ML20236F981

Exam Rept 50-113/OL-87-01 on 870922-24.Exam Results:Three Reactor Operator Candidates Passed Both Written & Oral Exams.One Reactor Operator Candidate Failed Written Exam & Passed Oral Exam.Written Exam & Answer Key Encl

ML20236F981
Person / Time
Site:	05000113
Issue date:	10/20/1987
From:	Elin J, Johnston G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20236F958	List: ML20236F956 ML20236F981
References
50-113-OL-87-01, 50-113-OL-87-1, NUDOCS 8711020361
Download: ML20236F981 (50)

Text

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, ,, Examination . Report No.: 113/M.-87-01 j.f

. e, Facility: University of Arizona Research Reactor Docket No.: 50-113

, Examinations-administered a 'Universit of Arizona TRIGA reactor, Tuscon,iArizona.. .)

Chief Examiner:- / b. // [ <

Gary \lf.f ohr$ tron, .

D&te/ Signed 3

.0perator Lic .si,ng Examiner. , 1 Approved: hf/ 1 , .

/[ '2h O d6hn 0.~Elin DatyS- gned ~

.C[ief,OperationsSection

. Summa ry:-

1 Examinations on September 22-24, 1987 (Report No. 50-113/0L-87-0M Written and oral. examinations were administered to four Reactor Operator candidates. Three R0 candidates.~ passed both examinations.'One R0 candidate

' failed the written examination and' passed the' ora 1' examination.

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I REPORT DETAILS

1. Examiner:  !

G.Johnston,RV(ChiefExaminer) 2

2. Persons ' Attending the Exit Meeting: j G. Johnston, RV G. Nelson, UA H. Doane, UA

3. Written Examination and Facility Review:

The written examinations were administered to four R0 candidates on September 22, 1987..

At the conclusion of the written exam, the facility staff was given copies of the written exam for review. The comments made by the staff at the conclusion of the review are included in the attachment (1). These comments were discussed with the staff and appropriate changes were made to the exams prior to the grading of the exams.

4.. Operating Examinations The four Reactor Operator candidates passed the oral portion. -l The examiner did not identify any concerns of generic importance during the conduct of the oral examinations.  !

5. Reference Material The examiner experienced some problems with the facility provided reference material. Specifically the material provided did not include an adequate description of the facility. The examiner experienced considerable problems in determining adequate references for questions on facility design features.

The preparation of portions of the written examination was made with materiel provided by the vendor that was present in the Region V offices.

The examiner was able to prepare an examination that sufficient to satisfy i the examinor's Standard, this problem did re ult in a considerable burden. I

6. Exit Meeting  !

The Chief Examiner met with the facility representative denoted in  !

Paragraph 2 on September 24, 1987. The examiner discussed the findings j to that point and the examination process.

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. _c Resolution:oflFactility. Comments.-

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University of Arizonai s

Reactor Operator'Exami. nation.

Question l A.2 J'

Facility, Comment:

" 80'sec period determined by half life of longest precursor group.

Reso10 tion:

~

1The examiner will accept this as answer,'but' sees no reason to change key.

, [ Question A.4 J c. . .

-Facility. Comment: j "Using'. C. R. proportional to n _ = -ql/ rho 4 - delta rho = 1.75% delta' k/k."? .

1 Resolution:'

The examiner will accept the above answer for fullLcredit.

s.

Question';.A.8-D Facility Coment':

i "on figure A-1 SUR and reactor. power should be shown in natural log plane." j Resolution:

The figure is meant to be:in the form it is in. The figure is. meant to 1: ' allow the candidate to show " relative"~ changes to.SUR and reactor power.

, Question E.la' -

M- Facility Comment:

Serial .nos. on-top end fitting of fuel element."

Resolution:

Agreed,-will change. key.  !

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. Question.jB.3u

• , Facility' Comment: *

, " Question, refers to preventing. pulsing'in'S. S.~only. Examiner'.s. a yp <

" answers-1 and.3Lonly are pertinent." y n , .

