ML20059G147
| ML20059G147 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 10/08/1993 |
| From: | Caldwell J, Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059G136 | List: |
| References | |
| 50-134-OL-93-03, 50-134-OL-93-3, NUDOCS 9311080019 | |
| Download: ML20059G147 (74) | |
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i ENCLOSURE 1-U. S. NUCLEAR REGULATORY COMMISSION i
OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-134/0L-93-03 FACILIlY DOCKET NO.:
50-134 1
.l FACILITY LICENSE NO.:
R-61 FACILITY:
Worcester Polytechnic Institute i
EXAMINATION DATES:
September 13, 1993 EXAMINER:
Patrick Is,aac, Chief Examiner
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am SUBMITTED BY:
atric IsaaccCh' f 'xaminer Date g?
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D APPROVED BY:
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Janeis4. Caldwe/Il,LChief. '
Date NonyPower Reactor Section Opyrator Licensing Branch Division of Reactor Controls i
/ and Human Factors Office of Nuclear Reactor Regulation
SUMMARY
A retake of Section A of the written examination was administered to one R0 candidate. A retake of Section B of the written examination was administered to another R0 candidate. Both candidates passed the applicable portion of the examination.
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=! -t REPORT DETAILS l.
Examiners:
i Patrick Isaac, Chief Examiner i
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Results:
R0 SRO Total j
(Pass / Fail)
(Pass / Fail)
(Pass / Fail) i NRC Grading:
2/0 N/A 2/0 3.
Written Examination:
A retake of Section A of the written examination was administered to one R0 candidate. A retake of Section B of the written examination was administered to another R0 candidate. At the conclusion of the examination, the Chief Examiner immediately secured the master examination answer key and all the candidates answer sheets.
A copy of the master "as given" examination with answer key was given to the f acility for a formal review.
The facility's written examination comments and the NRC resolution to those comments are found in Enclosure 2.
Both candidates passed the applicable portion of the examination.
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Operating Tests:
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Exit Meeting:
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i ENCLOSURE 2 NRC RESOLUTIONS - WRITTEN EXAMINATION SECTION A l
OUESTION A.]
WHICH ONE (1) of the following is the percentage of the total neutron flux made up by THERMAL neutrons while operating at 10 kw?
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- a. 10%
- b. 33%
- c. 50%
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- d. 75%
t ANSWER A.1 i
b.
FACILITY COMMENT A.1 At best, this question is stated incorrectly. The question asks the candidate to state the ratio of thermal (presumably total thermal) flux to total neutron flux (integrated spectrum of neutron energies) in the core. The reference data used for the question provides average rather than total (integral) flux data at each energy group.
Regardless, the candidate has been expected to have studied and memorized inconsequential data.
NRC RESOLUTION A.1 The staff agrees with your comment and the question will be deleted.
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OVESTION A.2 l
WHICH ONE (1) of the following is the effect of an INCREASE in water l
temperature?
- a. Neutron spectrum hardens due to less moderation.
- b. Neutron spectrum softens due to increased leakage.
- c. Reactivity increases due to less leakage.
- d. Reactivity decreases due to more moderation.
ANSWER A.2 a.
FACILITY COMMENT A.2 This is an unfair question in that the candidate is expected to understand the terms " soft spectrum" and "hard spectrum", ntither of which are referenced in the WPI FSAR or Lamarsh's Introduction to Nuclear Technology (2nd ed.).
Such terms are more readily associated with higher powered research reactors rather than lower power teaching reactors.
NRC RESOLUTION A.2 j
On page 29 of the WPI FSAR, the Negative Temperature coefficient is described as having the following effects: "(1) hardening of the neutron spectrum due to an increase in the water temperature only, (2) the increase in i
neutron leakage due to a decrease in the water density only,...". Since the terms " hardening of the neutron spectrum" and " softening of the neutron spectrum" are not explained in any WPI reference manuals, the NRC will not penalize this candidate for this knowledge deficiency. The candidate, by choosing either a (less moderation) or b (increase in neutron leakage) as the answer and not c and d, demonstrated an understanding of the effects of the Negative Temperature coefficient..
The answer key will be modified to accept either a or b as correct.
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i QUESTION A.3 WHICH ONE (1) of the following reactor locations has the HIGHEST thermal i
neutron flux?
(Assume distances are along the midplane X axis from the Core center.)
- a. Core centerline i
- b. Halfway between core centerline and edge of core
- c. Two-thirds of the way from the core centerline to edge of core
- d. In the reflector l
ANSWER A.3 d.
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FACILITY COMMENT A.3 As with Question 1, this question requires the candidate to know l
inconsequential data given the scope and uses of. the reactor.
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NRC RESOLUTION A.3 The staff does not agree with your comment.
Research reactors are often used to irradiate experiments. An important consideration in irradiation studies is the radiation fluence or integrated flux. The fluence here is the t
product of the neutron flux and the exposure time.
The licensed operator should have an understanding of the core flux profile since the amount of dose received by a particle being radiated is related to the location in the core where the particle is inserted.
Furthermore, in Appendix C to License No. R-i 61, Experiment 12 describes the " Diffusion Length and Migration Area of Neutrons in Graphite" In Experiment 7 (Reactivity Changes due to Absorption), it is stated that "It is important to understand the effect of additions of external materials into the reactor core area".
Figure 6 (Appendix B to License No. R-61) describes the midplane neutron fluxes from core center.
No change to the examination grading is required.
