IR 05000170/1990002
| ML20034A207 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 03/30/1990 |
| From: | Eselgroth P, Brian Hughes NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20034A204 | List: |
| References | |
| 50-170-90-02OL, 50-170-90-2OL, NUDOCS 9004200430 | |
| Download: ML20034A207 (92) | |
Text
{{#Wiki_filter:- ,. . L .- . - . , ! U.S. NVCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NOS.
50-170/90-02 (0L) FACILITY DOCKET NOS.
50-170 FACILITY LICENSE NOS.
R-84 LICENSEE: Defense Nuclear _ Agency Armed Forces Radiobiology Research Institute Bethesda, MD 20814-5145 FACILITY: Armed Forces Radiobiology Research Institute EXAMINATION DATES: March 5-6, 1990 CHIEF EXAMINER: /42.- 11< f k 3-E-90 Brian Hughes," Operations Ingineer Date APPROVED BY: 3-# 4/ ' . Peter W. Eselgr , Chief, PWR Section Date SUMMARY: Written examinations were administered to three instant SR0 candidates, and four operating tests were conducted. One written exam was waived. All SRO candidates passed the examination and were issued licenses, t ' 9004200430 900404 f ADOCK0500g0 PDR
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, , ,_ gl l'_ q' -.y DETAILS , . TYPE OF EXAMINATIONS: Replacement
EXAMINATION RESULTS: NRC l SR0.l TOTAL l , Grading Pass / Fail Pass /Faill-l , . 3/0 l l-l Written l 3/0
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- I - - l 'l Operating l 4/0 l - 4/0 Ll l l l l l l - l l - l-Overall l-4/0 l _4/0-l - ,, I l I l- ,j , '1.
CHIEF EXAMINER: B. Hughes ' 2.
OTHER EXAMINERS: L. Vick + R. Laufer.
s B. Weitzel 3.
Operating Test Deficiencies: The following is a generic def.iciency noted on the operating tests. This information is being provided to aid the licensee in_ upgrading license and requalification_ training programs.
No licensee response is required.
There were noted weaknesses in the use of. the Emergency Plan and ll interpreting piping and instrument drawings.
4.
Personnel Present at Exit Interview NRC Personnel
L L. Vick AFRRI Personnel ! l M. Moore, Facility Director . 5.
Summary of NRC Comments made at Exit Interview < l A summary of the week's activities was presented and discussed. This included a discussion of the results of the review of the' SRO written examinations conducted the week before the test was administered. The
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purpose of this pre-exam review was' to verify that =the-questions . accurately reflected the plant configuration-and the material taught.
Facility written comments were resolved satisfactory to all parties.
6.
Summary of Facility Comments and Commitments made at the Exit Interview: The facility expressed appreciation for having the opportunity to review-the written examinations prior to their being administered.
Comments received from the training staff 1following the exam were favorable in that they felt the test reflected conditions-peculiar to AFRRI.
Attachment: Written Examination and Answer Key'(SRO) , i ? P r ! l i l l l . l' l
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1 ~NRC Official Use Only.
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, i-l l Nuclear Regulatory h inaion-c W a h= Licensing-
' Examination \\ . ! 'Ihis document is removed frun Official Use only category on date of examination.
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NRC Official Use Only ! ! i .,, - - -
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, k . r U. S. NUCIEAR REGUIA'KRY 00lWISSICH - u IKH-POWER REACKR LIGNSE EXAMDRTION I REGION-1.
L l FACIIITY: APRRI ' c , ' ! REACKR TYPE: 'IRIGA l - L IATE AIMDEIERED:. 90/03/05 ' l CANDIDATE:-
.. LICDISE APP 12ED FOR: . INSIRDCTIWS 'IO CANDIDATE:
Answers are to be written on the exam page itself, or on the answer sheet ~ prwided. Write answers on cne side suly. Attach any answer sheets to the -
examination.- Points for each question are indicated in pai.edle.ses for.
each question. A 70% in and section is required to pass the examination.
Examinations will be picked up three (3) hours after the examination starts.
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% OF-L CATEGORY % OF CANDIDATE'S CATHXRY VAUJE 'IUIAL SCORE VAIDE CATEGORY .; 20.00 31.75 A. ' REACIOR 'IHBORY, 'IHERIODYNAMICS AND FACILITY OPEPATING , GARACTERISTICS ; I 22.00 34.92 B.
NORMAL AND DERGDK:Y OPERATING PROCEDURES AND RADIOIJ0GICAL CONIROIS 21.00 33.33 C.
PLANT AND RADIATION IDEIORING SYSTENS i 63.00 % TOTALS FINAL GRADE
All work done on this examination is my own. I have~neither given nor remived aid.
Candidate's Signature - ~. ,, . -- . -... .... . . -.
_ . _ ~ _ _ L .; _.. 'a.
. . L' e \\ , > NRC HJIES AND GUIDELINES FtR LICENSE DGMDOTICNS During the' administration of this examination the followig rules apply: 1. Cheatig on the examination means an autanatic denial of your applicaticn - arri oculd result in mre severe penalties.. 2. After the examination has been ocmpleted, you mst sign the statanant on the cover sheet. indicating that the work is your own and you have not . received or given assistance in ocupleting the examinatim. 'Ihis mst be done after you couplete the examination..
3. hLwn trips are to be limited arri only-one candidate at a time may.
> leave. You mst avoid all contacts with anyme outside the examination room to avoid even the appearance or possibility of cheating.- , 4. Use black ink or dark pencil only to facilitate legible tw.doctions.
5. Print your name in the blank provided in the upper right-hand corner of-the examination cover sheet.
! 6. Fill in the date on the cover sheet of the examination -(if !='an==U). l 7. You may write your answers on the examination' question page or on a ' l separate sheet of paper. USE CELY 'IHE PAPER PRWIDED AND DO NOP WRITE CN ' 'IHE BACK SIDE OF 'IHE PAGE.
