ML20058D669
| ML20058D669 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 11/15/1993 |
| From: | Caldwell J, Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058A573 | List: |
| References | |
| 50-020-OL-93-01, 50-20-OL-93-1, NUDOCS 9312030255 | |
| Download: ML20058D669 (52) | |
Text
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ENCLOSURE 1 -
U. S. NUCLEAR REGULATORY COMMISSION
[
OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-020/0L-93-01 FACILITY DOCKET NO.:
50-020 i
FACILITY LICENSE NO.:
R-37 1
FACILITY:
Massachusetts Institute of Technology EXAMINATION DATES:
September. 13-15, 1993 i
EXAMINER:
Patrick saac, Chief Examiner M o!/Jt[!Io.,-
- [2.
J SUBMITTED BY:
P'tti:
Isaac;T 1f xaminer j/
ate l
g APPROVED BY:
AM/
I
/6 Jam 't.'Caldwell,LChief
/ Date Non Power Reactor Section Ope ator Licensing Branch Div'sion of Reactor Controls l
and Human Factors Office of Nuclear Reactor Regulation
SUMMARY
i NRC administered written examination and operating tests to one Senior Reactor Operator Instant (SROI) and two Reactor Operator (RO) candidates. Operating tests were also administered to one Senior Reactor Operator Upgrade (SROU) candidate. All applicants passed their respective portion of the examinations and have been issued the appropriate license.
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i 9312030255 931115 PDR ADOCK 05000020 V
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REPORT DETAILS 1.
Examiners:
Patrick Isaac, Chief Examiner 2.
Results:
R0 SRO Total (Pass / Fail)
(Pass / Fail)
(Pass / Fail) i NRC Grading:
2/0 2/0 4/0 3.
Written Examination:
The written examination was administered on September 13, 1993 to two R0 and one SROI candidates. At the conclusion of the examination, the Chief Examiner immediately secured the master examination answer key and all the candidate answer sheets. A copy of the master "as given" examination with answer key was given to the Reactor Supervisor for his formal review.
The facility's written examination comments and the NRC's resolution to those comments are found in Enclosure 2.
All candidates passed the written examination.
4.
Operating Tests:
Operating tests were administered on September 14 and 15, 1993 to two R0, one SROI and one SROU candidates. There were no generic deficiencies identified by the examiner.
All candidates passed the operating tests.
5.
Exit Meeting:
Personnel attending:
Dr. John Bernard, Director of Reactor Operations Mr. Edward S. Lau, Asst. Superintendent for Engineering Mr. Patrick Isaac, NRC The exit meeting was conducted on September 15, 1993. The facility examination comments were discussed as noted in Enclosure 2.
Dr. Bernard commented on what he thought was a very well written exam and the professional manner in which NRC conducted the operator licensing examination.
There were no generic concerns raised by the examiner.
4 i
ENCLOSURE 2 NRC RESOLUTIONS - WRITTEN EXAMINATION SECTION A OVEST10N B.008 Which ONE of the following actions is required in the event of a large tritiated heavy water spill?
a.
Initiate a major scram.
b.
Close the dampers thus securing the ventilation system.
c.
Evacuate the NW12 building by initiating a fire alarm.
i d.
Have all personnel in the affected area don respirators.
ANSWER B.008 b.
FACILITY COMMENT B.008 Suggest question be deleted, as none of the four choices provided corresponds to correct procedure for immediate action (although #d is appropriate for a follow-up action). When the reactor is operating, required "Immediate Actions" (2), (3), & (7) for Abnormal Operating Procedure PM 5.8.16 (Spill of Heavy Water) are to " Scram the reactor (minor)," " Building ventilation must be maintained at all times," and " Evacuate non-essential personnel from the reactor containment building..." (not NW12 building). The answer specified in MIT Exam Bank #20 (on which this modified question was based), where securing the containment building ventilation was given as the correct one, needs to be revised.
NRC RESOLUTION B.008 The staff agrees with your comment and the question will be deleted.
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QUESTION B.018 The reactor was operated at half-power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, then subsequently shutdown during experiment data acquisition and analysis.
The reactor was attended during this 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period. The reactor is now to be started up and operated at full-power.
Which ONE of the following Startup Checklists is required to be performed for this reactor startup?
a.
Non-Routine Reactor Startup.
b.
Restart Following an Unanticipated or a Brief-Duration Shutdown.
c.
Two Loop Startup.
d.
Two Loop Startup, Shutdown less than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
ANSWER B.018 C.
FACILITY COMMFNT B.018 I
Suggest either answer #b or #c be accepted, because the question does 1
not specify whether the initial startup checklist performed was for " full" or-I
" half-power" mode of operation.
NRC RESOLUTION B.018 The staff agrees with your comment. The answer key has been corrected to reflect (b) and (c) as acceptable answers.
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'j ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Mass. Inst. of Tech.
