_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ | U. S. NUCLEAR REGULATORY COMMISSION REGION V Examination' Report No. 50-89/0L-87-02 Facility: GA Technologies, Inc. - Mark I and Mark F TRIGAs Docket Nos: 50-89 and 50-163- | Examinations administered at the GA Technologies TRIGA Test Reactor Facilities, La Jolla, California O//3/87 Chief Examiner: PhilipyMo ill, Operator Licensing Examiner Uate Signed . __ h 3/V7 Approved: ohn 0. Elin, Chief, Operations Secion pte Vigned Summary: Examinations on August 4 and 5, 1987. Written and oral examinations were administered to three SR0 candidates. All candidates passed the oral examinations and two candidates passed the SR0 written examinations. Two SR0 licenses were issued. R DO K 9
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Examination' Report No. 50-89/0L-87-02
Facility: GA Technologies, Inc. - Mark I and Mark F TRIGAs
Docket Nos: 50-89 and 50-163- |
Examinations administered at the GA Technologies TRIGA Test ReactorFacilities, La Jolla, California
O//3/87Chief Examiner:PhilipyMo ill, Operator Licensing Examiner Uate Signed
.__ h 3/V7Approved:
ohn 0. Elin, Chief, Operations Secion pte Vigned
Summary:
Examinations on August 4 and 5, 1987.
Written and oral examinations were administered to three SR0 candidates. Allcandidates passed the oral examinations and two candidates passed the SR0written examinations. Two SR0 licenses were issued.
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REPORT DETAILS
1. Examiners:
*P. Morrill, NRCJ.Elin,NRC(Auditor)
* Chief Examiner
2. Persons attending the exit meeting:
P. Morrill, NRCW. Whittemore, GA TechnologiesJ. Razvi, GA Technologies
3. Written Examinations and Facility Review
Written examinations were administered as follows:
3 SR0 Exams - August 4, 1987. All sections.
At the conclusion of the examination, the facility staff reviewed theexamination. Based on this review, the facility staff had comments onthe examination which were discussed with the Chief Examiner. Based onthese discussions, appropriate revisions were made to the masterexamination key by the Chief Examination prior to grading the candidateresponses. The examiner's resolution of the licensee's comments aredocumented in Attachment 1.
During the grading of the written examinations the examiner observedthat all the candidates appeared to have some difficulty answeringquestions on infrequent operations, such as emergency shutdown, craneoperations, and response to fire.
4. Operating Examinations:
Oral examinations and facility walkthroughs we're administered to threeSR0 candidates on August 5, 1987.
5. Exit Meeting:
On August 6, 1987, the Chief Examiner met with the licenseerepresentatives listed in paragraph 2, above. The Chief Examinerobserved that some of the candidates had difficulty explaining how theautomatic make-up water supply for tne Mark F cooling tower operated.The Chief Examiner also discussed the grading process for the writtenexamination and the schedule.
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ATTACHMENT 1;
EXAMINATION REPORT - FACILITY COMMENTS'
GA TECHNOLOGIES SR0 EXAMINATION. AUGUST 4-5, 1987
' Question: N/A
Facility Comment:
The equation sheet did not appear to be used for any of theexamination questions.
Resolution:
The examiner will consider updating the standard examinationsheet prior to the next examination.
Question: H-1
Facility Comment:
On Figure H-1 the " Reactor Power" scale should be moreproperly labled " Reactor Log Power".
Resolution:
The connient is correct, however no change to the key appearsappropriate.
Question: H-3
Facility Comment:
In the question " delta K" should have been "K effective".
Resolution:
None of the candidates questioned this item. However, theexaminer agrees. The correct answer then becomes 0.8 - 0.9,which is -0.10, answer "C". Since there is no single correctanswer the question will be deleted.
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' ATTACHMENT IL- C NTINUED-
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Question: H-6
Facility Coment:
.In parti (d).the, candidates ma'y also state-that:the xenon- peaking ;is.due to the fact' that the half. life of I-131 isless than the half: life of Xe-131. This is'an equally valid
L " answer.
: Resolution:
The examiner-. agrees this'is'also'a correct answer and willadd this response to the key..
Question: H-13-u
Facility Coment:i In part (a)'the answer. given is for low enriched fuel with
stainless' steel cladding. The correct answer should be that:"The cell effect is much more significant to the NTC in FLIP
' fuel-due-to the short neutron range or due to'the largeabsorber.(erbium and U-235) cross section in the fuel."Reference is on page 23 of Chapter VI.
Resolution:
. The examiner . agrees. The key will be appropriately modifiedand the reference added.-
Question: H-16
Facility Coment:
Fuel can pressure is not very important, since it never getsabove several PSI during pulses and the bur:;t pressure ismuch' higher.
Resolution:
No change to the. key was requested, nor does one appear-
In the question the word " radiation" should be " sourceradiation". This is due to the fact that some beam ports useboron as part of the shielding material and boron willinteract with neutrons to form alpha particles.
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Resolution:
No change to the key was requested, nor does one appearappropriate. The examiner will consider rephrasing thequestion in the future.
Question: 1-11
Facility Coment:
Theanswertopart(c)couldalsobe"toallowthedetectorto operate". Without the holes in the attenuator, no neutronwould get through and the detector would not work.
Resolution:
After rereading the reference material the examiner agrees.The answer will be changed to read " Holes in the attenuatorallow some of the thermal neutrons (from the outermoderator) to pass into the inner moderator (and mix withneutrons thermalized in the inner moderator to provide aneutron field proportional to the dose rate in tissue)."
Question: J-4
Facility Comment:
The facility personnel consider "a. incore, hollow eleuent"and "d. dry irradiation facility" to be the same irradiationdevice (ie, a dry tube). Thus, the correct answer to J-4(a)is either "a" or "d", and there is no correct answer to J-4(b).
Resolution:
The examiner agrees that the four options presented couldhave been worded better. However, none of the candidatesquestioned the examiner regarding this point. "a" or "d"will be accepted for part (a) and part (b) will be deleted.
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LATTACHMENT 1 - CONTINUED'
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. Question: J-6,
Facility. Comment:
b The question should state.which reactor, since the void tank-*
would be the preferred test facility for fast neutrons in the-
Mark F..
Resolution:-,
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! None of the candidates had any questions regarding this Litem.'
; The question was not. reactor specific -therefor the best.,
choice'is still'"d". No change will.be'made.to the key.'
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Fa'cility Comment:~
The correct answer is "c". Typographical error. !
