ML20211D698
| ML20211D698 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 09/17/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211D683 | List: |
| References | |
| 50-002-OL-97-02, 50-2-OL-97-2, NUDOCS 9709290208 | |
| Download: ML20211D698 (34) | |
Text
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j I
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50/J2/OL 97 02 FACILITY DOCKET No.:
50-02 FACILITY LICENSE No.:
R 28 FACILITY:
University of Michigan EXAMINATION DATES:
August 18 19,1997 EXAMINER:
Patrick Isaac, Chief aminer fB 7
SUBMITTED BY:
c Patr%~lsaac,. Chief Examiner
'Da'te
SUMMARY
During the week of August 18,1997, the NRC administered Operator Licensing Examinations to two Senior Reactor Operator Upgrade (SROU) candidates and a retake to one Reactor Operator (RO) candidate.
One SROU candidate failed the examinations.
h ENCLOSURE 1 9709290208 970917 PDR ADOCK 05000007 V
-... _ -. -. _ -.. _,.. _... _ _ - _ _. ~ _ _ -..
__________._..m_.__..
1 2
REPORT DETAILS 1.
Examiners:
Patrick Isaac, Chief Eraminer 2.
Results:
RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall Written 1/0 N/A 1/0 Operating Tests N/A ili 111 Overall 1/0 ili 2/1 3.
Exit Meeting:
Personnel attending:
Mr. Bernard Ducamp, FNR Assistant Manager Patrick Isaac, Chief Examiner Following his review of the written examination, Mr. Ducamp requested that two correct answers be accepted for questions C.2 and C.12 of the written examination. The NRC examiner agreed with the request and the examination answer key was modified accordingly.
~
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY:
University of Michigan REACTOR TYPE:
POOL DATE ADMINISTERED:
1997/08/18 REGION:
lil CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach all answer sheets to the examination. Point values are indicated in parentheses for each question. A 70%
in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00
_LLI.
A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS
-.20.00 33.3 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00
. 33.3.
C.
FACILITY AND RADIATION MONITORING SYSTEMS 60.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 2 J
l l
A. RX THEORY. THERMO & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice) i If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 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 i
008 a b c d f
009 a b c d 010 a b c d 011 abcd 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
("*" END OF CATEGORY A ""*)
B. NC#uA1/FupRG PROCEDURES & RAD CON -
ANSWER SHEET Multiple Choice (Ci cle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 abcd 002 1 2
3 4
003 a b c d 004 a b c d __,
005 a b c d l
006 e b c d 007 a b c d 008 a b
c d
009 a b c - d 010 a b c d 011 abcd 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
(""* END OF CATEGORY B '"")
C. PLANT AND RAD MONITORING SYSTEMS i
ANSWER SHEET Multiple Choice (Circle or X your choice) if you change your answer, write your selection in the blank.
l l
MULTIPLE CHOlCE l
001 abcd 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 abcd 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
(*"" END OF_ CATEGORY C "*")
("""""_ END_ OF EXAMINATION """"")
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l
1 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 neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3.
Restroom trips are tc 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 and each answer sheet.
6.
Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7.
The point value for each question is indicated in [ brackets) after the question.
8.
If the intent of a quettion is unclear, ask questions of the examiner only.
9.
When turning in your examinatiuri, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.
10.
Ensure allinformation you wish to have evaluated as part of your answer is on your answer sheet.
Scrap paper will be disposed of immediately following the examination.
11.
To pass the examination you must achieve a grade of 70 percent or greater in each category.
12.
There is a time limit of three (3) hours for completion of the examination.
13.
When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is stillin progress, your license may be denied or revoked.
EQUATION SHEET 6 = th c, b T = til bH
S S
=
-p 1 - K,,,
0.1 seconds'2 A,ff
=
CR, ( 1 -K,f f,) = CR, ( 1 - K,f f,)
3,o,po73 CR (-p3) = CR,(-p,)
e u, A,,o g,
SUR = 2 6. 0 6 1.g 6 -0,
e rr, E"#
0 0
M=
=
1 - K,ff CR, 1
( 1 - K,,, )
T SDM =
p = p, e g
ett t'
(1~ }
T=-
P=
P' O-f 0*p
" n,~ **tt l',
5-0 sp,
7, s
0 0
ett efi e!!n g
0.693 (K,,f-1)
T* =
p*
X
,e r r DR =DR, e
- DR,d,# = DR d,#
y (C ~0)
IP:~0) 2 6CIE(n)
OR c p2
- Peak, Peak, I = I,e ""
? Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm 1 BTU l18 ft lbf
'F = 9/5 'C + 32 1 gal (H O) = f, ihm
'C = 5/9 (*F - 32) 2 cp = 1.0 BTU /hr/lbml*F c, = 1 callsec/gml'C
v Aar+N A R Theory. Thermo & Fac. Operating Characteristics QUESTION (A.1)
(1.0)
A mixed beta-gamma point source measures 200 mrem /hr at one foot and 0.1 mrem /hr at 20 feet. The beta cmission has an energy of 1.0 MeV. What is the fraction of botas in the source?
a.
