02-05-LP-053; N-FH-53-CLC, Pre-Refueling Checklist; RF-01.00, KNPP Refueling Procedure; New Higher 2.2.27..(KAs)

ANSWER: 053 D

REFERENCE:

LP RO2-05-36C, Pzr Pressure Control; SD 36, RCS; A-MI-87, Bistable Tripping for Failed RP or Safeguards Inst.

New Higher 000057A102..(KAs)

ANSWER: 086 D

REFERENCE:

BKG E-3, Steam Generator Tube Rupture; IPEOP Background Document; E-3, Steam Generator Tube Rupture New Memory 000038K308..(KAs)

ANSWER: 021 C

REFERENCE:

LP R02-05-LP-053; NAD-02.07, KNPP Refueling Operations New Memory 2.2.26..(KAs)

ANSWER: 054 C

REFERENCE:

KNPP SD 49, Rod Control and RPI; KNPP EQB RO2-05-LP049.004 010; LP RO2-05-LP049, Rod Control and RPI.

Bank Higher 014000K502..(KAs)

ANSWER: 087 C

REFERENCE:

A-FW-05B, Abnormal AFW System Operation; FR-H.1, Response to Loss of Secondary Heat Sink; BKG FR-H.1, Loss of Secondary Heat Sink; IPEOP Background Document New Higher E05EK22..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 112 ANSWER: 022 C

REFERENCE:

12/11/2000 KNPP Exam.

Modified Higher 2.3.2..(KAs)

ANSWER: 055 C

REFERENCE:

Fire Protection Program Plan, Appendix D; E-0-06, Fire in Alternate Fire Zone; E-FP-08, EOP - Fire.

New Memory 016000K401..(KAs)

ANSWER: 088 C

REFERENCE:

Tech Spec and Bases; A-EDC-38, Abnormal DC Supply and Distribution System; SD 38, "DC and Emergency AC Distribution; LP RO2-03-LP 038, DC and Emergency AC Distribution New Memory 000058 2.2.22..(KAs)

ANSWER: 023 B

REFERENCE:

FR-S.1, Response to a Nuclear Power Generation/ATWS; E-0, Reactor Trip or Safety Injection.

New Higher 2.4.1..(KAs)

ANSWER: 056 C

REFERENCE:

FR-Z.1, Response to High Ctnmt Pressure, Step 3, pgs 3-4; CS Integrated Logic Diag E-1604; System Integrated Logic Diagram ICS E-2012.

Bank Memory 026000A301..(KAs)

ANSWER: 089 B

REFERENCE:

10CFR20, definitions and part 1204; SD 32B, Gaseous Radioactive Waste Disposal; New Higher 000060K102..(KAs)

ANSWER: 024 B

REFERENCE:

Byron Exam 10/20/2000; ECA-0.0, LOSS OF ALL AC POWER and Background Document.

New Higher 2.4.7..(KAs)

ANSWER: 057 A

REFERENCE:

A-RM-45, Abnormal Radiation Monitoring System.

New Memory 029000A102..(KAs)

ANSWER: 090 A

REFERENCE:

ARP 47033-35, TLA-15, RMS ABOVE NORMAL; New Memory 000061AK30..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 113 ANSWER: 025 C

REFERENCE:

FR-C.2, Response to Degraded Core Cooling.

Bank Memory E11EK32..(KAs)

ANSWER: 058 D

REFERENCE:

Byron Exam 06/29/2000.

Bank Memory 103000A101..(KAs)

ANSWER: 091 A

REFERENCE:

FR-Z.3, Response to High Containment Radiation Level; BKG FR-Z.3,Response to High Containment Radiation Level; IPEOP Background Document; KNPP NRC Exam 12/11/2000 Modified Higher E16EK33..(KAs)

ANSWER: 026 B

REFERENCE:

LP RO2-05-LP 049, Rod Control and RPI; SD-49, Section 3.3.2.

New Higher 001000K103..(KAs)

ANSWER: 059 B

REFERENCE:

KNPP Exam 02/24/1997 Modified Memory 033000A203..(KAs)

ANSWER: 092 B

REFERENCE:

E-0-06, Fire in Alternate Fire Zone; Byron Exam 06/29/2000 New Higher 000067A217..(KAs)

ANSWER: 027 B

REFERENCE:

RO2-05-LP 049, Rod Control and RPI, pg 43 and 44; ARP 47043-R, Rod Control System Abnormal New Memory 001000K611..(KAs)

ANSWER: 060 B

REFERENCE:

Beaver Valley 2 Exam 03/17/1997; Modified Higher 035000A301..(KAs)

ANSWER: 093 C

REFERENCE:

LO R02-04-LP056.007; Tech Spec 3.6.b.3.B, Containment System New Memory 000069 2.2.23..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 114 ANSWER: 028 D

REFERENCE:

KNPP SD 55, ESF Bank Memory 013000K403..(KAs)

ANSWER: 061 C

REFERENCE:

KNPP SD 05B, AFW System; ARP 47062-N Bank Higher 039000A404..(KAs)

ANSWER: 094 C

REFERENCE:

FR-C.3, Response to Saturated Core Cooling; New Higher E07EK13..(KAs)

ANSWER: 029 A

REFERENCE:

LP RO2-05-035, CVCS; SD 35, CVCS.