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.t 00EST10N A.7
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WHICH ONE (1) of the following is the MAXIMUM amount of reactivity that j
can be promptly inserted into the reactor WITHOUT causing the reactor to i
go " Prompt Critical"?
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- a. 0.10 dollars
- b. 0.50 dollars r
- c. 0.75 dollars j
d.1.90 dollars ANSWER A.7 b.
FACILITY COMMENT A.7 N/A NRC RESOLUTION A.7 While grading the written exam, the staff discovered a typographical-i error'on the answer key. The answer key has been corrected to reflect "c" as the correct answer.
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DVESTION A.ll The following conditions exist:
- 1. The reactor scrammed from full power at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on 9/12/93
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due to a malfunction.
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- 2. Repairs were completed and the reactor was restarted at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on 9/13/93.
- 3. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> the reactor operator is moving the regulating blade to maintain a steady state power.
WHICH ONE (1) of the following describes the PRIMARY reason for this regulating blade movement?
- a. The regulating blade is slowly being withdrawn due to increase in Xenon absorption.
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- b. The regulating blade is slowly being withdrawn due to increase in Samarium absorption.
- c. The regulating blade is slowly being inserted due to decrease in Xenon absorption.
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- d. The regulating blade is slowly being inserted due to decrease in Samarium absorption.
ANSWER A.11 i
c.
i, FACILITY COMMENT A.11 This question requires the candidate to understand Xenon and Samarium effects. These concepts are not given to R0 candidates during training.
Please see the enclosed file copy of letter to P. Doyle dated February 25, 1993 indicating information for the initial examination, which to my understanding was to be used also for the re-examination.
While not understanding fission product poisoning may seem incongruous l
for students in a nuclear engineering program, students do not receive
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classroom instruction on reactor theory until usually their senior year. As we have only an undergraduate program, we cannot license students'in their senior year and must therefore rely on sophomore'and junior year candidates.
Additionally, as a full-time staff of only one, I must focus on only that material which is pertinent.to the WPI Reactor during training of the candidate.
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b NRC RESOLUTION A.11 Xenon and Samarium are the byproducts of nuclear reactors and have large cross sections for thermal-neutron absorption. The knowledge of the effect on the reactivity of these fission-product poison is fundamental.
t While we understand that the small changes in Xenon and Samarium concentration in the WPI reactor will not force the reactor operator to move rods to maintain reactor power constant, 10CFR55.41 requires a licensed operator to understand the fundamentals of reactor theory, including fission process and poison effects to the extent applicable to the facility. The staff agrees that the depth of knowledge required to answer this particular question is beyond that required of the Reactor Operator at the WPI reactor.
i This question will be deleted from the examination.
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i OUESTION A.12 l
The following conditions exist-t
- l. Element "X" is a 1/v absorber.
- 2. The cross for absorption for Element "X" for 0.0253 eV neutrons is 100 barns.
l WHICH ONE (1) of the following is the absorption _ cross section for' l
Element "X" for 0.0506 eV neutrons?
- a. 25 barns
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- b. 50 barns
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- c. 100 barns
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- d. 200 barns i
ANSWER A.12 b.
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FACILITY COMMENT A.12 l
L N/A NRC RESOLUTION A.12 l
Due to an editing error, the correct answer to this question was not provided as one of the choices.
This question will be deleted from the i
examination.
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OUEST10N A.18 The following conditions exist:
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- 1. The reactor was operating at a stable power..
- 2. The regulating blade was then withdrawn to establish a positive reactor period.
- 3. The positive period was then maintained for five (5) minutes when the regulating blade was inserted to its original position-prior to withdrawal when reactor power was stable.
WHICH ONE (1).of the following is the new reactor power?
- a. The stable power level equal to the original power level prior to blade withdrawal.
- b. A power level lower than the original power level prior to blade withdrawal and decreasing due to Xenon formation.
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- c. A power level higher than the original power level prior to-blade withdrawal and increasing due to Xenon burnout.
- d. A power level higher than the original power level prior to j
blade withdrawal and decreasing due to Xenon formation.
i ANSWER A.18 C.
FACILITY COMMENT A.18 This question requires the candidate to understand Xenon and Samarium 1
effects. These concepts are not given to R0 candidates during training.
Please see the enclosed file copy. of letter to P. Doyle dated February 25, 1993 indicat ing information for the initial examination, which to my understanding was to be used also for the re-examination.
While not understanding fission product poisoning may seem incongruous.
for students in a nuclear engineering program, students do not receive classroom instruction on reactor theory until usually their senior year. As l
we have only an undergraduate program, we cannot license students in their l
senior year and must therefore rely on sophomore and junior year candidates.
Additionally, as a full-time staff of only one, I must focus on only that material which is pertinent to the WPI Reactor during training of the candidate.
i NRC RESOLUTION A.18 10CFR55.41 requires a licensed operator to understand the fundamentals of reactor theory, including fission process and poison effects to the extent applicable to the facility. The knowledge level of fission product poisoning l
required to answer this question is basic. The staff disagrees with the facility comments.
j No change to the examination grading is required.
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SECTION B OUEST10N B.1 WHICH ONE (1) of the following is a REPORTABLE Occurrence?
- a. The Safety System Setting for reactor period was set at 15 seconds and caused a Reactor scram.
- b. Shutdown Margin was calculated as 2% delta k/k.
- c. The B10 chamber is INOPERABLE while the reactor is SHUTDOWN.
- d. A test procedure requires the pool temperature to be raised to 105 degrees F. while operating at 10 kw.
ANSWER B.1 d.