10%
b.
20 %
c.
80 %
d.-
90 %
QUESTION (A.2)
[1.0)
An slement decays at a rate of 20% per day. Detenr.!rie ts half life.
a.
3 hr.
b.
75 hr.
c.
108 hr.
d.
158 hr.
QUESTION (A.3)
[1,0)
The reactor has scrammed following an extended period of operation at full power.
Which one of the following accounts for generation of a majority of the heat one (1) hour after the scram?
a.
Spontaneous fissions b.
Delayed neutron fissions c.
Alpha fission product decay d.
Beta fission product decay
v Section A R Theory. Thermo & Fac. Ooerating Characteristics QUESTION (A.4)
[1.0)
In a suberitical Rx, Keff is increased from 0.861 to 0.946. Which one of the following is the amount of reactivity th:t was added to the core?
a.
0.090 delta K/K b.
0.220 delta K/K c.
0.104 delta K/K d.
0.125 delta K/K QUESTION (A.5)
[1.0)
Which one of the following is a correct statement concerning the factors affecting control rod worth?
a.
With all other rods withdrawn, an inserted rod exhibits its minimum worth.
b.
As the temperature of the moderator increases, rod worth decreases, c.
As Rx power increases rod worth increases.
d.
With all other rods inserted, a withdrawn rod exhibits its greatest total worth.
QUESTION (A.6)
[1.0)
A reactor startup is in progress by withdrawing a control rod and then waiting until count rate stabilizes. The reactor is not critical. Assume that the control rod is being withdrawn in equal amounts each time and each
- control rod withdrawal adds equivalent amounts of reactivity.
Ccmpare two consecutive control rod withdrawals.
Time for power to stabilize will be equal for both withdrawals and the power increase will be the same a.
for both withdrawals.
b, The power increase will be the same for both withdrawals but the time for power to stabilize will be less for the second withdrawal.
- The power increase will be the same for both withdrawals but time for power to stabiliz6 will be longer c.
for the second withdrawal.
d.
The power increase will be larger for the second withdrawal and the time for power to stabilize will be longer for the second withdrawal.
l
~
Section A R Theory. Thermo & Fac. Ooeratino Characteristics QUESTION (A.7)
[1.0)
Tws critical reactors are identical with the exception that Reactor 1 has a beta fraction of.0072 and Reactor 2 has a beta fraction of 0.0060. An equal amount of positive reactivity is inserted into both reactors.
Which one of the following will be the response of Reactor 27 a.
The resulting power level will be lower.
b.
The resulting power level will be higher, c.
The resulting period will be shorter.
d.
The resulting period will be moger.
QUESTION (A.8)
(1.0)
Assume that reactor power is 50% and equilibrium Xenon is attained. Reactor power is then increased to 100%. Which one of the following correctly describes the new equilibrium Xenon value?
a.
The 100% equilibrium xenon is half the 50% value b.
The 100% equilibilum xenon is equal to the 50% value.
c.
The 100% equilibrium xenon is higher than the 50% value but not twice as high.
d.
The 100% equilibrium xenon is twice as high as the 50% value.
QUESTION (A.9)
[1.0)
Which of the following six factor formula terms are affected most by temperature?
a.
Therrnal utilization and resonance escape probability b.
Fast fission factor and resonance escape probability c.
Fast fission factor and reproduction factor d.
Reproduction factor ar:d thermal utilization i
Section A R Theory Thermo & Fac. Ooerating Characteristics QUESTION (A.10)
[1.0)
Which one of the following describes how doubling the time a target nuclide is irradiated affects the activity leve.
c.
Less than doubles the activity.
b.
More than doubles the activity, c
Exactly doubles the activity.
d.
Increases the activity by a factor of e.
QUESTION (A.11)
[1.0)
If reactor power is increasing by a decade every minute, it has a period of; a
13 sec b.
26 sec c.
52 sec d.
65 sec QUESTION (A.12)
[1.0)
Which one of the following is the primary reason a neutron source is installed in the core?
a.
To allow for testing and irradiation of experiments when the reactor is shutdown.
b, To supply the neutrons required to start the chain reaction for subsequent reactor startups.
c.
To provide a neutron level high enough to be monitored for a controlled reactor startup.
d.
To increase the excess reactivity of the reactor which reduces the frequency for refueling.
Section A R Theory. Therrno & Fac. Ooerating Characteristics QUESTION (A.13)
[1.0)
If Keff equals 1.0, how much ienctivity must be added to make the reactor prompt critical?
a.
The beta fraction.
b.
The amount to make Keff equal to 1.1.
c.
The amount to make the reactor period infinite, d.
The amount needed to increase the mean neutron lifetime to 0.080 seconds.