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- Resolution:  !.

w . .

The examineer views' answer number.2 as pertinent, since it. prevents: "

pulsing above 1 kw in Steady State. However, answer 4Eappears ambiguous-

-and will be deleted.:

oQuestion B . S f. .

FacilityCommenth

, "Regandshimrodb'havestainlesssteelcladding." .

A 1 Resolution:

'; Agreed,'will change-key.,

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-Question B.7 '

FacilityiComment:

" Pool makeup water added manually from 5. gallon bottles, not throu'gh 7

demineralized system. -

Resolution:

Agr'eed_, will change key.

-Question C.1-Facility Comment:

b. . $0.0074kw. (providedforCher.k'atthefacility.)

c. $2.62

d. $2.43  ;

Resolution:.

Will insert into key for Check at Facility values.

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Question': C.21 L Facility, Coment:

To paraphrase the coment, the facility staff was concerned about the.

relative effect a; bubble would have passing throught the core of the'TRIGA.

.They point out that the core is overmoderated at the center of the core,

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and.therefore a bubble could cause a positive reactivity additiontif it passed through,the center.

f Resolution:-

N\ . The examiner cannot change _ the key on the ' basis of this coment. However f if the' candidates' response does elaborate on this factor consideration ,

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=will'be given for credit.

Question C.7 1 Facility Coment:

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~"The. integral worth may also represent the reactivity added in withdrawing the rod to'that position. In that case,. full out = full worth.1(Of the three control rod'inegral worth tables provided..the shim and reg have 4 full in = full owrth,-while the transient rod table, since it is used to j calculate pulse reactivity has fulliout = full; worth.)" j Resolution:. ]

?Theiexaminer notes that i.e. (id est: that is) full in_= full worth'ma'kes. )

noludgement- that a worth table is' either positive or negative. If the candidate indicates that the worth of the rod is somehow cumulative for H

integral worth full credit will be given. =j QuestionLJC.8' i Facility Coment

" Reactor will go suberitical to power source levels."

-Resolution:

The examiner notes that intrinsic sources are always present in an

' irradiated core. However, if the candidate infers that power goes to

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.subcritical--conditions full credit will be given. What is being sought i

.here is the contribution of source neutrons to the critical condition at '

low power: levels.

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- 4 Facility. Comment:

" Peak; pulse 1 power?

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, Resolution::

/ Agreed, will; change key.

i Question ;0 3

j. LFacility Coment: .

e:c d J s  :"Also,-log channel provides period signal to servoicontroller." .

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. Resolution:; '

u Agreed, however the: question refers'.to-.only a channel. The examiner will' J iaccept either response =for full: credit.. 1 a

Question : D 4b -

Facil'ity. 'Coment: ,

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"Theylog ' power channel meter and' recorder both read out in kilowatts. -"

. When ' cold and subcritical :the reading is' 2x10**-7L.to 3x10**-7 kw. (This .

corresponds-to:abont'4;4' cps.)'

Resol utio'ni'-

.Sinceithis-is:a Checkiat Facility item the examiner will.-accept.al1 to-

'Sx10**-7-.kw;or,3 to~~5 cps as answer. The key-'will be. changed.

. Question 0.5:- l t -

Facility Comment:

" Answer is correct, but not addressed in T. S." l' Resolution:

Agreed.

Question- D.7b

. Facility Comment:

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'" Reg rod should drive in to make period longer (10 seconds) - circuit

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. Resol'ution:

. Agreed, will change key.

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Question D.10a 1

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Facility Comment:  ;

" Flowmeter. Because of by-past. valves, on cannot know if all flow is through the demineralized."  !

Resolution:

Agreed, will change key.

Question D.11 i Facility Coment:

The answer could include the fact that the channel is calibrated at steady state power with the gamma portion of the signal present, which .is also proportional to power. The channel is thus accurate for activating safety channel trips even though part of the signal may be due to gammas and not neutrons."'