FACILITY COMMENT B.1 There is no correct answer for this question. The Reportable Occurrence used at the premise of the question (WPI Tech. Specs. page 2, Reportable Occurrence 9) references "... an observed inadequacy in the implementation of
... procedural control s...". Where the word " implementation" as used in this context would be defined as the execution or performance of the procedural control.
It does not refer to an inadequacy in the actual procedural control as would be the case as presented in the question.
For answer D to be correct the Reportable Occurrence would have to read:
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"(A)n observed inadequacy in an administrative or procedural control such that the implementation of such control caused...".
In the context of the question, if this situation were to arise, it would be reportable only if actual operation caused the violation of an L.C.0.
(WPI Tech. Specs page 2, Reportable Occurrence 2).
NRC RESOLUTION B.1 The staff agrees with the facility comment. This question will be deleted from the examination.
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ENCLOSURE 3-U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Worcester Poly. Inst.
REACTOR TYPE:
Pool DATE ADMINISTERED:
1993/09/13 REGION:
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CANDIDATE:
t INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.
Points for each question are indicated in paren-theses for each question. A 70% is required to pass the examination.
Examinations will be picked up one (I) hour after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY j
VALUE TOTAL SCORE VALUE CATEGORY 17.00 100.00 A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 17.00 TOTALS FINAL GRADE All work done on this examination is my ewn.
I have neither given nor received aid.
Candidate's Signature i
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RX THEORY, THERM 0 & FAC OP CHARS ANSWER SHEET F
i Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
i MULTIPLE CHOICE j
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
'I 006 a
b c
d j
007 a
b c
d i
008 a
b c
d i
-t 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d i
f 013 a
b c
d
=!
014 a
b c
d l
015 a
b c
d j
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 1
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(***** END OF CATEGORY A *****)
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(********** END OF EXAMINATION **********)
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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 j
and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on
-i 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 j
done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may l
leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
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- 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 j
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 the first page of.each section of your answer sheets.
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- 8. Eanh question is worth one (1) point.
Partial credit will NOT be given.
- 9. If the intent of a question is unclear, ask questions of the examiner only.
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RX THEORY, THERM 0 & FAC OP CHARS QUESTION: 001 (1.00)
DELETED WHICH ONE (1) of the following is the percentage of the total neutron flux made up by THERMAL neutrons while operating at 10 kw?
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- a. 10%
- b. 33%
- c. 50%
- d. 75%
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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1 A.
RX THEORY, THERM 0 & FAC OP CHARS Page 7
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l QUESTION: 002 (1.00)
WHICH ONE (1) of the following is the affect of an INCREASE in water t
temperature?
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- a. Neutron spectrum hardens due to less moderation.
- b. Neutron spectrum softens due to increased leakage.
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- c. Reactivity increases due to less 1 Rage.
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- d. Reactivity decreases due to more moderation.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS-Page 8 QUESTION: 003 (1.00)
WHICH ONE (1) of the following reactor locations has the HIGHEST thermal neutron flux?
(Assume distances arc along the midplane X axis from the Core center.)
- a. Core centerline
- b. Halfway between core centerline and edge of core
- c. Two-thirds of the way from the core centerline to edge of core
- d. In the reflector
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 9 QUESTION: 004 (1.00)
The following conditions exist
- 1. At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> the reactor power was 10 watts.
- 2. A steady positive reactor period was established.
- 3. At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> the reactor power hr.d increased to 8 kw.
j WHICH ONE (1) of the following is the reactor period for this power ascension?
- a. 150 sec
- b. 210 sec
- c. 270 sec
- d. 330 sec
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THE0RV, THERM 0 & FAC OP CHARS Page 10 QUESTION: 005 (1.00) 1 At the beginning of a reactor startup, Keff is 0.90 with a count rate of 30 CPS.
Power is increased to a new, steady value of 60 CPS. The new Keff is:
a.
0.91 b.
0.925 c.
0.95 d.
0.975
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 11 QUESTION: 006 (1.00)
WHICH ONE (1) of the following factors is affected MOST by an increase in fission product poisoning?
- a. Resonance Escape Probability i
- b. Fast Fission Factor j
- c. Thermal Utilization
- d. Source Term 4
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 12 l
QUESTION: 007 (1.00)
WHICH ONE (1) of the following is the MAXIMUM amount of reactivity that i
can be promptly inserted into the reactor WITHOUT causing the reactor to go " Prompt Critical"?
- a. 0.10 dollars
- b. 0.50 dollars i
- c. 0.75 dollars
- d. 1.90 dollars e
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THECRY, THERMO & FAC OP CHARS Page 13 QUESTION: 008 (1.00)
The following conditions exist:
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- 1. A thermal beam of neutrons is aimed at a thin foil target made i
- of 10% copper and 90% cluminum.
- 2. The absorption cross sections for copper and aluminum are 3.79 barns and 0.23 barns respectively.
barns and 1.49 barns respectively.
i WHICH ONE (1) of the following has the HIGHEST probability of occurrence?
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- a. A neutron absorption in copper.
- b. A neutron absorption in aluminum.
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- c. A neutron scattering reaction with copper.
- d. A neutron scattering reaction with aluminum.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A. -RX THEORY, THERM 0 & FAC OP CHARS.
Page 14 QUESTION: 009 (1.00) f WHICH ONE (1) of the following conditions describes a reactor that is exactly critical?