, , 8. If you write your answers on the examination question page and you need more space to answer a specific question,'use a separate sheet of the - paper provided and insert it directly after the specific question. DO NOP WRITE ON 'IHE BACK SIDE OF 'IHE EXAMINATION QUESTION PAGE.
l 9. Prjat your nam.in the upper right-hand corner of the first page of each ' ' section of your answer sheets whether you use the examination. question i pages or separate sheets of paper. Initial each page.
10. Before you turn in your examination, consecutively > number each answer i sheet, including any additional pages inserted when writing your answers on the examination question page.
I l 11. If you are using separate sheets, number each answer as to category and number (i.e. 1.04, 6.10) and skip at least 3 lines between answers to allow space for grading.
12. Write "Erri of Category " at the end of your answers to a category.
> 13. Start each category on a now page.
14. Write "Iast Page" on the last answer sheet.
15. Use abbreviations only if they are w-ady ussi in facility literature.
Avoid using symbols such as < or > signs to avoid a sinple transposition error resultirq in an incolla:ct answer. Write it out.
l , - . .. ,, ,, . , ,..,,,
. . - . . . -- - , ' Q '. . . -. . . , .. , I 16. 7he point value for each question is' indicated in parentheses after the question. The amount of blank space on an examinatico question page is NCTP an indication of the depth of answer required.. s 17. Show all calculations, methods, or assumptions used to obtain an answer.
18. Partial credit may be given. Therefore, ANSWER ALL PARTS OF 'IHE QUESTION AND DO NOT IEAVE ANY ANSWER BIANK. N7IE: partial credit will NCfr be given on alltiple choice questions.
19. Fwrational grading will be applied. Any additional wrong information l l that is provided may count against you. For exanple, if a questicm is' ' worth one point and asks.for four responses,. endt of which is worth 0.25 t points, and you give five responses, each of your responses will be worth
! 0.20 points. If one of your five responses is ir mmt, 0.20 will be deducted and your total credit-for that question will be 0.80 instead of - 1.00 even though you got the four correct answers.
- 20. If the intent of a question is unclear, ask questions of the examiner only.
. 21. When turning in your examination, a=aanhle the coupleted examination with examinatico questions,- examination aids and answer sheets. In addition, l turn in all scrap paper.
22. To pass the examination, you taist achieve at least 70% in each category.
l 23. There is a time limit of (3) hours -for ocupletion of the examination.
(or some other time if less that the full examination is taken.)
24. 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 prwi s, your license may be denied or revoked.
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AVAILABLE IN CONTROL ROOM -FOR . ,y .- L REFERENCE BY OPERATOR AT ALL TIMES 13 SEP 89- , APPRI 'IRIGA REACIOR PARAMETERS ', t Prmpt Neutron Lifetim 39psec B3ta effective 0.0070 Prompt Negative Temperature' Coefficient ofl Reactivity-1.26x10~4 LK/K/#C (-SO.018/*C) Stoady State Temperature Coefficient' of Reactivity (Both components) t - 5.1x10-5 oK/K/"C- (-S O. 007/* C)
. Void-Coefficient of' Reactivity F-0.2x10'4 E/K/1% Void Tank. Constant l'48'C/100-Kw-br .' . Power ~ Coefficient of Reactivity: 15 Watts to 100KW S0.56 15 Watts to 1MW S3.17 Nominal ~ Fuel Element Worth (compared to H 0)
. %AX/K (S) Ring' O.82 1.17 ' . B C 0.74 1.06 D 0.62-0.88 E 0.40 0.57 F 0.21 0.30 Nominal Control Rod Worths Standard $1.87 Transient $3.67 Standard Follower.
$0.20 l . Transient Follower S0.30 Other Magic Numbers E = 3.1x1010 fissions / watt-second v = 2.47 neutrons / fission -, REFLECTOR COEFFICIENTS I Coro' Position Rod Position Measured Excess Difference from 567 t 231 REG 645 S3.67-480 i.
567 REG 456 S4.15
L 833 REG 459 S4.15
' 903 REG 623 S3.72-43C ll' For all measurements: SAFE-Up SHIM-Up TRANS-250 l I
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2(o-3) ( C) , MD-8) MWS g , max o a tot k (Q ) =f0[
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E " E ~If $1+1T 1+A T-e i
For T >10 sec.
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REACTIVITY Measure of departure from prompt critical ak k-1 Ak ~.L.
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RX 'nErRY, 7Hmc & tac op omRs page -4
t t - QUESTION A.01 (1.00) ' Wilch one of the followirg is the AM reason that delayed neutrons ' enhance control of the reactor? a.
More delayed neutrons are pMM than prtmpt neutrons.
. b.
Dalayed neutrons increase the mean neutron lifetime.
c.
Delayed neutrons taka lon;per to thermalize than swvi. neutrons.
d.
Dalayed neutrons are bom at hi$mr energies than s w vi. neutztms.
,
r I l . b (***** CATEXXRY A C0tfrINUED ON NEXT PAGE *****) ' . . ..- _ _.. . _,. _. __ _... ._ _, _-.
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RX '1HEDRY, 'IMERPO & FAC OP ORRS Page S ' ,
. ) QUESI' ION A.02 (1.00) { Which one of the following terms can be zwpresented by the equatient .
- of fast neutrons inhich are slowed dQdi in the core W of neutrons prMM_ by thermal fissions
- a.
fast fission factor
b.
reprodxtion factor . ' , c.
fast non-leakage probability d.
thermal utilization factor i , l i ,
h (***** CATEGORY A CONI'INUED CH NEXT PAGE *****) , f - - - - - -
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RX DEKRY. THD00 & FAC OP WARS Page 6 !
I t GJESTION A.03 (1.00) f Which one of the followirq oorrectly describes the relationship between
differential rod worth (Inf) and integral rod worth (N)? i a.
36f is the slope of the N ourve at a given location.
i b.
[Hf is the arma under the W ourve at a given location.
'
Inf is the square root of the N ourve at a given location.
c.
d.
There is no relationship between II6f and M.
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RX 'DDI5tY, 'IHERO & FAC OP ODRS page 7 ' , b GJESTICH A.04 (1.00) , Samarium wafers are used in the AFRRI fuel elenants for whidt one of the follwing reasons? - s a.
to exterd the life of the fuel elenant I b.
to add structural support to the fuel element ' c.
to reflect fast neutrons back into the oors d.
to slw down the fast neutrons emitted fran fission i ?