REACTOR TYPE:
MITR-II i
DATE ADMINISTERED:2))Ejl3
~{
l REGION:
J l
CANDIDATE:
.i i
INSTRUCTIONS TO CANDIDATE:
i i
j Answers are to be written on the answer sheets provided.. Attach all answer i
sheets tc the examination. Points for each question are indicated in parentheses i
for each question. A 70% in each section is required to pass the examination.
Examinations will be picked up three (3) hours after the examination starts.
j
% OF r
CATEGORY % OF CANDIDATE'S CATEGORY j
VALUE TOTAL SCORE VALUE CATEGORY i
E 20.00 33.90 A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING-CHARACTERISTICS i
19.00 32.20 B.
NORMAL AND EMERGENCY OPERATING 4
' PROCEDURES AND RADIOLOGICAL CONTROLS a
20.00 33.90 C.
PLANT AND RADIATION MONITORING l
SYSTEMS
.i i
59.00 TOTALS i
FINAL GRADE
-t All work done on this examination is my own.
I.have neither given nor i
received aid.
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Candidate's Signature 4
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A.
RX THEORY, THERM 0 & FAC OP CHARS Page 2 i
ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
1 MULTIPLE CH0 ICE I
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 i
l 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
(***** END OF CATEGORY A *****)
i
)
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 3 i
ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE P
001 a
b c
d 002 a
b c
d 003 a
b c
d 004 a
b c
d f
f 005 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d i
009 a
b c
d 010 a
b c
d 011 a
b c
d i
012 a
b c
d 013 a
b c
d i
014 a
b c
d f
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 i
020 a
b c
d P
i t
I i
i
(***** END OF CATEGORY B *****)
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C.
PLANT AND RAD MONITORING SYSTEMS Page 4 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a
b c
d
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i 002 a
b c
d 003 a
b c
d 004 a
b c
d i
005 a
b c
d 1
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 I
011 a
b c
d l
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 t
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
7
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must 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. This must be done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. Print your name in the upper right-hand corner of each answer sheet.
- 8. Partial credit will NOT be given on multiple choice questions.
- 9. If the intent of a question is unclear, ask questions of the examiner only.
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- 10. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
- 11. To pass the examination, you must achieve at least 70% in each category.
- 12. There is a time limit of (3) hours for completion of the examination.
I (or some other time if less than the full examination is taken.)
- 13. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.
If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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RX THEORY, THERM 0 & FAC OP CHARS Page 7 QUESTION: 001 (1.00)
With the reactor on a constant positive period, which ONE of the following power changes will take the SHORTEST time?
a.
5% power - from 1% to 6% power.
b.
10% power - from 10% to 20% power.
t c.
15% power - from 20% to 35% power.
~
d.
20% power - from 40% to 60% power.
QUESTION: 002 (1.00)
Which ONE of the following describe the reactivity effect(s) that would occur if heavy water leaks from the reflector into the core periphery and into the core proper?
a.
Only negative reactivity is added.
b.
Only positive reactivity is added.
c.
First negative then strongly positive reactivity is added.
d.
First positive then strongly negative reactivity is added.
i QUESTION: 003 (1.00) t As primary coolant temperature increases, control rod worth:
a.
decreases due to lower reflector efficiency.
1 b.
decreases due to higher neutron absorption in the moderator.
c.
increases due to the increase in thermal diffusion length.
d.
remains the same due to constant poison cross-section of the control rods.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 8 QUESTION: 004 (1.00)
Which ONE of the following factors is the most significant in determining the differential worth of a control rod?
e a.
The rod speed.
b.
Reactor power.
c.
The flux shape.
d.
The amount of fuel in the core.
1 QUESTION: 005 (1.00)
The major source of neutrons used for normal / routine startups of the MITR-II is from the:
a.
Alpha decay of Uranium 238.
b.
Antimony-Beryllium (Sb-Be) source.
c.
Plutonium-Beryllium (Pu-Be) source.
l d.
Photo-neutrons produced by interaction of gamma rays with heavy water.
i QUESTION: 006 (1.00)
Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected stable neutron count rate would be?
a.
125 N/sec
{
b.
250 N/sec c.
400 N/sec t
d.
500 N/sec P
{
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A.
RX THEORY, THERM 0 & FAC OP CHARS Page 9 i
QUESTION: 007 (1.00)
With a 30 second period, power would double in approximately:
a.
15 seconds b.
21 seconds c.
30 seconds d.
60 seconds QUESTION: 008 (l 00)
Which ONE of the following describes how delayed neutrons affect control of the reactor?
a.
More delayed neutrons are produced than prompt neutrons resulting in a longer time to reach a stable subcritical countrate.
b.
Delayed neutrons are born at higher energies than prompt neutrons resulting in a shorter reactor period from increased leakage.
c.
Delayed neutrons take longer to thermalize than prompt neutrons resulting in a longer reactor period.
d.
Delayed neutrons increase the average neutron lifetime resulting in a longer reactor period.
