ML20035H090
| ML20035H090 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 04/22/1993 |
| From: | Caldwell J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035H014 | List: |
| References | |
| 50-062-OL-93-01, 50-62-OL-93-1, NUDOCS 9305030109 | |
| Download: ML20035H090 (77) | |
Text
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ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-62/0L-93-01 FACILITY DOCKET NO.:
50-62 FACILITY LICENSE NO.:
R-66 FACILITY:
University of Virginia EXAMINATION DATES:
April 8, 1993 EXAMINER:
Frank Collins, /
Chief Examiner idf.Mec '< 0 Fo o C.s
/
/
i SUBMITTED BY:
F a k Collins, hi # Examiner Date APPROVED BY:
/)SC 8
13 Ja'es L. CaldwelT, Chief Date N -Power Reactor Section O erator Licensing Branch Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation I
SUMMARY
Operator licensing first retake examinations were conducted at the University l
of Virginia Reactor on April 8,1993. The examination was administered by Mr. Frank Collins to two Reactor Operator (RO) applicants. One applicant passed all sections of the examination. One applicant failed two sections of the examination.
Both applicants had raquested and were granted a waiver of the operating examination.
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PDR ADOCK 05000062 j
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REPORT DETAILS i
1.
Examiners:
j Frank Collins, Chief Examiner t
2.
Results:
i R0 SRO Total (Pass / Fail)
(Pass / Fail)
(Pass / Fail)
NRC Grading:
1/1 0/0 1/1 i
3.
Written Examination:
The written examination was administered on Thursday, April 8,1993-for f
the two R0 applicants.
Both applicants completed the examination within l
the allotted three hours.
Facility management concurrently reviewed the i
examination. The facility submitted comments on eight examination questions, which are included as Attachment 2 to this report. -The i
comments and their resolution were discussed by telephone with the facility on Friday, April 16, 1993.
Three questions, C-1, C-16, and C-17, were deleted because facility changes that were'not accurately described in the reference data rendered question and answer unrepresentative of the current facility.
i One question, C-9, was deleted because more than two of the four l'
optional answers could be considered to be correct.
Question A-7 was changed to correct a typographical error in the answer i
key.
Question A-8 was changed to accept option "c" as a correct answer in addition to option "d" because the current core loading is greater than the loading described in the reference data, enabling the facility l
condition described in option "c" to be valid for the question as stated.
I Question B-12 was clarified during the examination to the effect that i
the applicant was advised to consider the definition of "all modes" to l
be the same usage as found in Technical Specifications.
Part answer for r
part "b" of the question was corrected to be "7 (All Modes)" in accordance with Table #.1 of Technical Specifications.
Question C-12 was reviewed and found to be correct as stated.
Changes were hand entered in the master copy of the examination.
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Operating Tests:
i The applicant had requested and was granted a waiver of the operating examination based on previous satisfactory performance in accordance with the guidance provided in Examiner Standard ES-204.0.1 (Regionally Granted Routine Waivers) and ES-404.B.2 (Processing Waivers Requested by Operator and Senior Operator Applicants).
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5.
Exit Meeting.
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An exit meeting was conducted between Mr. Collins and Mr. Preston Farrar. The examiner explained the question clarifications that had been provided to the applicants during the examination and reviewed the procedures for submittal and resolution of facility comments.
1.
A 1
EXAMINATION REPORT 50-62/0L-93-01 SCHOOL OF ENGINEERING @
& APPLIED SCIENCE NUCLEAR REACTOR E4CILITY Department of Mechanical.
Aerospace & Nuclear Engineering University of Virginia Charlottesville. VA 22903-2442 8f4-982-5440 F AX: NM 482-5473 April 13,1993 Mr. Frank Collins U.S. Nuclear Regulatog Commission Mail Stop 10/D/22 Washington, D.C. 20555
Dear Mr. Collins:
This is to offer comments on the operator examination administered to Messrs.
Doyle and Wilson on April 8,1993.
Attached please find comments on 8 questions, some of which obviously had the wrong answer listed in the answer key. Your consideration of these comments will be appreciated.
Sincerely, Q-hmV J.Y. Farrar, Administrator U.Va. Reactor Facility
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Part A. Question 007 i
The reactor is critical at 10 kWt.
The regulating rod is pulled to insert a positive reactivity of $0.18.
I Which of the following will be the stable reactor period as a result of this-
)
reactivity insertion?
(Assume a beta of 0.0075 and a lambda of 0 1) l
-l' a.
10.5 seconds b.
45.5 seconds
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c.
55.5 seconds d.
65.5 seconds j
i The answer is 45.5 seconds, as calculated in the solutions provided. The correct i
answer is inadvertently indicated a being c, instead of b.
B should be accepted as the correct answer.
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Part A.
Question 008
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WAR scrammed after 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> of operation at 1.75 MWt.
The problem has been corrected and a start-up for return to power is commenced 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the i
i Which one of the following describes the reactor behavior during the start-up/ return to power?
I k
a.
After reaching power operation, rods will have to be withdrawn for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to xenon build-up.
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b.
After reaching power operation, rods will have to be withdrawn for the l
first 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> due to xenon burnout.
l c.
During the startup, rods must be almost fully withdrawn to attain
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criticality and then must be inserted for the first 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to maintain a l
constant power.
d.
During the startup, rods would be fully withdrawn and the reactor would remain suberitical until xenon has decayed for 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
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The correct answer indicated by official solutions is d, but it is questionable' that one could arrive at this with the information given. Rod positions during i
start-up will depend on the amount of excess reactivity in the cold, clean core, j
the steady-state xenon level attained (non-linear with steady-state power level j
and), total shim rod worths, and other less important considerations.
It is certainly possible that the situation described in d could occur, but'it is not 1
obvious that this is more likely to occur than that described.in c.
Since neither the amount of negative reactivity from steady-state plus rising-to' peak
-l xenon resulting from steady-state operation at 1.75 Mwt operation, nor values of
'l these other parameters are specified in the problem statement, it is not possible to determine if the WAR can be made to go critical. under the circumstances posed. Given that, e is also a reasonable response, since it describes the more usual start-ups (sometimes after recovery from a scram) performed with the WAR -
during the week as xenon builds in.
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1 Part B. Question 012
- For the instrumentation in Column I, SELECT the Operating Mode from Column 11 for j
which the instrumentation is required to be operable.
(Items in Column II may.
be used once, more than once, or not at all.
Only one answer may occupy each space in Column I.)
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COLUMN I COLUMN II i
(Instrumentation)
(Operational Mode) i 1
- a. Pool Water
- 1. Forced Convection
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Level Monitor
- 2. Natural Convection j
- 3. Reactor Startup j
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- b. Pool Water
- 4. Forced and Natural Convection i
Temperature
- 5. Reactor Secured I
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- 6. Reactor Shutdown 3
c.
Start-up Count Rate
- 7. All Modes i
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7
- d. Reactor Period i
The indicated answers in official solutions are as indicated above in Column I.
.r Parts b and d of this problem should be thrown out because. the problem is poorly l
posed with respect to them.
It was unclear whether choice 7, All Modes, was intended to mean "all of the above in Column II".. which is labeled as
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- Operational Modes," or whether it was meant to be defined as in. technical specifications Reactor Secured and Reactor Shutdown are not. considered f
operational modes for the UVAR, by their definitions and the definition. of j
" reactor operation" in technical specifications; clearly, reactor period is not required when the reactor is secured.
Table 3.1 and Table 3.2 in technical specifications list the various instruments and safety channels and when they are.
required; pool water temperature, according to Table 3.1, is required for-All Modes -- which in this case means operation in forced or natural convection, but not all of the " modes" listed in column II; in technical specifications, "all
' i modes" means startup, operation in forced convection, or operation in natural I
convection.
Parts a and c have indicated correct answers in official solutions which are consistent with the treatment of this material in technical specifications, and i
therefore, should remain valid.
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Part C. Question 001 1.
-Which one of the following types of fuel elements is designed for loading into the core to reduce the amount of core excess reactivity?
a '.
Standard MTR curved plate fuel element with 18 curved plates b.
Half loaded standard fuel element with 12 flat plates MTR curved plate fuel element with 9 curved plates c.
d.
Half-leaded fuel element with the 6 central flat plated removed The correct answer indicated in official solutions is b.
Mr. Doyle believes that c should be accepted as the or another correct answer.
B was correct at one time, when the UVAR was operated with flat-plate element assemblies; it no longer is. The currently-loaded partial element assembly types -
now has 18 curved plates, half of which (9) contain fuel. Mr..Doyle asked the examiner for clarification on this point.