?
t i l P l l
. l . (***** CATEGORY A CONTINUED ON NDer PAGE *****) ? t , -- - - - - - ,e ,a-.
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RX 'IHBCRY, DIEIDO & TAC OP ORRS Page 8 , , P I QUIsrION A.05 (1.00) { The AERRI startup source produces neutrons by Wcts one of the followirg ' methods? i l a.
photoelectric absorption b.
pair production ' - c.
ganna absorption d.
alpha particle absorption
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RX 'nEIRY, THERPO & FAC OP GARS Page 9 .
QUESTION A.06 (1.00) [
Which one of the followirg wn4dy describes a Isactor's state if one I dollar's worth ($1.00) of positive zwactivity is inserted into a critical reactor? a.
sqpercritical ' b.
prunpt critical + c.
prtspt supercritical d.
critica).
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RX WEKRY, 2D00 & FAC OP OU@S Page 10 ) i
h
CUESTION A.07 (1.00) Whidt one of the followirg describes the effect of nauwing the ocurce , with the reactor critical at 1 att? I a. the effect will not be noticeable at this power level b. a large negative period will drive the reactor subcritical
c. a slight negative period will result
d. a slight positive period will result
, t ? ,
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RX '1HEORY, 'INERO & FAC OP OERS Page 11 , , t QUESTICH A.08 (1.00) .Given - the reactor is operating at a steady state power level . - the primary cooling system is secutred ' - pool tauperature has incomamari 7.5 degrees C over the last half
hour ! Which one of the following is the wuximate reactor power level? t a.
10 W b.
250 W c.
500 W l d.
1W , . t , l l , I l l l
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RX 'HENI, 'ItlERPO & FAC OP CHAR _S Page 12 - i l QUESTICH A.09 (1.00) i Which one of the followinJ is NCTP a reason why the AFRRI core was designed with a significant amount of exoass reactivity? a.
to overcame heat up b.
to allow for pulsing c.
to produce higher power levels d.
to ocupensate for burn up over time . q , ? - e ! i t l , , t (***** CATB30RY A CmrINUED CN IEXT PAGE *****) , -. - , - a v.,-s,,,.y e
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RX 'nEERY, THERPO T FAC OP QRRS Fage 13 ! t QUESTICE A.10 (1.00) Given the reactor is critical at 15 watts with the following rod . positions: Sat 100% ' Shim 100% i Trans 25% ' Reg 50% >
Nhidi cne of the following is the K-ecoess for the ATRRI core? a.
$1.50 b.
$2.07 . c.
$3.03 ' d.
$4.03 l l l l , ( ' l i I i , , , (***** CAIE30RY A CONTINUED ON NEAT PAGE *****) r . . -. . - _ , , .- --
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RX 7HEKRY, 7HERPO & FAC OP ORRS Page 14 l 'l i i l QUESTION A.11 (1.00)
7he hiption of an experiment on a Beactor Use Request requires that - power be ranped frun 15 watts to 50 m on a 5 second period. Which one of l_ the following will be the elapsed time to reach 50 W for this ranp? a.
10 secords b.
20 seconds i.
c.
30 seconds ( d.
40 seconds ! l ' , l l . '
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! l A RX 7HEIRY, THE:HPO & FAC OP ODJts Page 15
i i QUESIION A.12 (1.00) i
Which one of the follosing is the reactivity change widt occurs in the I AFRRI reactor if the fJel tatoerature goes flun 200 deg.C to 230 deg.C during a pulse?
a.
+$. 21 b.
-$.31 i c.
-$.54 d.
+$.75
. I
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RX 'mBORY, 'MG350 & FAC OP ORRS Page 16 QUESTICH A.13 (1.00) 'Ibe reactor is started up ard K-eccess measured during the startup was $3.68. If the pool temperaturn had been 10 dag.C higher when the K-a-a s measurement was made then the measured K-excess would have been which one of the followirg? a.
$3.50 b.
$3.61 i c.
$3.68 d.
$3.75 t L t
I . , D (***** CATD3ORY A CCtifI!UED ON NEXT PAGE *****) ,
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RX 'DIBORY, 'n{ERO & FAC OP ORRS Page 17 i
QUESTION A.14 (1.00) i J At whidt one of the following power levels would you av=t to start seeirg the effects of core heat up?
i a.
1W b.
5W j c.
10 m d.
50 W ' (***** CATEGORY A CONTINUED ON NEXT PAGE *****) , I
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RX 'IHBORY, 'nE:RPO & FAC OP N 1 9 is ! (!UEETTION A.15 (1.00) 'Ihe following data was taken durirg a core loading:
- of elements detector A (cm)
detector B (cm)
16
12
31
29
I
48
42
So M11d1 ane of the followirg is the number of elements that will be required for a critical mass? , a.
b.
c.
d.
l
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RX 'INEERY, THERO & FAC OP OWS Page 19 i QUISITON A.16 (1.00) An experiment is 1* in the B-ring of the core when the reactor is
operating at 1 PM. After loading, the reactor pwer level decreases to ' 500 )M.
Neglecting heating gain or loss, which one of the following is the reactivity wWri by this experiment? a.
$0.50 b.
$0.96 c.
$1.13 d.
$2.84 i ! . ? , i t , i (***** CATEGORY A C0tfl2NUED CN NDCP PAGE *****) . .,
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RX 'nEIRY, 'IHERPO & FAC OP ORRS Page 20 i GJESTION A.17 (1.00) , , Which ana of the following is the correct value for Faff of a subcritical reactor if count rate has incrmaand flun 100 cps to 150 cps and Kaff was initially 0.95? a.
925 b.-.950 c.
967 d.
976 ? l l , ? l l . .:
,
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RX 'IHEKRY, 'D{E300 & FAC OP ONtS Page 21 i h GESTICH A.18 (1.00) ' Milch one of the followiry is the stad reason for the -80 second period followirg a reactor scram? 'Ihe fuel temperature coefficient adding positive reactivity a.
i due to the fuel tanparature decrease following a scram.
b.