QUESTION (A.14)
[1.0)
During normal operations at 2 MW, the typleal reactor core coolant temperature profile is such that the 12mperature peaks are...
a,
...at the top of the core.
b.
...at the bottom of the core.
c.
...between the top and the middle of the core.
d.
...between the bottom and the middle of the core OUESTION (A.15)
[1.0)
Th] rcactor is suberitical with a Keff of 0.95 and a source range count rate of 15 counts per second. Control rods cre withdrawn until the source range count rate equals 45 counts per second.
Which of the following is the Keff of the core after the control rod withdrawal?
a.
0.953 b.
0.970 c.
O_.983 d.
0.995
=
v Section A R Theorv. Thermo & Fac. Ooeratina Characteristics QUESTION (A.16)
[1.0)
The regulating blade was withdrawn two (2) inches. The steady reactor period following blade withdrawalis observed to be sixty (60) seconds.
Which one of the following is the differential blade worth 7 a.
9.1 x 10d delta k/k per inch b.
5.0 x 108 delta k/k per inch c.
1.2 x 10d delta k/k per inch d.
5.4 x 104 delta k/k per inch QUESTION (A.17)
[1.0)
Which one of the following desenbes the MAJOR contribution to the production and depletbn of xenon in the rc ctor?
Produced from radioactive decay of iodine and depletes by neutron absorption only a.
b.
Produced from radioactive decay of lodine and depletes by radioactive decay and neutron absorption c.
Produced directly from fission and depletes by neutron absorption only d.
Produced directly from fission and depletes by radioactive decay and neutron absorption QUESTION (A 18)
[1.0)
Following a scram, the value of the stable reactor period is:
approximately 50 seconds, because the rate of negative reactivity insertion rapidly approaches zero, a.
b.
approximately 10 seconds, as determined by the rate of decay of the shortest lived delayed neutron precursors.
approximately 80 seconds, as determined by the rate of decay of the longest lived delayed neutron c.
precursors, d.
infinity, since neutron production has been terminated.
l
Section A R Theorv. Thermo & Fac. Oooratina Characteristic.s l
i QUESTION (A.ig)
[1.0)
The following data was obtained during a reactor fuel load.
j No. of Elements Detector A (cos) i 0
20 8
25 12 33 16 38 i
20 72 24 134 4
)
Which one of the following is the number of fuel elements required to make the reactor critical? (The attached figure may be used to determine tne correct response.)
s.
22 b.
24 c.
28 d.
32 1
1.0 1
0.9 0.0 2
0.7 l
1 0.6 M
0.5 0.4 i
0.3 0.2
'1 O.1 4-0.0 1
2 4
6 0
10 12 14 16 18 20 22 24 26 28 30 32 NUMBER oF ELEMENTS INSTALLED
?
QUESTION (A.20)
[10)
Th] reactor is operating at 100 KW. The reactor operator withdraws the Regulating Rod allowing power to incr:ase. The operator then inserts the same rod to its original position, decreasing power.
_ In c:mparison to the rod withdrawal, the rod insertion will result in:
a.
a longer period due to long lived delayed neutron precursors, b,
a shorter period due to long lived delayed neutron precursors, c.
the same period due to equal amounts of reactivity being added, d.
the same period due to equal reactivity rates from the rod.
""* END OF SECTION A *""
4 Mhn B Normal /Emera. PrarMures & Rad Con QUESTION (B.1)
[1,0)
A point source of gamma radiation measures 50 mr/hr at a distance of 5 ft.
What is the exposure rate (mr/hr) from the source at a distance of 10 ft.
a.
25 mr/hr b.
12.5 mr/hr c.
6.25 mr/hr d.
17.5 mr/hr QUESTION (B.2)
[2.0)
Match the requirements for maintaining an active operator license in column A with the correct time period from column B.
Column A Column B 1.
Renewal of license a.
1 year 2.
Medical Examination b.
2 years 3.
Requalification Written examination c.
4 years 4.
Requalification Operating Test d.
6 years QUESTION (B.3)
[1.0)
Which one of the following does NOT require NRC approval for changes?
a.
License b.
Requalification plan s
c.
Emergency implementation Procedures d.
Emergency Plan m__m._._
Section B Normal /Emerg. Procedures & Rad CDD l
QUESTION (0.4)
[1.0)
The governor of OHIO requests radiation workers to clean up an accident at Davis-Besse Nuclear facility, i
While helping out you, an employee of UMich, receive a dose of 6 Rem.10 CFR 20 requires that this dose be tracked as a Planned special exposure. Who is responsible for maintaining a permanent record of this dose?
a.
Federal Emergency Management Agency (FEMA).
b.
University of Michigan FNR.
I c.
Nuclear Regulatory Commission.
d.
State of Michigan,(an cgreement state).