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- a. Keff equals 0; delta K/K equals 0
- b. Keff equals 0; delta K/K equals 1
- c. Keff equals I; delta K/K equals 0
- d. Keff equals 1; delta K/K equals 1 l
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RX THEORY, THERM 0 & FAC OP CHARS Page 15 QUESTION: 010 (1.00)
The following conditior.s exist:
- 1. The reactor is operating at full power.
- 2. The Regulating Blade is moved into the core one (1) inch from each of three different positions (top, middle, and bottom of the core).
- 3. The reactor flux profile along the "Y" axis is a symmetric half-cosine curve.
WHICH ONE (1) of the following describes the affect of the three blade movements on core reactivity?
- a. The blade has the greatest negative reactivity affect at the top of the core because the thermal neutron flux is greatest at the top of the core.
- b. The blade has the greatest negative reactivity affect at the middle of the core because the overall neutron flux is higher in the middle of the core.
- c. The blade has the smallest negative reactivity affect at the bottom of the core because the integral blade worth curve.is linear.
- d. The blade has the same reactivity worth at all locations in the core because the integral blade worth curve is linear.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 16 a
l QUESTION: 011 (1.00)
E)ElJETEE)
The following conditions exist:
- 1. The reactor scrammed from full power at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on 9/12/93 due to a malfunction, i
- 2. Repairs were completed and the reactor was restarted at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on 9/13/93.
- 3. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> the reactor operator is moving the regulating blade to maintain a steady state power.
WHICH ONE (1) of the following describes the PRIMARY reason for this regulating blade movement?
- a. The regulating blade is slowly being withdrawn due to increase in Xenon absorption.
- b. The regulating Dlade is slowly being witndrawn due to increase l
in Samarium absorption.
- c. The regulating blade is slowly being inserted due to decrease in Xenon absorption.
- d. The regulating blade is slowly being inserted due to decrease in Samarium absorption.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 17 l
QUESTION: 012 (1.00)
DELETED I
The following conditions exist:
- 1. Element "X" is a 1/v absorber.
- 2. The cross for absorption for Element "X" for 0.0253 eV neutrons is 100 barns.
WHICH ONE (1) of the following is the absorption cross section for l
Element "X" for 0.0506 eV neutrons?
- a. 25 barns
- b. 50 barns
- c. 100 barns
- d. 200 barns i
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX~ THEORY, THERM 0 & FAC OP CHARS' Page'18 QUESTION: 013 (1.00)
The following conditions exist:
- 1. Two reactors are identical with the exception that Reactor I has a beta fraction of.0072 and Reactor 2 has a beta fraction of
+
0.0060.
- 2. An equal amount of reactivity is inserted into both reactors.
WHICH ONE (1) of the following will be the response of Reactor I?
- a. The resulting power level will be lower.
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- b. The resulting power level wiil he higher.
- c. The resulting period will be shorter.
- d. The resulting period will be longer.
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RX THEORY, THERM 0 & FAC OP CHARS Page 19 i
e QUESTION: 014 (1.00)
WHICH ONE (1) of the following accounts for generation of a majority of the heat one hour after a reactor scram following an extended period of l
operation?
- a. Fission product decay
- b. Delayed neutron fissions
- c. Stored heat energy in reactor components
- d. Spontaneous fissions i
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J A. 'R,1 THEORY, THERM 0 & FAC OP CHARS Page 20 i
-i QUESTION: 015 (1.00)
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WHICH ONE (1) of the following is the PRIMARY method of heat transfer used to remove heat from the reactor core during full power operation?
- a. Conduction to the water moderator
- b. Convection to the water moderator
- c. Conduction to the reactor support structure,
- d. Radiation to the reactor support structure.
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RX THEORY, THERM 0 & FAC OP CHARS Page 21 i
i QUESTION: 016 (1.00)
The following conditions exist:
- 1. Experimenters are attempting to determine the critical mass of a new fuel material.
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- 2. Initial count rate is 100 counts /sec.
- 3. As more fuel was added the following fuel to count rate data was taken:
Fuel Count Rate i'
1.00 kg 500 c/sec 1.50 kg 3000 c/sec 1.75 kg 8000 c/sec 2.00 kg 13000 c/sec 2.25 kg 25000 c/sec WHICH ONE (1) of the following is the amount of fuel needed for a critical mass?
- a. 2.3 kg
- b. 2.5 kg
- c. 2.8 kg
- d. 3.5 kg 5
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A.
RX THEORY, THt'RM0 & FAC OP CHARS Page 22 l
QUESTION: 017 (1.00)
The following conditions exist:
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- 1. The regulating blade was withdrawn two (2) inches.
- 2. The steady reactor period following blade withdrawal is observed to be sixty (60) seconds.
WHICH ONE (1) of the following is the differeatial blade worth?
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- a. 5.6 x 10-4 delta k/k per inch
- b. 5.6 x 10-3 delta k/k per inch
^
- c. 1.12 x 10-4 delta k/k per inch d.1.12 x 10-3 delta k/k per inch
?
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1
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 23 i
QUESTION: 018 (1.00)
The following conditions exist:
- 1. The reactor was operating at a stable power.
3
- 2. The regulating blade was then withdrawn to' establish a positive reactor period.
- 3. The positive period was then maintained for five (5) minutes when the regulating blade was inserted to its original position prior to withdrawal when reactor power was stable.
WHICH ONE (1) of the following is the new reactor power?
- a. The stable power level equal to the original power level prior j
to blade withdrawal.
- b. A power level lower than the original power level prior to blade withdrawal and decreasing due to Xenon formation.
j
- c. A power level higher than the original power level prior to blade withdrawal and increasing due to Xenon burnout.