New Higher 004000K305..(KAs)

ANSWER: 062 C

REFERENCE:

KNPP 12/11/00 NRC Exam; SD 09, Air Removal System Bank Higher 055000K106..(KAs)

ANSWER: 095 A

REFERENCE:

A-RC-36A, High Reactor Coolant Activity; KNPP NRC Exam 12/18/1997 Bank Higher 000076K305..(KAs)

ANSWER: 030 A

REFERENCE:

LP RO2-05-048, NIS; SD 48, NIS; 11/13/1990 Millstone 3 Exam.

Bank Higher 015000K603..(KAs)

ANSWER: 063 A

REFERENCE:

A-RM-45, Abnormal Radiation Monitoring System; LP Obj RO2-01-LP045.004; Dwg XK-100-131; FD Waste Disposal System.

New Memory 068000A204..(KAs)

ANSWER: 096 B

REFERENCE:

SD 23, ICS System; Dwg A-204, A-210, OPERXK-100-18; Dwg OPERM-217; New Memory 026000 2.4.34..(KAs)

REACTOR OPERATOR

REFERENCES:

Page 115 ANSWER: 031 D

REFERENCE:

SD 50, Incore Instrumentation; Inadequate Core Cooling Monitor, Sect. 1.4, CET Operation, and 3.4.3, CET Instrumentation.

New Memory 017000A401..(KAs)

ANSWER: 064 D

REFERENCE:

SD RHR pg 16; Dwgs OPERXK-100-18, -19.

New Memory 005000K101..(KAs)

ANSWER: 097 C

REFERENCE:

SD 18, Reactor Building Ventilation; ARP 47051-B, Containment Vent High Radiation Disabled; N-RBV-18B, Reactor Bldg Vent System Cold Operation and Releases New Higher 029000 2.3.9..(KAs)

ANSWER: 032 C

REFERENCE:

SD 18, RBV; Hydrogen Control; LP RO2-04-LP 18, RBV System.

New Higher 022000A301..(KAs)

ANSWER: 065 A

REFERENCE:

N-RBV-18C, POST-LOCA Hydrogen Control.

New Memory 028000K502..(KAs)

ANSWER: 098 C

REFERENCE:

KNPP Exam 12/18/97; Reactor Data Manual Bank Higher 000040 2.2.34..(KAs)

ANSWER: 033 D

REFERENCE:

SD 2, Service Water; KNPP EQB.

Bank Higher 076000K307..(KAs)

ANSWER: 066 B

REFERENCE:

E-RH-53A, "Dropped or Damaged FA,8/17/2001; SD Rad Mon, pgs 12-13; SD FH, pgs 13,16, 28.

New Higher 034000A201..(KAs)

ANSWER: 099 B

REFERENCE:

N-CRD-49B, Reactor Startup; N-CRD-49C, Reactor Shutdown; New Higher 2.2.1..(KAs)

ANSWER: 100 D

REFERENCE:

KNPP Exam 12/11/2000; SD 18, Reactor Building Vent Bank Higher 2.1.32..(KAs)

Page 116 A N S W E R K E Y MULTIPLE CHOICE 001 c 002 b 003 a 004 d 005 b 006 c 007 d 008 d 009 a 010 b 011 b 012 a 013 a 014 a 015 a 016 b 017 d 018 b 019 c 020 a 021 c 022 c 023 b 024 b 025 c 026 b 027 b 028 d 029 a 030 a 031 d 032 c 033 d 034 d 035 a 036 a 037 a 038 a 039 c 040 c 041 c 042 a 043 d 044 b 045 a 046 a 047 a 048 d 049 c 050 d 051 c 052 c 053 d 054 c 055 c 056 c 057 a 058 d 059 b 060 b 061 c 062 c 063 a 064 d 065 a 066 b 067 c 068 c 069 b 070 c 071 b 072 c 073 c 074 c 075 a 076 a 077 a 078 b 079 b 080 b 081 c 082 a 083 c 084 a 085 b 086 d 087 c 088 c 089 b 090 a 091 a 092 b 093 c 094 c 095 a 096 b 097 c 098 c 099 b 100 d

Retrieved from "https://kanterella.com/w/index.php?title=ML040690107&oldid=5405362"