ML20203H264
| ML20203H264 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 02/11/1998 |
| From: | Isaac P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203H261 | List: |
| References | |
| 50-223-OL-98-01, 50-223-OL-98-1, NUDOCS 9803030186 | |
| Download: ML20203H264 (15) | |
Text
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e LS. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50 223/OL 98 01 FACILITY DOCKET NO.:
50 223 FACILITY LICENSE NO.:
R 125 FACILITY:
University of Massachusetts - Lowell EXAMINATION DATES:
January 30,1998 EXAMINER:
Patr saac, Chief Examiner ed
// 98 SUBMITTED BY:
I
~
PgekIsa{oJ/ief Examiner
/ /
Date
SUMMARY
During the week of January 26,1998, NRC administered a retake of section B of the written examination to one Reactor Operator candidate. The candidate passed the examination.
P.EPORT DETAILS 1.
Examiners:
Patrick Isaac, Chief Examiner 2.
Results:
RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall Written 1/0 N/A 1/0 Operating Tests N/A N/A N/A Overall 1/0 N/A 1/0 ENCLOSURE 1_
9003030106 900217 PDR ADOCK 05000223 V
o NRC RESOLUTIONS WRITTEN EXAMINATION i
QUESTION fB.01)
- 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 shleiding was to be used, a Radiation Area barrier would have to be erected from the source at a distance of approximately:
a.
48 inches b.
21 inches c.
12 inches d.
6 inches Answer: b Facility Commi J There appears to be no correct answer to this question using the source strength stated.
NRCEensluttom Comment Accepted. The correct answeris 56 ft. This question will be deleted from the examination.
ENCLOSURE 2 f
,-r c,-
n.
1.,
r,
U. S NUCLEAR REGULATORY COMMISSION 1
NON POWEl1 REACTOR LICENSE EXAMINATION FACILITY:
University of Massachusetts - Lowell.
l DATE ADMINISTERED:
01/30/98 l
CANDIDATE:
l INSTRUCTIONS TO CANDIDATE:
- Answers are to be written on the answer sheet provided. Attach any answer sheets to the examination. Points values are indicated in parentheses for each question. A 70% is required to pass the examination. Examinations wi!! be picked up one (1) hour after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE 10TAL SCORE VALUE CATEGORY 19.00 100.00 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 3 6
-,---w.
v m,e.
- ~ ' + ' - - -
G 4
B. NORMAUEMERG PROCEDURES & RAD CON -
Page 2 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 abcd
- 002 a - b c d 003 1 2
3 4
004 abcd 005 a b c d _
i-i 000 - a b c d 007 a b c d 1008 a b c _ d 009 e b c d 010 a b c d
.011 a b c'd i
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 c 018 _ a b c - d -
019 a b. c d ___
E
(""""" END OF EXAMINATION *""""*)
_a
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l t
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 neither received nor 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 reproductiens.
5.
Print your name in the blank provided in die upper right hand corner of the examination cover sheet and each answer sheet.
6.
Mark your answers on the answer sheet provds. USE ONLY Tile PAPER PROVIDED AND DO NOT WRITE ON Tile IIACK SIDE OF Tile PAGE.
7.
The point value for each question is indicated in [ brackets] after the question, 8.
If the intent of a question is unclear, ask questions of the examiner only.
9.
When turning in your examination, assemble the completed examination with examination questions. examination aids and answer sheets. In addition turn in all scrap paper.
10.
Ensure all infonnation 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 one (1) hour 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 still in progress. your license may be denied or revoked.
s EQUATION SHEET I
O = de or = n ox = UA or (p.p):
p p***
a 2a(k)I t' = 5 x 10:* seconds SCR =
y g
=
~p 1 - X,,,
A,,f =_ 0.1 seconds *1 ~
CR ( 1 - K,,,, ) = CR, ( 1 -K,,,,)
3 5
- G.0075
- I ~D )
- CN I"P I 1
1 2
1 - K* "*
SUR = 2 6. 0 6 M=
- tt Q-p e t t, P = P, 10 '"' 8 "
8 1
M*
=
1 - K,,,
CR, i
( 1 - K,,, )
.i SDM =
ya p e i
g p
ett T=
l' _
OII"P) p r.
p' p-p 0-p K,,,, - K,,,,
y_
gp,_ k,,,=K,,,
p' A,,,p 0.693 T* =
- ( g,,- 1 ) -
A p*
elf DR =DR,-e
- DR, d, * = DR, d,'
6ClE(n)
(P ~0)
(P '0)#
a t
DR =
p2
- Peak, Peak, I = Z,e * "
1 Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm i BTU = 778 ft lbf
'F = 9/5 'C + 32 1 g21(110) = 8 lbm
'C = 5/9 ('F - 32) 3 c3 a 1.0 BTUllbmi'F c,, = 1 callsec/gmi'C
= _, - _ - _ _ _ _ _
Section B: Normal /Emera. Emendures & Rad Con Page1 Qt;n S r. (B.1)
[1.0)
DELETED A small radioactive source is to be stored in the reactur 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.