Resolution:
LThe examinerf agrees and ~will change the key., ,
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Question:'J-11
FacilityLComment:
'A more appropriate alternative would have been "e. Analternative source of secondary water can be suppliedthrbugh the cooler access plate."
Resolution::
The facility comment may be used for future questions,_however, the comment does not change the key.
:The question does not state whetber steady state or pulsemode is being considered. More importantly, the referencematerial is out of date. Consequently, the correct SCRAMsetpoint for the Mark F K-1 linear power channel is 1650 Kwor 110% and the Mark F T-2 fuel temperature SCRAM is set at650.C. The reference material will be corrected.
Resolution:
The ' examiner confirmed that the setpoints for SCRAMS were asstated. The examiner also confirmed that these settings were
. consistent with the Technical Specifications. The key willbe changed as requested.
Question:'K-1
Facility Comment:
The words " basic limit" in the question should be " basicsafety limit", which for TRIGA fuel is 1150 C. The ultimatelimit is 1350 C, at which point the zirconium hydride woulddecompose violently. As a practical matter the facilitylimit for fuel temperature is 800 C. The limits for fueltemperature for the Mark F in the Technical Specificationsare for transient operation.
Resolution:
The facility personnels' comments have merit, however, thereference material clearly indicates an operational limitfor steady state operation in the 650 to 700 C range. Nochange will be made to the key. '
Pulses are started from low power. Thus, the initial'statement is confusing. All of the choices are reasons why
. pulses are startedffrom low power._
Resolution: i
The examiner agrees that the initial statement could bestated more clearly. However, none of the candidatesquestioned the examiner regarding this item. It is clearfrom the reference material that three of the four itemslisted are concerns if pulsing were started from high power, <
-consequently the key will not be changed. >
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Question: K-13
Facility. Comment:
In K-13(a) the lead-in statement should state "very lowpower" in place of " low power" since the linear increase dueto source neutrons will not be seen in the mill-watt range,which we consider " low power". Also, in the choices to K-13(b) the word " logarithmic" should be "expoential".
Resolution:
The facility comments would improve the questions' clarity.None of the candidates asked for any clarification of these |two points. No change appears appropriate for the key. j
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Question: L-9
Facility Comment:
The annual and semi-annual calibrations conducted by theHealth Physics personnel are recorded in the H.P. Service iRecords, however daily and weekly calibration checks are '
conducted by the operators on watch and recorded in theOperations Log. "C" is the correct answer. The reference ;
material does not discuss these daily and weekly checks.]i
Resolution:
The examiner verified the facility personnels' statements.The key will be changed to indicate "C" is the correct I
There is no maximum reactivity limit for experiments in theMark F anymore. Amendment 33 .to the Technical Specificationssets limits of $3.00 per experiment, but no overa;l limit.This amendment was accidentally omitted from the copy of theTechnical Specifications sent to the examiner. In any case,the answer in the key is still correct since both the Mark Iand the Mark F were included in the question.
U.S. NUCLEAR REGULATORY COMMISSIONSENIOR REACTOR OPERATOR LICENSE EXAMINATION
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..Facility: cA TechnologiesReactor Type: TRIGA MK1 and MKFDate Administered: Aucust 4. 1987Examiner: p- 3. Mntr mCandidate:
INSTRUCTIONS TO CANDIDATE
Use separate paper for the answers. Write answers on one side only. Staple-[. ques. tion sheet on top of the answer sheets. Points for each question areindicated in parentheses after the question. The passing grade requires -atleast 70% in each category. Examination papers will be picked up six (6) hours-after the examination starts.
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Category % of . Applicant's % of Categoryif: Value Total Score Cat. Value
H. Reactor Theory
;j I. Radioactive MaterialsHandling Disposal andHazards
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_ J. Specific Ope' rating - jCharacteristics
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K. Fuel Handling and,
Core Parameters '
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L. Administrative Procedures,Conditions and Limitations
Totals
Final Grade %
All work done on this exam is my own. I have neither given nor recieved aid.
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Candidate's Signature
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REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS[ |
' 1. A single room shall be provided for completing the written examination.,
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The location of this room and supporting restroom facilities shall be silchas to prevent contact with all other facility and/or contractor personnelduring the duration of the written examination. If necessary, the facilityshould make arrangements for the use of a suitable room at a local school,motel, or other building.the licensee. Obtaining this room is the responsibility of
2. Minimum spacing is required to ensure examination integrity as determinedby the chG # examiner.with a 3-ft space between tables. Minimum spacing should be one candidate per table,No wall charts, models, and/or othertraining materials shall be present in the examination room._,
3. Suitable arrangements shall be made by the facility if the candidates areto have lunch, coffee, or other refreshments. These arrangements challcomply with Item 1 above. These arrangements shall be reviewed by theexaminer and/or proctor.
4. The facility staff shall be provided a copy of the written examination andanswer key after the last candidate has completed and handed in his writtenexamination. The facility staff shall then have five working days to pro-vide formal written comments with supporting documentation on the examina-tion and answer key to the chief examiner or to the regional office sectionchief.
5. The facility licensee shall provide pads of 8-1/2 by 11 in lined paper inunopened packages for each candidate's use in completing the examination.The examiner shall distribute these pads to the candidates. All referencematerial needed to complete the examination shall be furnished by theexaminer. Candidates can bring pens, pencils, calculators, or slide rillesinto the examination coord,shall be allowed. and no other equipment or reference material
6. Only black ink or dark pencils should be used for writing answers toquestions.
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
During the administration of this examination the following rules apply:~-
1. Cheating on the examination means an automatic denial of your applicatioitand could result in more severe penalties.
2. Restroom trips are to be limited and only one candidate at a time mayleave. You must avoid all contacts with anyone outside the examinationroom to avoid even the appearance or possibility of cheating. i
3. Use black ink or dark pencil only to facilitate legible reproductions.4. Print your name in the blank provided on the cover sheet of the examinatica.
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S. Fill in the date on the cover sheet of the examination (if necessary). !6. Use only the. paper provided for answers.
7. Print your name in the upper right-hand corner of the first page of eachsection of the enswer sheet.
8. Consecutively number each answer sheet, write "End of Category " asappropriate, start each category on a new page, write o g one side ofthe paper, and write "Last Page" on the last answer sheet.
9. Number each answer as to category and number, for example,1.4, 6.3.
10. Skip at least three lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets facedown on your desk or table.
12. Use abbreviations only if they are commonly used in facility literature.
13. The point value for each question is indicated in parentheses after thequestion and can be used as a guide for the deptn of answer required;-
14. Show all calculations, methods, or assumptions used to obtain an answerto mathematical problems whether indicated in the cuestion or not.
