ML20043H690
| ML20043H690 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 06/04/1990 |
| From: | Miller L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20043H686 | List: |
| References | |
| 50-288-OL-90-01, 50-288-OL-90-1, NUDOCS 9006260302 | |
| Download: ML20043H690 (67) | |
Text
_-. _ _ _
i 1
Examination Report No.:
50-288/0L-90-01 Facility:
Reed Reactor Facility Examinations administered at the Reed Reactor facility, Reed College, Portland, Oregon.
f Examiners:
Ralph Cooley, Headquarters Thomas Meadows, Region V Approved:
b' L4 F. Miller dri, Chief Date Signed Operations Section Summary:
NRC initial licensing examinations were administrated from May 15 through May 17, 1990 (Report No. 50-288/0L-90-01).
Initial operator licensing examinations were administered to one Senior Reactor Orarator (SRO) upgrade candidate and seven Reactor Operator (RO) candidates.
These examinations were administered in accordance with NUREG-1021, ES-304 and ES-404, Revision 6.
Two of the seven R0 candidates were first retake examination applicants. One of these applicants received a waiver of the written examination requirement, because of an acceptable performance on the first licensing attempt.
Two of the seven Reactor Operators failed the operating portions of their examinations.
All of the other candidates passed their examinations and were subsequently issued licenses.
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-REPORT DETAILS
- 1..
Examiners Thomas Meadows, RV, Chief Examiner
'l
' Ralph Cooley, OLB Headquarters 2.
Personnel Attending the Exit Meeting on May 18, 1990' u
^
i 1* Thomas Meadows, RV, Chief Examiner
. Douglas.Bennett, Provost, Reed College 3
- Michael Pollock. Acting Director, Reed Reactor Facility.
j Sara Herbelin, Reactor Supervisor, Reed: Reactor Facility
'i w
- Attended the written examinati.on review on May 17, 1990 3'
y 3.,
' Written Examination andiFacility Review.
w The written examinations were administered on May 15, 1990 on the, Reed College campus. This examination was prepared and administrated in' accordance with NUREG 1021,'ES-404, Revision 6.
At the conclusi r of the examination the Chief Examiner innediately secured the mastr
- i examination answer key and all of the candidate's answer sheets _ All..
1 other examination materials were forwarded to the licensee'sl training 1
staff, including'a copy of the master "as given" examination answer key, for their formal review.
q The Chief Examiner held a formal examination review on May.17, 1990:with Mr. Michael Pollock, Acting Director, Reed _ Reactor Facility. All facility connents.were resolved during this review. These comments were fonnally 1
documented by the licensee in a letter dated May 23. 19901(Attachment A)
'l sent to Region V, in accordance with NUREG 1021, ES-201..The Chief Examiner considered all of the licensee's connents and proposed resolutions, and accepted the connents proposed. These changes did not: alter the grading structure of the original answer key, but were made' to improve question clarity prior to uploading on the NRC Examination-Question Bank (EQB).
All cf the operator candidates passed this portion of the examination.
~4..
Operating Examinations The operating examinations were administered on May 15-17, 1990, in accordance with NUREG 1021. ES-404, Revision.6. These examinations were conducted using operational scenarios that tested the candidate's integral; system knowledge and ability to actually operate the reactor facility. Aspects'of facility design and control, administration,'and emergency plan were also thoroughly tested.
Two of the seven reactor operator candidates failed this portion of' their examination. All of the othe" candidatis passed, and subsequently passed the written examination as well.
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- 5. EGeneri T Program Weaknesses,
TheexaminNrsidentifiedfourgenericprogramweaknesses.- These findings ~
encompass this examination ~ cycle. Some of these findings'also occurred-during the previous:two NRC_ administered examinations at Reed College-
- (cdministeredLinMay,;1988and-May,19G9).
First, the examiners found Reed's operator' training program to be, ineffectlve in ensuring that all licensed candidates were prepared to pass the exaiaination. This lack of preparation wast also evidenced by-the continued high failure rates of the initial (mainly freshmen) 1 1
applicants:
Twenty = five percent of this year 3.<dicants failed their -
licensing examinations.
Approximately fifty percent of the initial applicants-failed their licensing examinations-in the 1989 fiscal' year.:
Second, the examiners found that'some initial candidates were unsure of-their responsibilities, as reactor operators, under Reed's Emergency Plan.
1 Tor example, they did not know when and how to sound the emergency a
evacuation alarm under emergency conditions.
1 i
Third, the examiner's found that the majority of the. initial applicants showed some weakness in their comprehension of Reed's administrative i
procedures;and practices that govern reactor operation and_ documentation, l
including procedures for handling and transferring irradiatedispecimens.
1 Most initial candidates have indicated'that_they had never been trained or involved in material transfer procedures even though this is an 1
operator responsibility at Reed.
1 Finally, three nut of the five operator candidates, examined by the Chief 1
Examiner during this ext.ination, were observed: placing their foot directly 1
on the fixed hand and foot radiation contamination monitor, when exiting i
-the reactor room. This is contrary to sound radiol _ogical safety practices, a
since it would eventually contaminate the monitor, makingI.itlinoperable.-
.The licensee's management acknowledged these findings and committed to resolve these issues by upgrading their operator training program _ prior to the next examination.
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- On May F;, 1990, the Chief, Examiner met witn the representatives of the
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%,;11cen%c's_stafftodiscussthe;examinationandtheNRCfindings.
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tihe-licendee staff acknowledged the findings and! indicated that steps 1
fwere.being:taken'inttheseareastocorrectthedeficiencies.
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Attachment A
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. REED C 0 L 1. E G E
'Fordand, Oregon 97 o2 -
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., y; VICE rat IDE T-- P h o v0ST
.May 23, f 4 : 56 John B. Martin, Regional Administrator i
U.S.N.R.C., Region V -
1450 Maria Lane, Suite 210 -
Walnut Creek, CA 94596
Dear Mr. Martin:
q
-i The purpose of this letter is to provide thelN.R.C. with comments on h
the written exams given to our reactor operator candidates' at Reed i
College during the week of. May a 14-18,1990.
i As we indicated to Mr. Meadows,' Chief Examiner, at' the exit review,-
we believe this exam was fair and well, run.