QUESTION: 009 (1.00)
A source of delayed neutrons is from:
a.
gamma interactions with structural materials.
b.
decay of fission products.
c.
alpha interactions with the reflector.
d.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 10 4
QUESTION: 010 (1.00)
Which ONE of the following describes the reason for the constant rate of power change several minutes after a reactor scram from full power?
a.
The decay of the longer-lived delayed neutron precursors.
b.
The decay of the shorter-lived delayed neutron precursors.
c.
The mean average decay of the delayed neutron precursors.
d.
The decay of fission product gammas producing photoneutrons.
QUESTION: 011 (1.00)
After a week of full power operation, Xenon will reach its peak l
following shutdown in approximately:
a.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> b.
9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> i
c.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> d.
40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> QUESTION: 012 (1.00) i Which ONE of the following is the reason why it takes approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of constant power operation before thermal equilibrium is attained in the MITR-II reactor?
i a.
The time required for equilibrium Xenon and Samarium conditions to be established.
b.
The time required for the large volume of the Deuterium tank to heat up.
c.
The shield coolant system has a small flowrate to accomplish adequate mixing before temperature is uniformly stabilized.
d.
The graphite reflector has a large heat capacity and is slow to reach equilibrium temperature distribution.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 11 QUESTION: 013 (1.00)
Excess reactivity is the amount of reactivity:
a.
associated with samples.
b.
needed to achieve prompt criticality.
c.
available above that which is required to make the reactor subcritical.
d.
available above that which is required to keep the reactor critical.
QUESTION: 014 (1.00) t The term " prompt jump" refers to:
a.
the instantaneous change in power due to raising a control rod.
b.
a reactor which has attained criticality on prompt neutrons alone.
a reactor which is critical using both prompt and delayed c.
neutrons.
d.
a negative reactivity insertion which is less than Beta-effective.
QUESTION: 015 (1.00)
A subcritical reactor is being started up. A control rod (shim blade) is raised in four equal steps (inches). Which statement most accurately describes the expected reactor response?
a.
Power increases by the same amount for each withdrawal.
b.
Each withdrawal will add the same amount of reactivity.
c.
The time for power to stabilize after each successive withdrawal increases.
d.
A lower critical rod height is attained by decreasing the time intervals between withdrawals.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A.
RX THEORY, THERM 0 & FAC OP CHARS Page 12 i
QUESTION: 016 (1.00)
The inherent safety feature provided by the temperature coefficient of reactivity is described by:
a.
its negative value causes positive reactivity to be added as moderator temperature increases.
b.
its negative value causes negative reactivity to be added as moderator temperature increases.
c.
its positive value causes positive reactivity to be added as moderator temperature increases.
d.
its positive value causes negative reactivity to be added as moderator temperature increases.
QUESTION: 017 (1.00)
Which ONE of the following describe the difference between a moderator and reflector?
a.
A reflector increases the fast non-leakage factor and a moderator increases the thermal utilization factor.
b.
A reflector increases the neutron production factor and a moderator increases the fast fission factor.
c.
A reflector decreases the thermal utilization factor and a moderator increases the fast fission factor.
d.
A reflector decreases the neutron production factor.and a moderator decreases the fast non-leakage factor, P
f l
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 13 QUESTION: 018 (1.00)
During the neutron cycle from one generation tr. the next, several processes occur that may increase or decrease the available number of neutrons.
SELECT from the following the six-factor formula term that describes an INCREASE in the number of neutrons during the cycle.
a.
Thermal utilization factor.
b.
Resonance escape probability.
c.
Thermal non-leakage probability.
d.
Fast fission factor.
QUESTION: 019 (1.00)
The reactor has just been started up, power raised to 5 megawatts and is in auto control.
Which ONE of the following is the expected response of the regulating rod for the next half hour?
a.
Drive in b.
Drive out f
c.
Not move d.
Drive out then back in I
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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4 A.
RX THEORY, THERM 0 & FAC OP CHARS Page 14 QUESTION: 020 (1.00)
A control rod is withdrawn until 100 millibeta is added to a critical reactor.
Which ONE of the following will be the expected reactor period imediately after rod motion stops? (Assume delayed neutron. decay constant is 0.1 s-1) a.
30 second b.
45 second c.
90 second 1
d.
110 second I
(***** END OF CATEGORY A *****)
1
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 15 i
QUESTION: 001 (1.00)
The maximum reactivity worth of a single movable experiment allowed by Technical Specifications is:
a.
0.2 % Delta K/K b.
0.5 % Delta K/K c.
1.0 % Delta K/K d.
1.8 % Delta K/K i
QUESTION: 002 (1.00) l The reactor is defined by Technical Specifications as being " Shutdown" when:
a.
the fuel in the reactor core is removed.
b.
all of the control blades are fully inserted.
c.
reactor period is negative and power is less than 10 Watts, d.
no maintenance involving fuel, experiments, core structure, or control blades is in progress.
QUESTION: 003 (1.00)
The maximum power level allowed without primary coolant pumps operating is:
a.
100 Watts b.
10 kW c.
100 kW d.