15. Partial credit may be given. Therefore, ANSWER ALL PARIS OF THE QUESTICNAND DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions ofthe examiner only.
| 17. You must sign the statement on the cover sheet that indicates that thework is your own and you have not received or been given assistance incompleting the examination. This must be done after the examination hasbeen completed.
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|18. When you complete your examination, you shall: '
a. Assemble your examination as follows':!
(1) Exam questions on top. ,'*.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
b. Turn in your copy of the' examination and all pages used to answerthe examination questions.
Turn in all scrap paper and the balance of the paper that you didc.not use for answering the questions.
d. Leave the examination area, as defined by the examiner. If after'leaving, you are found in this area while the examination is stillin progress, your license may be denied or revoked.
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EQUATION SHEET
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l| f = ma v = s/t
2 Cycle efficiency = N W k t)' v = mg s=vt+ at
E=mC a = (vf - v )/t ~*KE = hmv v A = AN A=Ae ,"f = v, + a g
PE = mgh e = e/t A = in 2/tg = 0.693/tgW = vaP
aE = 931am *h(* ) " (t )(t )i s
(t +t)bQ = mC ar 1 ,f ,-Ixp
9Q = UAAT -px7,7
f [nPwr = V I=I 10 *! M~
SUR(t)'P=P 10 TVL = 1.3/p,
e /T HVL = 0.693/ptP=P
SUR = 26.06/T
T = 1.44 DT SCR = S/(1 - K gg)/Aeff )p
WR = 26 CR = S/(1 - Keffx)g
CR (1 - Keff)1 = CR (1 ~~Keff)2T = '(1*/p )+ {(6 a )/x fg ] 1 2f p p
3 10Density = 62.4 *,5m/ft 1 Curie = 3.7 x 10 dpsDensity = 1 gm/cm I kg = 2.21 lbm
3Heat of vaporization = 970 Etu/lbm I hp = 2.54 x 10 BTU /hr6IIcat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 10 Btu /hr
1 Atm = 14.7 psi = 29.9 in. Ig. . Ctu = 778 ft-lbf1 ft. H O = 0.4333 lbf/in 1 inch = 2.54 cm
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F = 9/5 C + 32
"C = 5/9 ( F - 32)_ _ _ _ - _ .
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! CATEGGRY HREACTOR THEORY
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H-1 (2.0)
Refer to Figure H-1 which shows an instantaneous negstive. reactivity insertion into an already critical reactor core -at' tame 'T = 0. After a stable period is reached an instantaneousremoval of this negative reactivity occurs at time T = 1.-Respondto the following ~ questions, assuming source neutrons are notsignificant.
(a) Sketch the reactor power level as a function of (1.0)time on Figure H-1 for these reactivity changes.
(b) Sketch'the resulting reactor period as a function (1.0)of time on Figure H-1 for these reactivitychanges.
The reactorcis shutdown with a count rate of 10 CPS cn the count-rate channel. K(eff) has been determined to be 0.95. What K(eff)is' necessary to increase the count rate to 80 CPS with the ,*samesource neutrons ?
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a. 0.990
b. 0.994
c. 0.988
d. 0.983
H-? answer-
.b. E.CR 1 ( 1 - Neff1) = GR2(1 - 1.eff2) (1.0) i
10(1 - O.95) 80(1 - Kef f .?. )=
.Kuif2 .0,99373
Ref farence: Chiepter VI, page 16
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MULTIPLE CHOICE.-. SELECT THE'BEST ANSWER. I'
I t' delta K changes f rom 0.0 to 0.9 the reactivity changes by: ?. c-
Source neutrons 'for the Mark F reactor come f. rom. an inste.11edsource which uses.: t~
a.. Americium - cesium
.. b . . Plutonium - antimony
c. Plutonium - polimium|
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..d. Americium - beryllium!
H-4 ~ Answern
d. (0.5) ki
Reference: Chanter I,. pace 14 and Chapter VI, page 16
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H-5 (0. 5 ):
I MULTIPLE'CHDICE - SELECT THE EEST ANSWERt-| ,. i
i An' installed neutron source is needed to conduct .a reactor*
.startup'in order"to:'
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. a'. provide overlap between' neutron detector channels
b. allow calibration of compensated ion chambers at low powern.
c.- permit contrc11ed startups using; accurate indicatien
d. ' reduce uncertainty in the period meter after a long shutdown
H- S Answer :-
c. ' ( 0. '3 )
Referencer-gbapter VI, page 16
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'H-6 '(2.O),
.The Mark will be operating at full power for sevetal: days.
(A) How long will''it take xenon to reach equilibrum'P . (0. 5)
(b)- What'condit-ions cause equilibrum xenon? ,,"( O . 5 )(in terms of xenon sources and losses)
_. c ). How long will it tak'e f or xenon to peak f ollowing(
a shutdown? (maximum negative reactivity) (G.5, 1
(d) What causes xenon to peak following a shutdown?. (0. 5) .3, .
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H-6 ~ AnuwersI
-(a) 50-70 hourn (0.5) ;
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(b) Xenon is decayina cin c being burned out at the name i
rate it in being produced. (0.5) |
(c) 5 to 7'hourri (0,5)
(d) Xenon i < ., c t i l l b ai n ti produced from decaying J a d i n a ( 131 )
while it is no l on g e r" being removed by bu: nou* , or thehal#-1if e at 1-131 in 2. e n s ::han the half-1if e of X e - 1 3 1 .,
(0.5)
Ref erenca: Chapter VI, pegac 5-27
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L H-7 (0.5)
MULTIPLE CHOICE - SELECT THE BEST ANSWER
The negative. reactivity due to the fission product' poisonsamarium:
a. has an equilibrum value independent of power -level "~anddecreases slowly after shutdown.
'b.- has an equilibrum value independent of power 'l eve l and'increases slowly after shutdown,
c. has an equilibrum value which increases with power level anddecrease slowly after shutdown.
d.- has an equilibrum value which increases with power level andincreases slowly after shutdown,
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M ~'/ in u wser N
b. (0. 5)
Re f ern nr:et Chapter VI, page '? 7
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H-9 (0.5)
MULTIPLE CHOICE - SELECT THE BEST ANSWER
Refer to-Figure H-2 which graphs heat flux as a. f unction of deltaT between the fuel cladding and the coolant temperature. The , typeof heat transfer at point "X" on Figure H-2 is best described by:
a. Convection
6. Film boiling
c. Nucleate boiling
d, Conduction:
H-B Answer
c. (0,5)
Referente: . Chapter V: pagoa .d7-52si
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MULTIPLE CHOICE - SELECT THE BEST ANSWER
Refer to' Figure H-2 which graphs heat. flux as a function of delt&T between the fuel cladding and the coolant temperature,- areactor has been started.up frem zero power and is new producing
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50,000 Btu /Hr-SqFt. If the heat flux could be increased to100,000 - Btu /Hr-SqFt, the delta:T would change from:
a. 20tto 30 F
b. 20 to 120 F
c. 150 TD1 1000 f!
d. 700 TO 1000 F
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M-9 fan 5WLtr
a. (i.0)
Reference: Citapter- VI , p ages 27--32!