We are requesting no changes to the Answer Key discussed between Mr. Meadows and Mr.
Pollock, Acting Director following the administration.of the exam.
Attached to this letter are minor suggestions from the reactor staff o
3
-which we believe would improve three of.the questions' before they are loaded into the N.R.C. exam bank-for; subsequent use.
These have-l already been discussed with / Mr. ' Meadows.and - are included here j
simply to formalize our feedback to the N.R.C.
]
Again, Mr. Pollack and I would like to thank Mr. Tom Meadows and Mr. Ralph Cooley for conducting, the exams this -y' ear.
O Sinherely, g
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Doug as 13ennett -
Prov'os t i
i 3 2 03 S o u t h e a n s R'a ods s oc k R o ule v a rd Pers tan d. Gregon' 9 7202 Telep h o n e (5 03) 771 1112
Comments on the NRC Written Exam administered at Reed College on May 14,1990.
Prepared by 1. Michael Pollock, Acting; Director-j Requests for changes in answer key:
Non e. - The-staff. review of -
this exam indicated that it was an excellent exam.
All questions were
- fair and, except for question -C. 06, had completely unambiguous answers..
Although question C. 06 could have been ambiguous,to some examinees, we do not believe it was sufficiently so as to require a change on the answer key.
1 Suggestions for rewording:
As discussed with Mr. Meadows at the ~
time of the exam, we would like to make the following suggestions-i purpose of improving these questions before loading onto the " exam bank" for potential use in subsequent exams.
Question B-12:
At Reed, a reactor operator may be called upon to verify the proper labeling of a container of radioactive materials being prepared for shipping.
For-the "-Maximmn-Total-Dece" rate determination-of-the-shipping-eentainer+- One of the radiation:
j levels recorded most be the Maximum External Surface Dose Rate-
^
.l How far must the operator -hold the detector ' probe from the I
container surface for the second radiation measurement?
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1 Question 0-12;E
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-e, a o m c. rm s,.,,...,.,. K Which of the following safety. devices alarms _ with a high
' ' f g j frequency audible alarm and flahing red light, and is located on a 1
panel on the -North South wall of the Reactor Room?
Question C. 06:
There are -fixed several safety devices at Reed that are capable of detecting fuel failure, -or other hazardous reactor conditions.
As specified in Reed's Emergency Plan:
Which of the following safety devices normally reads abotit 0_.1 mR/hr when the reactor is operating and is located -at near the Reactor Room door, in the control room.
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UNITED STATES NUCLEAR REOULATORY COMMISSION a
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RE000N Y 8,
1460 MARIA LANE, SUITE 210 WALNUT CREEK.CALIFORNI A 94688 WRITTEN EXAMINATION ANSWER SHEET / NON-POWER REACTORi Reed College EXAMINATION DATE: May 15, 1990 / Reactor Type:
MK1 - TRIGA Region:
V P.assing Grade:
70%/Ca tegory Time Limit:
3 hrs.
CANDIDATE'S NAME (please print):
MULTIPLE CHOICE, MARK THE CORRECT ANSWER WITH AN X:
Example:.01: A )( C D Reactor Operational Procedures / Radiological Plant Design &
Physics Controls.
Radiation Monitoring
_ CATEGORY A:
CATEGORY B:
CATEGORY C:
.01: A E-C D
.01: $ B C D
.01: A( C D
.02: A BC D
.02: A( C D
.02: ( B CD
.03: (' B C D
.03: A BCD
.03: AB C:(
.04: A O C D
.04: A(~CD
.04: ( B C D
.05: OB CD
.05: A B C
.05: A ( C D
.07: $ (B B - ( (0
.06: a C D
.06: A
.06: A B-C C.D
.07: ( B C D'
.07: A B C
.08: A B@D
.08: AB (
D'
.08: A B (
D-
.09 : ( B C D
.09: ( B C D
.09: ACC D
.10: A B CD
.10: A OC D
.10: ( BC D
.11: A B ( D
.11: O (B A
C D
.11: A B ( D
.12: ( B C.D
.12:
C D
.12: ( B C D
.13:-A B CD
.13: A -B C-(
.13: A-['C D
.14: ( B C D
.14 : - A (,f Q('
A-( O D C
D-
.14: A B
.15: A B CO
+.15: A B
.15:
C D
.16: A (- C D
.16: A B L D
.16: ( B C D
.17: A ~B
( D
.17: A BC(
.17: A B CC
.18: ( B C D
.18: ( B C D-
.18: A B CD
.19: A( C D
.19: ( B C-D
.19: A LC D
.20: A B CO
.20: A-B C l'
.20: A B CO Category Value 20 Category Value _2_0 Category Value 20 Score:
Score:
Score:
Grade:
Grade:
Grade:
Overall Grade:
NOTE:
1.
Check that you responded to ALL questions, and that all responses are correctly marked ON THIS ANSWER SHEET!
2.
Sign this answer sheet and turn in ALL exam materials to the NRC EXAMINER.
All work done on this examination is my own, I have neither given or received aid:
Candidate's Signature
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'EQUA, TION SHEET f = ma
,7t w = ag 2
a
- v t +, Isat Cycle efficiency, Met' Work (out)-
E * "I 0
hergy (in) a = (yI.,)fg 2
KE = Iggy
-v o
~-
g = v + at
' A = AN -
A = A'e-At-PE
- ash o
""M A
2/c
= 0.693/e u. ygp g
AE = 9314a-eg(efg), Mi;)(t j ' q
6=fcAT
( 1 + "b) 5 p
._..k=.UAAT I = I,e I = I e~I'*
Pwr = Wg&'
I=I 10-x/ m '
-P=P 10SUR(t) o TVL = 1.3/u
- e
- t/T y.p HVL = 0.693/u-SUR = 26.06/T T = 1.44 DT SCR = S/(1.. g'If)
(x'If g SUR = 26 l A - p)j
(
CR '= S/(1. getfx),
.CR (1 - gaff){ = CR (1.* g y
T=fp+ (8 ak) t' y
eff)2 M = 1/(1 - K,gg) = CR /CR g
0 eff OIII ' Km){
eff'l)/K gf = AK,gg/K,gg.