'Ibe ability of U-235 to fission with source nartrons.
, 'Ihe amount of negative reactivity added on a scram being greater c.
than the shutdown margin.
, d.
'Ihe decay constant of the longest lived gruup of delayed neutron . precursors.
' ' .
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RX 'IMEDRY, 'IMEF00 & FAC OP CHAR _S Pege 22 e !
! QUESTICN A.19 (1.00)
thich one of the following statements correctly describes the effect of a fuel tenperature increase on a fuel-moderator element? ! , i me probability that a thermal neutron will lose energy in a ! a.
collision with an excited state Hydrogen atom i e nam.
'
b.
Se prtiebility that a neutztm will escape fran the element before being captured significantly increases.
- , c.
me thermal neutron % hum in the fuel clement shifts to a lower I average energy.
d.
We mean free path for neutrons in the elenent is decreased appreciably.
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RX MERY, WE:RC & TAC OP OIARS Pege 23 QUESTICH A.20 (1.00) Milch one of the following elements bas the highest neutzun absorption cross section? a.
Cadmium-113 I b.
Baron-10 - c.
Xenon-135 ' d.
Sanarium-149 ' e i , l I l !
, +
(***** END OF CAIB30RY A *****)
I . . . O B.
NORRI/aEpc moamDRES & PAD Cui Enge 24 . QUESTIQ4 B.01 (1.00) Aside fmn a licensed operator present in the -Lul rocan, which one of the following correctly theribes the additional Weal Specification marning requinsnents when the reactor is not secured? , a.
A licensed SIC on call and a radiation control technician within the AFRRI canplex.
b.
A licensed SIC on call, a radiation %Rul technician on call, L and another person in the AFRRI ocmplex capable of assisting l the operator.
- A licensed SRO on call within 10 mi. of the facility, a radiation c.
control technician within the AERRI otmplex, and another licensed
person available within the AFRRI ocmplex.
I d.
A licensed SRO on call capable of reaching the facility in 30 ! min. and a radiation control technician capable of assisting the , operator available in the AFRRI ocuplex.
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!KHRI/D4 ERG PROCEDURES & RAD CIN Page 25 i ! QUESTICH B.02 (2.00) , Match each of the administrative requirements listed belcw with the title of the individual responsible for its aootmplishment. (responses may be
used more than arca) Administrative Mir==arits: 1.
establishing tenporary rue 3 ares for a specific situation 2.
granting r=mi== ion to enter an E-re room 3.
reactor facility key control 4.
supervising the insertion of an approved in core experiment ! Title of Individtm1: A. SRO on duty ! B. Reactor Staff Representative ' C. Reactor Operations Supervisor - D. Reactor Facility Director E. Reactor and Radiation Facility Safety Comnittee , (***** CATIDORY B CINTINUED CN 107 PAGE *****) , - -- n
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NOR9&DE3G F50CEDLRES & RAD CrW Page 26 ! l i QUESTICH B.03 (1.00) After an incident, a gama survey of the affected area is ocmducted Wticta results in a radiation level of 3.5 R/hr. What is the longest time you j can remain in the area without W_ Lng your normal quarterly whole i body limit? ) a. 21 min, b. 42 min.
- c. 51 min.
' d. 102 min.
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}OOR1/DIEFG PROCIIIRES & RAD CrH Page 27 ' , i h ,. QUESTICH B.04 (1.00) A point soume of radioactivity maamming 80 mr/hr of game radiation at l one meter has been detected. Assuming 100% detector efficiency for gama, - at what distance frun the source will your aware be reduced to 20 l mr/hr? f i a.
2 meters b.
3 mters c.
4 meters d.
8 meters ,
, i i , ! < < (***** CATDQORY B CDtifDUED CN NEXT PAGE *****) . , F .
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N309J/DGmG PROCEEURES & RAD CIN Page 28 , , QUESTICH B.05 (1.00) l . An accessible area with a radiation lwel of 150 mr/hr should be posted . as a(n) , i , a.
restricted area b.
radiation area c.
high rwiiation area ' d.
exclusion area + , , , . ~ l a , t , E > (***** CATEGORY B CONTDRJED CN NEXT PAGE *****) i i
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lORRI/DGE MOCE:DURES & RAD Cm Page 29 t , QUESTICH B.06 (1.00) i Which one of the followirr;i best describes " warm" liquid radioactive waste? ' waste too highly radioactive to be diluted ard discharged into the a.
sanitary sewer
b.
waste fran areas in AFRRI in which high level radioactive activation or contamination may occur , c.
waste frun areas in AlHRI in which low level radioactive activation ' or cantamination may occur d.
waste frun normal reactor operations !
i ! . L b i d (***** CATFGORY B O2frDUED ON NEXT PAGE *****)
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NORMAI/ENERG 190CE[1RES & RAD OJN Ptufe 30 !
r
QUEErfICH B.07 (1.00)
M11 cts one of the following reactor operations has the highest Ar-41 . i production rate? . r a.
exposure roca #1 with the core at the extreme position closest to exposure #1 , i b.
exposure roca #2 with the core at the extrume position closest to ! exposure #2 } c.
pneumatic transfer system with the core at the position adjacent
to the pneumatic t,iham , d.
in-pool experi2nant irradiation
i !
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NORMAI/INURG PROCEDURES & RAD ON Page 31
- . , QUEETI'ICH .B.08 (1.00) -l Match the evolutions listed below with the color that should be used to- ' make the entry in the reactor operator's logbook. (responses nay be used more than onos)- , Evolutions: Colors: 1.
core movement A.
Black . 2.
maintenance items B.- Green 3.
. pulses.
C.
Red 4._ _ K-excess measurements "
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NORMAI/DGJC PROCEIURES & RAD CON Page 32 L ! QUESTIQi B.09-(1.00) Which one of the followirg evolutions is required to be performed daily? ' a.
shutdowm margin b.
visual inspection:of control rods functional check of the facility. interlock system c.
d.
functional performance of the transient rod system
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N@MAI/DEU PROCEDURES & RAD CON Page 33- , QUESTION-B.10 (1. 00) - Which cne of the following evolutions requires a'ocupleted Reactor Use Request? a.
maintenance in a&M #1 when the reactor is secured $ b, calibrating the m21tirange linear power channel performing an experiment that has previously been performed safely c.
d.
performing pulairg operations for reactor operator trainirg
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NWMAIADG5G PRD2 DURE & RAD CW-Page 34
. 'i QUESTION B.31 l (1.00).