- d. A power level higher than the original power level prior to blade withdrawal and decreasing due to Xenon formation.
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~
i A.
RX THEORY, THERM 0 & FAC OP CHARS-Page-24 i
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QUESTION: 019 (1.00)
Reactor power decreases on a stable negative period following a reactor -
scram, following an initial prompt drop. The reason for this is the following.
i a.
All prompt neutrons decay during the prompt drop, and the subsequent, rate of power change is dependent only on the half-life of the longest lived prompt gamma emitter.
b.
This rate of power change is dependent on the mean lifetime of the shortest lived delayed neutron precursors.
c.
This rate of power change is dependent on the mean lifetime of the longest lived delayed neutron precursor.
d.
This rate of power change is dependent on the constant decay rate of prompt neutrons following a scram.
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1 A.
RX THEORY, THERM 0 & FAC OP CHARS Page 25 j
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QUESTION: 020 (1.00) i WHICH ONE (1) of the following is the effect of a failure to install the i
source for a reactor startup?
- a. Criticality can not be sustained.
- b. Criticality will be achieved with the Regulating Blade fully withdrawn.
r
- c. The Log N Channel will be out of calibration for startup.
- d. The B10 detector will be below level necessary to allow Control Blade withdrawal.
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(***** END OF CATEGORY A *****)
(********** END OF EXAMINATION **********)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 26 ANSWER:
001 (1.00) del.ETEE) l b.
REFERENCE:
l 1.
Safety Analysis Report, Section 5.2.2, " Reactor Operating Characteristics", page 28.
2.
Topic 9.
i ANSWER:
002 (1.00) a, b.
REFERENCE:
1.
Safety Analysis Report, Section 5.2.5, " Reactor Operating Characteristics", page 28.
2.
Topic 17.
P 4
ANSWER:
003 (1.00) d.
REFERENCE:
1.
Safety Analysis Report, Section 5.2.2, " Reactor Operating Characteristics", figure 6.
2.
Topic 20.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
- A.
RX THEORY, THERM 0 & FAC OP~ CHARS Page 27 l
r ANSWER:
004 (1.00) i C.
REFERENCE:
.i 1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition,' page i
284.
2.
Topic 8 3.
P(2) = P(l)
- e (t/T)
.l 8 x 10E3 = 10
- e (1800/T) 1800/T = In (8 x 10E3/10) j T - 1800/6.68 - 269.28 l
i ANSWER:
005 (1.00)
.j c.
REFERENCE t
)/(1-Keff)
(CR /CR ) = (1-Keff'Keff )
2 (60/30)3 - (0.90)(1-2 Keff = 0.95
- 1 z
ANSWER:
006 (1.00)
C.
h
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 316.
2.
Topic 5.
'l
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
r
l A.
RX1 THEORY, THERM 0 & FAC OP CHARS Page 28 I
i ANSWER:
007 (1.00) c.
I
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition,~page 286.
2.
Topic 6.
3.
k - 1 / (1-beta) k-I when roe - beta l
ANSWER:
008 (1.00) d.
REFERENCE:
j 1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 47.
2.
Topic 1.
3.
Reaction rate is proportional to (cross section
- number of atoms)
ANSWER:
009 (1.00)
C.
i i
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, pages 102, 282.
2.
Topic 7.
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i
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 29-t ANSWER:
010 (1.00)
I b.
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 303.
2.
Topic 16.
i i
i ANSWER:
011 (1.00)
DELETED c.
i
REFERENCE:
.t 1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 322.
2.
Topic 18.
ANSWEP-012 (1.00)
DELETED r
b.
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 57.
2.
Topic 2.
3.
Cross sections are proportional to 1/ neutron velocity (v) f
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
i
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 30 l
ANSWER:
013 (1.00) d.
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 1
248.
j 2.
Topic 4 P
t ANSWER:
014 (1.00) a.
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page.
t 350.
2.
Topic 3 i
ANSWER:
015 (1.00) l b.
't
REFERENCE:
1.
Safety Analysis Report, Section 2.1, " Reactor Operating Characteristics", page 9.
2.
Topic 19.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
i
s A.
RX THEORY, THERM 0 & FAC OP CHARS
'Page 31 ANSWER:
016 (1.00) b.
I
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 102.
i 2.
Topic 13.
3.
keff 01/C2 j
1 i
1 ANSWER:
017 (1.00) a.
i
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 290.
j 2.
Topic 16 i
3.
roe - betabar/((lamdaeff
- period) + 1) roe = 0.0065/((0.08
- 60) + 1) l roe - 0.0065/(4.80 + 1) roe - 0.0065/5.8 l
roe - 1.12 x 10E-3 roe / inch
.1.12 x 10E-3 / 2 - 5.6 x 10E-4 t
ANSWER:
018 (1.00)
C.
L
REFERENCE:
1.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, Figure 7.14, page 323.
j 2.
Topic 10 i
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
t i
A.
RX THEORV, THERM 0 & FAC OP CHARS Page 32 ANSWER:
019 (1.00) c.
REFERENCE:
i
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 289.
i i
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ANSWER:
020 (1.00) f i
d.
REFERENCE:
1.
Safety Analysis Report, Section 4, " Reactor Facility Description",
page 26.
2.
Topic 14.
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(***** END OF CATEGORY A *****)
I
(********** END OF EXAMINATION **********)
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A.