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N-10 0,0)
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During high power operation or large positive reacti vi tyi nr.erti ons , what are the two principle' characteristics of TRIGAreactors which prevent departure from nucleate boiling andsubsequent burn-out of the fuel? ,
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-H-10 Answer
The l ar ge negative temp!rature coefficient (0.5) and the l ar g:3nieg at i ve void coefficient (0,5) will decrease power beform DNBand burnout cccur.
Reference: Chapter VI, page 32
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H-11 (1.0)
MU'LTIPLE' CHOICE - SELECT THE BEST ANSWER |q
The symbol b (beta) and b(eff)- (beta effective) both denote the-total fracton of delayed neutrons. The difference between thesetwo is: [ j
a. b(eff) is smaller than b since delayed neutrons are bornwith lower energy levels than prompt neutrons.
b. b(eff) is larger than b since delayed neutrons are born withlower energy levels than prompt neutrons.
c. b(eff) is smaller than b since delayed neutrons are bornwith higher energy levels than prcmpt neutrons.
d. b(eff) is larger than b since delayed neutrons are born withhigher energy levels than prompt neutrons.
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H-11 Answer l
b. C(eff) denotes the # f*vct:ve del ayed neutron (1.0)fracton and in lara'tr tnan o aince the ageragedelayed neutron enerny in.1ower t h s.n the promptneutrono.3
'What is the difference'between. fast neutrons and prompt neutrons?-i
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H-12:Annwer -1.-
Fast neutrons- are- neutrcna with a h?gh cenergy 2evyt t n d, -thuc. travel a.t high velocity (0.5) while pec>act.neutrens are etnittedimmediatly at er during the fiosion precesc (O 5), j,
The TRIGA reactors. have-_been designed. with :a large prompt ]negative fuel temperature coefficient (NTC). "
(a) Why'is the " cell effect" contribution to the NTC.much more significant for " FLIP" fuel? [(1.0)(Dyson effect) ~ |.
.I:(b) Why'does the " FLIP" fuel NTC increase i apidly as a j
function of fuel temperature? (1.0) i
(c) .What are'two' advantages of the NTC increasingrapidly with fuel temperature? (1.0)
H-13 Annwers.. |
(a) .The cell effect i s much more tu.ani f i cant to 'li
the NTC in FLIP fuel due to the short neutron '
]irange in the fuel, or due tc the .i arne abso:-bercrasaw ection in the tuel (due to erbium poison i
and Et t r a U-2??.i) , (The j n r.r p4ftrM! p<9 r p si t i c ;;;ipturein the stainless steal _tadding far neutronsthermalined in the coolant :t n the ajo- contriDutert o 3. $ +, Cldd'lGW Gnr i chPi fuCl.' ( 1. O)
(b) An increasing n urrt er at thernal ~urrann nr epushed into the erbien rcucnance p: A N) as.thef uOl' tc'fi.per at ur"O r i n:Pt. (1,0)
(C) A IT,i '. imum react 1VItV | d 5 'O i% JIC u r r G C inFUiching normal op er ai.i n g o"'p e r ett ur r e , but i.n y
Gizeable increana.in care temper =:ture wili i n c e _. e ethU NTC to act as ' chutdown cv nan i ";n. (1.0)
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"ULTI' P'' E''EC'' H' OI' C' E' "* - : S'' E' LE' 'CT' ? THE i BEST ANSWER.
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While the TRIGA reacters are operating the fuel is hatter thanA the surrounding coolant.
(a) During steady state full power operation, where *
is the hottest location in a given fuel element? (0.5),
(b) Immediatly after a pulse (before heat transferbecomes significant) where is the hattest location'in a given fuel element? (O.5)
e
(c) Immediatly after a pulse (before heat transferbecomes significant) where is the greatest delta T?(across fuel, across fuel / clad gap, across clacding,or between cladding and the bulk ccclant) (0.5)
4
H-19 Answers
(a) Al on ti the ce.nterrlane of tho fut' element sO.5)
e, ta ) At the edge of the fi'ol aide tht' c l a dtii n c: N.5)
(c) Gcrnas the fuel /c3md nap '..S'<.
Reference: Chapter VI, pages IO - 51 103 H
1
.
END OF EECTION HSO ON TO SECTION I.
3
- _ _ _ - . _ _ _ _ _ _ . _ _ _ _
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:b-
CATAGORY IRADIOACTIVE MATERIALS
HANDLING, DISPOSAL, AND HAZARDS
I-1' (1.0).,
'
MULTIPLE CHOICE - SELECT _THE BEST. ANSWER
How long can you remain in an area with a gamma dose-rate of 2.5R/hr without. exceeding the 10 CFR 20 quarterly whole body limit?'
a. 15 min
b. 30 min-
c. 45 min
d. 60 min
1-1- Answer
b ,, (QUARTERLY LlillT r 1.25 H
Time w C'(1.,25 H) / (2,5 R/nr) J C 60 min / hr 1*
A point source of GAMMA radiation measures 32 R/hr at a distanceof.2 feet.
9
^
Which of the f ollowing is the best estimate of the radiation doserate from the GAMMA source at a distance of 16 feet ?
a. 500 R /hr
b. 2 R/hr
c. 500 mR/hr
d. 1000 mR/hr
I-2 Answer
C. ( DOEE RATE iriversely proparta anal to distance nquared )
500 Mr n-IR )( 32 r/HR) (2/16)E2 3 2 +i- 1/ M =>=
Reference: RTD Time, Di atance , Shelding c a1 cul ati on .
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I-3 (2.0)
ANSWER THE FOLLOWING MULTIPLE CHOICE OUESTIONS :J
A survey of radiation and contamination levels has been made by ]Radiation Protection personnel. The map (Figure I-1) on the i
'
following page has the results of this survey. Portions of 10 CFR20 Appendix B, Concentrations in Air and Water Above NaturalBackground (Figure I-2), are also provided. j
!