Duiig the perfoottnance of the quality assurance check on the stack gas - .! monitor, the counts per minute reading falls outside the 5% deviation E lines for the detector and check source. Which one of the followirg - actions should you take? , a. repeat the-entire test i b. r=1= the particulate filter.
c. immediately report the deviation'to the Safety and Health Dept.
d. innadiately report the deviation to the Reactor Facility Director , . l l' , t ! , t .1 \\
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NCEMM/DG5G PROCEWRES & IUE) ON.
Page 35.
l l l . QUESTICH B.12 (1.00)- i , Which cria of the followire irriividuals has sole respcmsibility for I dowrgradirxJ an aancf during its course?. , a.
Emergency hrti Post (ECP) Oczanarglar b.
Daargency Action Station (1%S) Otannander c.
Amw 4al Advisor on hpcf Mticos (SADEC) ' d.
E==,.pcy coordinator , b i l i l - t ! l' l .
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B. ~ NOR9&DGEG PROCE:DURES & RAD 00N Page 36 . QUEErrICH B.13 (1.00) During a core unloading, a fuel element is dropped and it is visually _ l cbvious that the claddirg has ruptured. 'Ihis incident would Inost lik ly
e be classified as a(n) . a.
Notification of Unusual Event i b.
Alert c.
Site Area Daargency - d.
General Emargency . L .
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f ,- QUESTICH' B.14 (2.00).
Matd1 the items listed in Coltan A with their 'nchnical Specification 1 l limit fran Coltan B. (Coltawn B responses may be used more than once) l-l Column A: l' ? 1.- mavi= = K-avr== . l-2. - mininan shutdown margin - 3.- total experiment worth . . , ~ 4.
mavi== step insertion of reactivity in the pulse mode
Column B: A.
$0.50 B.
$1.00 > C.
$1.50 D.
$2.00 E. -$3.00 i - i F.
$4.00 - G.
$5.00
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NORMAI/DERG PROCEDURES & RAD ON Page 38 QUESTION B.15.
(1.00) The follcwing steps are.taken from the AFRRI operating procedure for reactor core _lnaM ng-Place a~ 1,2,3, or 4 next to each step to indicate the order in which they would be performed.
a.
calibrate'the Trans rod b. -load alaments until critical loading is adileved c.
load core to full operational. load d.
load core to $2.00 excess reactivity , . ' -3 h . -
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NOROJ/EMENG PROCE[URES & RAD OCN Page 39 . QUESTION B.16 (1.00) ! If the following alarms are reosived sinultaneously which one would you investigate first?- a.- Water t e s* m .b.
stack gas.
c.
water level .j d.
stack particulate ,! ! --l-l ! ! . i ,
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B.
N0ft9&EMERG McCEWRES & BAD CON Page 40 ! -- QUESTION' B.17-(1.00) Which one of the following tenns is defined as.the introduction of a signal into the channel to verify that-it is operable? a.
channel calibration- . b.
channel check c. - channel contimity check d.
channel test , -i . ! ! >
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6 me & RAD CM-Page 41 j 't QUESTION B.18 (1.00)
. ' Nhidl one of the following is the mav4== power level fmn which a pulse i can be initiated? -a.
500 W-b.
1 IW > c.
5')W d.
10 IW
. l.
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l-i l ' ! l.
.
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NORMAI/DERG PROCEIIRES & RAD CON ~ Page 42
i I QUESTION B.19 (1.00) Which one of the following is the reason that the corxtuctivity of the bulk l water is required by 'nminical Specifications to be maintained less than l or equal to S umho/cm ? l l~ a.
to ' enhance the effectiveness of the demineralizer at removirq ions b.
to more easily detect an abnormal increase in ion curmhation c, corrosion of metal ww-in.s is slower at lower oorductivity levels d.
a higher conductivity level would cha2ge the moderating effect of the water i L i l l
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16 MXEDURES & RAD CON Page_43-f
QUESTICH _B.20 (1.00) Nhich of the follwing alans does for require a reactor scram as a regia siie? a.
R1 and R2 alarm b.
pool Water level alarm , c.
stack particulate alarm d.
fire alarm . t i , l l l i t.
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N AND RAD N SYSTEMS Page 44 .d ? ) GJESTION C.01 (1.00) Ech one of the following is the primary cooling mechanism of-the AFRRI reactor core?.- r ~ a.
natural co mection b.
natural conduction , c.
forced circulation
d.
radiation C
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PIANr AND RAD ICNTIORDC SYSTDE Page 45 i
QUESTION - C.02 (1.00) , .) Fill in the blanks.
A tube leak in the primary to secondary heat exchanger with both systems , operating would cause pool level to because the primary systen ' operates at~a pressure than.the secondary systen.
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PIANP AND RAD PONFKRING SYSTDS Page 46 a / QUESTION C.03 (1.00) '. Ihe thamples in the irstrumented fuel rod measure tenperature at which one of the following locations? a.- surface of the fuel rod cladding b.
center of the zirconium rod-( c.
auter surfaos of the fuel d.. interior of the fuel- , I t (***** CATEGORY C CONTINUED ON TEXT PAGE *****)
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m AND RAD MEI'IORING SYSTEMS Page 47
> f QUESTION-C.04 (1.00) ! Which one of the following statements best describes the purpose of the-
diffuser system? ' a.
it enhances the natural. circulation flow in the pool - .
b.
it creates turbulence in the pool'to dissolve N-16 before it l rises to the pool surface
it prwides additional' decay time for N-16 before it rises to the c.
pool surface ' l d.
it deaerates the pool water to reduce the formation of Ar-41 ~ ' !- i-i
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., - .... i .. . l C PIANT AND__ RAD 70t TIORING SLcTDt3 Page 48 l.
i t , QUESTICH C.05 (1.00) . Fill'in the blanks.