RX THEORY, THERM 0 & FAC OP CHARS Page :1-ANSWER KEY MULTIPLE CHOICE 001 b
DELETED 002 a,b I
003 d
004 c
005 c
006 c
007 c
008 d
009 c
010 b
011 c
DELETED l
4 012 b
DELETED
'l 013 d
014 a
015 b
016 b
017 a
018 c
019 c
020 d
(***** END OF CATEGORY A *****)
(********** END OF EXAMINATION **********)
9
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U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION l
FACILITY:
Worcester Poly.- Inst.
REACTOR TYPE:
Pool i
DATE ADMINISTERED:
1993/09/13 REGION:
I CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.
Points for each question are indicated in paren-theses for each question. A 70% is required to pass the examination.
Examinations will be picked up one (1) hour after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY r
19.00 100.00 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL' CONTROLS 19.00 TOTALS FINAL GRADE All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature l
1
t B.
NOPJ4AL/EMERG PROCEDURES & RAD CON.
Page 2 i
s 1
- SHEET ANSWER l
J Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
]
MULTIPLE CH0 ICE 001-a b
c d
002 a
b c
d
]
003 a
b c
d 004 a
b c
.d i
005 a
b c
d
'[
006 a
b c
d 007 a
b c
d l
i 008 a
b c
d j
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 7
015 a
b c
d
[
016 a
b c
d l
017 a
b c
d
- 018 a
b c
d r
019 a
b c
d i
020 a
b c
d i
(***** END OF CATEGORY B *****)
(********** END OF EXAMINATION **********)
i i
3 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 i
the examination cover sheet.
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- 6. Fill in the date on the cover sheet of the examination (if necessary).
e
- 7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets.
- 8. Each question is worth one (1) point.
Partial credit will NOT be given.
- 9. If the intent of a question is unclear, ask questions of the examiner f
- only, i
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B.
NORMAL /EMERG PROCEDURES _& RAD CON-Page 6 l
QUESTION: 001 (1.00)
[)ElJEllEE) f WHICH ONE (1) of the following is a REPORTABLE Occurrence?
j
- a. The Safety System Setting for reactor period was set at 15 seconds and caused a Reactor scram.
- b. Shutdown Margin was calculated as 2% delta k/k.
- c. The B10 chamber is IN0PERABLE while the reactor is SHUTDOWN.
- d. A test procedure requires the pool temperature to be raised to 105 degrees F. while operating at 10 kw.
P P
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 7 j
l QUESTION: 002 (1.00) l WHICH ONE (1) of the following is a violation of Technical Specifications with regard to conducting experiments 7 i
- a. A sample to be irradiated inserts 0.75% delta k/k positive reactivity.
- b. An experiment has' a moving Plutonium ball that inserts 0.1%
.I delta k/k positive reactivity,
- c. A bomb fragment containing 15 mg of UNEXPLODED TNT is to be irradiated for activation analysis.
- d. A previously approved experiment is performed a second time j
without the second approval of the Radiation, Health, and i
Safeguards Committee (RHSC).
-i 5
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i 1
-1
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 8'
i
-QUESTION: 003 (1.00) l WHICH ONE (1) of the following Safety System settings may be BYPASSED during " critical operation" of the reactor?
- a. Neutron Count rate
- b. Reactor period
- c. Pool water level
- d. Manual scram switch l
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B.
NORMAL /EMERr, PROCEDURES & RAD CON Page 9 i
QUESTION: 004 {1.00)
WHICH ONE (1) of the following is a violation of a Safety Limit (L.C.O.)
with regard to blade drop times.
l t
- a. Magnet release time for blade 2 is 100 msec.
}
1
- b. Drop time for blade 2 to insert the FULL 32 inches is 650 msec.
- c. Magnet release time for blade 3 is 80 msec and the drop time to q
insert the FULL 32 inches is 600 msec.
t
- d. Magnet release time for blade 3 is 70 msec and the drop time to j
insert the FIRST 24 inches is 550 msec.
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l
B.
_ NORMAL /EMERG PROCEDURES & RAD CON
- Page 10 t
i QUESTION: 005 (1.00)
WHICH ONE (1) of the following is the basis for maintaining ten (10) feet of water above the reactor during 10 kw operation?
[
t'
- a. Provides sufficient net positive suction pressure for pool circulating and cleanup pump.
- b. Provides shielding to limit dose rates at the water surface to less than 50 mR/hr.
[
- c. Provides sufficient delta T to establish natural circulation f
through the core.
i
- d. Provides adequate heat sink for the design basis positive reactivity excursion.
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 11 l
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I QUESTION: 006 (1.00)
The following conditions exist:
- 1. Operator "A" works a standard forty (40) hour work week.
- 2. His duties require him to work in a radiation area four (4) hours i
a day.
1
- 3. The dose rate in this area is 10 mR/ hour.
I WHICH ONE (1) of the fellowing is the MAXIMUM number of days Operator "A" may perform his duties without exceeding 10 CFR 20 limits?
- a. 12 days l
- b. 25 days j
- c. 31 days
- d. 75 days i
I 3
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j B.
NORHAL/EMERG PROCEDURES & RAD CON Page 12 i
QUESTION: 007 (1.00)
The following conditions exist:
- 1. An irradiated point source measures 10 R/hr at one (1) foot.
1
- 2. A High Radiation Area boundary needs to be established around l
the source.
WHICH ONE (1) of the following is the distance away from the. source where the High Radiation Area boundary should be located?
- a. 5 feet
- b. 10 feet
- c. 50 feet
- d. 100 feet l
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I i
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B. L NORMAL /EMERG PROCEDURES & RAD CON Page 13 QUESTION: 008 (1.00)
The following' conditions exist:
- 1. A High Radiation area must be established in a room for an-experiment that will last for six (6) months.