QUESTION (B.5)
[1.0)
Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep dose equivaient and the committed eff;ctive dose equivalent. The deep dose equivalent is related to the...
a.
dose to organs or tissues, b.
external exposure to the skin or an extremity, c.
external exposure to the lens to the eyes, d.
external whole-body exposure QUESTION (B.6)
[1.0)
Since he started employment at the FNR, a radiation worker has accumulated a dose of 3.27 R. So far this y ar, the worker has received a dose of 1.25 R. How long can he remain in an area with a gamma dose rate of 75 mR/hr without exceeding the 10CFR20 TEDE limit? (Assume zero committed dose.)
a.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> b.
23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> c.
50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> d.
66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />
___-__a
Section B Normal /Emera. Procedures & Rad con QUESTION (B.7)
[1.0)
A radioactive source generates a dose of 100 mr/hr at a distance of 10 feet. With two inches of lead shielding the reading drops to 50 mr/hr at a distance of 10 feet. If you were to add ANOTHER four inches of the same type of shielding, the reading at 10 feet would drop to...
a.
25 mr/hr b.
12% mr/hr c.
6% mr/hr d.
3% mr/hr QUESTION '(B.8)
[2.0) idIntify ewch of the actions listed below as either a Channel Check, Channel Test, or Channel Calibration.
a.
Verifying overlap between Nuclear Instrumentation me;ers.
b.
Replacing an RTD with a precision resistance decade box, to verify proper channel output for a given resistance.
c.
Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear Instrumentation to agree, d.
During shutdown you verify that the period meter reads 80 seconds.
QUESTION (B.9)
[1.0)
Limiting Safety System Settings (LSSS) are...
a.
limits on very important process variables which are found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity.
b.
s3ttings for automatic protective devices related to those variable having significant safety functions.
c.
settings for ANSI 15.8 suggested reactor scrams and/or alarms which form the protective system for the reactor or provide information which requires manual protective action to be initiated.
\\
d.
the lowest junctional capability or performance levels of equipment regt red for safe operation of the -
reactor.
1 1
Section B Normal /Emero. Procedures & Rad Con QUESTION (8.10)
[1.0]
Which one f the following lists reauired reactor scrams associated with the Technical Specification Safety Limits for the, natural convection mode?
a.
Reactor thermal power.
Reactor ccolant inlet temperature Height of water above the top of the core.
b.
High Power / Header Down.
Reactor coolant exit temperature.
Height of water above the center line of the core.
c.
Reactor thermal power.
Height of water above the top of the core, d.
Reactor coolant exit temperature.
Height of water above the top of the core.
QUESTION (B.11)
[1.0)
Consider two point sources, each having the same curie strength. Source A's gammas have an cnergy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading from the same G:iger counter 10 feet from each source. Concerning the two readings, which one of the following statements is correct?
- a. The reading from Source B is four times that of Source A.
- b. The reading from Source B is twice that of Source A.
- c. Both readings are the same,
- d. The reading from Source B is half that of Source A.
QUESTION (B.12)
[1.0)
Argon-41 is L oduced by neutron absorption of argon-40. Argon-41 decays by:
a:
a 1.3 MeV gamma with a half life of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
a 6.1 MeV gamma with a half life of 7 seconds.
c.
neutron emission with a half life of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d.
a 1.3 MeV beta with a half life of 7 seconds.
7 Mon B Normal /Emera. Procedures & Rad Con QUESTION (B.13)
[1.0)
For which ohn of the following operating conditions is the recommended action NOT to insert all rods?
a.
Inability to exercise control over primary water system components, b.
Loss of FNR exhaust radiation monitor.
J c.
Malfunction of auto-rundown circuit.
d.
Loss of shim safety rod magnet contact light.
QUESTION -(B.14)
[1.0)
The reactor is in steady state power at 90% when you, the operator, notice that the Reactor Bridge area -
rcdiation monitor is inoperable. Which one of the following describes the correct action you should take?
c.
Shutdown the reactor, Technical Specifications (T.S.) do not allow operations of the reactor without a fully operating Reactor Bridge radiation monitor.
b.
Continue operation. T.S. allow the unit to be out of service for up to 7 days.
c.
Continue operation. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of recognition of failure, replace the unit with a portable gamma-
. sensitive instrument with alarm.
d.
Continue operation as long as a minimum of three other area radiation monitors are operating.
QUESTION (B.15)-
[1.0)
Which one of the following is TRUE7 a.
If a
- duress" alarm is received at the control room, the operator on duty should initiate the building
- alarm, b.
Work scheduled on the Shutdown Maintenance Schedule is considered approved.
c.
The magnet power keys are normally in the custody of the SRO on duty.
- d.
If the reactor is shutdown and the magnet power kt y switch energized, the minimum control room staffing is a licensed reactor operator.
--mw m
s-ngr-,,
-my,-r-ga-m as-
q=--
,3+-
9 p-g
-4a-+
w--ee,y-wy,y aggyy-y-g
.g wwy g,w w r ar, rw - v m.ps'-wy'* gym 4,
,<p-g4m-w y-ep e-4 rm -w m y=p9&=n-e-
Mlan B Normal /Emerg. PrMures & Rad Con QUESTION (B.16)
[1.0)
Which one of the following statements is TRUE concerning experiments?
a.