-Based only on thia survey and the requirements of 10 CFR 20answer the following MULTIPLE CHOICE questions.
I-3(a) What posting is required in the LABORATORY ? (0,5)
(a) CAUTION AIRBORNE RADIOACTIVITY AREA.(b) CAUTION HIGH RADIATION AREA(c) CAUTION RADIATION AREA(d) NO RADIATION POSTING REQUIRED
I-3(b) What posting is required in the MARK F (0.5)REACTOR ROOM ?
(a) CAUTION AIRBORNE RADIOACTIVITY AREA(b) CAUTION HIGH RADIATION AREA(c) CAUTION RADIATION AREA(d) NO RADIATION POSTING REQUIRED
I-3(c) What posting is required in the EHOP ? (0,5)-
(a) CAUTION AIRBORNE RADIOACTIVITY AREA(b) CAUTION HIGH RADIATION AREA(c) CAUTION RADIATION AREA(d) NO RADIATION POSTING REQUIRED
I-3 (d ) What posting is required in the STORADE ( 0. 5.)BUILDING ?
(a) CAUTION AIRBORNE RADIOACTIVITY AREA(b) CAUTION HIGH RADIATION AREA(c) CAUTION RADIATICN AREA(d) NO RADIATION POETING REQUIRED
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APPENDfX B-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-COnlinWed1' ,
(See footnotes at and of Appends 81 e
,
dancope ' 7able i Tabie 11
Elememt (atomic number)Col.1- A, M 2- M 2- -ca,, ,,,4j,
(pCumn y*', (po/mq g''4'. lusene (53) i 125 S 5 x10'' 4 x10-' 8 x 10-H 2x 10-'i 2 x 10-8 8 x10-8 8 x 10-' 2x10-8l 126 S 8 x10-' Sx10** 9 x 10* H 3 x 10-'l 3x 10-* 3 x10-8 1 x 10-8 9 x 10-8,4 i129 6 2 x10*' 1 x 10* * 2 x 10-u 8x10-8
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l 7x 10-8 8 x10-8 2 x 10-' 2 x10-8l131 S 9 x 10-' 8 x 10-* 1 x 10-" 3x10*'I 3 x 10** 2 x10-8 1 x 10-' 8 x 10-'1132 8 2x t0-' 2x10*8 3 x 10-' 8 x10-*I 9 x 10-' 6 x 10* * 3 x 10-' ' 2x10-84133 8 3 x t0-' 2 r 10-* 4 x 10* " 1 x 10-e1 2 x 10'' 1 x10-e 7x 10-8 4 x10-ei 134 S 6 x 10-' 4 x 10-8 8 x 10-* 2 x 10**I 3 x 10-* 2x10-8 1 x 10'' 8 x 10-*i135 .8 1 x 10-' 7 x 10-* 1 x 10-' 4xto-e1 4 x 10-' e'x 10* * 1 x 10-8 7 x10-s...,s u..m... * indium 97) ir 100 8. 1 x10-8 8 x10-e 4 x 10-' 2 x 10-'i 4 x 10-' S W 10-s g x io-e 2 x t0-*k192 8 1 x 10-' 1 x 10-' 4 x 10** 4 x10-84 3 x 10-8 1 x 10-* D x 10-" 4 x 10"*1r 194 S 2 x 10*' 1x10 8 8 x10-8 3 x 10-'1 2 x 10* ' 0 x 10-8 5 x 10-' 3x10-8Iron F6) - Fe 65 5 0 x 10'' 2 x 10* ' 3 x10-8 8 x 10**l 1 x 10'' 7x 10-' 3x10-' 2x t0-8Fe 69
. 8 1 x t0*' 2 x 10* * 5 x 10-' 8 x 10-*I 8 x 10'' 2 x 10* * 2 x 10-' 6 x10-8Krypton (38) Kr r,5m Sub 8 x 10-* 1 x 10-'Kr85 Sub 1 x 10** 3 x 10-'-.Kt 87 Sub 1 x 10-* 2 x 10-8.-
Kr 88. Sub 1 x 10-8 2 x t0**Lanthanum (57).- La 140.
i 1 x10-8 7 x 10-e 4 xio-o 2x10-sS 2 x 10-' 7 x 10-8 5 x 10-* 2 x 10-'
Leed (82)- Pb 203 S 3 x 10-* 1 x 10-8 0 x10-8 4 x 10-*i ' 2 x 10-* 1x10** 8 x 10-e 4 xio-ePb 210 - S 1x10'" 4 x 10-8 4 x 10-" 1 x 10-'i 2x 10-" 5 x 10-8 8 x 10-** 2 x 10* *Pb 212 6 2 x 10** 8 x 10-8 8 x 10* " 2x 10* *I 2 x 10** 6 x 10-8 7 x 10- 8' 2 x10-8Luleeum p1) - LutT7 S 6 x 10* * 3 x 10-' 2 x 10-' 1 x 10-*i 6 x 10-' 3 x t0** 2x 10-e 1 x t0**Man 0anese (25) Mn62 S 2 x 10-' 1 x 10-' 7 x 10-' 3 x 10-*
-
i 1 x 10-' 8 x 10** 5 x 10-' 3 x 10-'i
}Mn$4 8 4 x 10-' 4 x 10-8 1 x 10-' 1 x 10-* iI 4 x 10-* 3 x 10-8 1 x 10-' 1 x 10-*Mn 66.,,. S 8 x 10-' 4 x 10-e 3 x 10-e 1 x 10**I 6 x 10-' 3 x 10-8 2 x 10** 1 x 10-*Mercury (80) , Hg 197m
.