I mW
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 16 QUESTION: 004 (1.00)
The basis for the D2 concentration limit in the Helium gas cover blanket
[
for the D20 reflector system is to:
a.
minimize personnel radiation exposure.
b.
limit the disassociation of D20 in the reflector.
c.
minimize the contamination of the Helium cover gas.
d.
prevent a flammable concentration of D2 gas in the Helium blanket.
QUESTION: 005 (1.00)
The Neutron level channel instruments are required to be tested:
a.
- daily, b.
weekly.
c.
quarteriy.
d.
before startup if the reactor has been shutdown more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
t QUESTION: 006 (1.00)
The MINIMUM shift staffing, in addition to the Radiation Protection Officer or alternate being onsite or on call, required by Technical Specifications when the reactor is NOT " Shutdown" is:
a.
Two persons onsite, at least one of which is a licensed senior operator.
b.
Two licensed operators onsite, one of which is required to be in the control room.
c.
Two licensed operators onsite, at least one of which is a licensed senior operator and one of which is in the control room.
d.
Three persons onsite, two of which are licensed operators, and one licensed operator must be in the control room.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
t B.
NORMAL /EMERG PROCEDURES & RAD CON Page 17
^
t QUESTION: 007 (1.00)
Which ONE of the following is the HIGHEST exposure an operator could receive working in a posted Radiation Area for I hour?
a.
5 arem b.
25 mrem c.
90 mrem i
d.
125 mrem QUESTION: 008 (1.00)
DELETED Which ONE of the following actions is required in the event of a large tritiated heavy water spill?
a.
Initiate a major scram.
b.
Close the dampers thus securing the ventilation system.
c.
Evacuate the NW12 building by initiating a fire alarm.
d.
Have all personnel in the affected area don respirators.
QUESTION: 009 (1.00)
An Experimenter that is wearing a BLUE Film Badge may:
a.
operate the experiment unassisted.
b.
escort visitors through the reactor building.
c.
perform radiological operations only under direct supervision.
d.
approve changes to experimental procedures that do not affect radiological operations.
(** "' CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 18 i
QUESTION: 010 (1.00)
A small radioactive source'is to be stored in the reactor building.
The source is estimated to contain 2 curies and emit a 1.33 Mev gamma.
Assuming no shielding was to be used, a Radiation Area barrier would have to be erected from the source at a distance of approximately:
a.
6 inches b.
12 inches t
c.
21 inches d.
4 feet QUESTION: 311 (1.00)
The type of radiation hazard associated with tritiated D20 is:
a.
Beta b.
Alpha c.
Gamma d.
Neutron QUESTION: 012 (1.00)
An emergency shutdown was initiated from the control room console.
Power failed to decrease after the minor scram pushhatton was depressed.
Which ONE of the following actions should be taken first?
4 a.
Initiate a major scram.
b.
Insert the control rods.
c.
Dump the reflector.
d.
Evacuate the reactor building.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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4 B.
NORMAL /EMERG PROCEDURES & RAD CON Page 19 QUESTION: 013 (1.00)
Which ONE of the following is the assembly area in the event of a NW12 fire alarm?
a.
Reception Area, b.
NW13 Machine Shop.
c.
Far side of Albany Street.
+
d.
Campus Police Headquarters.
L QUESTION: 014 (1.00)
The Emergency Exposure guideline for establishing the nuclear safety of the reactor is:
a.
3 Rem b.
10 Rem c.
25 Rem d.
100 Rem
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 20 i
QUESTION: 015 (1.00)
Which ONE of the following describes the responsibility of a licensed j
operator regarding the Equipment Tagout procedure, (PM 1.14.3)?
a.
Any member of the NRL/RPO staff including electronics and maintenance may post a warning tag provided prior verbal permission is obtained from the on-duty console operator.
b.
After the individual has completed the posting of the warning tag a licensed operator must independently verify the posting is correct.
c.
If there is any doubt as to whether a warning tag should be removed the operator-in-charge must be consulted for resolution.
d.
The operator-in-charge must ensure that any system that could jeopardize equipment safety in addition to being tagged out is also locked out.
QUESTION: 016 (1.00)
Before any change is made in the core configuration (refueling), the proposed change must be reviewed and approved by:
a.
the Operator-in-charge and a Senior Reactor Operator.
b.
a Senior Reactor Operator and the Reactor Superintendent.
i c.
the MIT Reactor Safeguards Comittee and the Reactor Superintendent.
d.
the MIT Reactor Safeguards Comittee and the Director of Reactor Operations.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 21 QUESTION: 017 (1.00)
During continuous power operation with the automatic control system it may be necessary for the operator to reshim the control blades to maintain the regulating rod within its useful range.
Which ONE of the following describes the requiremer.ts associated with this reshim of control blades?
a.
Reactor power is to be maintained within 2.5% of the desired level while reshimming.
b.
All shim blades must be maintained within 2.5 inches of eacn other during the reshim and within 1.0 inch following the reshim.
c.
The first motion of any control absorber during a reshim should be inward so as to lower reactor power.
d.