.SDM = (1'. g
[ **/7K 'ff 1 + [E/c1 + x,,,1)]
,*. 1,,, l") fg*"
e 1
P = I(y/(3 x 10,0)
I = No eff = 0.I' seconds ~I Id l t =*I d2 2-
'I d2 t
- Id 2
R/hr " (0.'5 CE)/d (meters) 2 2
R/hr =.6hCE/d (geet)
WATER MISCELLANEOUS.
PARAMETERS CONVERSIONS -
1 gal = 8.345 lbm 1 gal = 3.78 liters 1 Curie = 3.7x10
- dpe l
1 kg = 2.21 lbm 1 ft3 = 7.48 gal 1 bp = 2.54x103 Blu/hr -
Density = 62.4 lbm/ft 8 1 MW = 3.41x10* Dtu/hr -
Density = 1 gm/cm3 1 Dtu = 778 ft.lbf Heat of Wporisation = 970 Dtu/lbm 1 inch = 2.54 cm lient of fusion = 144 Blu/lbm 1 Atm = 14.7 poi = 29.9 in, lig.
'F = (9/5'O ) + 32
'C = 5/9 (*F - 32)
I ft. II 0 = 0.4335 lbf/ina 3
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V KEY' CATEGORY [A-'
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- QUESTION : A.01 C 1. OF ij a
MULTIPLEJCHOICE, SEL.ECT THEICORRECT: ANSWER:
WhatR-arelthe~three materialsithatLareidesignedlas moderators'.If'ord
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Reed's MARKf11. reactor?!
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ZirconiumfHydride'(ZrH2F,4 Concrete,fand~ Graphite; g[
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Water, '_Graphi tu, f and.' Zi rconi um Hydri def- ( ZrH2f ^
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Aluminum. Concrete,fand Waterl i
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- ANSWER'
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.b.
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- REFERENCE.
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.4 si Reed - Trai ni ng Manual', Modul e: 12-6 j!
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- QUESTION A.02 E1.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER:
j Which one of.the following statements correctly describes the property of a GOOD MODERATOR 7 a.
It slows down fast' neutrons =to thermal energy levels via a large number of collicions.
b.
It reduces gamma radiation to thermal energy levels via a small number of collisions.
c.
It slows down fast neutrons to thermal energy levels via a small number.of collisions.
d.
It reduces gamma radiation to thermal energy levels vin a large number =of col l i si ons.
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- ANSWER c.
c-
- REFERENCE Reed Training Manual, pages 12-2-37 8<
12-6-15-19 E
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- 0UESTION A. OT.
E1.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER The reactor in at a power of 1 watt, with a 30 second Ekebl0' period.
How long will it take for power'to reach 500 watts?
a.
106 seconds b.
140 seconds c.
124 seconds d.
81 seconds
- ANSWER a.
n/no a expEt/T3 500 = e>tp [ t /T3 In 500 = t/30 t = 6.21 x 30 = 186 seconds
- REFERENCE
.i Reed Training Manual, page 12-5-22
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- OUESTION A.04 C1.03 MULTIPLE CHOICE. SELECT THE CORFCCT ANSWER The reactor is at a utable power-of 0.1 watt.
2S cents of reactivity is inserted.
Given thatt T
(del avec neutron mean lif etimei = 12.3 seconds Ap (prompt neutron lif etime) =2x 10^-14 seconds Beff
= 0.0065:
What i s the resul ting gtgQLe reactor period?
a.
48 seconds b.
30 secondu c.
28 unconds k
d.
22 seconds i
- ANSWER b.
deltaK
- m. 25 x.00.65 =.0016 t
["atable period", therefore P
can be neglected 3' T=
CBeff - deltaK/3 x i
/ del tcK T = CO.OO65 - 0.00163 x 12.3 /O.0016 T = 0.069/O.0016 T = 37.67 (30) secondu i
- REFERENCE Reed Trainino Manual, page 12-5-19-22 ij a
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- OUESTION A.05 C1.01
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y SELECT THE' CORRECT:-ANSWER?
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MULTIPLE CHOICE,
- I The, reactor.was shutdown after an? extended,ttwe' week,?high power; j
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=run at2OO kilowatts, to : A rradi ate.a-; speci men.:
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- How :l ong. will;.i t - take f f or.the: MAX IMUM X. enon. P.OISONieffectatoi
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_O to 15-hours r
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-29 to135 hours;
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- 1 to^3l hours.
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- f)NSWER a.,
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- REFERENCE Iq kend Trai'ning Manual, pags?'12-7-25:
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- 0UESTION A.06 [1.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER The' reactor is gubstiliggl with a Keff of 0.96 and 30 counts per second-indicated. After a fuel element in removed the count rate drops to 10 counts per second. No other changes have occurred.
What is the Keff of the core with the fuel element removed?
a.
0.9733 b.
0.8800 c.
0.8400 d.-
0.0000
- ANSWER b.
CR1/CR2 a E1 - Keff23 / [1 - Keff13 30/10 = E1 - Keffl /
El-- 0.963 1 - Keff =3x 0.04 = 0.12 Keff = 0.8800
- REFERENCE Reed Training Manual, page 12-4-21 6
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- 0UESTION'A.07 C 14 03
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- MULTIPLE CHOICE, SELECTiTHE CORRNCTlANSWERi
-Which of4 the f allowings statements best defines :a " dollars"' warthi of reactivity,,at-the-Reed Reactor-Facility?;
a.
One dall'ar [$1. 003 x.i si equi val ent? to I Bef f L = ' O. 0065 7
' delta-K/K.-
b.
One; dollar-[$1.003.is~ equivalent to,Keff
-[1. 00;
=
delta-K/K.
4 c.
One-doll at: t$1.003.i s equi valent.to Bef f =11.OOt
-delta-K/K.-
d.-
One doll ar - [$1. 003. i s equi val ent ' to. Kef f.' = 0.0065 -
delta K/K..