He asked whether - response c was indicative of an element assembly of 18 curved plates, only 9 of which were fuel-bearing-(These are described in section 3.2 of the UVAR' Design and Analysis Handbook.). The examiner's response was affirmative, and so, c was selected as :
Mr. Doyle's response, with no doubt in his aind -- he has been handling the upcoming spent fuel shipment from the UVAR and is intimately familiar with the design of fuel assemblies currently loaded in the UVAR.
C should be accepted as the correct answer to this question, and future questions should not quiz applicants on any information dealing with the outmoded flat plat elements.
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.Part C.'Ouestion 009
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Which one of the following will satisfy the scram logic and allow the operation of the reactor with reactor coolant flow less than 900 gpm?
i
.. t reactor coolant header in the down position a.
b.
reactor coolant pump switch in the off position c.
reactor power less than 200 kW i
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d.
scram logic drawer range switch in the 200 Kw position 1
The indicated correct answer in official solutions is a.
1 The reference is the Design and Analysis Handbook, page 3-37.
[
One must assume for this problem that the UVAR is operating in natural convection-l mode. The reactor SCRAMS are not re-settable for conditions of header-down, pump l
on, and header up, flow less than 900 gpm.
Given that, it is. impossible to j
choose any of the responses offered as better than the others; all of the choices are requirements for natural convection operation. The intent of the referenced comment about "no flow indicated by the flowmeter providing the header is down" j
is to point out that in natural convection mode, there is coolant flow, but there
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is no direct indication of its magnitude. Noted elsewhere is that the pump must also be off, the header down,-and the range switch in the 200 Kw position for
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operation in natural convection at up to,200 Kwt.
This is a poorly l posed r
question and it should be thrown out.
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'I Part C. Question 012 I
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Which of the following describes the design of the demineralized makeup system that prevents the back-flow of water into the city water system?.
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f Unprocessed city water is discharged through a float valve-to the catch-a.
tank and the float valve isolates the discharge before the catch tank level rises j
above the discharge pipe.
1 b.
Unprocessed city water is discharged to the catch tank through a stand-j
- pipe, f
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Deionized city water is discharged to the pool through a float valve that
.I c.
isolates the discharge before pool level rises above the discharge pipe.
-[
Deionized city water is discharged to the pool through a. stand-pipe.
f d.
I The indicated correct answer in official solutions is d, which is' incorrect.
I r
Two answers should be accepted as correct for this question.
- The - UVAR - is equipped with two water make-up systems. One of these, located in the reactor 4
room, is described by response d.. The other source of make-up water is. through the pool demineralizer system, as described in Section 4.2 of the UVAR Design and Analysis Handbook and diagrammed on page 89 of the UVAR Operator training manual.
The method of isolation of the city water system from the reactor coolant system is accurately described by response a, which should, therefore, be accepted as j
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a second correct response.
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Part C. Question 016
'ii SELECT the choice that completes the following statement.
Upon a high radiation condit. ion on the Reactor Bridge, the Reactor Room door i
I a.
will close causing the Reactor Room air to be recirculated at 2700 cfm through the exhaust ducts to the absolute filters on the mezzanine floor and returned through floor registers.
b.
and the exhaust ducts will close but the stack exhaust flow rate will
[
remain approximately 8600 cfm due to operation of an exhaust fan intake on the Reactor Building roof I
c.
and the exhaust ducts will close but the Reactor Room air will be recirculated at 2700 cfm through the absolute filters utilizing the floor I
registers.
r
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the exhaust ducts, and the floor register will close causing the stack exhaust flow rate to decrease by nearly 7000 cfm due to the loss of any exhaust l
flow from the Reactor Room j
i The indicated correct response in official solutions is b.
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At present, a high radiation condition at the Reactor Bridge initiates isolation
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of confinement, in part, by de-energizing controlling magnets which remotely hold
.i open the duct vent door. The door then drops and remains closed'under force of gravity. At the same time the door is dropped, power to the vent fan is cut, as switch contacts, normally held closed by a steel plate attracted by the energized -
controlling magnets, are allowed to open.
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This question should be thrown out because all of the choices offered fail to j
J describe the current configuration and operation of the Reactor Room ventilation system upon a high radiation condition on the Reactor Bridge.
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<j Part C. Question 017 SELECT the choice that completes the following statement.
Both beam ports have been drained. A reactor scram will be actuated if the beam I
port neutron detector detects neutrons
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on the outside of the blockhouse beam stop j
a.
l b.
in the beam path of the beam port at the neutron camera station in the light mean of the light beam actuator inside the beam port -
c.
d.
in the beam port sight glass vent tube.
I Response c is indicated by official solutions to be the correct response.
{
Response c is not correct, and in fact, no reasonable response was available to.
the candidates.
There will be a scram initiated in the beam port area if the light beam is interrupted while one or both beam ports ' are drained and the l
reactor is operating (as indicated by neutrons detected in the area). This would i
be an indication of personnel entry of the blockhouse while a high radiation level existed inside.
The scram is not initiated as a result of neutron detection, except in coniunction with the li ht beam being broken, nor is it initiated as a result only of high neutron level detection anywhere in any of the
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S locations offered as choices. Section 6.6.A.4 of UVAR SOPS describes the actual combination of conditions that will initiate a reactor SCRAM in the course of beamport operation. This problem should be thrown out.
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Nuclear Regulatory Commission Operator Licensing Examination I
This document is removed from Official Use Only category on date of examination.
I NRC Official'Use Only i
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U.
S.
NUCLEAR REGULATORY COMMISSION j
NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
UNIV. OF VIRGINIA j
REACTOR TYPE:
UVAR DATE ADMINISTERED:
1993/04/08 REGION:
2 i
.7 CANDIDATE:
3 LICENSE APPLIED FOR:
V
.a t
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.V V !i K INSTRUCTIONS TO CANDIDATE:
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Answers are to be written on the exam page itself, or the answer sheet provided.
Write answers one side ONLY.
Attach any answer sheets to'the examination.
Points for each question are indicated in_ parentheses for each question.
A 70% in each section is required to pass the examination.
i Examinations will be picked up three (3) hours after the examination i
starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY i
VALUE TOTAL SCORE VALUE CATEGORY 20.00 31.75 A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 21.00 33.33 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS i
22.00 34.92 C.
PLANT AND RADIATION MONITORING SYSTEMS 63.00 TOTALS FINAL GRADE
[
All work done on this examination is my own.
I have neither given nor received aid.
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Candidate's Signature I
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'A.
RX THEORY, THERMO & FAC OP CHARS Page 1
ANSWER SHEET Multiple Choice (Circle or X your choice)
[
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a
b c
d 002 a
b c
d i
003 a
b c
d 004 a
b c
d
'005 a
b c
d e
006 a
b c
d t
G07 a
b c
d l
008 a
b c
d 009 a
b c
d 010 a
b c
d
[
011 a
b c
d i
012 a
b c
d i
1 013 a
b c
d 014 3
b c
d I
i 015 a
b c
d 016 a
b c
d 017 a
b c
d 018 a
b c
d f
i 019 a
b c
d 020 a
b c
d l
(***** END OF CATEGORY A *****)
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B.
NORMAL /EMERG PROCEDURES fn RAD CON Page 2
ANSWER SHEET t
Multiple Choice (Circle or X your choice) i If you change your answer, write your selection in the blank.
.i MULTIPLE CHOICE 017 a
b c
d 001 a
b c
d 018 a
b c
d I
r 002 a
b c
d 019 a
b c
d i
l 003 a
b c
d 020 a
b c
d 004 a
b c
d i
005 a
b c
d I
i 006 a
b c
d 1
007 a
b c
d 008 a
b c
d I
009 a
b c
d I
010 a
b c
d 011 a
b c
d 012 MATCHING I
a b
l C
d l
MULTIPLE CHOICE 013 a
b c
d
.I 014 a
b c
d 015 a
b c
d I
016 a
b c
d l
(***** END OF CATEGORY B *****)
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C. ' PZANT AND RAD MONITORING SYSTEMS Page 3
i ANSWER SHEET
-i Multiple Choice (Circle or X your choice)
I If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 021 MATCHING I
001 a
b c
d a
l 002 a
b c
d b
003 a
b c
d c
i 004 a
b c
d d
1 005 a
b c
d 006 a
b c
d 007 a
b c
d i
008 a
b c
d
.009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d
-013 a
b c
d, f
014 a
b c
d 015 a
b c
d i
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 *****)
(********4* END OF EXAMINATION **********)
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t NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l
During the administration of this examination the following rules apply:
i 1.
Cheating on the examination means an automatic denial of your application t
and could result in more severe penalties.
f
- 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 t
received or given assistance in completing the examination.
This must be i
done after you complete the examination, i
- 3. Restroom trips are to be limited and only one candidate at a time may
[
1 eave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
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I 4.