'Ibe primary water makeup system supplies approximately gallons of water per week to makeup for evaporation. 'Ihis couairgr.Esiis to i :. 'approximately inches of pool-level.
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PIANP AND RAD N SYSTDE Page 49
r l GJESTICE C.06 (1.00) Fill in the colors of the lights that would be illuminated on' the ' core ! location board in the prep area if you were about to entar ewvwn rocan !
- 1.
'i ! Given: A - reprssuius ER #1 ' B-rea Ls lead shield doors C - represents ER #2 A: Bi~ C: _ i k s l r.
y I . - i
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PImrt AND RAD M2TTKRING SYSI1!MS Page 50' j ! ,. I
QUESTION C.07 (1.00) I Which one of the following caniitions must be' satisfied befom tho' avr-im room #. 2 plug door can be opened? a.
com is in POS I and lead shield doors are closed ' b, oore is in POS II and lead shield doors are closed oore is in POS III and land shield doors are open c.
d.
oore is in POS II_ and lead shield doors are open
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PLANP AND RAD IONTIORING SYSTEMS Page 51 ' i QUESTICH C.08 - (1. 00) Nhen a stardard control rod is being withdrawn fran the core the.
elevLwget is inagnetically coupled to which one of the follcwing u ip=uits? a.
the waim?dng rod b.
the piston ' c.
the artnature d.
the draw tuba - > i , l
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PIAMP AND RAD MJNrKRING SYSTDE Page 52 l
QUESTION.C.09 (1.00) M11d1 of tha' followirs rod switch ocambinations is abnormal? < '
a.
cant. - on; mag - on; up - off; down-off
b.
cont.'- on; mag - off; up - offs down - on c.
cont. - an; mag - on; up - on; down - off > d.
cont. - off; mag - off; pp - off; down - off , , .{ .. ! ! f f f , (***** CATEGORY C CONTINUED ON NEXT PAGE *****) , ! ,, ..
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PIANP AND RAD }ONT!tRING SYSTDtB Page 53 , QUESTION C.10 ' (1. 00) While operating at 50 IW the operator accidentally pushes the magnet "on" switch for the REG rod. Which one of the following is the wum-t . resperuse of the Inctor control system? - a.
all rods scram < b.
only the REG rod scrams c.
the REG rod drives inward d.
the "on" light mcznantarily goes 'out but the RBG rod does not m:ne - s
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QUESTICN C.11 (1.00)
adle operating in Mode IA, tL actual pcwr imit imd by the servo systen ' - to adjust power to the demanded level is provided by .
l a.!highfluxsafetychannelone i b.
the' wide range log power channel c.
the Imiltirange linear channel ' d. - the highest reading power channel . I
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PIANT AND RAD METIORING SYSTDE . lege 55 '
QUESTION C.12 (1.00) ' e The pressurized air supply systen provides ocmp1=w. air'at-approximately
20 psi-to the , a.
reactor tank lead shield door bearings b.
transient rod system c.
pneumatic transfer systen . ! d.
reactor rocan ventilation system isolation danpers
, . . < . (***** CNIE ORY C CONTINUED ON NEXT PAGE *****) . . b , + ' n
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m AND RAD NE SYSTDE Page 56
t , QUESTICH C.13 (1. 00)' l-Match the radiation monitors listed belcw with the type of detector used in each system. (detector types may be used nore than onoe) Badiation Monitors Detector Tvoe 1.
remote area nonitors A. thermoluminaar=nt dosimeter 2.
contirmous air nonitors B. scintillation detector 3.' stack particulate monitor C. G-M deteccor- . 4.
perimeter monitors D. prtportional counter ! !
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PLANT AND RAD IOrfKRING SYSTDS Page 57 i QUESTICH - C.14 (1.00) Nhich one of the following statenents describes what will occur if the primary CAM reaches its high level alarm setpoint? a, audio and visual alarms will be activated ' b.
audio and visual alarms will be activated and the reactor rocta ventilation danpers will close - c.
the reactor will" scram d.- the reactor will scram and the reactor rocxn ventilation danpers ' will close ! , ,
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PIAMP AND RAD MEITCRIM; SYFmtS Page 58 t QUESTICH - C.15 (1.00) j . On a loss of all AC powar to AFRRI,- the only radiation nonitoring systam(s) that will remain ~in operation is(are) the . a. - stack nonitoring system .; b.
continuous air monitors ' c.
criticality nonitors . , d.
per h' monitors and criticality monitor - l ~'i ,- ! ! , t ? < , l >
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PIAwr AND RAD MJNTKRDC SYSTDES Page 59 {
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! QUESTION C.16 (1.00) ! [ Airing pulsing cperations the alarm setpoint(s) on which of the following f radiation monitors will be reset to full scale?
t a. 'R-1 and R-2 b.
R-1 and R-5 c.
primary OM d.
R-5 and R-6 l (***** CATBXRY C 00NTINUID ON NEXT PAGE *****) n
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PIAlfr AND RAD ICNTITRING SYN Page 60 i ' t ! , GESTION C.17 (1.00) ! If reactor power ah its technical specification==v4== limit during a i l pulse, a scram signal will be generated by . . ! ' a.
high flux safety channel one l b.
high flux safetv channel two !
' c.
the wide range log power channel ' d.
the mitirange linear power channel ' i
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PIANP AND RAD N SYSTDtB Page 61
i QUESTIQ4 C.18 (1.00) f f When scram relays are & a=vir,ed by a high flux scram signal they runnin & r-rgized until they are reset by idtidt one of the following methods? , e a.
automatically when the scram condition clears b.
by pressirg the applicable Inset switch for high flux scram c.
by turning the key to the reset position , > d.
by pressing the manual scram bar , ,
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PLANr AND RAD KNIERDG SYSMS Pege 62 . I QUESTICri C.19 (1.00)
R11 cts one of the following canditions will cause a reactor scram?
a.
power level charging on a 2 secord pericd b.
bulk pool water tamparature is 65 degrees C t I lead shield doors in any position othar than fully open or fully [ c.
closed < d.
wide rarge log power channel in calibrata r . l , t
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PIANT AND RAD N SYFFDt3 Fege 63
) QUESTION C.20 (2.00) { l Match the conditions lista:1 belcw with the safety signal they provide.