- ANSWER a..
Sj
- REFERENCE Reed Training Manual:, pages 12-5--13. ~12 5-2E andi.12-7--5 )
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- QUESTION A.OB C1.03-T
!MULTIPLELCHOICE, SELECi~THE CORRECT. ANSWER-Whidh 'of, thw[f all'owing: ef f acts / i s' the : PRIMARY /contri butor ' to thha e
temperature coefficient of reactivity?
- a.
- doppler resonant effects-(doppler' broadening);
.n
- 4. m core 1e"akago _ ef f ects!
b '. -
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sc.
. coroTspectrum-hardening) ef f nets L(ZrH2 ef f acts $
D
- o d.
~ core voiding effects-o u.
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- ANSWER;-
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- REFERENCE a
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Reed Training Manual,.pageL12-6-19 31
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- OUEST10N A.09 C 1. O J -
MULTIPLE CHOICE, SELECT THE CORRECT ANSWER When Reed's reactor is operating at steady state 200 kW, the heat
' transfer from the fuel centerline to the fuel cladding is correctly characteri:*ed as:
a.
conduction b.
Film boiling c.
convection-d.
Nucleate boi1ing
- ANSWER a.
- REFERENCE Thermo-Dynamics, Enrico Fermi (1987 Reed e>tamination)
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- OUESTION.
A'.10.
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MULTIPLE' CHOICE, SELECT THE.CORRECTJANSWER.
=
=
a During; steadyThighJpower cperation:
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. How i s the heat.. transier f rom the?f uel? cl adding ~ t o ithe reactor 1.
EU j
. upper pool: correctly; characterized 7 6
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s b.,
Film boiling-o
.j c.-
convectian!
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t
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T.
d.-
Nucleate boiling!..
1 e
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- ANSWER
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- REFERENCE-t ;
Thermo-Dvnamien, Enrico Fermi-f (1987 Reed examination)'
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- QUESTION A.11
[1.01
' MULTIPLE CHOICE, SELECT THE CORRECT ANSWER Which of the f ollowing statements correct 1v describe the influence of DELAYED NEUTRONS on the neutron lif e cycle?
a.
Delayed neutrons increase the time required for PU-239 to moderate the fission process.
b.
Delayed neutrons decrease the time. required f or the neutron population to change between generations.
c.
Delayed neutrons increase the time _ required for the nuutron population to change between generations, d.
Delayed neutrons decreaue the amount of reflection possible with a steel refIector.
= ANSWER c.
- REFERENCE RRF Training Manual, 'Modulen 12-4 and 12-5 (copyt; 1988 Reed e> tam) t 11 1
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A'.~ 12 - E1.03
- 1;
' MULTIPLE CHOICE.LSELECT THE, CORRECT' ANSWER
- Which of-' the f oll owingJ utatements. correctl y descri be-how del ayed '
neutrons are produced?i l
4 w-j a.-
Delayed lneutronsf are produced 'f rom' deleyed neutron precursor nuclei'by. beta' decay-isequences,-each.havingLaE
+
-definite'halfflife.
W>
! b '.
. Delayed [neuteons[are produced fromIthefradi'b1bgicalL.
j
~
di sassociati onJof JSasnari um, ' under thef infl uence '.of.c a t L!
~*
r.<
neutron. flux.;.
l 0
N 4;
- Del nyed neutt ons are. produced f rom del nyedonou'thon' '.
c.
precursorsnuclei by; alpha; decay; sequences,'each having-i a definite. half life, l
s
.d.
Delayed neutirons are produced from;thehradialogical A
di sassoci ati on of U-240, under -thel-i nf I uence ~ of-a '
f neutron fl'ux.
f
- ANSWER
'l 4
a.
- +
- REFERENCE
- c.
~
-RRF Training Manual, Modules 12-4 and-12 - >
(copy. 1988 exam)'
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_ OUESTION,.A.~13-C 1'. O T
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'MULTIPLEiCHOICE,: SELECT.-THE CORRECT.JANSWER-I 4
4 i
g
- What s i s a '" THERMAL' NEUTRON"?-
t e..c h 9 '.
I
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+_
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'a.
- The, pri mary l source - of J thermal. energy: increase (inithet reactorJcore during:reactoraoperation..
- i
-i
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2 b. --
- A neutron ati resonantE capture : energyt l evel s.
./
-i f'
c.
A. neutron that experiencenjno net changefinienergyl a
t
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- af tors severalTcol1 i ni ons~ wi th, atoms.of + the, moderator.
- (
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k' '
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Alneutrontin the 3-6 megawattf-energy range;:
m-vi
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' ANSWER
.R"
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e,q.,
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YA q
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+ REFERENCE'
=(
RRF Training Manual,MModuleD12-6 4
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.* QUESTION 1
m, a,
s 1.n i'
- MULTIPLEL CHOICE 4., SELECT.THE:' CORRECTF ANSWER '
a 8 1
Whati-ci s; the; man-made"; neutronJ source ; made: of ?J. _.
4 R
ai Americ1um-Deryllium!
M 4
i.
t a
.'g v
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Anti monys-Iri di um ~
i
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c.-
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V d.-
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y.
my
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M' i* ANSWER-
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4 :4 g a
- REFERENCE W
a i
RRF Trai ning Manual c Modul e.=.12-1;: Periodie. Table <of the Elements.
y.
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-* QUESTION! A;15 '[1.03 MULTIPLE CHOICE, SELECT THE-CORRECT? ANSWER.
4*
l fWhy were burnabl e poi sons 'added< to1 Reeds core f dur'i ng "initi al'.
_ core =1oading?'
~
If a.
To shape the Lenti neutron flun Ef or maxi ~ mum-f specimen
- irtadiatton,capabillty.
n; tb.-
To reduce theisecondary=inotopiciradiation:-effects-:from?
'ai
- -i rradiated control l rods.:
c.
To shapo: the it)ettne); noutron flux Ef orimaximum specimen U
irradiation capability.-
.d..