Use black ink or dark pencil only to facilitate legible reproductions.
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5.
Print your name in the blank provided in the upper right-hand corner of
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the examination cover sheet.
6.
Fill in the date on the cover sheet of the examination (if necessary).
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- 7. The point value for each question is indicated in parentheses after the question.
The amount of blank spece on an examination question page is i
NOT an indication of the depth of answer required.
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8.
If the intent of a question is unclear, ask questions of the examiner i
only.
- 9. When turning in your examination, assemble the completed examination with I
1 examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
- 10. To pass the examination, you must achieve at least 70% in each category.
- 11. There is a time limit of (3) hours for completion of the examination.
- 12. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.
If you are found in this area while the examination is still in progress, your license may be denied or j
revoked.
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I EQUATION SilEET i
f = ma A = AN w = mg A = A,6*'
)
v=s/t A = In2/( = 0.693/(
2 E
s = V t + % at I = (e '
o a = (V, - V,)/t 1 = (e*"
V, = V, + at 1 = ( 10" E=ml TVL = 1.3/s
}
KE=%mJ HVL = -0.693/y PE = mgh SCR = S/(1 -()
w = 0 /t CR, = S/(1 - (,)
W = UAP CR,(1 - Km) = CP,(1 - b2) 7 A = (aD )/4 M = 1/(1 - () = CR,/CR, A E = 931A m M = (1-4 )/(1 - K,)
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m = V,Ap SDM = (1 -()/Keff e
= mQAt l' = 10 seconds d
O - UAat I= 0.1 seconds' Pwr = W,Ah 1 d, = %
3 P = P l(f"")
1, d2=%
l 2
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P = P d'i R/hr = (0.5 CE)/d (meters) i o
SUR = 26M/T R/hr = 6 CE/8 (feet)
S U R = 2fp /t + ($ - p )T T = (l'/p) + [($ - p)/Q)
T = t/(e -4)
T = (s -p)/(rp)
J.
p = (4-1)/L = AQ/4 p = [(t /(T IQ)] + [Q/(1 + IT)]
P = 04V)/(3 x 10' )
I = 6N Cycle efficiency = (Net work out)/(Energy in) 5 k
Water Parameters Miscellaneous Conversions i
1 gal. = 8.345 lbm.
1 Curic = 3.7 x 10" dps 1 gal. - 3.78 liters 1 kg = 2.21 lbm i
i ff = 7.48 gal.
I hp = 2.54 x 16 Bru/hr Density = 62.4 lbm/ff 1 mw = 3.41 x 16 Bru/hr Density = 1 gm/cnf 1 in = 2.54 cm Heat of vaporization = 970 Btu /lbm
- F = 9/S* C + 32 Heat of fusion = 144 Btu /lbm
'C = 5/9(F-32) 2 Atm = 14.7 psi = 29.9 in Hg.
1 Btu = 778 ft-lbf I ft. H O = 0.4335 lbf/in.
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RX THEORY, THERMO & FAC OP CHARS Page 10
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QUESTION: 001 (1.00) r Assume a reactor is at 1 MWt at time zero. If there were NO EFFECTS due to delayed neutrons, which one of the following would be the power level l
after one (1) second if Keff were changed from 1.000 to 1.001?
(Assume a I = 10 sec. )
l p
F a.
1100 MWt i
b.
1300 MWt f
c.
10000 MWt i
d.
22000 MWt j
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QUESTION: 002 (1.00)
Consider the following ratio:
i number of thermal neutrons absorbed in the fuel
}
number of thermal neutrons absorbed in the fuel, moderator, and poisons i
Which one of the terms below is defined by the ratio above?
l, a.
Thermal Nonleakage Probability i
i b.
Thermal Resonance Escape Probablity f
c.
Thermal Neutron Fission Factor d.
Thermal Utilization Factor I
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(*****
CATEGOIlY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERMO & FAC OP CHARS Page 11 f
l QUESTION: 003 (1.00) l i
l SELECT the choice that completes the following statement.
'I As the moderator temperature increases, the Fermi Age (t) becomes and the core neutron leakage f
- a. smaller; increases i
- b. smaller; decreases t
l
- c. larger; increases f
d.
larger; decreases l
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QUESTION: 004 (1.00) 4 l
t SELECT the choice that completes the following statement.
I t
l All of the fuel has been removed from the core.
As fuel assemblies are I
added to the core, the Macroscopic Cross Section of Absorption for the l
core (Ia) will and neutron diffusion length (L2) will
- a. decrease; decrease 1
- b. decrease; increase s
c.
increase; decrease l
1 d.
increase; increase l
?
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
)
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RX THEORY, THERMO & FAC OP CHARS Page 12 l
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QUESTION: 005 (1.00) i A complete core reload is in progress at UVAR.
The following data has i'
been taken:
Number of Elements Detector Counts Installed (cpm) l 0
15 2
18 4
20 6
27 I
8 33 10 45 i
Using the Inverse Count Rate Plot (Figure 1) provided, determine which one of the following is the number of fuel elements that will be 1 required to be loaded for a critical mass.
I a.
12 i
i b.
13 i
C..
16 d.
1B QUESTION: 006 (1.00)
The reactor is critical at 2 MW.
Which one of the following would be the stable reactor period resulting j
from a rod drop which inserted 0.003 AK/K negative reactivity?
j
- a. -15 seconds
)
- b. -35 seconds
- c. -80 seconds
- d. -112 seconds I
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a h
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1.0 1.0 4
0.9 0.9 l
0.8 0.8
[
f 0.7 0.7 l
P 0.6 0.6 l
1/M t
0.5 0.5 i
0.4 0.4 i
I 0.3 0.3 l
0.2 0.2 0.1 0.1 t
0.0 0.0 2
4 6
8 10 12 14 16 18 20 Puel Elements Added
)
FIGURE I 1/M PLOT i
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A.
RX THEORY, THERMO & FAC OP CHARS Page 13 i
QUESTION: 007 (1.00) f The reactor is critical at 10 KWt.
The regulating rod is pulled to 1
insert a positive reactivity of S 0.18.
Which one of the following will be the stable reactor period as a result i
of this reactivity insertion?
(Assume a S of.0075 and a 1 of 0.1) a.
10.5 seconds b.
45.5 seconds c.
55.5 seconds
[
d.
65.5 seconds i
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QUESTION: 008 (1.00)
{
UVAR scrammed after 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> of operation at 1.75 MWt.
The problem has been corrected and a startup for return to power is commenced 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the scram.
Which one of the following describes the reactor behavior during the startup/ return to power operation?
- a. After reaching power operation, rods will have to be withdrawn for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to xenon buildup.
- b. After reaching power operation, rods will have to be inserted t
for the first 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> due to xenon burnout.
- c. During the startup, rods must be almost fully withdrawn to attain criticality and then must be inserted for the first 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to maintain a constant power.
- d. During the startup, rods would be fully withdrawn and the reactor would remain subcritical until xenon has decayed for 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
M
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RX THEORY, THERMO & FAC OP CHARS Page 14 i
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. QUESTION: 009 (1.00) l Which one of the following factors of the 4 factor formula is affected the most by an increase in the Xenon concentration in the reactor
- a. The Thermal Utilization Factor (f) i
- b. The Thermal Non-leakage Probability (Pt)
- c. The Resonance Escape Probability (P)
- d. The Fast Fission Factor (E) f QUESTION: 010 (1.00) l l
Which one of the following explains fission fragment behavior in the reactor?
- a. They have a large positive charge and decay by beta emission in order to become neutral.
- b. They have a neutral charge and lose energy by collisions with other dense materials.
{
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- c. They have a large positive charge and lose energy by specific l
ionization in the dense materials.
- d. They have a neutral charge and lose energy only by radioactive decay.
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P A.
RX THEORY, THERMO & FAC OP CHARS Page 15 i
QUESTION: 011 (1.00) i Which one of the following describes the characteristics of a good moderator?
a.
Low scattering cross section and low absorption cross section b.
Low scattering cross section and high absorption cross section c.
High scattering cross section and low absorption cross l
section I
d.
High scattering cross section and high absorption cross i
section 1
l
-QUESTION: 012 (1.00) l Which one of the following is the length of time required for reactor power to increase from 10 watts to 12.5 kilowatts on a lo second period?
(Neglect heating effects.)
a.
2 seconds b.
31 seconds j
c.
48 seconds i
d.
71 seconds i
4
?
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i A.
RX THEORY, THERMO & FAC OP CHARS Page 16 QUESTION: 013 (1.00)
Which one of the following is the maximum allowable excess reactivity in the reactor as specified in the University of Virginia (UVAR) Reactor Technical Specifications?
a.