An experiment approved for control fuel element irradiation may be irradiated in a polyethylene container if the irradiation is for six hours or less.
b.
The reactivity worth of any moveable experiment shall not exceed 0.01 AK/K.
c.
Experiments approved for the sample stringer can be loaded or unloaded from the reactor only during reactor shutdown periods.
4 d.
The total reactivity worth of moveable and secured experiments shall not exceed 0.0436 AK/K.
QUESTION (B.17)
[1.0)
Following an irradiation of a specimen, the resulting radioisotope is expected to equal 200 curies. The radioisotope will decay by the emission of two gamma rays per disintegration with energies of 1.10 MeV and 1.29 MeV.
Which one of the following is the radiation exposure rate (R/hr) at one (1) foot from the specimen with no shttding?
a.
1708 R/hr b.
2868 R/hr c.
3405 R/hr
- d.
5736 R/hr
- w___,
Saggion B Normal /Emerg. Procedures & Rad Con QUESTION (B.18)
[1.0)
The T.S. require a minimum Shutdown Margin (SDM) of 0.0045 AK/K for a specific core and control rods configuration. Assuming Xenon free conditions and the following worths, which one of the following is the calculated SDM7 5g poj ca (cu ':%
i,
u ex worth %AK/K Shim Safety red #1:
2.41 Shim Safety rod #2:
2.32 Shim Safety rod #3:
2.49 Control rod (Reg.)
0.084 Excess Reactivity:
1,42 Experiments (Max Worth) 0.60 a.
7.96 %
b.
5.28%
c 5.20 %
t d.
2.71 %
1
(*" End of Section B "')
i ww-a---wer'newrym-Tzwve-rwew
C.
PLANT AND RAD MONITORING SYSTEMS P ga 16 QUESTION (C.1)
[1.0]
While operating in tho Forced Convection Flow Mode which one of the following will result in a reactor scram?
a.
Primary Coolant Flow = 1100 gpm b.
Coolant inlet Temperature = 118'F c.
Log N amplifier high voltage at 40 volts d.
Pool Levelis 14 inches below normal QUESTION (C.2) [1.0)
Fillin the blank.
In th) event of a reactor scram, the momentum of the descending rod is absorbed on the a.
fuel element b.
lower shock c.
mounting block d.
holdown QUESTION (C.3) [1.0]
Which one of the following would indicate that a leak has developed between the heavy water tank and the r actor pool?
a.
Increase in the gross beta analysis due to tritium in the pool water, b.
Increase in beamport thermal flux due to greater moderation of fast neutrons, c,
Positive reactivity addition as light water dilutes the heavy water in the heavy water tank.
d.
Abnormal rod insertions due to greater reflection of neutrons from the heavy water tank into the core.
C.
PLANT AND RAD MONITORING SYCTEMS Pcga 17 QUESTION (C.4) [1.0)
Which one of the following is the reason for the pool level scram setpoint7 a
To provide an acceptable safety margin to the maximum fuel cladding temperature, b.
To prevent incipient boiling event if transient power rises to the thermal power trip limit.
l c.
To assure that an adequate pool volume is available to provide cooling of the core in the event of a loss a coolant accident.
d.
To maintain an adequate poollevel for the dash pot action of the control blades in the event of a scam.
QUESTION (C.5) [1.0]
Which one of the following willlimit the loss of coolant Iri the event of a coolant leak due to rupture of a be:mtube while the beamport is being used for an experiment?
a.
Beamport shield door, b.
Flanges at each end of beamport.
c.
Damage control plugs.
d.
Collimator.
QUESTION (C.6) [1.0)
Th3 bus transfer, which switches the emergency supply from the normal building supply to the emergency g:nerator, is located in:
a.
Beamport floor b.
Room 2074 c.
Room 1033 d.
Room 2077
C.
PLANT AND RAD MONITORING SYSTEMS Paga 18 QUESTION (C.7)
[1.0)
Select the choice that completes the following statement, in the event of a rupture in the Hot Demineralizer system, system isolation is accomplished by a flow switch th:t:
c.
sends a signal to the inlet and outlet pump controllers to stop both pumps and also deenergizes the auto shut off valve, b.
signals the intet and outlet pump motor controllers to stop both pumps. The inlet pump motor controller also deenemizes the auto shut off valve.
c.
deenergu.es the auto shut off valve. The closure of the auto shut off valve causes the inlet and outlet pump motor controllers to stop both pumps.
d.
signals the inlet and outlet pump motor controllers to stop both pumps. The auto shut off valve closes upon sensing a low water pressure.
QUESTION (C.8)
[1.0)
The reactor is operating at 2 MW with Primary Pump number 1 providing forced circulation flow. A low pressure is sensed at the Holdup Tank.