- -To increase -the ; avai'l ab'ili ty: oi;. unabl e; nucl ear [f uelb with. the ex i sting ' control rod dent gn.-
.. W 1
a :-
- ANSWER-y
'd.
~
i g -:
- REFERENCE i
- 4
=,.......
,.3 I
RRF. Training l Manual,cpanen 12-6-23 andD12-6-24 d
!.Y
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33
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- OUESTION A.16
[1.03 MULTIPLE CHOICE, SELECT THE CORRECT. ANSWER Reed's reactor has been shut down for three' months.
The operstors are preparing for a reactor startup.
Why are source neutrons important, particularly for t'his operation?
a.
To ensure that the reactor will go' cri tical at 5 kilowatts in the power r an'g e.
b.
To ennure that nuclear power can be accurately-monitored in the range of the count rate channels, c.
To ensure that the reactor will go critical at 200 kilowatts in the power range.
d.
To ensure that nuclear powern can be cccurately monitored in the range of the l'aq power channels.
-
- ANSWER b
- REFERENCE RRF Training. Manual, pages 12-1-7 and 12-4-6
+
16
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- QUEST IONe1 A.17 : : C 1. OL 9 gg-j
! MULTIPLE CHOICE,. SELECT.-THE CbRRECTUANSWER; l
o 3
Followi ng : a _ scram; thereai s a> power decrease on l a stabler negative (
1
. period.
~ '
^
1 l[
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n i.:
-r, i
7 Q
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What"1s'<the value of this! negative; period *?-
o ut O.621' seconds 1
o
- m.
W m,.
(-f s
s
- b._
8 minutes-l' O
3 s
i 1
i
% (
l
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80; seconds
~ )W d
,0.621" minutes
.d.:
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- ANSWER
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- REFERENCE 4
gs RRF Training Manual, Modul es 4; EU,f pagen(12-5-10--12;-arid'.12-5-13$
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- OUEST10N A.18 C1.03 MULTIPLE CHOICE, SELECT-THE CORRECT ANSWER Following a scram there is a power decrease on a stable negative period.
Why is this period always the same value, regardless of the initial power level?
a.
The rate of power change i s dependent on the mean lif etime of the lgogggt lived delayed neutron precursor.
b.
The rate of power change is dependent on the constant decay rate of prompt neutrons.
c.
The rate of power tihange i s dependent on - the mean lif etime of the abgrtent lived delayed neutron precursor, d.
The rate of power change is dependent on the constant decay rate of prompt gamma emitters.
- ANSWER a.
- REFERENCE RRF Training Manual, Modules 4 & 5.
pages 12-5-10-12 and 12-5-13 18 1
4 -
l-
- DUESTION A.19 01.03 MULTIPLE CHO1CE. SELECT THE CORRECT ANSWER-What'is " CORE EXCESS"?
a.
Extra fuel. loaded into the core to. extend the reactor's
}
f unc ti onal lifetime.
b.-
Represents the maximum possible reactivity insertion, considering the, control rod position, at an exactly cri ti cal condition.
c.
Extra fuel loaded into the core to minimine the=need g-for control rod innertion at.high power levels.
d.
. Represents the maximum possible reactivity-insertion, considering-the Xenon concentration, with the reactor increasing power with prompt neutrons.
- ANSWER b.
=
- REFERENCE RRF Trainino Manual, nages 12-6-4 and 12-6-5 1
e W
W
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i 1
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v
- OUESTION A.20 E1.03 MUL.TIPLE CHOICE. SELECT THE CORRECT ANSWER Why does the effect on reactivity by the Fuel Temperature Coe f f i ci ent (FTC) decrease as fuel temperature increases?
a.
The water density decreasen. causing the neutron tggggggge escape probability (p) to decrease.
b.
The neutron energy resonance absorption' peaks-broaden n)gtg for the same degree of fuel temperature change.
c.
The neutron thermal yttlij_eti,go f actor (f )' predominates in its effect on the neutron 1-1ie cycle, d.
The neutron energy resonance absorption peaks broaden legg ior the same degree-of f uel. temperature change.
- ANSWER d.
+ REFERENCE RRF Training Manual, Modules 12-6 through 12-7
- u o o m * *
- u *- * * *
- m *
- m n +
- m * -> > n + m
- m
- m m m m *
- i END OF CATEGORY A 20
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.CATEGORYrBy a
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-.Normaltand Emergency Operating Procedures}and.
' ?,.,
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.RadiologicaliControls
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-
- QUESTION!B. Oil t 1. O T-4,
- . MULTIPLE -CHOICEi-SELECT-THE-CORRECT ANSWER -
s'
. Whatiis thei titl'e j ob:the/ eed of fici'al h
thatfia: responsible [f'or; Yd L
R 1
the sel ectionf ofl-. personnel to:operateithecReediReactor Facilityn
.l,
- (RRF)? W R
si; o
- a.-
) Director RRF.
p
~- =
, m.
o 1 '
,-,s, Prest ldentLof) Reed College:
~ fi %
b..
t:
<x,,.
' c.-
- Reactora Saf ety Commi ttee. Chairman:
1
,;y)
,d.
' Reactor Supervisor =
7.'
i
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1
- ANSWER
-d d
1 a.
d s.---
.g-1 1
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s.,_
- REFERENCE
.f W
it s,
SOP-03.. SOP-04, RRF Administrative Proceduren9 y
4 5
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- QUESTION B.02 C1.03L j
r t
MULTIPLE CHOICE. BELECT'THE CORRECT ANSWER:
i RRF procedure: SOP-04,-Reactor Operat.1ons,' precautions-the operator against" operating the reactorfaboveL96%--of the
'f "licenced" reactor-power..
What i n the. reactor power. L i n ikilowat tn MUIW), that correspondsLto:
"]
96*N power?
s
'a.'
230'kW b.
240 kW 11-l o
c.
'250'kW-4!
d.-
260 kW UI v
- ANSWER
'I
. p b.