48 Inches b.
21 inches c.
12 inches d.
6 inches Question (B.2)
[1.0)
A room contains a source which, when exposed, results in a general area dose rate of 175 millirem por hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room, a.
Post the area with the words
- Danger Radiation Area".
b.
.. quip the room with a device to visually display the current dose rate within the room.
c.
Equip the room with a motion detector that will alarm in the control room.
d.
Lock the room to present inadvertent entry into the room.
Question (B.3)
[2.0)
Match the requirements for maintaining an active operator license in column A with iN 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
Section B: Normal /Emera. Procedures & Rad Con Page 2 Question (B.4)
[1.0)
I Consider two point sources, each having the sarne curie strength. Source A's gammas have an energy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading l
from the same Geiger 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.5)
[1.0)
Which one of the following is the definition for ' Annual Limit on latake" (All)?
The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, a.
results in a total effective dose equivalent of 100 millirem, b.
10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 0 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.
The effluent concentration of a radionuclide in air which, if inhaled continuously over a c.
year, would result in a total effective dose equivalent of 50 rnillirem for noble gases.
d, Projected dose commitment values to individuals, that warrant protective action following a release of radioactive material.
Question (B.6)
[1.0)
P = 125 kW(max)
T, = 108'F (max)
L = 24.25 ft (min)
The above variabbs associated with core thermal and hydrautic performance are:
Safety limits in the natural convection mode (full pool level).
a.
b.
Safety limits in the natural convection mode (low pool level),
c.
LSSS in the natural convection mode (full pool level).
d.
LSSS In the natural convection mode (low pool level).
\\
Section B: Normal /Emera Procedures & Rad con Page 3
- Question (B.7)
[1.0)
Which one of the following statements is TRUE concerning samples?
a.
No single experiment shall have a worth of f Of% AK/K or greater.
b.
The reactivity worth of any moveable sample is limited to 0.2% AK/K.
c.
Samples having a worth of f 0.2% AK/K or greater will only be inserted via the incore system if the reactor remains suberitical after the insertion.
d.
Samples estimated at <0.02% AK/K are not expected to have any significant reactivity worth.
Question (B.8)
[1.0)
When attempting to move a control blade, no indication of movement on the position indicator was detected. The action required to be taken is to:
a.
deenergize the affected control blade and attempt recovery if the blade was not stuck.
b.
dispatch the Auxiliary Operator to visually inspect and attempt to free the affected control blade, c.
maintain stable plant conditions and notify the Reactor Supervisor and wait for instructions, d.
drive the other blades and Regulating Rod fully in, then verify the reactor is subcritical.
Question (B.9)
[1.0) 4 While the reactor is at rated power, what is the greatest allowed discrepancy between nuclear instrumentation channels before a calorimetric is required?
a.
2%
b.
3%
C.
4%
d.
5%
l
Section B: Normal /Emera Procedures & Rad Co_n Page 4 Question (B.10)
[1.0) l The reactor is operating at 90% (900 kW). The ventilation system is to be temporarily doenergized for inspections. Negative pressure will be maintJned by temporary fans. Which one of the following correctly descri%s the actions to be taken?
Shut.%n the reactor. Technical Specifications do not allow operations of the reactor a
without a fully operating ventilation system.
l b.
Based on the discretion of the Reactor Operator, reactor operations may continue if the duration of the ventilation outage is less than 15 minutes.
c.
Reactor operations may continue based on the discretion of the Senior Reactor
- Operator, d.
Shutdown the reactor if the duration of the ventilation outage will exceed one hour.
Question (B.11)
[1.0)
Which one of the following is NEVER allowed in the reactor containment building?
a.
Gun powder b.
Liquid Nitrogen c.
Mercury thermometer d.
Peroxides Question (B.12)
[1.0)
Which one of the following is the major hazard of concern when venting a Co-60 cask?
a.