The duty supervisor must approve all reshims prior to performance.
QUESTION: 018 (1.00)
The reactor was operated at half-power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, then subsequently shutdown during experiment data acquisition and analysis.
The reactor was attended during this 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period. The reactor is now to be started up and operated at full-power.
Which ONE of the following Startup Checklists is required to be performed for this reactor startup?
a.
Non-Routine Reactor Startup.
b.
Restart following an Unanticipated or a Brief-Duration Shutdown.
c.
Two Loop Startup, d.
Two Loop Starup, Shutdown less than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
i
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
4 B.
NORMAL /EMERG PRDCEDURES & RAD CON Page 22 QUESTION: 019 (1.00)
The key switch bypasses on the scam panel:
a.
may only be used for maintenance or testing during reactor shutdown.
b.
must be individually approved before use by the Duty-Shift-Supervisor or Reactor Supervisor, c.
if used as part of a startup procedure checklist don't need to be recorded on the bypass log sheet.
d.
must be checked by TWO responsible persons immediately after use ano recorded on the bypass log sheet.
QUESTION: 020 (1.00)
In response to a " COOLING TOWER FANS OFF" alarm an attempt to restart the fans was unsuccessful. With the reactor operating at 4 MW the immediate action required is to:
a.
perform a minor scram.
b.
perform a major scram.
c.
depress the "ALL RODS IN" pushbutton and lower power to 1 MW or less.
d.
shut the secondary blowdown valves and monitor primary coolant fl ow.
4
(***** END OF CATEGORY B *****)
i C.
PLANT AND RAD MONITORING SYSTEMS Page 23 QUESTION: 001 (1.00)
Which ONE of the following alarm conditions will result in an automatic scram?
l a.
High Level Emergency Power Channel.
b.
High Temperature Reflector Outlet.
t 1
c.
Low Level Shield Coolant Storage Tank.
d.
Low Voltage Chamber Power Supply.
I t
QUESTION: 002 (1.00)
The Emergency Power Distribution System can supply power to the:
f a.
NIS Channel 8.
b.
Recombiner Heaters.
c.
TV and Intercom System.
d.
Main Personnel Lock Hydraulic Pump.
i QUESTION: 003 (1.00)
Which ONE of the following describes decay heat removal capability while on Emergency Power?
a.
Primary coolant system auxiliary pump MM2 can be restarted after resetting the low-voltage protection.
b.
Primary coolant system pump MMI can be restarted after i
resetting the low-voltage protection.
c.
Standby Transfer Pump DM-2 will automatically start on high j
temperature.
d.
Natural circulation provides cooling since pumping power is not available.
i t
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
4
e C.
PLANT AND RAD MONITORING SYSTEMS Page 24 l
t QUESTION: 004 (1.00)
Which ONE of the following automatic actions will occur, if the on-line liquid waste storage tank reaches a high level alarm condition?
a.
City water inlet solenoid valve closes, b.
Waste tank vent valve closes.
c.
On-line sewer pump trips.
3 d.
Sump pump trips.
QUESTION: 005 (1.00)
Blowdown of the cooling tower basins is secured when the reactor is shutdown because:
a.
secondary water monitors can no longer detect in-leakage, b.
the automatic makeup system is secured on reactor shutdown.
c.
the efficiency of blowdown decreases without secondary flow.
t d.
it is no longer required when cooling tower spray is secured.
QUESTION: 006 (1.00)
If secondary water tritium concentration exceeds 1 micro Curie / liter then which ONE of the following actions must be taken?
a.
The charcoal filters in the pressure relief system must be placed on-line.
b.
The D20 reflector heat exchanger must be sampled for activity to detect leakage.
c.
Secondary system discharge must be lined up to the sanitary sewer.
l d.
The cooling tower spray must be shut down.
i i
i 3
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
i C.
PLANT AND RAD MONITORING SYSTEMS Page 25 i
QUESTION: 007 (1.00)
Which ONE of the following describes the purpose for the subcritical interlock?
a.
To prevent withdrawing more than one shim blade at a time.
b.
To allow for perforraance of individual shim blade drop time testing.
c.
To aid in maintaining the shim blade bank at a uniform height during the final approach to criticality.
d.
To ensure the nuclear instruments are on scale prior to allowing shim blade withdrawal.
QUESTION: 008 (1.00)
Which ONE of the following describes en automatic response of the ventilation system?
If temperature of the outside air drops below freezing the a.
intake fan will trip.
b.
If the auxiliary intake damper fails to close within ten seconds of a trip signal, then the main damper will close.
c.
If the main intake damper fails to close within ten seconds of a trip signal, then the intake fan will trip.
d.
In the " weekend-open" position, if activity is detected by the plenum monitors, the inlet dampers and intake fan will trip.
\\
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
i
C.
PLANT AND RAD MONITORING SYSTEMS Page 26 QUESTION: 009 (1.00)
The reason for specifying that four days elapse before removing a fuel element from the reactor that has operated above 100 kW is to:
a.
prevent the fuel element from melting.
b.
limit the radiation exposure of personnel during refueling.
c.
ensure the reactivity of the fuel element is within the Spent Fuel Storage rack limits.