Resolution:

~The examiner does recognize that the comment is true, and therefore is a viable answer in its own.

Question E.2b Facility Comment:

The facility made a. comment about the Cont /0n lights being two and not i one light.

Resolution: '

The examiner accepts the comment as advisory, and will change the question prior to exam bank upload.

Question E.3 Facility Comment:

" Add 10% reduction in H.V. on either safety channel."

Resolution: ,

l Agreed, will change key. j 1

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' Question ~ E.4 i

Facility Comment:

" Answer 1.fTS requires icps. Facility acmenistrative limit 2 cps.

Answer'2. TS requires '10kw. Facility administrative. limit 1 kw."

Resolution:

If candidates provide 'either TS or administrative limits they will recieve full credit. The key will bel changed.

. Question E.8a Facility Comment:

"5000 counts per minute. (5 units full scale indicates 500 cpm X 10 multiplier = 5000. cpm.)"

. Resolution:

Agreed, will change key.

Question.E.5 Facility Commenti

" Shutdown. implies being subcritical by more than $1.00."

Resolution:

Doesn't affect gist of answer, will change key.

Question F.1 Facility Comment:

"a. $2.50

b. 10 kw" Resolution:

Will change key for a. and will accept either 10 kw TS limit or admin limit of 1 kw for b.

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l. ' Question- F.2a h Facility Coment:

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" Question implies one experiment. Answer should be false."

Resolution: i Agreed, will change key.

Question F.3a  ;

Facility Coment.

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" Answer a: Reactor may not be operated with neutron radiography tube in storage position unless interior sheilo'ng plugs are in place."  ;

Resolution:

Will accept answer as worded, and will change key. i

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Question F.4a Facility Coment: l l

" Instrumented fuel element can be placed in the inspection tool and is.

However it can be inspected only for bend." jl 1

Resolution:  !

Agreed. Will change the key to read: The instruemnted element cannot be measured for elongation.

Question G.I.1 Facility Comment:

"No floor drains in facility."

Resolution: ,

Agreed, will delete 1.  !

Question G.1.3 i

Facility Coment:  ;

" Air handlers do not recirculate room air."

Resolution:

The examiner does not see relationship. j i

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t L' ' '" Answer l'should also be acceptable since the'qua'lity Vactorl- -4 iis 20 Lfor alpha pa.rticles'with' sufficient l energy:to reach -

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Rhsolution:1 Agreed, will-~ change key. .

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U.S. NUCLEAR REGULATORY COMMISSION.  ;

REACTOR OPERATOR LICENSE. EXAMINATION z

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I vn /h Facility: University of Arizona Reactor Type: TRIGA N 4 Date Administ'ered: september 22, 1987

~ , . . _ .

Examiner: c. Johnston Candidate: -

INSTRUCTIONS TO CANDIDATE 2 Use separate paper for the answers. Write-answers on one side only. Staple.

question. sheet on. top .of the answer sheets. Points for each question are indi-cated in parentheses after the question. The passing grade requires ht least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.-

LCategory % of Candidate's  % of Value Total Score Cat. Value

'16.0 16.0 A. Principles of Reactor Operation

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,14.0 114.0 __

B. Features of Facility Design 15.0 15.0- C. General Operati,ng Characteristics n 13.0 D. Instruments and Controls-n 14.0 _

E. Safety and Emergency Systems m m _

F. Standard and Emergency Operating Procedures 14.5 14.5 G. Radiation Control and Safety 100.0 .

Final Grade  %

All. work done on this exam is my own. I have neither given nor received aid.

Candidate's Signature e

9 ES-231-1 l

l- EnclosurG 2-

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' REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINAT

• 1.

A single room shall be provided for completing the written examination.

The location of-this room and supporting restroom facilitie's shall_besuch i

as to prevent contact with all.other facility and/or contractor personnel during the duration of.-the' written examination.

-should motel, ormake arrangements for the use of a suitable room at'a local.' s other building.

'the licensee.