Which one of the following describes the impact of these events on the plant?
a.
The reactor will scram on high power / low flow due to the Primary Pump tripping on low Net Positive Suction pressure.
b.
The reactor will scram due to the low pressure in the holdup tank c.
The Holdup tank will be slowly pumped dry resulting in a high radiation condition due to insufficient N-16 holdup time.
d.
The butterfly valve at the inlet of the tank will cause a reactor scram due to a low flow condition.
QUESTION (C.9)
[1.0)
Which one of the following does NOT exhaust into PML stack 27 a.
Fuel Vault b.
Hood in room 3103 c.
P tube exhaust d.
PML room 1069
7m' C.-
PMNT AND RAD MONITORING SYSTEMS Paga 19 QUESTION ;(C.10)
[1.0)
Wixh one of the following it NOT a function of the poollevel monitoring system?
a, An ultrasonic probe generates a local alarm at 3 inches to warn of decreas;., col levelt,.
i),
- An audible alarm is generated at approximately 0.3 inches as a warning during pool fills, c.
- A control room alarm is generated at 5 inches.
l d.
A low pool alarm is sent to the University Department of Public Safety and Security at -12 inch QUESTION (C.11)
[1.0)
Which one of the following describes the N 16 Power Level Monitor detector?
a.
b.
Fission chamber
- c.
Gamma ion chamber d.
Compensated ion enamber 4
QlJc.STICN (C.12)
['i.0) -
Which one of the following is generated by the Log N Recorder?
af Reactor power level scram.
b.
Control rod inhibit.
- c.
Reactor on clock, d.
Reactor at full power light.
A
0 C.
- PLANT AND RAD MONiiCRING SYSTEMS Paga 20
- QUESTION (C.13'
[1.0)
Which one of the following will cause BOTH an alarm and a reactor scram?
a.
Stack GAD reads 1100 cpm.
b.
Radiation hot Di area monitor reads 30 mrem /hr.
c.
Building exhaust NMC reading 1.1 mrem /hr.
d.'
Fuel Vault NMC reads 7 mrem /hr.
-QUESTION (C.14) g if]
The reactor is operating with the servo control system maintaining power at 50v kw when compensating v:ltage is lost to the Linear Level Compensated lon Chamber Which one of the following describes the response of the plant to this malfunction?
Indicated power will decrease, resulting in the automatic control system dropping out of automatic a.
control.
b.
Indicated power will decrease, resulting in the control rod being withdrawn from the core.
c,
- Indicated power will increase, resul'ing in the contml rod being driven inward.
d.
Indicated power will remain constant.
QUc3 TION -- (C.15)
[1.0)
Wr..ch one of the following is an approxirrate reactivity change introduced by replacing the content of the-heavy water tank with H O?
2 a.'
1% AK/K '
b.
3% AK/K c.
.25% AK/K d
4% AK/K k
L C.
PLANT AND RAD MONITORING SYSTEMS-Ptga 21 QUESTION (C.16)
[1.0)
Which,ne of the following scram signals is defeated by bypassing the interlock scram section of the magnet sirent control?
a.
High power / header down.
b.
Beamport door open.
c.
Building exhaust high radiation level.
d.
Low poollevel.
QUESTION (C.17)
[1.0]
The Nitrogen Supply System pressure is decreasing slowly. Which one of the foimwing describes how backup supply is initiated?
a.
The Bonie Gas System is manually aligned when the Nitrogen tank pressure decreases below 40 psig.
b.
The Bottle Gas System is manually aligned when pressure on G-3 decreases below 20 psig.
c.
The Bottle Gas System comes on line automatically when the Nitrogen tank pres.ure decreases below 50 psig.
d.
The Bottle Gas System comes on line automatically when pressure on G " decreases below 20 psig..
QUESTION (C.18)
[1.0)
When an auto rundown condition occurs from 2 MW the contro! rod will...
a.
..be automatically driven into the core until the auto rundown condition is cleared.
b.
..be automatically driven into the core.
c.
... remain in automat lc and maintain its current position.
d.
.. shift to manual and maintain its current position.
1 Q_
C.
PLANT AND RAD MONITORING SYSTEMS Paga 22 QUESTION (C.19).
[1.0)
W:ste water is being transferred from RT2 to RT1 using the centrifugal pump. Which one of the following is the rsason the breaker for the positive displacement pump must be verified OPEN?
a.
The positive displacement pump may over pressurize RT1.
b.
The positive displacement pump has no suction from RT2.
One START pushbutton controls the start of both the centrifugal pump and the positive displacement c.
pump.
d.
The positive displacement pump will automatically start if tank level decreases to 200 gallons.
QUESTION (C '9)
(1.0)
Which one of the following radiation monitors is required to be operable for reactor criticality?
a.
MAP PML Stack #2 b.
Nortn Wall area monitor c.
MAP Beamport Floor d.