! (responses may be used more than once) l Coniltion i
1.
loss of high voltage to the nultirarge linear channel detector 2.
high flux safety channel cr4 in calibrate
3.
wide rarge log power channel reading 1.2 W . 4.
fuel tenperature channel two reading 585 degrees C Safety Sianal > S - Scram R - Rod Withdrawal Prevent N - No signal provided , , b ) (***** DO OF CATEGORY C *****) ( * * * * * * * * * * DO OF EXAMDRTION * * * * * * * * * * ) i
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ra mK5tY, 'IHERMD & FAC OP ORRS Page 64 r . NiSWER A.01 - (1.00) , b.
REFERENCE -, AFRRI R1nd. of Nuc. Eng. (p.36) NISWER A.02 (1.00) , C.
ic2LKtJICE AIRRI hand. of Nuc. Dg. (p.55), Sanple Q/A H.5 - - ANSWER A.03 (1.00) . ' a, , icauc21CE , AFERI hand. of Nuc. Eng. (p.77)
ANSWER A.04 (1.00) a.
REFERENCE AFRRI SAR (p.4-14), Simplified Technical Description (p.8) , ANSWER A.05 (1.00) d.
j REFERD4CE > AFERI SAR (p.4-11) ' (***** CATEDORY A 02fFD10ED CN NEXT PAGE *****) ' . '$ .
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Rx nnxmy, uteeo & FAc oP QARS Page 65 , i ANSWER A.06 (1.00) b.
REFIRDK2 AFRRI Wrd. of Nx:. Eng. (p.65), Sanple Q/A A.1.d ANSWER A.07 (1.00) d.
RETERENCE ATRRI Sanple Q/A A.16 ANSWER A.08 (1. 00) d.
xtaueNCE AIRRI Sanple Q/A A.4 ANSWER A.09 (1.00) c.
REFERINCE AFRRI Sanple Q/A A. 6, SAR (p.4-34) ANSWER A.10 (1. 00) d.
PIFERENCE APRRI Operatirs Proc. VIII TAB D, Sanple O/A A.6 (***** CATE ORY A CONTINUED ON NEXT PAGE *****)
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RX 'IHB3E 'IHERO & FAC DP ORRS Page 66 -
! h
ANSWER A.11 (1.00) , d.
t N '!
- t AERRI Sanple Q/A A.D
ANSWER A.12 (1.00) i C.
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! AFRRI SAR (p.4-35), Reference Package ' , T ANSWER A.13 (1.00) b.
le2uez1CE ' i: AFRRI SAR (p.4-35), Refennoe Package ' s ANSWER A.14 (1.00) / A.. leaue24CC AIRRI Sanple Q/A J.8 i t ANSWER A.15 (1.00) b.
RLTERENCE AFRRI Ibrd of Nuc. Eng. (p.145-150), Sanple Q/A K.5 (***** CATEDORY A CDtfrINUED Otl NEXT PAGE *****) i I .
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RX 'nHIRY, 7 HERO & FAC OP ODJts Page 67 ) i l j ? ANSWER A.16 (1.00) I l . b.
- RE2TRENCE ' AFRRI Sanple Q/A C.15, Reference h ckage , , ANSWER A.17 (1.00) ' c.
, i REFERENCE ' AFRRI Ibrd. of Nuc. Eng. (p.144-150), Reference Package l . ANSWER A.18 (1.00) d.
REFERENCE ' AFRRI Sanple Q/A C.4 . ANSWER A.19 (1.00) b.
RDIRENCE . APRRI SAR (p. 4-35) , ANSWER A.20 (1.00) - c.
REFERENCE AFRRI rund. of Nuc. Erg. (p.19) (***** END OF CATD30RY A *****) . - .
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NOR9d/EMERG PROCEEURES & RAD CIN Page 68 t i i i f i ANSWER B.01 (1.00)
b.
, APRRI T.S. (p.30-31) i i
ANSWER B.02 (2.00) i
1.Dt2.Bt3.C;4.A i REFERD4CE , A1HRI Operatiry Proc. O, I ('IAB A,E) ard V
. ANSWER B.03 (1.00) a or C.
REFERDiCE 10 CFR 20.101
ANSWER B.04 (1.00) a.
RtauwM AFRRI Sanple Q/A G.17 ANSWER B.05 (1.00) c.
(***** CATD30RY B CONI'INUED CH IEXT PAGE *****)
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NCEDOJ/DERG PROCEDURES & PAD OCH Page 69 RErERENCE AFRRI Sanple Q/A G.1, 10 CFR 20.202 ANSWER B.06 (1.00) ' c.
t N AFRRI SAR (p.3-26) NEWER B.07 (1.00) b.
inne24CE AIRRI SAR (p.5-17) ANSWER B.08 (1.00) 1. C ; 2 B ; 3. A ; 4. C Ecuu213 AFRRI Operating Proc. VIII TAB A , ANSWER B 09 (1.00) . d.
xtauu242 AIRR1 Sanple O/A L.13, L.14 , (***** CATD3ORY B OWrDUED ON NEXT PAGE *****)
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NOR9d/DERG PROCEIURES tr RAD CON Page 70 - ANSWER B.10 (1.00) c.
l ' - AFRRI T.S. (p.34-35), Operating Proc. I, Sanple Q/A F.12 ' ! i ANSWER B.11 (1.00) [ a.
RDTRENCE i ATRRI Operating Proc. VIII TAB K , , ANSWER B.12 (1.00) a.
. REFERENCE AIRRI Emergency Plan (p.33) ANSWER B.13 (1.00) R,w b.
Rt.runNCE AFRRI Emergency Plan (p.42) > > , (***** CATDGORY B 02frDUED ON lEXT PAGE *****) > L !