- 2. The Area has been posted as a High Radiation Area.
WHICH of the following additional actions must be taken for access to the High Radiation Area?
- a. Place a break away lock on the door.
- b. Equip the door with an audible or visible alarm.
- c. Place portable radiation monitors in the area.
- d. Equip the area with surveillance cameras.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NORMAL /EMERG-PROCEDURES & RAD CON Page 14 QUESTION: 009 (1.00)
The following conditions exist:
- 1. A radioactive spill has created a need to evacuate the facility.
- 2. The spill contaminated one (1) individual.
WHICH ONE (1) of the following actions should be taken by the contaminated individual?
- a. Report to Room 106 of the Project Center for monitoring and decontamination,
- b. Report to the WPI Infirmary for monitoring and decontamination.
- c. Remain at the location until monitored and released by the Campus Radiological Safety Officer.
- d. Exit the building to a safe location and wait for further instructions from the Campus Radiological Safety Officer.
(***** C ATEGORY B CONTINUED ON NEXT PAGE *****)
- B.
NORMAL /EMERG PROCEDURES & RAD CON Page 15 i
t QUESTION: 010 (1.00).
The following conditions exist:
- 1. The reactor is operating at 10 kw.
- 2. An experiment using the Beam Port is in progress.
- 3. The Fixed Radiation Monitor for the Beam Port has just failed.
WHICH ONE (1) of the following is the MINIMUM action required per Technical Specification?
- a. Stop use of the Beam Port until the Fixed Radiation Monitor is OPERABLE.
- c. Operation may continue as long as alternate monitoring is provided by the Fixed Area Monitor for the Thermal Column Door.
- d. Operation may continue provided alternate monitoring and alarms are provided by a portable radiation monitor with a range of 0.1 to 50 mrem /hr.
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4'
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 16 l
QUESTION: 011 (1.00) i The following conditions exist:
- 1. A sample has just been irradiated.
i
- 2. One (1) minute after irradiation the sample was yielding a dose rate of 500 mR/hr at six (6) inches.
t
- 3. Half life of the sample is 60 seconds.
WHICH ONE (1) of the following is the dose rate of the sample at six (6) inches five (5) minutes after irradiation?
- a. 9.1 mR/hr t
- b. 16 mR/hr
- c. 31 mR/hr i
- d. 472 mR/hr
}
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I
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 17-QUESTION: 012 (1.00)
WHICH ONE (1) of the following is designated as the Emergency Support Center during a site emergency and facility evacuation?
- a. WPI Campus Police Department
- b. Worcester Police Department
- c. Project Center
- d. Atwater Kent Laboratories
)
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a b
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page IB QUESTION: 013 (1.00)
The following conditions exist:
- 1. The reactor has been operating at 10 Kw for one (1) hour.
- 2. Safety Channel 1 fails high.
- 3. Safety Channel 2 continues to indicate 10 kw reactor power,
- 4. N0 other changes in reactor status are observed.
WHICH ONE (1) of the following operator actions should be taken?
- a. Initiate a MANUAL reactor trip.
i
- b. Ensure recorder channel select switch is selected to the OPERABLE channel.
- c. MANUALLY insert the Regulating Blade until the reactor is subtritical.
y
- d. MANUALLY insert the Regulating Blade until Safety Channel 1 indicates less than or eoual to 10 kw.
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 19 1
i QUESTION: 014 (1.00) l WHICH ONE (1) of the following approvals are required for a change to an i
Emergency Procedure?
l
- a. Facility Director
- b. Dean of Faculty f
- c. A Licensed Operator l
- d. Radiation, Safety, and Safeguards Committee i
+
+
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B.
NORMAL /EMERG PROCEDURES & RAD CON.
Page 20 QUESTION: 015 (1.00) k'HICH ONE (1) of the following will be the result of the " Power Level Calibration Procedure" if the detector dead time is 15% during the counting of the irradiated gold foil?
- a. Calculated power level will be less than actual because the detector efficiency is incorrect.
- b. Calculated power level will be higher than actual because the detector efficiency is incorrect.
f
- c. Calculated power will be the same but a longer counting time is-l needed.
- d. Calculated power will be the same but a broader photopeak will be observed.
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.4
B.
NORMAL /EMERG PROCEDURES & RAD CON
_Page 21 e
QUESTION: 016 (1.00) f WHICH ONE (1) of the following staffing conditions meets the requirements for a MINIMUM staff for critical reactor operation?
- a. One (1) licensed reactor operator at the controls and one~(1, licensed reactor operator in the reactor facility.
t
- b. Two (2) non-licensod students at the controls with a senior operator observing at their side.
i
- c. One (1) licensed reactor operator at the controls with a senior operator on call.
r
- d. One (1) licensed reactor operator at the controls with a student observing and a senior operator on call.
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B.
NORMAL /EMERG PROCEDURES & RAD _ CON Page 22 QUESTION: 017 (1.00)
WHICH ONE (1) of the following is the affect of the automatic temperature compensator elements being at 90 degrees F. when conducting the " Pool Water Conductivity Meter and Probe Calibration Checks"?
- a. Measured temperature will be HIGHER.
- b. Measured resistances will be LOWER.
I
- c. Measured conductivity will be LOWER.
- d. Measured temperature will be LOWER.
?
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 23 i
QUESTION: 018 (1.00) t WHICH ONE (1) of the following pool levels would be considered NORMAL when conducting Reactor Check-Out Visual Checks?