[.96.x.250'1imit = 2403-if 1
.t l
- REFERENCE l) 1 SOP-03,' SOP-04 Reed TechnicallSpecl'ficetion's
{
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- OUESTION B.03 C1.03 MULTIPLE CHOICE. SELECT THE CORRECT ANSWER Of particular concern when handlino radiologically contaminated mat eri al 5 is the ingestion of radiation ineidu the body. Given the name curie amount of ingestion and neglecting the chemical hazardt:
Which of the f ollowing types of radiation will cause the most internal biological damage?
a.
Deta b.
Gamma c.
Alpha d.
Xray
- ANSWER c.
)
i i
- REFERENCE RRF Trai ni ng Manual. Chapter 1 CVerbatim May 1988 e>t am3
\\
l 27
g, 17 :t':
W.
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g; O g^ ' h y =
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- QUESTION B.04
[1.03 V..
s
.b 1
g MULTIPLE CHOICE,.BELECT THE-CORRECT ANSWER
'The terms." somatic.offacts"'and " genetic-offects" are usea to describe. biological damage caused'by 1onizing radiation.
'Which - of Lthe f allowing statements correctly describe the genetic
.(
ef f ects of, radiation damage?
e 4'
IC a..
The ef f ects of - radi ati on.: damage. on.the---" skin of 7the human body."
- J b'.
The of f ectu 'of radiationidamage on, the " sperm or L egg '
cells of the human-body."-
j
..n c.
The offacts of radiatton damage on,the." head and,trunis;
~
active blood forming;organn of thre human. body."
-4, j.
t iP
- d..
iThe 'eif acts of radiatton-damage'onLthe " hands and ln fcrearms feet and' ankles'of the human' body."
i q.-
4 d*
i
- ANSWER:
.;t o.
- REFERENCE RRF-Training Manual, Chapter 2 CVerbatim May 1980 ' mt am 3 s
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- OUESTION B.05 C 1. 0L q
MULTIPLE. CHOICE,.SELEL1 THE CORRECT' ANSWER.
A point source of GAMMA' radiation; measures'50 roentgenthr CR/hr3'.
gamma, at a distance off2 feet.
Assuming ' 100'/. detector?. ef f t eihncy:
L i
What ia the'.exposurs:rc.tc-tR/hr3'fromJO1e GAMMA. source'at:di
_ ')
- ~
distance of 16 f eet?-
n-
-l
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48
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9.' s b.:
7.0
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c.
4.0
=.
1 d.
.70'
- t i
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- ANSWER J;
- 1
.d.
a
~7 L.,
d!
D2 = C50 R/hr3-n C2/161^2 = 50/64'=.78f
-
- REFERENCE
.p mi
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RRF: Training Manual, Chapte,r,2.
3
' i 1
13
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- QUESTION.B.06 C1.0]
.I i
q, 3
MULTIPLE' CHOICE. SELECT THE CORRECT l ANSWER' 9>
q.
( -.
,t..
t A point source of GAMMA radiation, measures.50 roentgen /hr4[R/hr3.
1
. p l.'
<s 1-1 6
4-4
,a What ls;the?."Qualith Factor"'necessary to convert this'Valueifrom.
~
?
- R/hr to' rem /hr?
l l
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10 '-
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- ANSWER-t;t
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c.
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- REFERENCE j
- 1 RRF Training Manual, Chapter 2 fj
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- OUESTION-B.07 L1.03 MULTIPLE CHOICE. - SELECT : THE : CORRECT: ANSWER -
The' Code of' Federal Regulations,:part-20.101 C1OCFR203:seta three occupati anal. radi ati on. dose. standards.f or;- i ndi vi dual s i n c
c
- restricted -areas ; f or.the peri od of h one' cal enda'r.) guettet.'
What is the'10CFR2O QUARTERLY"utandard;for,1"Whole bodys; head an'd-trunkt active blood forming organni lens of-'.the eye;;or gonads?"
a.
- 1.25 rum.
b.
- /. 5 r em,
J.o
?
c.-
10.75 rem d.
DIN-183, where N = age >
.e
- ANSWER l
s.
- REFERENCE 1
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. MULTIPLE CHO!CE,. SELECT THE CORRECT ANSWER-t 3.,_
The Code of Federal: Regulations,l part. 20.101 (10CFR203; sets three-
.:l occupationalL radi ation dose standards-. f or >indi vi dual s 'in jj
- restricted areas f or the period of.' one calendar gu,att!!c.:
R t
What 1m the 10CFR2O. QUARTERLY atandard:for,1"handsiand: forearms;.:,-
4eetHand' ankles?"
j r
' i s
.a.
1.25 rem -
v:... u:
1 r,
b.
7.5 rem W-
~
ef
,w b
c.
- 10. 75 - r em 7!
d.
SIN-103, where.N i age-
- ANSWER-'
l'-
i.
- L v
c.
1
, i.
t i
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- REFERENCE t
- c Y
9
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+
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- QUESTION B.09 - C1.OJ.
MULTIPLE CHOICE,: SELECT 5TH CORRECT-ANSWER 3
, i.
Procedure; SOP-03, Startup and' Core Excess Check...statestthat the' it h
core' excess check must be consistent with 'TWO prior reactor condi ti ons.: One of these conditions is, " previous reactor i
history?"
What is=the other reactor condition?-
d
.a.
Experiment loading.
. ;; d
~
b.
Anticlpated-power level for next two weeks.
c.
Current reactor pool: temperature.
.c d.
Anticipated power level [for-hentltwo days.
l a:
. i 0
- ANSWER a-e a,
il i
- REFERENCE i
SOP-03 w
h L
e i
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[ 1. 0 3 -
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.M'ULTIPLE' CHOICE; SELECT:THE CORRECT ANSWER' i
Thel Code of Federal Regul ati ons ', piart 20; 105 t 10CFR20.' 1053..: sets :
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"permi sai bln 1 evel s L.cf.. radi ati on in untegitigigd;stgen.:
What'is.,the 10CFR20.105Lwhole body, MAXIMUM done[ limit...l1n.any:
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period. of. One calendar i yeari-l that : deiLQgg ' an '"unrestri cted. area?"-
li #
2 a.
O.25 rom.
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0.5 rem m
c.
- 1.25 rom.
d.-
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- ANSWER.
~ b.