Het Demineralizer area monitor
("* End of Examination *)
I
^
.J
'v
'LSection A R Theory. - Thermo & FacL Ooeratina Characteristics
.Page_23
~
' ANSWER L (A.1).
c-
- REFERENCE Burn, R., introduction to Nuclear Rea: tor Operations,
- 1988 pg. 2-35 At 20 feet, all measured radiation is from gammas.
D,r,' = Da,'
r D, (1)' = 0.1 mr (20)'
D, = 40 mrom/hr gamrua i
Rttio of beta to total = 1 -(40/200) = 80%
- ANSWER (A.2) b-
- REFERENCE A = A, e
A =.693/T2 l
In(A/A.) =.693t/T2 l
T2 =.693t/In 0.8 = 75 hr i
' ANSWER (A.3) di
- REFERENCE
" Introduction To Nuclear Engineering", Lamarsh,2nd Edition, page 350.
. Burn, R., introduction to Nuclear Reactor Operations,
- I988 pg. 3 !
- ANSWER - (A.~4).
l
- ci I
- REFERENCE Burn, R., introduction to Nuclear Reactor Operations, c 1988, l 3.3.4, p. 3-21.
l
' ANSWER (A.5) d-
- REFERENCE Burn, R.:, introduction to Nuclear Reactor Operations, c 1988, f 7.6, p. 7-15.
I
-
- ANSWER (A.6) d
- REFERENCE
- Burn, R., intro &ction to Nuclear Reactor Operations,
- 1988, Chapt. 5, pp. 5 5-28.
.[
. ANSWER (A.7) l c.
'* REFERENCE i
Burn, R., Introduction to Nuclear Reactor Operations, c 1988, Q 3.3.4, pp. 3 3-22.
[
T = (8 - p)/1J -
i
Section A R Theory Thermo & Fac. Doeratina Characteristics Page 24
' ANSWER (A.8) c
' REFERENCE Burn, R., introduction to Nuclear Reactor Operatioru,
- 1988, fI 8.2 - 8.4, pp. 8 8-14, Fig. 8-2
' ANSWER (A.9) a
' REFERENCE
" Introduction To Nuclear Engineering", Lamarsh,2nd Edition, page 313.
Burn, R., Intr.Muction to Nuclear Reactor Operations,
- 1988, 6 3.3, pp. 313 19
- ANSWER (A.10) a
' REFERENCE Burn, R., introduction to Nuclear Reactor Operations,
- l*S8, pp. 2 65
- ANSWER (A.11) b
' REFERENCE Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, Q 5.18, p.
234.
P = P,e "
10 = le*T
- In 10 = 60/T 2.3 = 60/T T = 60/2.3 T = 26 seconds
' ANSWER (A.12) c
' REFERENCE-Burn, R., introduction to Nuclear Reactor Operations,
- 1982, g 5.2 (b), p. 5-4.
' ANSWER (A.13) a
' REFERENCE Burn, R., introduction to Nuclear Reactor Ogerations,
- 1982, f 4.2, p. 4-l.
Section A R Theory Thermo & Fac. Doeratina Characteristics Page 25
- - ANSWER (A.14).
b REFEMNCE FNR Exam Question Bank A, page A-22
- ANSWER (A.15)-
c
' REFERENCE
- CR,/CR,= (1-Keff,)/(1-Keff,)
15/45= (1 Keff /(1-0.95) ~ (0.05)(0.3333)= 1-Keff, 2
K;ff,= 1- 0.016665= 0.983
- ANSWER (A.16) d-
- REFERENCE Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, Q 7.2 & 7.3, pp. 7 7-9.
T 0"~# - 0 N C' p = 0.00751((0.1
- 60) + 1) = 0.0075/7 0"
p = 1.07 x 10 8 delta k/k p/ inch = 1.07 x 10-8 delta k/k/2 inches = 5.4 x 10" deha k/k per inch
' ANSWER (A.17) b
' REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983. {
7.4, pp. 316 - 322.
Burn, R., introduction to Nuclear Reactor Operations,
- 1988, $$ 8.1 -S.4, pp. 8 8-14.
- ANSWER (A,18) c
' REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1982, f 4.6, p. 4-16.
- ANSWER (A.19) c
' REFERENCE Burn, R., introduction to Nuclear Reactor Operations, o 1982, Q 5.5, pp. 5-l8 25.
- ANSWER (A 20) a
- REFERENCE Burn, R., Introduction to Nuclear Reactor Operations,
- 1982, il 3.2.2 - 3.2.3, pp. 3 3-12.