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NCENAI/DG3C 1RXIIURES & RAD CON Page 71
! ! , l ANSWER B.14 (2.00) 1. G t 2. A i 3. E F 4. F ! M
> ATRRI T.S. (p.7,8,16) ! ANSWER B.15 (1. 00) ! 2,4,1,2 to 3),4,L ' REFERDiCE ' ATERI Operating Plu::. VII , ANSWER B.16 (1.00) , c.
, REFERENCE AIERI Sanple Q/A F.13, SAR (p.6-20) , ANSWER B.17 (1.00) d.
, le;tue24CE ' AFRRI T.S. (p.1) ANSWER B.18 (1.00) b.
! . (***** CATDGORY B 00NTINUED CN NEAT PAGE *****) - i + . .
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NOF99d/DtERG PROGRRES & RAD CON Pege 72 REFDENCE AFRRI Operatire Proc. VIII TAB G.1 . . ANWDL B.19 (1.00) - c.
REFERENCE i AIRRI T.S. (p.13) ANWER B.20 (1.00) c.
REFDUNCE AIBRI Sanple Q/A F.9, 10/27/89 Requalification Exam (p.11) , f . i l (***** DO OF CATD30RY B *****)
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PUuYP AND RAD ENTKRDC SYSTDs Page 73 ANSWER C.01 (1.00) a.
REFITENCE A1RRI SAR (p.3-15) ANSWER C.02 (1.00) increase, lower inutt243 AFRRI Saltple Q/A E.13 ANSWER C.03 (1.00) d.
RFIERDiCE AFERI SAR (p.4-14) ANSWER C.04 (1.00) c.
inue212 AFERI SAR (p.3-20) j i ANSWER C.05 (1.00)
- 10 '10,I~l.S X, b2" (67 gal./in.)
~stue24CE
! AFERI SAR (p.3-18) (***** CATD30RY C CNTINUED ON NEXT PAGE *****)
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PLANP AND RAD ENI'ICRDC SYErrDts Page 74 M4SWER C.06 (1.00) ' green, green, red
i n u <t24 % AFRRI Sanple Q/A D.15 ANSWER C.07 (1.00) a.
leuc 2iB AmRI SAR (p.4-28), Sanple Q/A I.8 ANSWER C.08 (1.00) c.
mn<t243 AERI SAR (p.4-17) ANSWER C.09 (1.00) d.
, ' mu(D13 AERI Sanple Q/A D.11, SAR (p.4-17,4-18) ANSWER C.10 (1.00) b.
REFERm3 . > A E RI Opelations manual (p.94) (* * * * * CATD30RY C C%2frDUED ON NEXT PAGE *****)
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PIANT AND RAD MEI'KRING SYgmts Page 75 ANSWER C.11 (1.00) c.
itt.t US21CE AIERI Operations manual (p.97) ANSWER C.12 (1.00) d.
inuc24CE AIRRI SAR (p.3-49) ANSWER C.13 (1.00) 1. B ; 2. C 3 3. C ; 4. A l ic2uc21CE AFRRI SAR (p.3-34-3-43) , { l l ANSWER C.14 (1.00) i l b.
Istue21CE AFRRI SAR (p.3-40) ANSWER C.15 (1.00) d.
xtaue21CE AFRRI SAR (p.3-43,3-45) (***** CATD30RY C CIN1'D1UED ON lEXT PAGE *****)
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PIANT AND RAD MJNIKRING SYSTDs Page 76 ANSWER C.16 (1.00) b.
REFERD4CE: AFRRI Operating Proc. VIII TAB G.1 ANSWER C.17 (1.00) b.
le.r m u1CE AFRRI SAR (p. 4-31) ANSWER C.18 (1.00) b.
xtaueNCE AFRRI Operations manual (p.96) ANSWER C.19 (1.00) c.
REEIRD4CE AFERI SAR (p.4-27, 4-30) ANSWER C.20 (2. 00) R,S,N,S REFERD4CE AIRRI SAR (p.4-26, 4-30-4-31) (***** DO OF CATD3ORY C *****) ( * * * * * * * * * * DO OF EXAMD& TION * * * * * * * * * * ) l
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, i V i TEST QCSS REFERINCE Page 1 l QUESTIQi VAllE REFERENCE f ! , A.01 1.00 9000905 f A.02 1.00 9000906 l A.03 1.00 9000907 ! A.04 1.00 9000908 l A.05 1.00 9000909
A.06 1.00 9000910 ! A.07 1.00 9000911 l A.08 1.00 9000912 ' A.09 1.00 9000913 ! A.10 1.00 9000914 l A.11 1.00 9000915 A.12 1.00 9000916.
t A.13 1.00 9000917 l A.14 1.00 9000918 A.15 1.00 9000919 [ A.16 1.00 9000920 j A.17 1.00 9000921
, A.18 1.00 9000922 A.19 1.00 9000923 A.20 1.00 9000924 ' 20.00
& B.01 1.00 900D925
B.02 2.00 9000926 t B.03 1.00 9000927
B.04 1.00 9000928 B.05 1.00 9000929 3.06 1.00 9000930 B.07 1.00 9000931 ' B.08 1.00 9000932 B.09 1.00 9000933 , B.10 1.00 9000934 B.11 1.00 9000935 B.12 1.00 9000936 ' B.13 1.00 9000937 B.14 2.00 9000938 ' B.15 1.00 9000939 B.16 1.00-9000940 B.17 1.00 9000941 ~i - B.18 1.00 9000942 t B.19 1.00 9000943 , B.20 1.00 9000944 22.00- 'i - .
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'IE!TT OCSS RE2ERENCE Inge 2 QUESTICH VALUE RE7ERENCE C.01 1.00 9000945 C.02 1.00 9000946 C.03 1.00 9000947 C.04 1.00 9000948 C.05 1.00 9000949 C.06 1.00 9000950 C.07 1.00 9000951 C.08 1.00 9000952 C.09 1.00 9000953 C.10 1.00 9000954 C.11 1.00 9000955 C.12 1.00 9000956 C.13 1.00 9000957 C.14 1.00 9000958 C.15 1.00 9000959 C.16 1.00 9000960 C.17 1.00 9000961 C.18 1.00 9000962 C.19 1.00 9000963 C.20 2.00 9000964 21.00 63.00 ! . }}