- REFERENCE 10CFR20'
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N '*DUESTION B.11
[1.03 l
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- MULTIPLE CHOICE,. SELECT.THE. CORRECT ANSWER.
., t a:
I s
,You are the Reactor': Operator, on duty _..during!an' experiment.
- You,
.3,;
[;
. di scover-that ' the " maximum' core excess reactivi ty. worth". li mi t ~ H j
i :,
'has been exceeded. Per SOP-03, Startup.and Core Excess Check
.t i
6 What are the TWO immediate actions that must be"taken?
?
1 3,
'N a.-
SCRAM the reactor /Notif y the Sernior7 Health Physici st -
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_ Shutdown 'the reactor /Notif y the Reactor l Supervisor b.
I'.
c.
SCRAM the reactor / Initiate - the confinernent system..
]
_d.
Shutdown the ' reactor /Ini ti at e th'e t,vacuati on al arm e
lh e
- ANSWER
- .I b,
c
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y 1
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' REFERENCE ~
- ii SOP-03
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.NULTIPLE CHOICE.' SELECT THE' CORRECT AN'SWER -
'l 1
At Reed. a reactor operator may. be called uperf toj verif y. the
-j proper -labeling. of.; a container of1 radioactive materials'being; '
cd prepared for shipping._ One_of1thecradiationflevels recorded must be the' Maximum' External Dose Rate. :
How f ar must. the operator _ holdjthe detNetor tprobe f rom the -
container surf ace ' f or-the SECOND 1ratil ati on' treasurement?
A ;g a.
I' meter 1.
>bj b.
2 inches
.Ii c.
'2 centimeters
'I d.
i foot-
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+ ANSWER 1
a.-
j d
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- REFERENCE j
4,
RRF Administ rati ve Procedures. 50l t34..;;pp 9-10:
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- QUESTION B.13-t1.03 IT ' TIPLE CHOICE, [ SELECT THE CORRECT ANSWER rh, :,:
~
],
Where is the emergency key kept-for access-:to'the maini+2cilityi
. Tg l electrical br eaker?;
',1 3
a.
Control console-4
- M n
.b.
Reactor room M-1
(
c.-
Director's~ office
~
d.
Grab - bag i n ' access -' hal l way,
i
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- REPERENCE RRF-EPIPs
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- 0UESTION B414-C't. 0 3..
7 1
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MULTIPLE. CHOICE,:-SELECT THE, CORRECT; ANSWER
- t v.
"Spect al inuclear material" is - atL-al1.E times. the propeEty; of.' the j
United States.Departmentiof. Energy {CDDE3.-
As.f ar-L as: DOE is concerned, while Iwased = to Reed Colleget' u
.).
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- i. f -t" Who han '." primary accountabi11ty" ff or; i tz' saf e Letorage. and proper handling?.
=,
,n a.i Reactor Operatians, Committee
~
gt.1-o
- b.
'Diructor, j Reed Reactors ' Fact li ty
.I atiion. Saf ety; Commi ttee :
c.
Radi.
/
3 d.
Reactor. Supervisor.
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- ANSWER-s b.'
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/
- REFERENCE' s
S RRF Admi ni strati ve. Procedures =,;. pp 115 '
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l mQUESTION B.15 ti.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER Reed's Technical Specificationn and operating procedures require the reactor to be shutdown if the reactor pool temperature exceeds a specified limit.
What is thin limit?
a.
95 degrees F' b.
120 degrees C c.
95 diegreen'C d.
120 degreen F
- ANSWER d.
j
+ REFERENCE RRF SOP's 63 and 70 RRF Technical Specifications 1
i 35 I
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- QOESTION'D.'16' C1.03 c.
X.
MULTIPLE CHOICE. SELECT-THE CORRECTjANSWER O '-
Reed's Technical' Specifications'and-operati'ng proceduren requite:i p
'.the reactor l' pool water l evel..to be mai.ntained at l npecified : amount above-the top'~gridtplate.
1 I
What in this minimum level?
a.-
'l foot.
b..
- 10-fnet-c..
16 ieet 4
d.-
26 feet
/1
-
- ANSWER
..e s
c.
-
- REFERENCE
- RRF GDP's--63 and 70 RRF Technical Specifications
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- QUESTION D.17
[ 1. O.1
~ MULTIPLE. CHOICE.-SELECTLTHE. CORRECT ANSWER I
t As speci f ied by' Reed 's. Operati ng Proceduremi and LTNchnicalf j
5pecificationst, y
o
-l-What'. i s.the maxi mum reacti vi ty, worth of - any i ndi vi dual ~.i n-core J.
~
experiment?.
l
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$ 3. 00 -
-t b.-
l'. 35. del ta-K/K
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3.0! delta-K/K' fi d.
.$1.35:
't I
- ANSWER i
i d.
~
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- REFERENCE
' 1';
- RRF Admini strati ve Proceduren.;- pp' 11 [
RRF Technical Specifications
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- OUESTION B.10-01.03 2
l MULTIPLE CHOICE.-SELECT THE CORRECT' ANSWER l
i The Reactor Facilitv must be evacuatedidue to a fire.,Per: Reed's'.
. Emergency Implementation. Procedures::
l LWhere do Facility ' personnel' assemble?
f
'l i
4
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Reac' tor Parki ng' Area.
.- i 1
j b..
ChemistryJ Building hallway!
l c.
~ Reactor back lawn d
- )
d.
Chemiutry Laboratory-a 1
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i
-* ANSWER
--j a.
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- REFERENCE
'j Emergency Implementation Procedures; 1
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- QUEST 10N D.19 C1.03 MULTIPLE CHOICE. SELECT THE CORRECT ANSWER The evacuation alarm can be sounded i n two places.
One of these is by the reactor control consol e.
Where in the other place that the evacuation alarm can be sounded?
a.
Renttor bay [nouth wal13 b.
Chemi stry Buil di nci hall way c.
Reactor Rabbit Facility d.
Chemi stry Laboratory (north wall]
4
+ ANSWER a.