0.45% AK/K b.
1.60% AK/K c.
2.00% AK/K d.
5.00% AK/K QUESTION: 014 (1.00)
Which one of the fol.'.owing is the major source of energy released during i
fission?
a.
Kinetic energy of prompt gamma rays b.
Kinetic energy of capture' gammas l
c.
Kinetic energy of Beta particles d.
Kinetic energy of fission fragments l
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RX THEORY, THERMO & FAC OP CHARS Page 17 t
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QUESTION: 015 (1.00)
[
An initial count rate of 100 is doubled five times during a startup.
l Assuming an initial Keff of 0.950, which one of the following is the new i
Keff7 i
a.
0.957 i
i b.
0.979 i
c.
0.985 d.
0.998 I
l QUESTION: 016 (1.00) l Beta and beta effective both describe the total fraction of delayed i
neutrons.
i Which one of the following defines the difference between the two?
a.
Beta effective is smaller than beta since delayed neutrons are born at lower energy levels than prompt neutrons.
- b. Beta effective is larger than beta since delayed neutrons are j
born at lower energy levels than prompt neutrons, Beta effective is smaller than beta since delayed neutrons are c.
born at higher energy levels than prompt neutrons.
d.
Beta effective is larger than beta since delayed neutrons are born at higher energy levels than prompt neutrons.
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1 1
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A.
RX THEORY, THERMO & FAC OP CHARS Page 18 l
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l QUESTION: 017 (1.00)
Consider two identical critical reactors, with the exception that one has a beta of 0.0072 and the other has a beta of 0.0060.
Which one of the following compares the response of the reactors to a given positive reactivity insertion?
Assume the magnitude of the positive reactivity insertion is less than beta.
[
i
- a. The resulting period will be shorter for the reactor with the
.0072 beta fraction.
- b. The resulting period will be shorter for the reactor with the
.0060 beta fraction.
- c. The resulting power level will be higher for the reactor with the.0072 beta fraction.
i
- d. The resulting power level will be higher for the reactor with the.0060 beta fraction.
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QUESTION: 018 (1.00)
SELECT the choice that completes the following statement.
During a reactor startup, as Keff approaches unity in a subcritical reactor, a given change in Keff causes the change in the neutron level to become and the period of time required to reach the equilibrium neutron level to become l
a.
larger; shorter
- b. larger; longer
- c. smaller; shorter d.
smaller; longer
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RX THEORY, THERMO 6 FAC OP CHARS Page 19 i
QUESTION: 019 (1.00)
Which one of the following is the dominant factor affecting the UVAR temperature coefficient as the temperature of the core (moderator and fuel) increases.
- a. Thermal utilization decreases.
- b. kesonance absorption increases.
- c. Thermal non-leakage probability increases.
l
- d. Fast non-leakage probability decreases.
I QUESTION: 020 (1.00)
Which one of the following lists the major core constituents that contribute to the Doppler Broadening Effect as the fuel temperature increases?
- b. U-235, Pu-240
- d. U-238, Pu-240
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END OF CATEGORY A *****)
i
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 20 i
QUESTION: 001 (1.00)
A point source measures 5 mr/hr gamma at a distance of 50 feet.
Which one of the following is the distance from the source that a measured reading of 100 nr/hr would occur?
a.
2.5 feet b.
11.2 feet f
- c. 25.0 feet d.
31.6 feet l
QUESTION: 002 (1.00) i Which one of the following is the whole body QUARTERLY radiation exposure limit in accordance with 10 CFR 20?
- a. 100 mrem F
b.
1250 mrem
- c. 2000 mrem
-l d.
5000 mrem
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U B.
NORMAL /EMERG PROCEDURES & RAD CON Page 21 QUESTION: 003 (1.00)
Which one of the following is the Technical Specification definition of REACTOR SHUTDOWN?
- a. All shim rods are fully inserted.
{
- b. The console-key is in the OFF position and is removed from the lock.
i
- c. All shim rods are fully inserted and no work is in progress involving fuel or experiments.
- d. The reactor is subcritical by at least $0.50 of reactivity.
l QUESTION: 004 (1.00)
Which one of the following describes the Beam Port condition indicated by two (2) green lights on the reactor console?
- a. The Beam Ports are drained and radiation barriers have been installed.
t
- b. The Beam Ports are filled with water up to the top of the ports.
- c. The Beam Ports are drained with radiation levels less than 100 mr/hr.
- d. The Beam Ports are filled with water and the radiation barriers have been installed.
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NORMAL /EMERG PROCEDURES & RAD CON Page 22 5
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QUESTION: 005 (1.00) r Upon removal of an experiment from the UVAR Reactor, radiation readings j
indicate 12 Rem /hr at one (1) foot from the experiment.
Two (2) hours i
4 later a reading of 9.8 Rem /hr is recorded at one (1) foot.
In order to work on the experiment, its radiation level must be less than 10 mrem /hr l
at one (1) foot.
j t
Which one of the following is the total length of time, after removal of the experiment, before work on the experiment may begin?
l i
a.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> l
3 b.
22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> c.
37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> i
d.
70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> P
QUESTION: 006 (1.00)
'I I
SELECT the choice tha t completes the following statement.
1 The Working Excess Reantivity shall be calculated by I
- a. adding the measured positive worth of a NON-SECURED experiment to the base excess reactivity i
b.
subtracting the measured positive worth of a NON-SECURED
-h experiment from the base excess reactivity
- c. adding the measured positive worth of a SECURED experiment to i
the base excess reactivity
- d. subtracting the measured positive worth of a SECURED experiment f
from the base excess reactivity 4
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 23 e
i QUESTION: 007 (1.00)
An experiment is removed from the reactor after irr3diation and is documented to have a radiation dose rate of 150 mr/hr at one foot in air.
Which one of the following describes a requirement for removing the experiment?
- a. The experiment should be placed back in the UVAR pool or other appropriate shielded location.
- b. The personnel are required to be wearing self-reading i
dosimeters.
- c. The radiation level shall be reported the authorized personnel l
requesting the irradiation.
l
- d. Temporary shielding should be placed to reduce the exposure to less than 100 mr/hr.
l QUESTION: 008 (1.00)
Liquid Rad Waste Tank #1 has had 4000 gallons of water stored in it for two weeks.
i Which one of the following describes an acceptable method, per UVAR procedures, for releasing the contents of the tank?
- a. After recirculation and sampling, Tank #1 is released directly l
to Meadow Creek with dilution flow from the pond.
T
- b. After filtration and sampling, Tank #1 is released directly to the pond for dilution in the pond.
- c. Tank #1 is transferred to tank #2 for filtration and sampling, l
then released directly to Meadow Creek with dilution flow from the pond.
l
- d. Tank #1 is transferred to tank #2 for an additional storage
-i period, dilution and sampling, then released-directly to the pond.
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i B.
NORMAL /EMERG PROCEDURES & RAD CON Page 24 i
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QUESTION: 009 (1.00) i When loading fuel, no reactor core shall be taken critical with shim rod l
positions below ten (10) inches and the regulating rod fully withdrawn.
i Which one of the following is the basis for this restriction?
I
- a. This assures that sufficient shutdown margin is available for the reactor to be shut down with the insertion of the shim rods alone.
- b. This assures that the regulating rod will remain in the operating band.
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- c. This assures that shim and regulating rod positions at 100%
[
j power will maximize fuel burnup.
- d. This assures that the reactor will not go critical when pulling shim rods two at a time during startup.
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s QUESTION: 010 (1.00)
Which one of the following organizations is responsible for the transportation of contaminated injured personnel from the UVAR facility?
l
- a. UVAR Health Physics Department j
- b. University of Virginia Medical Center
- c. University of Virginia Radiation Safety Office
- d. Charlottesville-Albemarle Rescue Squad i
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B.
NORMAL /EMERG PROCEDURES 6 RAD CON Page 25 1
. QUESTION: 011 (1. 00)
An event has occurred requiring the evacuation of the reactor facility.
It is later determined that the Primary Assembly Area must also be evacuated.
Which one of the following is designated as the " Reassembly Area"?
a.
Special Materials Handling Area L
- b. University of Viginia Radiation Safety Office l
- c. University of Virginia Medical Center i
- d. Charlottsville Fire House QUESTION: 012 (2.00)
For the instrumentation in Column I, SELECT the Operating Mode from Column II for which the instrumentation is required to be operable.
(Items in Column II may be used once, more than once, or not at all.
Only one answer may occupy each space in Column I.)
(4 answers required at 0.5 each) l COLUMN I COLUMN II (Instrumentation)
(Operational Mode) t a.
Pool Water 1.
Forced Convection Level Monitor i
2.
Natural Convection b.