4 d.
allow for sufficient time for the buildup of poisons to satisfy shutdown margin requirements.
QUESTION: 010 (1.00)
During refueling of the core the indicated neutron level has increased by a factor of 2.5.
Which ONE of the following operator actions is required to be taken?
a.
Evacuate personnel from the reactor top.
b.
Dump the reflector, if not already dumped.
c.
Notify Radiation Protection to perform a radiation survey of the reactor top area.
d.
Notify personnel on the reactor top to insert a dummy element in place of the fuel element just removed.
+
QUESTION: 011 (1.00) t The cycle time for the H2O medical shutter is:
a.
I minute to open and 3 minutes to close.
I b.
3 minutes to open and I minute to close.
c.
3 minutes to open and 5 minutes to close.
d.
5 minutes to open and 3 minutes to close.
I
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 27 QUESTION: 012 (1.00)
A CO2 purge is maintained 'to the Vertical Thimbles during reactor operation. Which ONE of the following is the reason for maintaining this purge?
a.
To maintain a positive pressure in the thimbles to prevent filling with water in the event of a seal leak.
b.
To limit the amount of tritium produced during reactor operation.
c.
To provide cooling to the samples during irradiation.
d.
To reduce the production of Argon-41 and prevent formation of Nitric acid.
QUESTION: 013 (1.00)
If the radiation monitor in the off-gas system detects abnormal radiation levels, the pool ventilation will be automatically secured.
Protection from overpressure of the coolant system in this condition is provided by:
a.
a Vacuum breaker on suction side of the off-gas blower.
b.
a Blowout patch on the coolant storage tank.
c.
the sample line connections between the isolation valves.
d.
a relief valve on the off-gas discharge piping which relieves to the main ventilation exhaust plenum.
QUESTION: 014 (1.00)
The type of detector used in the power range for Channel 2 (Startup, Log Count-Rate) is a:
a.
fission chamber.
b.
compensated ion chamber.
c.
uncompensated ion chamber.
d.
boron lined scintillation detector.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 28 t
QUESTION: 015 (1.00)
Which ONE of the following Nuclear Instrumentation Channels provide input to the automatic reactor control system?
a.
Channel 3 b.
Channel 5 c.
Channel 7 d.
Channel 9 QUESTION: 016 (1.00)
Which ONE of the following radiation monitors can be used for estimating reactor power?
a.
Argon-41 b.
Reactor Top r
c.
Medical Room d.
Linear N-16 i
QUESTION: 017 (1.00)
Which ONE of the following describes the expected response in the event both door gaskets are deflated simultaneously on the Basement Air Lock?
a.
Campus Patrol receives an " INTRUSION" alarm.
l b.
The reactor will automatically scram.
c.
A " LOW PRESSURE AIR" alarm is received in the control room and reception area.
d.
The Backup bottle of compressed air automatically supplies the door gaskets.
l r
t
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
i
C.
PLANT AND RAD MONITORING SYSTEMS Page 29 l
^
QUESTION: 018 (1.00)
If the normal heat removal path is NOT available for the Shutdown Cooling System, alternative cooling can be obtained from the:
a.
fire protection system.
b.
secondary cooling system.
c.
city water supply to HE-2.
d.
H2O medical shutter cooling system.
QUESTION: 019 (1.00)
Which ONE of the following describes the operator action (s) required to determine the location of a leak in the D20 Leak Detection System?
a.
TV camera displays are vie n;d to check areas for leaks on receipt of a sump level detector alarm.
b.
The neon lamp that is illuminated on the leak alarm console is compared to the leak tape location list.
1 c.
The neon lamp that is illuminated on the leak alarm console is extinguished by depressing the pushbuttons above the light one at a time, then referring to the leak tape location list.
j i
d.
With more than one leak tape in the same channel shorted then an operator must be dispatched to the affected areas, since the alarm can not be cleared until the leak tapes are repl, aced.
l
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 30 g
QUESTION: 020 (1.00)
Which ONE of the following actions should be performed to determine if the ion column resin is exhausted?
t a.
Measure the differential pressure drop across the ion column, if normal then the ion column resin is not exhausted.
b.
Bypass the ion column flow and if the primary coolant i
conductance increases then the f on column is not exhausted.
c.
Measure the inlet and outlet ior column conductivities, if both are increasing then the ion coltmn is exhausted.
d.
Determine if the temperature of the ion column has reached 53 degrees-C, if so then the ion column is exhausted.
i r
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 31 ANSWER:
001 (1.00)
D
REFERENCE:
MIT Reactor Physics Notes, Reactor Period, Section (g); P(t)-P(o)e*t/T ANSWER:
002 (1.00)
D
REFERENCE:
1 RSM 10.9.2 i
i ANSWER:
003 (1.00)
C
REFERENCE:
MIT Reactor Physics Notes, Reactivity Feedback, Section 5.