+ REFERENCE Emergency implementation Procedures 4
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- QUESTION B.20 C 1.' O L
' Mui.TIPLE.. CHOICE. BELECTi THE CORRECT ANSWER j
Core Excess Checks ere< perf ormed are perf ormed-at a low 'powerF level. at equi 1i bri um.,
Thi s, power '.1 evel 'i s ref erred - to as, " Low-J
-i Power Critical", by' Reed's' operating procedures.-
n What power level'is, " Low-Power' Critical *P" a.
500 cps b._
50' cps-o
-c.
50 Watts d.
5 Watts L
- ANSWER d.
i
- d..
a.
- REFERENCE RRF SOP-3 e
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4 40'
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CATEGORY C Plant and Radiation Monitoring Systems Note:
The following three questions deal with the radiation monitors at Reed that are capable of detecting fuel failure or other radiological hazards.
- QUESTION C.01 C1.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER Which of the f ollowing aaf ety devices han an alarm, and will also activate the ventilation confinement syntem?
a.
RAM b.
Gaseous Stack Monitor c.
Portable Survey Meter (GM) d.
Particulate Stack Monitor
- ANSWER b.
+ REFERENCE RRF Emergencv Implementation Procedures,.and Appendix D (Verbatim, 1989 exam) 41 1
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- QUESTION C.02 C1.03
! MULTIPLE CHOICE. SELECT.THE' CORRECT; ANSWER Which of the' fallowing-safety devdces uses a scintillation counter, and is used to monitor: gamma: radiation levels in tho reactoriroom?
ii f
'a.
RAM f
b.
,Gameous Stack Monitor'
.s c.
CAM-
?
'd.
-Particulate Stack Monitor ~
J
'I
- ANSWER t:
a.
1
- REFERENCE bi RRF Emergency Implementhtion Procedures, Land,Appendin D.
(Verbatim, 1909 e>t am)..
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.3
' MULTIPLE CHOICE - SELECT THE CORRECT ANSWER.
Whi ch ' of the f allowing! saf ety. devicom has an i al' arm metpoi nt '
c4 between11200 cpm and:1000:-cpm?
=.
a..
RAM-b.
Gaseous Stack.. Moni tor:
1:
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c.
. CAM'
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.p; d.
' Particulate Stack Monitor-9
- ANSWER.-
d.
- REFERENCE RRF Emergency.!mplementationi Proceduresi 'and Appendix ;D' 1l
-(Verbatim,-1989 exam) y-t.
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ie MULTIPLE-CHOICE. SELECT-THE CORRECT ANSWERL Which ' of the f ollowing saf ety devices ~ alarms 'withi a - high frecuency audi bl e, al arm and f I ashi ng, red :11 ght',.. and -i n.> 1 ocated = on _
a(r a panel f on the ' South" wall of,: thel Reactor. Room *?
l
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a.-
Secondary wateri: low" pressure monitor.
A_
b.
Dulk' water-monitor.-
^
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- Wat er ' condticti vi t9 moni tor.
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d.
Portabl e Survey Mater -(GM)'
H
,'. W:
- ANSWER
.n.
s.
o,
- REFERENCE n
It RRF Emorcency impl ementati on - Proceduros.;'and; Appendi n. D.
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- QUESTION C.05 C1.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER Which of the f ollowing saf ety devices activates a warning licht on the control console and audible buzzer in the control room 7 a.
Secondary water low pressure monitor.
b.
Bulk water monitor, c.
Water conductivity monitor.
d.
Portable Survey Meter (GM)
+ ANSWER b.
- REFERENCE 1
RRF Emergiency Implementation Proceduresi, and Appendin D l
45
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- QUESTION'C.06 t1.03-
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MULTIPLE-; CHOICE, SELECT.THE CORRECT ANSWER-~
-l N
z There are several safety-devices at' Reed.tNat are capable ooc.
L
.de ecting f uel -iallure, Jor-: other hazardous reactor,, conditione. An ~
t l
f specified.1n; Reed *s Emergency'PlanL Which of the f allowing Jmaiety devicem.no'rmallyf readniabout[0.'1, Jj
+
mR/hr. when.the: reactor ia? operating'and is: located at:the; Reactor-
~
- Room door,.in the' control: room?
~
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CAM r-
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b.
Buli: water-monitor.-
f
,(
c.-
~
7 d.
Portable Survey Meter.(GM)
- ANSWER
- q..
'd.
.* REFERENCE RRF Emergency Irnplement'ation Procedu'res,- and AppendiCD-Ji 3
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- QUESTION. C.07.E1.03!
MULTIPLE CHOICE, SELECT THE-CORRECT' ANSWER:
For Reed's. MARK.I. reactor:
~
Which one.of the f611owing represents the-PRINCIPAL REFLECTOR' used?-
sl 4
a.
' water.
H b.
zirconiunt J
c.
aluminum d.
.graphi te -
- ANSWER:
O d.
e 4
- REFERENCE m
GA-TRIGA Maintenancefand Operating Manual'.
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- OUESTION C. OB [ 1. O'l MULTIPLE CHOICE. SELECT THE CORRECT ANSWER What is the material composition of the Reed's reactor tank?
a.
iron b.
steel c.
aluminum d.
- ANSWER c.
S
+ REFERENCE GA TRIGA Maintenance and Operating Manual i
h 48 k
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- DUESTION C.09 [1.03 MULTIPLE CHOICE, SELECT THE CORRECT ANSWER The pool water lov61 must be maintained at a specified levul for proper skimmer operation?
Why is this pool level necessary7 a.
Above this pool, level, the reactor water system pumps will loose suction and fail.
b.
Below this pool level, air entry could damane the purification system demineralizern.
c.
Above this level, the water prennure could damage the purification nystem filtern.
d.
Below this Invel, air entry could interfere with proper operation of the rabbit tube.
- ANSWER b.
+ REFERENCE GA TRIGA Maintenance and Operating Manual 9
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m,, IMOUTIPLE CHOICE.: SELECT /THELCORRECTIANSWER; f
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'How i s7 water' (ori condensation)l removedi.f ram ther rotary;;specimeni
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y condensation-1tof evapora.te. ;
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