Pool Water Temperature 3.
Reactor Startup c.
Startup Count Rate 4.
Forced and Natural Convection
!i d.
Reactor Period 5.
Reactor Secured 6.
Reactor Shutdown 7.
All modes
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NORMAL /EMERG PROCEDURES & RAD CON Page 26 l
QUESTION: 013 (1.00) i Consider a 10 curie Cobalt-60 point source.
Which one of the following is the amount of lead shielding that must be placed ONE foot from the source to reduce the radiation level to 100 mr/hr at 5 feet from the source?
(Assume 1.2 and 1.3 Mev energy gammgs emitted by the source and a Linear Attenuation Factor (p) of 0.496 cm')
a.
6.9 cm t
b.
8.25 cm c.
11.2 cm d.
13.75 cm QUESTION: 014 (1.00) l Which one of the following describes reactor conditions that require a Senior Reactor Operator to be present at the facility?
i
- a. refueling operations, initial startups, and recovery from unplanned shutdowns
- b. refueling operations, approach to power, and planned shutdowns
[
- c. restarts from non-shutdown suberitical rod position and planned shutdowns d.
restarts from non-shutdown suberitical rod position and recovery from unplanned shutdowns P
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 27 QUESTION: 015 (1.00)
Which one of the following describes the required condition of the reactor in order to load an experiment worth 0.14% Ak/k into the reactor core per SOP 5.4, Core Manipulations?
- a. Subcritical with shim rods at 10 inches and regulating rod fully withdrawn
- b. Shim and regulating rods inserted to make reactor subcritical by 2% Ak/k
- c. Reactor shutdown per SOP 5.3
- d. Reactor critical per SOP 5.1 l
l QUESTION: 016 (1.00) s SELECT the choice that completes the following statement.
To determine the base shutdown margin, subtract the absolute value of the total reactivity worth of the from the combined reactivity worth of all rods when the rods are withdrawn a.
shim rod with the highest worth; fully from the core
- b. shim rod with the highest worth; to the critical rod positions
- c. regulating rod and the shim rod with the highest worth; fully from the core f
- d. regulating rod and the shim rod with the highest worth; to the critical rod positions t
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 28 QUESTION: 017 (1.00)-
SELECT the choice that completes the following statement.
For reactivity limits of Technical Specifications, the definition of the REFERENCE CORE condition is the cold, I
- a. xenon-free CRITICAL condition
- b. Xenon-free SHUTDOWN condition
- c. xenon and samarium-free CRITICAL condition
- d. xenon and samarium-free SHUTDOWN condition QUESTION: 018 (1.00) l The reactor is operating at 1.5 MWt when the operator observes the following conditions:
Shim rod #2 magnet engaged light goes OFF.
l Shim rod #2 seating light comes ON.
Reactor power suddenly decreases.
A reactor scram signal is not initiated.
Which one of the following lists the IMMEDIATE operator action?
- a. Take manual control of the regulating rod and fully insert it into the core.
- b. Monitor rod drive positions and insert shim rod #1 and #3 to 10 inches.
- c. Fully insert shim rods #1 and #3 to shutdown the reactor.
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4 B.
NORMAL /EMERG PROCEDURES & RAD CON Page 29 i
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QUESTION: 019 (1.00)
During power operation, the operator discovers that shim rod #3 will not drive inward.
Which one of the following is the required IMMEDIATE operator action?
a.
Insert all rods by initiating a scram and secure the reactor per SOP 5.3.
b.
Insert the remaining rods to shutdown the reactor, then secure the reactor per SOP 5.3.
c.
Fully insert the remaining rods, scram the reactor, and remove
^
two fuel elements from near the center of the core.
d.
Insert the remaining rods by initiating a scram, then remove two of the fuel elements adjacent to shim rod #3.
QUESTION: 020 (1.00)
The Core Spray header remote coupling has been engaged and secured.
The pressure test of the remote coupling is being performed.
Which one of the following indicates a failure of the remote coupling's integrity?
- a. air bubbles from the core spray header and air bubbles at the 4
remote coupling i
- b. air bubbles from the core spray header but NO air bubbles at the remote coupling
- c. NO air bubbles from the core spray header but air bubbles at the f
remote coupling
- d. NO air bubbles from the core spray header and NO air bubbles at
.t the remote coupling l-i i
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PLANT AND RAD MONITORING SYSTEMS Page 30 QUESTION: 001 (1.00)
Which one of the following types of fuel elements is designed for loading into the core to reduce the amount of core excess reactivity?
Standard MTR curved plate fuel element with 18 curved plates a.
- b. Half loaded standard fuel element with 12 flat plates
- c. MTR curved plate fuel element with 9 curved plates
- d. Half loaded fuel element with the 6 central flat plates removed t
QUESTION: 002 (1.00)
Which one of the following describes a typical UVAR core arrangement that could be utilized for a graphite-moderated core when producing the highest attainable thermal neutron flux?
l I
- a. A 4 by 5 array in the corner of the grid plate with graphite assemblies loaded in the remaining 44 grid plate positioning i
holes.
- b. A 4 by 5 array of fuel elements in the corner of the grid plate with one row of graphite reflector elements on two sides of the
+
fuel element array.
l
- c. A 4 by 4 array of graphite reflector elements in the center of the grid plate with two rows of fuel assemblies loaded on each side of the graphite array.
- d. A 4 by 4 array of fuel elements in the center of the grid plate with two rows of graphite reflector elements loaded on each side
]
of the fuel element array.
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C.
PLANT AND RAD MONITORING SYSTEMS Page 31 i
QUESTION: 003 (1.00) i Which one of the following describes the expected response of a control rod when a reactor scram occurs?
- a. The supporting magnet deenergizes, dropping the shim rod cylindrical support tube and absorber section into the core in i
less than 1 second.
- b. The supporting magnet deenergizes, dropping the shim rod absorber section into the core in less than 1 second.
- c. The lead screw mechanism disengages, dropping the regulating rod absorber section into the core in less than 3.74 seconds.
- d. The drive motor automatically energizes and drives the regulating rod absorber section into the core at 3.74 inches per minute.
i e
QUESTION: 004 (1.00)
The reactor is operating in the natural convection mode and the scram logic range switch is selected to the 200 KW position.
Reactor power is 150 KW.
Which one of the following describes the expected response when the i
range switch is taken to the 2 MW position?
- a. Operation with a scram setpoint of 2.5 MW and a power indication of 7.5% on the power range instrument channels because the power range instrumentation is desensitized by a factor of 10.
- b. Operation with a scram setpoint of 250 KW and a power indication of 7.5% on the linear power instrument channel because power range instrumentation is desensitized by a factor of 10.
- c. Scram because the safe +10 volt logic signal is momentarily interrupted as the switch passes through the center position.
- d. Scram because the deenergized header position relay prevents the safe +10 volt logic signal from reaching the Mixer Drivers.
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PLANT AND RAD MONITORING SYSTEMS Page 32 f
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QUESTION: 005 (1.00) t SELECT the choice that completes the following statement.
In addition to the nuclear power instrumentation, the operator has instrumentation available for comparative observation of reactor power.
Ona of these instruments is the a.
ionization chamber located on the bridge structure that detects the core gamma flux l
- b. geiger-mueller chamber located on the ground floor wall in the primary experiment area that detects core gamma flux.
- c. ionization chamber located on the ground floor adjacent to the
[
primary piping for detecting nitrogen-16 gamma d.
ionization chamber suspended above the core for detecting the
[
thermal neutron flux at the top of the core 3
QUESTION: 006 (1.00)
Which one of the following describes how a scram condition is generated in the Scram Logic Drawer when the operator DEPRESSES the Console Scram Pushbutton?
Both Mixer Drivers are deenergized causing the scram logic a.
output signal to go to zero volts, deenergizing the scram i
magnets.
j k
- b. Power to the scram magnets is directly interrupted by the console pushbutton, causing both Solid State Relays and the
{
scram magnets to deenergize.
- c. Both Solid State Relays are deenergized, sending a signal to open the console scram relays to remove power from the scram magnets.
I'
- d. Transistor Gate NA-45 is deenergized, causing the Auxiliary-control Relay output to go to zero volts and deenergize the scram magnets.
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C.
PLANT AND RAD MONITORING SYSTEMS Page 33 QUESTION: 007 (1.00)
A scram signal to both mixer drivers has occurred.
I Which one of the following failures would result in deenergizing only a
scram magnets #1 and #2, causing only two rods to scram?
(Assume each of the following failures results in a safe output signal from the l
component.)
- a. Mixer Driver #1 and Mixer Driver #2
- b. Solid State Relay #1 and Solid State Relay #2 F
- c. Mixer Driver #2
- d. Solid State Relay #2
[
L QUESTION: 008 (1.00)
SELECT the choice that completes the following statement.