(*** End of Section A "*)
l
W B Normal /Emero. ProcMures & Rad Con
' ANSWER (B.1) b
' REFERENCE Dr,D,8= Dr D,8 Dr, a Dr,Df / D,' = (50 mr/hr x 5 ft')/10 ft = 12.5 mr/hr 2
- ANSWER (B.2) 1, d; 2, b; 3, b; 4, a REFERENCE 10 CFR 55
- ANSWER (B.'3) c
' REFERENCE 10 CFR 50.54 p,); 10 CFR 50.59; 10 CFR 55.59
- ANSWER (B.4) b
' REFERENCE 10 CFR 20
- ANSWER (B.5) d
' REFERENCE 10 CFR 20.1201
- ANSWER (B.6) c
- REFERENCE 10 CFR 20 Whole Body Limit = 5 R Tims = ((5 R - 1.25 R) / 0.075 R/hr) = 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />
- ANSWER (B.7) b
' REFERENCE Two inches = one-half thickness (Tw). Using 3 half-thickness will drop the dose by a factor of (%)* = %.- 100/8
= 12.5
- ANSWER. (B.8)
-.a check; b, test; c, calibration; d. check
- REFERENCE FNR Tech. Specs, Definitions pg.1
Sitetion B Normal!Emera. Procedures & Rad Con l
l
- ANSWER (B.9) b
- REFERENCE FNR Tech. Specs, Definitions pg. 2
' ANSWER (B.10) a
- REFERENCE FNR T.S. 2.2.2
- ANSWER (B.11) c
- REFERENCE GM is not sensitive to energy.
- ANSWER (B.12) a
- REFERENCE NPP Health Physics pg. 5-20
- ANSWER (B.13) d
' REFERENCE Exam Question Bank Section B, pg. B-138 OP-109, Response to Scrams, Alarms, and Abnormal Conditions
- ANSWER (B.14) a
- REFERENCE T.S. Table 3.2, pg.14
- ANSWER (8.15) b
- ANSWER (B.16) c
T.S. 3.1
Section B Normal /Emera. Procedures & Rad Con f
' ANSWER (B.17) b l
fREFERENCE l
RuBCEn l
R a 6 (200 ci) (1.10 + 1.29 MeV) (1 disintegration)
R a 2868 R/hr
- ANSWER - (8.18) _
d
' REFERENCE OP-105 Core Excess, SDM and Control Rod Reactivity Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 6 6.2.3 p. 6-4.
SDM (cold / clean) = Total Rod wor th - K.,. - Most reactive rod - Reg Rod - Experiments worth SDM = (2.41 + 2.32 + 2.49 + 0.084) - 1.42 - 2.49 - 0.084 - 0.60 = 2.71%
("* End of Section B "*)
~
C.
PLANT ANO RAD MONITORING SYSTEMS Pego 29
- ANSWER (C.1) c
' REFERENCE T.S. Table 3.1 pg.13
' ANSWER (C.2) c, d
- REFERENCE System Description pg. 313
- ANSWER (C.3) a
- REFERENCE
. NR System Descriptions. Ch. 3 NRC exam 12/93
' ANSWER (C.4) c
- REFERENCE SAR; Abnormal Loss of Coolant; pg. 57
- ANSWER (C.5) d
- REFERENCE SAR; Loss of Coolant Analysis; 14.2,4 Beamports
- ANSWER (C.6) b J
- REFERENCE FNR System Description, Chapter 9, p. 9-1
- ANSWER (C.7) b
- REFERENCE FNR System Description; Sect. 7.3.3, pg. 7-2
' ANSWER (C.8) b
- REFERENCE FNR System Descriptions Sect. 4.3.4
C.
PLANT AND RAD MONITORING SYSTEMS.
Paga 30
- ANSWER (C.9) a
- REFERENCE System Descriptions Ch.12 pg.12-1
' ANSWER (C,10) a
- REFERENCE System Descriptions Ch.13 Sect.13.11,1
' ANSWER (C,11) c
- REFERENCE
. Syst;m Descriptions Ch.13 Sect.13.12,1
- ANSWER (C.12) a, d
- REFERENCE System Descriptions Ch.13 Sect.13.2.3.7
- ANSWER (C.13) c
- REFERENCE FNR System Descriptions Ch.13
' ANSWER (C.14) c
- REFERENCE FNR System Descriptions Ch.13 Sect.13.4 Gladstone & Sesonske, Nuclear Reactor Engineering 3rd Edition, sect. 5.254
- ANSWER (C.15).
d
'* REFERENCE System descriptions Ch. 2
' ANSWER-(C.16) b
- REFERENCE FNR System Descriptions Sect 13.9.2 k
~
C.
PLANT AND RAD MONITORING SYSTEMS Pago 31
- ANSWER (C.17) d
- REFERENCE FNR Supply Question Section C pg. C 329
- ANSWER (C.18) d
- REFERENCE FNR System Descriptions Sect.13.10.2
- ANSWER '
(C.19) c
' REFERENCE FNR supplied question bank Section B, pg. B-717 OP-208, " Operating the RTDI System *, pg. 2
' ANSWER (C.20) b
- REFERENCE FNR supplied question bank Section C, pg. C-81
("* End of Section C *")
("*" End of Examination *"")
_ _ _ _ _ _. - _ _ _ _ _ _ _ _ _.. _ _ _ _ _. _ _ _ _