- a. Two (2) inches above the overflow.
- b. Six (6) inches below the overflow.
- c. Two (2) feet below the Reactor Bridge.
- d. Six (6) feet below the Reactor Bridge.
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 24 QUESTION: 019 (1.00) i WHICH ONE (1) of the following radiation sources may be used for calibration of the Area Radiation Monitors?
i
- a. 137 Cs source
- b. 32 P source
- c. 226 Ra source
- d. Pu-Be source R
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 25 l
QUESTION: 020 (1.00) 1 WHICH ONE (1) of the following individuals supervises the control and distribution of keys to the Reactor Facility?
- a. Director of Campus Security i
- b. Dean of Faculty
- c. Chairman of the Radiation, Health, and Safeguards Committee
- d. Facility Director t
?
(***** END OF CATEGORY B *****)
(** ** ** ** ** END OF EXAMINAT ION * * ******* *)
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 26 ANSWER:
001 (1.00)
DELETED d.
REFERENCE:
i 1.
Technical Specifications 1.0, " Definitions", page 2.
2.
Topic - Technical Specifications g.
r ANSWER:
002 (1.00) a.
REFERENCE:
t 1.
Technical Specifications 2.3, " Experiments", page 4.
I 2.
Topic - Technical Specifications a.
t i
ANSWER:
003 (1.00) j c.
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REFERENCE:
1.
Technical Specifications, Table 4.1, page 10.
l 2.
Topic - Technical Specifications f.
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)
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B.
NORMAL /[MERG PROCEDURES & RAD CON Page 27 I
ANSWER:
004 (1.00)
L d.
REFERENCE:
1.
Technical Specifications 2.0, " Safety Limits", page 3.
2.
Topic - Technical Specification c.
B ANSWER:
005 (1.00) t b.
REFERENCE:
1.
Safety Analysis Report, Section 4, " Facility Description", page 27.
2.
Topic - Technical Specification d l
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t ANSWER:
006 (1.00)
C.
[
REFEREt:CE:
i 1.
Radiation, Health And Safeguards Committee (RHSC), page 1.
2.
Topic - Radiation Control g.
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1 B.
NORMAL /EMERG PROCEDURES & RAD CON Page 28 1
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' ANSWER:
007 (1.00) b.
I
REFERENCE:
1.
Radiation, Health And Safeguards Committee (RHSC), page 2.
l 2.
Topic - Radiation Control c.
3.
DR(1)/DR(2) - Distance (2) squared / Distance (l) squared l
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t ANSWER:
008 (1.00) b.
i h
REFERENCE:
i i
1.
Radiation, Health And Safeguards Committee (RHSC), page 2.
l 2.
Topic - Radiation Control a.
f ANSWER:
009 (1.00) a.
i L
REFERENCE:
1.
" Reactor Operating Procedures", page 38c.
F 2.
Topic - Radiation Control b.
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 29 ANSWER:
010' (1.00) l d.
REFERENCE:
i 1.
Technical Specification 3.0, " Surveillance Requirements", page 7.
2.
Topic - Radiation Control f.
P ANSWER:
011 (1.00) i i
c.
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REFERENCE:
l.
" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 23.
2.
Topic - Radiation Control d.
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ANSWER:
012 (1.00) a.
REFERENCE:
1.
Emergency Preparedness Plan, page 7 2.
Topic - Emergency Procedures b.
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' B.- NORMAL /EMERG PROCEDURES & RAD CON Page 30 i
1 P
ANSWER:
013 (1.00) f a.
REFERENCE:
l 1.
Technical Specifications 2.2, " General Operating Limitations", page 4.
2.
Topic - Emergency Procedures e.
i ANSWER:
014 (1.00) d.
I e
REFERENCE:
1.
Technical Specifications 5.5, " Procedures", page 11.
2.
Topic - Normal Procedures b.
ANSWER:
015 (1.00) a.
REFERENCE:
t 1
Operating and Test Procedures, " Power Level Calibration Procedure",
page 15.
I 2.
Topic - Normal Procedures c.
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 31 ANSWER:
016 (1.00) d.
REFERENCE:
i 1.
Technical Specifications 2.2, " General Operating Limitations", page 4.
2.
Topic - Normal Procedures g.
ANSWER:
017 (1.00) b.
REFERENCE:
1.
Operating and Test Procedures " Pool Water Conductivity Meter and.
Probe Calibration Checks", page 23.
2.
Topic - Normal Procedures i.
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ANSWER:
018 (1.00) b.
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REFERENCE:
1.
Operating and Test Procedures, " Check-Out and Operation", page 1.
1 2.
Topic - Normal Procedures p.
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 32 i
ANSWER:
019 (1.00) l
}
a.
REFERENCE:
1.
Operating and Test Procedure, " Area Monitor Calibration Procedure",
page 45.
2.
Topic - Normal Procedures o.
1 3.
Of the four choices Cs is the only gamma source.
4 ANSWER:
020 (1.00) d.
REFERENCE:
I 1.
Safety Analysis Report, Section 6, " Reactor Operating Procedures",
page 31.
2.
Topic - Normal Procedures d.
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e B.
NORMAL /EMERG PROCEDURES & RAD CON Page 1 ANSWER KEY MULTIPLE CHOICE 001 d
DELETED 002 a
003 c
004 d
005 b
006 c
007 b
008 b
009 a
010 d
011 c
012 a
013 a
014 d
015 a
016 d
017 b
018 b
019 a
020 d
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