Ar-41 gas b.
loose particulate c.
radiation streaming d.
steam
_ = _
=
. = =
.=
l
i Section B:... Normal /Emerg. Procedures & Rad con Page5 Question (B.13)
[14 Assume a core configuration is designated C 5-3. Which one of the following would require that the number 5 in the designation C 5 3 be changed?
a.
The exchange of a fuel element with another of the same configuration, b.
The exchange of a graphite element with another of the same type, c.
A change in the fuel configuration.
d.
The addition of a new graphite element.
Quertion- (B.14)
[1.0)
Which one of the following combinations of radiation monitoring detector a! arms would require initiation of the " Limited Radiation Emergency Alarm"(LREA)?
a.
Stack monitor (B) and Hot Cell Area monitor (H).
b.
Reactor Constant Air monitors (C and D).
c.
Building Exhaust monitor (1) and Fission Product monitor (E).
d.
Control Room monitor (R) and Pump Room monitor (P).
Question (B.15)
.[1.0)
In order to ensure the health and safety of the public,10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate from Tech. Specs?
a.
USNRC b.
Reactor Supervisor c.
Licensed Senior Reactor Operator.
d.
Licensed Reactor Operator.
r P
r e
Stetion B: NormaLEmera. Procedures & Rad _Qgn Page 6 Question (B.1C/
[1.0)
According to the SAR, Ar-41 production is potentially the greatest in:
a.
thermal column case vent b.
beam ports c.
pneumatic tubes E
d.
primary coolant Question (B.17)
[1.0)
Which ONE of the following persons is responsible for making the decision to downgrade an emergency cla::ific1 tion?
a.
The Emergency Director.
b.
Radiation Safety Officer c.
Reactor Supervisor d.
Facility Director Question (B.18)
[1.0)
The reactor is considered " SECURED", according to Technical Specifications if:
a.
all operable cuntrol rods are inserted and the console key is removed.
b.
the reactor is suberitical by at least 0.7% Ak/k.
c.
ti ? console key is in the "OFF" position and removed.
d.
It contains insufficient fissile roerial to obtain criticality.
e Section B: Normal /Emera. PrMMures & Rad Con Page 7 Question (B,19)
[1.0)
The Technical Specifications prohibit reactor operations without an operable Emergency Exhaust System. Which one of the following is the reason for the abo"e?
. To ensure that the building vacuum will not exceed 0.2 psi, a.
b.
To maintain containment integrity.
To maintain a negative building pressure without unloading large fraction of airuorne c.
activity.
d.
- To reduce the concentration of radionuclides released to the environment by a factor of three.
- "" END OF EXAMINATION "*"
f Section B* Norrrigl/Emera. Procedures & Rad Con Page0 ANOWER (B44)
DELETED b
REFERENCE Glasstone & Sesonske,9.41, p 525.
DR= 6CE/(f)(f) = 5 = 6(2)(1,33)/x, x' = 3.19, x = 1.79 feet 2
)
ANSWER (B.02) d REFERENCE 10CFR20.1601(a)(3)
ANSWER (B.03) r 1 d. 2 1 3.b_
4 A REFERENCE 10CFR55 ANSWER (B.W) c REFERENCE GM is not sensitive to energy.
ANSWER (0.05) b REFERENCE 10CFR..?.1003 ANSWER (B.06) c REFERENCE T.S. 2.0 ANSWER (B.07) d REFERENCE RO-4 Addition or Removal of Core Sarnples: Sect. 4.0 ANSWER (B 08) d REFERENCE ULR Emergency Procedure EO-7, Rev 1.
ANSWER (B.09) l b
REFERENCE ULR Standing Order #4, Rev 2, Step 4.
Section B Normal /Emera Procedures & Rad Con Page 9 ANSWER (B.10) c REFERENCE RO-6 Step 6.6 ANSWER (B.11) 3 a
REFERENCE Starding Crder #1.
I ANSWER (B.12) d REFERENCE SP-24 Receiving Co-60 Source, step 4 " Caution".
ANSWER (B.13) a REFERENCE Standing Order #3 M
ANSWER (B.14)
Q b
REFERENCE ULR SAR, Appendix 10, p 10-21.
ANSWER (B.15) c REFERENCE 10CFR50.54(y)
ANSWER (B.16) b REFERENCE SAR, pg. 7-2.
ANSWER (B.17) a REFERENCE E Plan, Sect. 3.3 Termination of an Emergency ANSWER (B.18) d REFERENCE TS 1.18 ANSWER (B.19) c REFERENCE T.S. 3.5
'"" END OF EXAMINATION *""
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