ANSWER:
004 (1.00)
C
REFERENCE:
MIT Reactor Physics Notes, Reactivity feedback, p 10.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
t
.a a-
- =
A.
RX THEORY, THERMO & FAC OP CHARS Page 32 l
i ANSWER:
005 (1.00)
D
}
REFERENCE:
MIT Reactor Physics Notes, Reactor Startup, p 7.
i ANSWER:
006 (1.00)
I D
REFERENCE:
MIT Reactor Physics Notes, Reactor Startup, p 8,9; CR-S/(1-K)
ANSWER:
007 (1.00)
B
REFERENCE:
i i
Glasstone, Nuclear Reactor Engineering, Chapter 5, Section 5.18; MIT Reactor Physics Notes, Reactor Kinetics, Section 6 a Calculations.
Equation Sheet:
i P-PoE*t/T P-2Po E*t/30 Ln2-t/30 0.693-t/30 t-20.8 ANSWER:
008 (1.00)
D 1
l
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
i
A.
RX THEORY, THERMO & FAC OP CHARS Page 33
REFERENCE:
MIT Reactor Physics Notes, Reactor Kinetics, p 8,9.
ANSWER:
009 (1.00)
B
REFERENCE:
MIT Reactor Physics Notes, Reactor Kinetics, p 2.
ANSWER:
010 (1.00)
A
REFERENCE:
Glasstone and Sesonske, Nuclear Reactor Engineering, Chapter 5, Section 5.47, p 247 ANSWER:
011 (1.00)
A
REFERENCE:
MIT Reactor Physics Notes, Reactivity Feedback and measurement of a Xenon Transient, p 28; RSM 10.6 ANSWER:
012 (1.00)
D I
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
)
A.
RX THEORY THERM 0 & FAC OP CHARS Page 34-I
REFERENCE:
RSM 6.4 i
ANSWER:
013 (1.00) i D
REFEP,ENCE:
l Glasstone and Sesonske, Nuclear Reactor Engineering, Chapter 5, Section t
5.114, p 272; MIT Exam Bank #48.
1 ANSWER:
014 (1.00)
A
REFERENCE:
i MIT Reactor Physics Notes, Reactivity Feedback, p 4.
f ANSWER:
015 (1.00)
C
REFERENCE:
MIT Reactor Physics Notes, Reactor Startup and Subcritical Multiplication, p 10.
+
ANSWER:
016 (1.00)
B
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
i i
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 35
REFERENCE:
Glasstone, Nuclear Reactor Engineering, Chapter 5, Section 5.91; MIT Reactor Physics Notes, Reactivity Feedback, p 18.
ANSWER:
017 (1.00)
A
REFERENCE:
Glasstone & Sesonke, Nuclear Reactor Engineering, Chapter 1, Section 1.51 & l.52 ANSWER:
018 (1.00)
D
REFERENCE:
MIT Reactor Physics Notes, Reactor Startup and Subtritical Multiplication, p 4.
i ANSWER:
019 (1.00)
B
REFERENCE:
HIT Reactor Physics Notes, Reactivity Feedback and Measurement of a Xenon Transient; Similar to MIT Exam Bank #A-43.
ANSWER:
020 (1.00)
C
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERMO & FAC OP CHARS Page 36 I
r
REFERENCE:
MIT Exam Bank #A-53; T - (B-p)/(lambda x p); T- (1-0.1)/(0.1x0.1); T-90s f
I t
1 i
e i
i l
r
(***** END OF CATEGORY A *****)
o B.
NOPJ4AL/EMERG PROCEDURES & RAD CON Page 37 t
t h
ANSWER:
001 (1.00)
A
REFERENCE:
MIT TS 6.1.1 t
ANSWER:
002 (1.00)
B
REFERENCE:
TS 1.2, p 1-1.
ANSWER:
003 (1.00)
C l
REFERENCE:
TS 2.2 ANSWER:
004 (1.00)
D
REFERENCE:
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
t, 8.
NORMAL /EMERG PROCEDURES & RAD CON Page 38 ANSWER:
005 (1.00)
D
REFERENCE:
TS 4.3.1.d ANSWER:
006 (1.00)
C
REFERENCE:
TS 7.2 ANSWER:
007 (1.00)
C
REFERENCE:
?
ANSWER:
008 (1.00)
DELETED B
REFERENCE:
MIT Exam Bank #B-20 (modified); RRP0 memorandum i
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
'r B.
NORMAL /EMERG PROCED' RES & RAD CON Page 39 J
i ANSWER:
009 (1.00)
C
REFERENCE:
PM 1.12, p 1.
ANSWER:
010 (1.00)
C
REFERENCE:
MIT Exam Bank #B-8 (modified); Glasstone & Sesonske, 9.41, p 525.
DR-6CE/(f)(f) 6(2)(1.33)/x2, x2 - 3.19, x - 1.79 feet ANSWER:
011 (1.00)
A
REFERENCE:
Nuclear Reactor Engineering, Glasstone & Sesonske, Section 2.85, p 60; MIT Exam Bank, #C-4 (modified).