The rod withdrawal interlock logic can prevent the withdrawal of the To satisfy the rod withdrawal logic, the source range count rate must be greater than or equal to 2 counts per.second AND the range instrument (s) must NOT be in TEST.
l a.
shin and regulating rods; source, intermediate, and power i
- b. shim and regulating rods; source
- c. shim rods; source, intermediate, and power
- d. shim rods; source l
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PLANT AND RAD MONITORING SYSTEMS Page 34 i
f
- QUESTION: 009 (1.00) i Which one of the following will satisfy the scram logic and allow the operation of the reactor with reactor coolant flow less than 900 gpm?
7
- a. reactor coolant header in the down position
- b. reactor coolant pump switch in the off position
- c. reactor power less than 200 KW
- d. scram logic drawer range switch in the 200 KW position QUESTION: 010 (1.00)
Which one of the following describes the functions provided by the Intermediate Range Nuclear Instrument drawer?
- a. Period, log level power, and recorded power indication, period bistable scram, and bistable trip initiating power integrator b.
Integrated power indication, integrated high power bistable scram, and recorded power indication
- c. Period, integrated power, recorded percent power, and log level power indication, and bistable trip initiating power integrator
- d. Period indication, period bistable scram, log level power I
indication, and integrated high power bistable scram P
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l C.
PLANT AND RAD MONITORING SYSTEMS Page 35 QUESTION: -011 (1.00) i The regulating rod is in automatic control.
Which one of the following conditions would result in the regulating rod remaining in automatic control?
- a. Attempting to move the regulating rod with the normal control switch r
- b. An 80 error signal on the automatic power controller's deviation meter i
- c. Turning off the power range safety channel recorder d.
Regulating rod reaches its bottom limit QUESTION: 012 (1.00)
Which one of the following describes the design of the demineralized makeup system that prevents the backflow of water into the city water system?
- a. Unprocessed city water is discharged through a float valve to the catch tank and the float valve isolates the discharge before the catch tank level rises above the discharge pipe.
- b. Unprocessed city water is discharged to the catch tank through a stand-pipe.
-t Deionized city water is discharged to the pool through a float c.
valve that isolates the discharge before pool level rises above the discharge pipe.
d.
Deionized city water is discharged to the pool through a stand-t pi e.
P i
i 5
I
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
i C.
PLANT AND RAD MONITORING SYSTEMS Page 36 QUESTION: 013 (1.00)
SELECT the choice that completes the following statement.
i The primary coolant header is raised into position by with 50 psig of compressed air.
When the primary pump trips, the header drops to the full down position by
- a. pressurizing a pneumatic cylinder; a loss of the differential pressure between the primary coolant and the pool
- b. pressurizing a pneumatic cylinder; rapidly dumping the air out of the pneumatic cylinder c.
inflating a header skirt; a loss of the differential pressure between the primary coolant and the pool d.
inflating a header skirt; rapidly dumping the air out of the header skirt i
QUESTION: 014 (1.00)
SELECT the choice that completes the following statement.
A Differential Temperature (dT) System is used to measure core dT for determining core power.
The temperature differential system measures the dT by subtracting the temperature of the primary coolant
{
from the temperature of the primary coolant a.
just downstream of the primary heat exchanger; just upstream of the primary pump
- b. just downstream of the primary heat exchanger; just upstream of the primary heat exchanger;
- c. pool temperature just above the reactor core:. just upstream of f
the primary pump
- d. pool temperature just above the reactor core; in the header f
l
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
{
t
C.
PLANT AND RAD MONITORING SYSTEMS Page 37 l
I i
I QUESTION: 015 (1.00)
)
i One inline radiation monitor is permanently installed in an exhaust duct of the Reactor Building Ventilation System.
j Which one of the following lists the areas that are monitored by this radiation monitor?
- a. Thermal column, reactor room, and mezzanine fume hoods
- b. Thermal column, access facility, and beam ports l
- c. Access facility, beam ports, and hot cell f
- d. Reactor room, mezzanine fume hoods, and hot cell QUESTION: 016 (1.00) 4 SELECT the choice that completes the following statement.
Upon a high radiation condition on the Reactor Bridge, the Reactor Room door L
- a. will close causing the Reactor Room air to be recirculated at r
2700 cfm through the exhaust ducts to the absolute filters on t
the mezzanine floor and returned through floor registers
- b. and the exhaust ducts will close but the stack exhaust flow rate will remain approximately 8600 cfm due to operation of an
{
exhaust fan intake on the Reactor Building roof l
L
- c. and the exhaust ducts will close but the reactor room air will be recirculated at 2700 cfm through the absolute filters utilizing the floor registers j
i
- d. the exhaust ducts, and the floor registers will close causing l
the stack exhaust flow rate to decrease by nearly 7000 cfm due i
to the loss of any exhaust flow from the Reactor Room
-l i
i l
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
f
-r-*
C.
PLANT AND RAD MONITORING SYSTEMS Page 38 QUESTION: 017 (1.00)
SELECT the choice that completes the following statement.
Both beam ports have been drained.
A reactor scram will be actuated if the beam port neutron detector detects neutrons
- a. on the outside of the blockhouse beam stop b.
in the beam path of the beam port at the neutron camera station L
c.
in the light beam of the light beam actuator inside the beam j
port d.
in the beam port sight glass vent tube l
QUESTION: 018 (1.00)
Which one of the following describes the operation of the hydraulic rabbit facility?
- a. Sample transport to the core requires the local operator and the reactor operator to each position a control switch.
- b. Operators can manually align it to the epithermal or the thermal irradiation facility from the reactor bridge.
I I. Allows operators to transport irradiated samples to the counting c
l room.
i
- d. Operators must load and unload the samples from the top of the l
reactor pool.
i
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 39 I
QUESTION: 019 (1.00)
Which one of the following describes the design that provides for the closure of the Reactor Room Ventilation Exhaust Duct door?
- a. Held closed by gravity and the pressure inside the Reactor Room
- b. Held closed by a solenoid-operated latch if the pressure inside the Reactor Room decreases below atmospheric pressure c.
Initially closed by the differential pressure across the exhaust duct, then held closed by an electromagnet d.
Initially closed by gravity, then held closed by an electromagnet 7
l f,
-QUESTION: 020 (1.00)
SELECT the choice that completes the following statement.
During reactor power operation, the Core Spray header flow rate will be I
- a. very small, to prevent corrosion of the headers j
- b. Very small, to ensure the emergency storage tanks remain filled I
c.
zero, to prevent corrosion of the headers
- d. zero, to ensure the emergency storage tanks remain filled i
(*****
CATEGOkY C CONTINUED ON NEXT PAGE *****)
I t
b C.
PLANT AND RAD MONITORING SYSTEMS Page 40 I
f QUESTION: 021 (2.00) i i
For the component in Column I, labelled "a" through "d" on Figure 2, l
SELECT the component's identification from Column II.
(Items in Column l
II will be used only once.
Only one answer may occupy each space in Column I.)
(4 answers required at 0.5 each) l COLUMN I COLUMN II l
(Component)
(Identification) a.
1.
Pressure Test Insert Tube l
l b.
2.
Core Support Structure c.
3.
Emergency Storage Tank-(
d.
4.
Top of Reactor Core 5.
Spray Header l
6.
Reactor Bridge 7.
Remote Coupler I
l f
1 i
i; h
t i
i
(*****
END OF. CATEGORY C *****)
(********** END OF EXAMINATION **********)
t t
k
i u,
13 sd-FROM i
e g i L _.S_
+-
7 w_ -: -
2_
gg *l A* DEMINERALIZER l
6 0
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o gi oe <
- se.
.o 4
ll o.
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o o A
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4 o
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i g
A i
g l
i A
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4 4 4
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4 e
4 A e j
e 4
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FIGURE 2 CORE SPRAY SYSTEM b
--..me-
,w
t
..f-i
-r,
=-
ti.
I 1..
~ q-h
.(, c!.,.;
=
i i
i i
I i
1 ANSWER KEY e
'l NON-POWER REACTOR LICENSE EXAMINATION l
UNIVERSITY OF VIRGINIA 1993/04/08 P
i i
k I
i I
t I
i I
t
-i l
s r
4.
L t
1 f
i b
/
1 5
?
- a
A.
RX THEORY, THERMO & FAC OP CHARS Page 41 i
ANSWER:
001 (1.00) f d.
REFERENCE:
T University of Virginia, Reactor Theory for Reactor Training Program, I
Pg 10 P = P e *#I o
i T = 1/ (k-1) = 10/ (1. 000-1. 001) =.1 sec.
p P = 1MWt (e'#)
P = 22026 MWt b
i ANSWER:
002 (1.00) d.