I 8 x 10-' 6x10 8 3 x 10-' 2x10"
S 7 x 10*' 8 x10* e 3 x 10** 2 x 10-*
Hg 197 S l x 10-8 9 x 10** 4 x 10-' 3 x 10**I 3 x 10* * 1 x 10-8 9 x 10-* 8 x 10-*Hg 203 8 7 x 10-' 6 x 10-* 2 x 10'' 2 x 10-8I l x 10-' 3 x 10* * 4 x 10-* 1 x t0-*Mo8ytxsonum (42).. Mo 09. S T x 10 ' 8 x 10-8 3 x 10-' 2 x t0-*
1 2 x 10-' 1 x 10-8 7x 10-' 4 x 10-*Neooynum (80) .. Nd144 S 8 x 10-" 2 x 10-8 3 x 10-a 7 x 10-*I 3 x 10-" 2 x 10-8 1 x tO-H 8 x 10-sNd 147 6 4 x 10-' 2 x 10* * 1 x 10* * 8 x 10-'I 2 x 10-' 2 x 10-a 8 x 10-* 8 x 10-8Nd 149 S 2x 10 ' 8 x 10-8 6 x 10-' 3 x 10-*I l x 10-* 8x10-' 5 x 10** 3 x 10"Neptumum (93) Np 237 - S 4 x 10-" 9 x 10-8 1 x 10 '' 3 x 10-8i tuto * 0x10 8 4x10 " 3 x 10-*Np 239 8 8 x 10 ' 4 k t0-* 3 x 10-8 1 x to-*1 7 x 10 * * 4 x 10-* 2 x 10-* 1 x 10"NKhel (28) ... , Ni 69. .S 6 x 10-' 8 x 10'' 2x 10 ' 2 x 10-*
political awareness group has arrived forca visit and-
A- local'tour'of the Gulf Atomic ~TRIGA facility. .This group consists of 12people; six adult males 1(>21 Years old), .four adult-females (>21years'old) cne of which is in her second trimester of pregnancy,one 14 year old adolesent male, and one 8 year old female. f
As the SRO =on shift at the operating facility, and with noauthority other than the NORMAL-ACESS' RULES,
(a) How many of these people may you allow to. enter (0.5)the reactor facility without violating normalaccess requirements?
(b) . What is the mimimun number of dosimeters required' (0.5)for access for thirty minutes by the six adultmales, (assuming access approved)?
(c) If three of the adult males are to be granted (0.5)access for a period of several hours, how manydosimeters will be required?
Which of the following-types of radiation will NOT be expected atthe beam ports of a reacter at full power ?
.
'
: (a) fast neutrons
(b) sicw neutrons
(c) alpha
- (d) gamma
' I--7 Answer
C
Reference: Chapter V, page 8
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II-8 (1.0)
The production of radioactive gasses is a potential hazard in theoperation of.a TRIGA reactor.
(a) What radioactive gas is produced by (0.5)irradiation of the reactor coolant ? / ;
(b) What radioactive gas is produced by (0.5)irradiation of air ?
I-8 Answers
(a) Nitrogen 16
(b) Arlon 41
Referencer Chapter V, page 3/7
.
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_ _ - _ - .
_
I-9 (2.0)
Figure I--3 shows a JUNO model 9 portable radiation meter.
. (a) What three types of radiation can this meter detect? (1.5)
(b) What type of detector does this meter have? [D.5)
I-9. Answers
(a) (0.0 each)
gammabetaalpha-(not caliorated)
(b) ionization chamber (0,5) ;
Reference: Chapter V, pacje 8
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Figure I-4 shows an Eberline PAC iSA Alpha Counter.
Why must care be taken not to set the detector down en areas that {may puncture the probe face? {
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I-10 Answer {
The sneter will respond to 12aht 1f i unc t ur ed.,4
(It uses a l i ght 'aeitui ti vo photc multinlier tube.> l
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Reference: Chapter V, Page 14
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Figure I-5 shows a NP-2 portable radiation detector.
(a) What is the purpose of the " outer moderator (0.5)"
(item 5 an Figure I-5) ? i
(b) Of what is the " outer moderator" made (i tem 5 cn (0.5)Figure I-5)? +
(c) Why does the attenuator (items 1,2,b. 3 of Figure' (1.0) ;
I-5) have holes ?''
(d) What type of detector does this instrument have ? (0.5)
!
I-1) Arunwer s
(a) t h or nitt l i r m + ,a r& n et.t t r oi ,->
(b) pOlYOthylena
(c) flo19n in t h r a L t' en t ta * a,- . C. , r a 4 ven - he r >ul-
neutrons (fran ? %> xrt e r vi e'r o r ) :o . intd<,_
the i n . . ! f' W O C i rse'' a t D r M1 fc' al . n UtF tGri illH *i6Gil i T &Cl. s i
in the inne . .-d w P o r "n ,, ,v a if s. n e u -: + t re] ci i
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a-___-__-_-___-______
-,
I-12- . (2. 0)'
Continuous- . monitors are employed at the TRIGA Reactors- Facility1to' detect airborne and water borne radioactive material.
(a) What- type of detector.is used .for continuous (0,5)
monitors-? ,'(b) What is the. alarm setpoint of the " Criticality (0.5)
Alarm" (RM-12) ? <
(c) What is,the alarm setpoint of the " water activity (0.5) i
alarm" (RM-14)
(d) What is the alarm setpoint of the " air filter (0.5)activity alarm" (RM-14)
I-12 Answers
(a) GM tubes
-(b) 15 mR/nr,
(c) 45 mR/hr
(d) 3 mR/hr *
R ef'erenc e : Chapter V ., Pageu 10 ':.6 |
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I-13 (3.0)
Figure-I-6 shows a TLD badge.
(a) Where should the TLD badge be worn ? (0.5)
- (b)L Of.what is.the TLD chips made ? ( O'. 5 )'
-(c) .What allows the difference in response between TLD (1.0)
' - 100 and TLD '700 to be a measure - of' ThermalNeutron' dose 7
(d) What it, the purpose of the cadmium (Cd) filter 7 (1.0)( lead or copper not used at TRIGA )
7-13 Answerr,
(a) left breast pocl::et
(b) lithium floride1
(c) Ono chip has a higher percuntr-ae c*- L: --b Whi l e the other has-a higher parcentage af L I--7 L J. -6 h .t c a higher thermalneutron ':r os s section than Li-7, thus the difference in-
r e ad i nct s is due to thermal neutrons..
(d) El i;ni n ateu thermal nututrons ( .hN ter a cut n et ttr cn f,
donc measurement.
Raference. Chaptet V, Pa g e ',- 3--?5
i
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END OF SECTION IGO ON TO SECTION L
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Cross sectional views of Personnel Dosimeter Badges
Thel TRIGA Mark I reactor is operating at 100 Kw steady st.$te in t
the servo , mode. Unknown to the operator, the high ' voltageconductor to'the fission chamber breaks. Otherwise, the high i
voltags: supply continues to operate normally.{
What initial indications would'ycu expect the cperator to observefor each of the following devices? (0.5 each)
i
(a) % power channel #1
(b) linear recorder
(c) log recorder
|(d) regulating rod position
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U*1 An%WOrG
(u) "'. power i>cxli n s to ircrease .(0 5)
(b) linerar ocarder f a i. t :; l a ;r.c r e (0. 5)-
(c) the ~.i n g r<.ords- 'alla to sen Kh S )
(d) tha recpd atin.7 rad mo vea cu t--. (0.9) j
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,J-2' (2.O)
The MK I reactor:is critical at 500 W in the " automatic" mode ofoperation. The transient rod is fully up.-
Consider each of the f ollowing situations one at a time. Bryefly !