ANSWER:
012 (1.00)
C
REFERENCE:
MIT PM 2.5, Section 2.5.2(2), p 2.
(***** CATEGORY B CONTINUED ON HEXT PAGE *****)
L
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 40 ANSWER:
013 (1.00)
C
REFERENCE:
PH 4.4.4.11-1, p 6.
ANSWER:
014 (1.00)
C
REFERENCE:
PH 4.7.5, Table 4.7.5.1-1, p 2.
ANSWER:
015 (1.00)
A
REFERENCE:
PM 1.14.3, p 9.
ANSWER:
016 (1.00)
B
REFERENCE:
PH 1.15, p 1.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NORMAL /EMERG' PROCEDURES & RAD CON Page 41 1
ANSWER:
017 (1.00)
C
REFERENCE:
i PM 2.4, Step 3(a), p 3.
ANSWER:
01B (1.00)
C,B
REFERENCE:
PM 2.2, Step 2.2.1.2(1), p 5.
ANSWER:
019 (1.00)
C
REFERENCE:
PM 1.9 ANSWER:
020 (1.00)
C
REFERENCE:
PM 5.4.12
-(***** END OF CATEGORY B *****)
P-t C.
PLANT AND RAD MONITORING SYSTEMS Page 42 i
i ANSWER:
001 (1.00)
D
REFERENCE:
RSM-9.3 to 9.5 5
ANSWER:
002 (1.00)
C
REFERENCE:
RSM-8.37, Table 8-8B i.
t ANSWER:
003 (1.00)
A
REFERENCE:
RSM-8.37 i
ANSWER:
004 (1.00)
A
REFERENCE:
PM 3.6 SAR Rev #36, SAR Section 12.1.1.2.
f r
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 43 l
ANSWER:
005 (1.00)
A
REFERENCE:
RSM-7.6, Section 7.4.1 ANSWER:
006 (1.00)
O
REFERENCE:
RSH-7.6, section 7.4.1; TS 3.8 ANSWER:
007 (1.00) i C
REFERENCE:
RSM-4.3 1
ANSWER:
008 (1.00)
A
REFERENCE:
RSM-8.12
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 44 ANSWER:
009 (1.00)
A r
REFERENCE:
TS 3.10 Basis, p 3-39 ANSWER:
010 (1.00)
B
REFERENCE:
PM 3.3.1.1, Step 39, p 3.
l ANSWER:
011 (1.00)
A
REFERENCE:
MIT Exam Bank # B-28.
ANSWER:
012 (1.00)
D
REFERENCE:
RSM-2.9, Section 2.4
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
o I
C.
PLANT AND RAD MONITORING SYSTEMS Page 45 l
9 ANSWER:
013 (1.00)
B
REFERENCE:
RSM-3.4, Section 3.2.5 ANSWER:
014 (1.00)
C
REFERENCE:
RSM-5.5, Section 5.3.1 I
ANSWER:
015 (1.00)
D
REFERENCE:
RSM-5.9, Section 5.6.3 r
l i
ANSWER:
016 (1.00)
D
REFERENCE:
RSM-5.1; -7.3
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
i
C.
PLANT AND RAD MONITORING SYSTEMS Page 46 ANSWER:
017 (1.00)
B
REFERENCE:
I RSM-8.10, Section 8.2.3 i
ANSWER:
018 (1.00)
C l
REFERENCE:
RSM-3.4, Section 3.2.6; PM 5.2.8, Step B.2 ANSWER:
019 (1.00)
C
REFERENCE:
RSM-3.9, Section 3.3.6 ANSWER:
020 (1.00)
C
REFERENCE:
PM 5.2.12, Step 7; RSM-6.1, Section 6.2.1 and Table 6.1 l
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
e a
A.
RX THEORY, THERMO & FAC OP CHARS Page 1 ANSWER KEY i
MULTIPLE CHOICE 001 0
002 D
003 C
004 C
005 0
006 0
007 B
r 008 D
009 B
010 A
011 A
012 0
013 0
014 A
015 C
016 B
017 A
018 0
019 8
020 C
(***** END OF CATEGORY A *****)
l
.,, o
'B.'
NORMAL /EMERG PROCEDURES & RAD CON Page 2 ANSWER KEY i
t r
MULTIPLE CHOICE 001 A
002 B
003 C
004 D
005 0
}
006 C
007 C
008 B
DELETED 009 C
010 C
011 A
012 C
013 C
014 C
015 A
016 B
017 C
018 C or B 019 C
020 C
p
(***** END OF CATEGORY B *****)
s '.
C.
PLANT AND RAD MONITORING SYSTEMS Page 3 ANSWER KEY HULTIPLE CHOICE 001 D
002 C
003 A
004 A
005 A
006 0
007 C
008 A
009 A
010 B
011 A
012 0
013 B
014 C
l 015 D
L 016 D
017 B
018 C
019 C
020 C
i i
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
i