REFERENCE:
University of Virginia, Reactor Theory for Reactor Training Program, l
P9 3 3
l ANSWER:
003 (1.00) c.
T
REFERENCE:
University of Virginia, Reactor Theory for Reactor Training Program, P9 7 3
i l
l
(*****
CATEGORY A CONTINUED ON NEXT PAGE *****)
r
A.
RX THEORY, THERMO & FAC OF CHARS Page 42 ANSWER:
004 (1.00) c.
i
REFERENCE:
j University of Virginia, Reactor Theory for Reactor Training Program, P9 7 1
f AMSWER:
005 (1.00) c.
REFERE ' s ;;
University of Virginia, Reactor Theory for Reactor Training Program pg 8 and 9
-i 4
ANSWER:
006 (1.00) c.
s
REFERENCE:
University of Virginia, Reactor Theory for Reactor Training Program pg le (maximum stable negative period is -80 sec.)
i ANSWER:
007 (1.00) i e
em
(*****
CATEGORY A CONTINUED ON NEXT PAGE *****)
i A.
RX THEORY, THERMO & FAC OP CHARS Page 43
REFERENCE:
i University of Virginia, Reactor Theory for Reactor Training Program, P9 17 p-c
.0075 -.00135 T = --- = -------------- = 45.5 second i
1 0
(.1) (.00135) i i
ANSWER:
008 (1.00) g g g' p/
j W
j e
d.
07 C
REFERENCE:
University of Virginia, Reactor Theory for Reactor Training Program, Pg 27 Note: 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> in distractor "d" comes from 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> minus the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that have passed since the reactor scrammed.
i ANSWER:
009 (1.00) a.
j
REFERENCE:
i University of Virginia, Reactor Theory for Reactor Training Program, P9 3 i
ANSWER:
010 (1.00) c.
I 1
REFERENCE:
Introduction to Nuclear Engineering, John R.
Lamarsh Section 3-5 pp 105 I
l i
)
(***** CATEGONY A CONTINUED ON NEXT PAGE *****)
I s
A.
RX THEORY, THERMO & FAC OP CHARS Page 44 h
ANSWER:
011 (1.00) f c.
REFERENCE:
Introduction to Nuclear Reactor Theory, John R. Lamarsh Chapter 6 pp 167-171 i
t L
r i
ANSWER:
012 (1.00) d.
REFERENCE:
Basic Reactor Theory Equatio,g Sheet P=Pe o
12500 = 10e""
In 12500/10 = t/10 l
7.13 = t/10 t = 71.3 seconds ANSWER:
013 (1.00) i d.
I
REFERENCE:
UVAR Technical Specifications Page 10 l.
i
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
i o
A.
RX THEORY, THERMO & FAC OP CHARS Page 45 i
l ANSWER:
014 (1.00) i d.
j
REFERENCE:
Introduction to Nuclear Engineering, John R. Lamarsh Section 3.7 pp 74 1
-ANSWER:
015 (1.00) d.
REFERENCE:
i University of Virginia, Reactor Theory for Reactor Training program, pg.
8 Equation Sheet l
CR ( 1-K,,,1 ) = CR (1 ~ K 2) g 2
eff CR /CR 32
=
2 g
CR (1-K,,,1) / CR2= 1 - K,,,2 g
100 (1-0.950)/3200 = 1 -
K,,,2 l
K,,,2 = 1 -.0015625 =.998 i
ANSWER:
016 (1.00) e b.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERMO & FAC OP CHARS Page 46
REFERENCE:
i University of Virginia, Reactor Theory for Reactor Training program, pg 10, 11, and 14.
Glasstone and Sesonske, pg 233 (footnote +)
ANSWER:
017 (1.00) b.
REFERENCE:
Introduction to Nuclear Engineering, John R.
Lamarsh Section 7.1 pp 248 j
i ANSWER:
018 (1.00) b.
REFERENCE:
Glasstone & Sesonske, Nuclear Reactor Engineering, Page 322 i
ANSWER:
019 (1. 00) d.
REFERENCE:
University of Virginia, Reactor Theory for Reactor Training Program, pg 23 ANSWER:
020 (1.00) d.
(*****
CATEGORY A CONTINUED ON NEXT PAGE *****)
A'.
RX THEORY, THERMO & FAC OP CHARS Page 47 i
REFERENCE:
University of Virginia, Reactor Theory for Reactor Training Program, Pg 23 Nuclear Reactor Engineering, Glasstone and Sesonske Page 260 t
r i
(***** END OF CATEGORY A *****)
_ = _.
i j
a
-B.
NORMAL /EMERG PROCEDURES & RAD CON Page 48 i
i I
ANSWER:
001 (1.00) l b.
REFERENCE:
l Equation Sheet z
1d
- 1d l
3 i 22 i
-5 mr/hr (50 ft)2 = 100 mr/hr (d )
2
-d2= ( 5(50)2/100)1/2 l
d2= 11.2 ft ANSWER:
002 (1.00) i b.
I
REFERENCE:
i 10 CFR 20 t
i
}
ANSWER:
003 (1.00) a.
f
REFERENCE:
UVAR Technical Secifications Page 4 i
ANSWER:
004 (1.00) i i
b.
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
f i
h I
F i
B.
NORMAL /EMER
G. PROCEDURE
S & RAD CON Page 49
REFERENCE:
[
[
UVAR Stand.trd Operating Procedure SOP 4 Page 25 I
L ANSWER:
005 (1.00) d.
i i
REFERENCE:
i Equation Sheet A = A,e
10 = 12000eU'*
-12 9.8 = 12e 10/12000 = e"**
l
-12 9.8/12 = e
. 0 008 3 = e.101t In0.817 = -12 In.00083 =
.101t
-2A =
.202
-7.09 =.101t 1 =.101 t = 70.19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> ANSWER:
006 (1.00) a.
REFERENCE:
UVAR SOP 6, Section 6.5.C.10, pg 6-21 ANSWER:
007 (1.00) b.
I i
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
t
4' B..
NORMAL /EMERG PROCEDURES & RAD CON Page 50 i
i
REFERENCE:
UVAR Standard Operating Procedure SOP-6 Page 13 L
ANSWER:
008 (1.00) j c.
REFERENCE:
j UVAR Standard Operating Procedure SOP 10, Page 11 UVAR Design and Analysis Handbook, Section 4.8, pg 4-10 j
i l
ANSWER:
009 (1.00) d.
REFERENCE:
UVAR Standard Operating Procedure SOP-5 Page 15 i
t ANSWER:
010 (1.00) d.
REFERENCE:
l UVAR Emergency Plan Page 46
' ANSWER:
011 (1.00) a.
i i
i
(*****
CATEGORY B CONTIITUED, ON NEXT PAGE * * * * *)
{
i
1 i
B.
NORMAL /EMERG PROCEDURES 6 RAD COM Page 51
REFERENCE:
UVAR Emergency Plan Implimenting Procedure EPIP-14 Page 3 i
i ANSWER:
012 (2.00)
I l1 )
fW a.
b.
c.
3 d.
7 (4 answers required at 0.5 each)
REFERENCE:
UVAR Technical Specifications Table 3.1' f
ANSWER:
013 (1.00) b.
r i
i i
(*****
CATEGO'RY B CONTINUED ON NEXT PAGE *****)
i
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 52
REFERENCE:
G:neral Electric BWR Academic Series Health Physics Page 5-27 l
Equation Sheet General Electric BWR Academic Series Health Physics Page 5-27 Equation Sheet I = 6CE/d 150 Rem /hr I=6 (10) (1. 2 + 1. 3 )
=
required radiation one foot from the shield; l
1d 12= (100 mr/hr) (5/1)2 = 2500 mr/hr or 2.5 Rem /hr 2
Id 3 3 22e I = I,e**
[
2.5 = 150e"*
f In (2.5/150) =
.496t
-4.09 =
.496t t = 8.25 cm l
l ANSWER:
014 (1.00) a.
_j i
o
REFERENCE:
UVAR SOP 3, Personnel Responsibilities, Section 3.5, pg 3-1 UVAR SOP 5.4, Core Manipulations, Section 5.4.1.2, pg SOP 5-9 Technical Specification, 6.1.3, pg 35 ANSWER:
015 (1.00) c.
REFERENCE:
UVAR SOP 5.4, Section 5.4.2.C.4)c), pg SOP 5-18
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 53 l
i e
ANSWER:
016 (1.00) d.
j
REFERENCE:
UVAR SOP 5.5, Section 5.5.B, pg 5-23 ANSWER:
017 (1.00) a.