-state- how. the control reds, ~1inear recorder . i ndi cati on ,' . and jactual reactor power will respond during the resulting transient.
(a) The shim rod UP switch is depressed briefly (1.0)
(b) The AIR push button under the manual SCRAM baris depressed .(1.O)
J-2 Anr4Wer 3
(a) t.he sh:i m r aci move, nut, reactor a n ci lin ar r ot , cn3ru
power i n C r G G.9H99 and the t egul atinel rad ,~ oves in (1.0)3
(b) the tr anni c.nt rod f alls _ a nto t he c cru, rmL:or andu nc ar recorner p. or .creese, tneremtwg ~cMU V e!5 D!At (1.O)
NefOrenCn: C h O pit Q r II, p aq H44 17-16 .
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J-3 '3.0)
The TRIGA control rods are controlled by illuminated push buttonswitches in the center of the control pannel. For each of. thefollowing indications state the location of the control rod (UP,.DN or between UP & DN), the location of its drive, and * (ifappropriate) any abnormal condition. You may assume all lightbulbs are good and the reactor. operate switch is ON. (0.75 each)
(a) UP light - offDOWN light - offCONT light - onON light - on
A control rod calibration of theLMark F regulating rod is beingconducted using the " bump period" method. ' Initially the reactoris critical at'20 watts and the regulating rod in " bumped" out.
o
(a) Why should the operator. Wait 90 seconds before '
-taking data? (0.5)
(b) Why must power be kept below about 1 Kw during'the calibration? (0.5)
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J-12 Answers
(a) To nilow the trarttients d u n- to red wi t hd r av;l (0.5)to decay.
(b) To prevent. negative reactivity additions fenm 00.5)NTC.
Reference: Mar le. F Operating Frecedureti I X -- 1 i:. n d 2
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| J-13 --(1. 5) 'lIiA control. rod calibration of the Mark I shim rod is being '
conducted using the " rod-drop" tnethod. Initially the reactor iscritical.at i KW.and the shim rod is full cut. The following data
| is recorded: '
a
TIME AFTER' ROD DROP REACTCR POWER (LINEAR RECORDER)15 seconds 180 watts
10 seconds 135 watts 'i
15 seconds 100 watts
Using this data and the attached figure J-2, what is the worth of .the shim rod 7
L.M d.Nkb.. a!. ..:h I!N !"d.I,')' 1[ M 'h.. j TEM ' i N.j. , b , | h | d"; b.*......:.. .. .:..6,) :! ,ui |$:-
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J-14 (0.5)
MULTIPLE CHOICE - EELECT THE BEST ANSWER
A reactor power calibration (cc.lorimetric) is being concucted ic v-the. Mark I. . hich of the following errors will cause calcul'ated-Wpower to be lower thari actual? "
a. 'The calorimetric is conducted at 150 Kw reactor power ratherthan 200 Kw required by procedure.
b.- The pool depth is six inches below the ":ero" mark(15 inches below the top of the tank).
c. The forced cooling water system is not fully isolateo andis left running.
d. The digital-thermometer used with the installed thermistorprobe has a constant -5 degrees error.
I!
J-14 Answer-
c.
Reference: Mark I Operatioq ? c o t:,a d u e n , VIII-1 .
Loss of the gamma compensating signal to a compensated ion.chanber will: ,'a. cause a sudden increase in indicated power at low power.b. cause a sudden decrease in indicated power at low power.
cause a sudden increase in indicated power at high power.c.
d.. cause a sudden decrease in indicated power at high power.
a.- to avoid a phace change in the. Mark'I (standard) fuel. '
b. to prevent DNB of the cladding. ;
Ic.- to prevent bulk boiling of the water coolant. ;
d. to prevent burnout of the fuel elements. i
K-5 'AMGWer
c.
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K-6 (1.0)
MULTIPLE CHOICE - SELECT THE BEST ANSWER
K-6(a) At low power the Mark I and Mark F reacter negatWevoid coefficients are approximately:
a. 1*10-4 Mk I and 2*10-3 Mk F|
b. 2*10-3 Mk I and 1*10-4 Mk F
c. 2*10-5 Mk I and 1*10-4 Mk F:
d. 1*10-4 Mk I and 2*10-5 Mk F !
K-6(b) At low power the Mark I and the Mark F reacterprompt negative temperature coefficients are
,
I
approximately: j
a. 1*10-4 Mk I and 2*10-3 Mk F
b. 2*10-3 Mk I and 1+10-4 Mk F
c. 2*10-5 Mk I and 1*10-4 Mk F.
d. 1*10-4 Mk I anc 2*10-5 Mk F
K% on amer s
K-6(a) b. ( 0, 5 ).
e s1 L d
Referonc rhapter VI, acu - ral , <. r u i3" r , -c. ,- ,,
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K-7 (2.5)
Technical Specifications require that fuel element inspectionsmust be accomplished at least once a year.
(a) Based on the Technical Specifications, whe.t are the *
| three criteria for " damaged" stainless' steel clad '
fuel? (1.5)|
(b) Which two inspections are not required for the|-
instrumented fuel elements? (1.0)
K-7 An%ers
(a) L.e n s thian 1/16 inch bend or sagitta (0.5) i
Less than 0.1 inch longer than .i t a ' original length (0.5)No elad def ects '( 0. ,5 )
(b) length e n t, bend examinations are not required ( '. 0 ).
Ref er r-n c e : Technical Specifications, MK I pelg e 5, MK P page 5 and -|3a '
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. K-8 .(1.0)
When- it= is suspected that fuel damage has occured, when doTechnical Specifications allow reactor operation'to be continued?
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' Operati on may continue for the~ ~i u r P r~ r~ f 1 cating a c:uspected~ ^
damaged fuel element.