REFERENCE:
UVAR Technical Specification Definition, Reactivity Limits, pg 4
[
ANSWER:
018 (1.00) b.
l
REFERENCE:
UVAR SOP 11, Section 11.D.b, pg 11-5 i
- i ANSWER:
019 (1.00) 9 C.
REFERENCE:
UVAR SOP 11, Section 11.N.b, pg 11-15
(***** CATEGOkY B CONTINUED ON NEXT PAGE *****)
i
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 54 1
1 ANSWER:
020 (1.00) c.
REFERENCE:
UVAR Design and Analysis Handbook, Section 4.10, pg 4-24 l
r P
t t
t P
i i
P i
E r
r
(*****
END OF CATEGORY B *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 55 Ob~#'[
ANSWER:
001 (1.00)
/
f
)
. f' l
b.
y
- h i
p
,i n
, 1:,!
)") ' <6 '
l/
REFERENCE:
j
/
UVAR Design and/ Anal'ys(M, Book, Section 3.2, pg 3-6 n/
ANSWER:
002 (1.00) d.
REFERENCE:
UVAR Design and Analysis Handbook, Section 3.3, pg 3-6 and 3-9 ANSWER:
003 (1.00) b.
REFERENCE:
UVAR Design and Analysis Handbook, Section 3.5, pg 3-16 ANSWER:
004 (1. 00) d.
r
REFERENCE:
UVAR Design and Analysis Handbook, Section 3.6.4, pg 3-33 UVAR Design and Analysis Handbook, Section 3.6.1, pg 3-21 r
I
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
e i
C.
PLANT AND RAD MONITORING SYSTEMS Page 56 I
ANSWER:
005 (1.00) c.
REFERENCE:
UVAR Design and Analysis Handbook, Section 3.6.1, pg 3-21 l
UVAR Design and Analysis Handbook, Section 7.4, pg 7-2 l
ANSWER:
006 (1.00) b.
REFERENCE:
I UVAR Design and Analysis Handbook, Fig. 3.15, pg 3-30 1
ANSWER:
007 (1.00) d.
REFERENCE:
UVAR Design and Analysis Handbook. Section 3.6.6.4, pg 3-35 ANSWER:
008 (1.00)
[
l C.
REFERENCE:
'r UVAR Design and Analysis Handbook, Section 3.6.6.4, pg 3-32 i
i t
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
?
5 C.
PLANT AND RAD MONITORING SYSTEMS Page 57 I
ANSW
>009
.00
./
a'!
REFEREICE
/ /
Design and Analysis Handbook, Section 3.7, pg 3-37 l
t
~
ANSWER:
010 (1.00) a.
REFERENCE:
UVAR Design and Analysis Handbook, Figure 3-13, pg 3-25; Section 3.6.3, pg 3-25; Section 3.7, pg 3-36 i
i ANSWER:
011 (1.00) l c.
REFERENCE:
UVAR Design and Analysis Handbook, Section 3.8, pg 3-39 ANSWER:
012 (1.00) d.
REFERENCE:
UVAR Design and Analysis Handbook, Section 4.2, pg 4-2 L
(***** CATEGONY C CONTINUED ON NEXT PAGE *****)
C.
PIANT AND RAD MONITORING SYSTEMS Page 58 ANSWER:
013 (1.00) c.
REFERENCE:
UVAR Design and Analysis Handbook, Section 4.2, pg 4-2 and 4-3 ANSWER:
014 (1.00) c.
REFERENCE:
UVAR Design and Analysis Handbook, Section 4.4, pg 4-4 and 4-5 ANSWER:
015 (1.00) b.
REFERENCE:
UVAR Design and Analysis Handbook, Section 4.9, pg 4-11 and Fig. 4-2, pg 4-12 ANSWER:
(1. O) b.
)
pl /t, /f y
/
y
,; w,
i
/j j gj REFE (CE:
4 UV D sign n
Analysis Handbook, Section 6.1, pg 6-4, and Fig.
4-2, pg 4-12
(*****
CATEGOftY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 59
- ANSWER:
17 4.00 Q l
l
,/
f f
/
, h9/
RE ERE x
/
/
W sign and Analysi Handbook, Section 5.1, pg 5-la h
ANSWER:
018 (1.00) d.
REFERENCE:
i WAR Design and Analysis Handbcok, Section 5.3, pg 5-lb i
1 ANSWER:
019 (1.00) a.
REFERENCE:
WAR Design and Analysis Handbook, Section 6.0, pg 6-1 and 6-4; Fig 6-3, pg 6-5 P
ANSWER:
020 (1.00) a.
REFERENCE:
WAR Design and Analysis Handbook, Section 4.10, pg 4-28 i
?
t
(***** CATEGOlkY C CONTINUED ON NEXT PAGE *****)
t C.
PLANT AND RAD MONITORING SYSTEMS Page 60 i
t ANSWER:
021 (2.00) a.
5 b.
7
- c. 3
- d. 6 (4 answers required at 0.5 each)
REFERENCE:
I UVAR Design and Analysis Handbook, Section 4.10, Fig 4-4, pg 4-26 l
I r
f i
i B
(***** END OF CATEGORY C *****)
(********** END OF EXAFIINATION **********)
A.
RX THEORY, THERMO & FAC OP CHARS Page-1 t
ANSWER KEY i
MULTIPLE CHOICE r
001 d
i 002 d
003 c
004 c
005 c
006 c
)
q) h 007 f4 f l}
008 d ~ en - C 009 a
010 c
011 c
012 d
013 d
014 d
015 d
016 b
017 b
018 b
019 d
l l
020 d
i l
(***** END OF CATEGORY A *****)
I m..
j
5 4
U B.
NORMAL /EMERG PROCEDURES & RAD CON Page 2
i i
ANSWER KEY
[
i MULTIPLE CHOICE 001
-b 002 b
i l
003 a
004 b
005 d
\\
{
006 a
007 b
008 c
009 d
{
010 d
f 011 a
012 MATCHING
. 2 IV h h
a 1
4 t
b
,1 7 F' f
c 3
d 7
MULTIPLE CHOICE 013 b
I t
t 014 a
1 015 c
t 016 d
I 017 a
i 018 b
i 019 c
000 c
{
(***** END OF CATEGORY B *****)
l f
C.
PLANT AND RAD MONITORING SYSTEMS Page 4
I ANSWER KEY MULTIPLE CHOICE 021 MATCHING
_c g1 L
A % d= : = -
p7 a
5 002 d
b 7
003 b
c 3
i 004 d
d 6
I 005 c
t 006 b
007 d
008 c
f4 6 t' 4,'k) 3?
- v 010 a
011 c
012 d
013 c
014 c
015 b
J2> h.,... j' f
/
Nh b
R Ad&p nge<ao 018 d
019 a
030 a
i
(*****
END OF CATEGORY C *****)
j
(********** END OF EXAMINATION **********)
i
~
F TEST CROSS REFERENCE Page 1.
RO Exam UVAR Reaetor Organized by Questio.n Nunber QUESTION VALUE REFERENCE 001 1.00 9001528 002 1.00 9001529 003 1.00 9001530 004 1.00 9001531 005 1.00 9001532 006 1.00 9001533 007 1.00 9001534 008 1.00 9001535 009 1.00 9001536 010 1.00 9001537 011 1.00 9001538 012 1.00 9001539 013 1.00 9001540 014 1.00 9001541 015 1.00 9002542 016 1.00 9001543 017 1.00 9001544 018 1.00 9001545 019 1.00 9001546-020 1.00
-9001547 20.00 001 1.00 9001548 002 1.00 9001549 003 1.00 9001550 004 1.00 9001551 005 1.00 9001552 006 1.00
~ 9001553 i
007.
1.00 9001554 008 1.00 9001555 i
009 1.00 9001556
{
010 1.00 9001557 011 1.00 9001558 012 2.00 9001559 i
013 1.00 9001560
[
014 1.00 9001561 015 1.00 9001562 016 1.00 9001563 017 1.00 9001564 018-1.00 9001565 019 1.00 9001566 020 1.00 9001567
{
21.00 j
i 001 1.00 9001568 002 1.00 9001569 l
003 1.00 9001570.
r
~
[
+
TEST CROSS REFERENCE
,Page 2
.i f
RO E x a in UVAR Reactor organized by Q u e s t i'o n Number QUESTION VALUE REFERENCE 004 1.00 9001571 005 1.00 9001572
'l 006 1.00 9001573 t
007 1.00 9001574 008 1.00 9001575
.{
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.l 015 1.00 9001582 i
016 1.00 9001583 l
017 1.00 9001584 018 1.00 9001585 i
019 1.00 9001586
{
020 1.00 9001587 021 2.00 9001588 22.00 l
j 63.00 l
I 6
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o i