~
-- Reference: Technical Specification 3 Pa?les -S and 5a-$b
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K-9 (2.0)
| The TRIGA cores contain both moderators and reflectors.(a) What (two items) provide neutron reflection for
the Mark I reactor? ( 1". 0 )
(b) What (two items) provide for neutron moderationin the Mark I reactor? (1,0)
K-9 Ansween-
(a) Graphite at the end of the fuel el en:ent s andgraphite in the annulus ar oun ct the coro. (1.0)
(b) Zirconium hydrida (f uel mixture) and water coolant. ( 1, 0 )
Reference: Chapter I, page 16, Chapter (' I p ag mi 6-0 a.qd 22,
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K-10 (0.5)
MULTIPLE CHOICE - SELECT THE BEST ANSWER|
! According to the Technical Specifications, all fuel elements orfuel devices must be stored in a safe geometry with: ,'a. Keff less than 0.9 for all conditions of moderation.
b. Keff less than O.O for all canditions of moderation
c. Subcritical by at least $4 for all conditions of moderation.
d. Subtritical by at least $3 for all conditions of moderation.
I-.-10 Answer
b.
Reef e* er);e: Gac;1r t <1 E r.> Eic i f i e i t L. i o n '> > > <. a _, '5 ^ n t.1 74_.
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!. . j.K-11 - (3. 5) :|
[ ~|. 'The- Mark I .and.the Mark F' written procedures require certain- ~l
I .-personnel to be present during' core modifications.
-(a) What personnel must be present during removal of '
a' control rod for-maintenance? (1.0)
.(b) What personnel must be present while. adding anadditional fuel element to the core? (1.0)
;(c) What personnel must be present while installing )an experiment with $2 of reactivity? (1.5) 1
1
K-11 Answere
(a) A nenior operator e,uct directly'cupervinci tne work ( 0. 5) and.
the conocle instrumentation must be monitored by a lit.cnced ;
operator. (0.5)
(b) A senier operatcr mast directly supervise the WorP (0.5) andthe caneale instrumentation murit be monitored by licensed . J-'
operatar. -(0. D).]
(c) The . m: p er i mer i t. can he innta.tled by a reactor operator (or '
persor Josignated bs the p?IC) (0,5), the ccnnale muut beobserved by a 1.icenstd operstor (0,5) 0.n d the-prccoEG must be g
-mupervised'by a santor reactor operator.(O<5) '
.)Ref eron::: : hapter IV pacio 2-3 and Oper ating Proceduren X ,, XI,and XII
| .L CATAGORY L ql' . ADMINISTRATIVE PROCEDURES, CONDITIONS, 5
| AND LIMITATIONS|
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L-1 (3.0) ," Ii
The three classes of experiments that can be perforned with the,; "TRIGA reactors are classified as " Routine", Modified Routine",i
| and "Speci al " .
(a) What is the difference between " Routine" and" Modified Routine" experiments? (1.0)
,
(b) Who can authorize " Modified Routine" experiments? (0.5)
(c) 'Who are three of the four persons or groups whomust review '"Special Experiments"? (1.5)
L- ;l (:,n swer s
(a) Routine a periments involve operations'which havr-_
been prevlaunly extenr.ively euamined. Modi 4iedRoutino experiments have not previoaul y been per #ormedbut Are aimiliar to prev'.ounty performed experimentsand do r;.t t have si gn1 +i ct~ntly greater t,nn ar d c . t1.O)
(b) Madi f i eri Rautinc experiments ara authorized bythe Phy%icitet in Charge (PTC) (0,5)
( c.) (0.5 for any 3 of the follchina)
PICHeal th Physi c t;
- Critical:.tv _ a f eguar de Comm'.tteeL i C a n 'f,i t t e.| 4tn d NdC .!. C @ r C OmD l l ::.n C D
Reference: Anmtniutr:1h m Feauir: ment iIi pam i 2-4
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'L-2 .(2.0)
An experimenter- wishes to use the crane to reposi ti on hisexperiment.
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i(a) Who-must give permission f or this individual to '
manipulate the crane? ([.0)(b) Whose authorization must be cotained by the
experimenter:to allow him to control the crane? (1.0)
L-2 Answers
( a') The SRO (on duty) or above ( 1. 0) .
l(b) The Phyaicist in Charge (1,0)
Reference Operating Proceduren, ,W I I I -
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L-3 (3.0) J'
1!
. The TRIGA facility Cri ti cali ty Safeguards Committee (CSC) Jreviews, evaluates, and . approves various aspects of reactor |
'
operations.
*(a) What are three minimum requirements for the ' 1,
composition of the CSC? (1.5)
(b) What are four of the six responsibilities ofthe CSC (or designated subcommittee)? (1.0)
i.i
(c) What constitutes a quorm of the CSC?- (0.5) !
:,
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L-3 Answers
(a) The I'5C murt concist of not 1. es s than four persons- ( 0 ., 5 ) ,, who must not be airectly involved in TRIGAoperationu (0.5), and collectively possens expertinein Ell arrns of reacto aperstiang and cafety(0.5).
(b) (O.23 OGCh f L.T any four of the fc1)orfing)
Reviaw anri approval of enporiments
Review and approval af rhangen to the 'acility, TechnicalSpecification ,.: Prncedurco
DEntDrm3nALion af Nheathr- i?. rcposed c h a n t,e , tOGt. Dr
f "o p OF i FT.?n t W0uld C Q r,'a t i t Li C An .An r O V i W W e d 03fOty::u h.st., o n of a ct:ange to the Tecnnical Spec;fications
Rev;.ow of the ap'arat i on and operational recoram
Reviow 3 a b n o r ra al per f orm ance a-; t lui p::w o t or oprarationo j
RG V i ':0 8.+1 Q :.b n OP P a l C '~ u r ? .t 0; L; J 'l * :: C ' ;r F O ti C O ' A "!C 11 ",idCnt3i
t'*j)[ r * ;d]l n !t!)(| a"" I iW; ^RP
(c) o r, .o r >.t < n m i e~
- . jar'' of tN fr,renb ' v t:i , (0.5)
R f-N U r t in c .,. : J'ir! Os i f l i. J 3 '.. r i : ! ;# J ' r qr.e r i t ; } i .9
The Emergency Response and Recovery Director (ERRD) for the TRIGAReactor Facility has responsibilities during normal operations !and during emergencies.
(a) Who is the ERRD for the TRIGA Facility? (d.5)
(b) What is the task of the ERRD during normaloperation? (0.5)
(c) What is the task of the ERRD during emergencies? (1.0)
L-4 Answorn
(a) Th C1 ERhD 15 the l l !. Lir i } e r,; O l ; ' t Dd {titernate ( 0, 5 )-
(b) Duri ng normal op o o.tinn thrr ERRO eval. u ca t em
t hn emerg: ncy pract,duran (to anm er > tha.t theyGr e O f f C.".i t i V e "' t.t rf) 1 1 i n F,177 Li t Od ) . ( U . '3 ) |v
(C) 1)Llr i n Cl D T:'.'.F Cl an C 11 :E thP 