Obtaining this room is the responsibility of 2.-

Minimum spacing by the. chief is required examiner. . Minimumtosensure examination integrity as determined with a 3-ft space between tables. pacing should No wall be models charts, one candidate per-table,

training materials shall be present in the examination roo,m.and/or'other  ;

3.

Suitable arrangements shall be made by the facility if the candidates are  ;

to have lunch, coffee, or other refreshments. These arrangements shall- ,

comply with Item 1- above.  !

a -examiner and/or proctor. These arrangements shall be reviewed by the 4.

The facility staff shall be provided a copy of the written examination and I

examination. answer key after the last candidate has completed and handed in his wri

' vide formal written comments with supporting documentation o tion and answer key to the chief examiner orf to the regional office section chief. .!

5.

The facility licensee shall provide pads of 8-1/2 by 11 in. lined paper in unopened packages for each_ candidate's use in completing the examination.

The examiner shall distribute these pads to the candidates. All reference material examiner.needed to complete the examination shall be furnished by the Candidates can bring pens, pencils, calculators, or slide rules '

.into the examination room, and no other equipment or reference material shall be allowed. 1 6.

Only black ink or dark pencils should be used for writing answers to questions.

4 Examiner Standards .

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ES-201-1

l. Enclosure 2

.i-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 ybur application and could result in more severe penalties. '

2. Restroom trips are to be limited and only one candidate at'a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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.

5. Fill in the date on the cover sheet of the examination (if necessary).

i

6. Use only the paper provided for answers.  !

7. Print your name in the upper right-hand corner of the first page of eacn section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only one side of the paper, and write "Last Page" on the last answer sheet.

j 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 face down 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 the question and can be used as a guide for the depth of answer required.

14. Snow all calculations, methoas, or assumptions used to obtain an answer

.to mathematical problems whether indicated in the question or not.

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.

Examiner Standards -

F ]

-E ES-201-1 Enclosure 2

-. 4 i -18. When you complete your examination, you shall: ),

a. Assemble your examination as follows:

(1) Exam questions on top.

{ j (2) Exam aids - figures, tables, etc. '

,.. l (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 answer the examination questions.

c. Turn in all scrap paper and the balance of the p per that you did not use for, answering the questions.

d. Leave the examination area, as defined by the examiner. If after i leaving, you are found in this area while the examination is still  !

in prcgress, your license may be denied or revoked.

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l Examiner Standards

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EQUATION SHEET

l. -

f = ma 'v = s/t

• w = 28 s = v,t + at 2

Cycle efficiency =

• E = sc a =;(vg - v,)/t KE = mv .vg = v, + at A =.AN A

• A,e .. . .

PE = agh. w - e/t A = In 2/tg = 0.693/tg -

W = v4P 6 (t, )(e )

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AE = 931Am b *'

(eg + t ). .

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1 ,y ,-Ix k=UAAT )

y ,y ,-ux j Pwr = Wg A i,y go-x/ M  !

10 3E(t)

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. P=P TVL = 1.3/u i

P:= F et/T HVL ='O.693/u SUR = 26.06/T ,-

T = 1.44 DT SCR = S/(1 - K,g ).

SUR = 26

/A'r,0) j CRg = S/(1 g ,",l K,gf )

T = '(1,/p )..+ [(f p)/Aeff)

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D CRI (1 - Ke f)l = CR 2 (1 'Keff)2 T = 1*/ (p - T) .

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M " I/II ~ Eeff) = CR /CR g 0

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eff' M = (1 - K /

eff)0 (1 - Keff)1 AEeffIEeff 1

, #[ ( eff~ )! aff " .

SDM - (1 - K gg)/geff p= ~

, [1*/TK,'ff.] + [E/(1 + A,ff7 )] ,

1* = 1 x 10 seconds P = I(V/(3 x 1010) 1,gg = 0.1 seconds

~

I = No .

Idlg=Id22 WATER PARAMETERS Id g =1d2 .2

,1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters)

I gal. = 3.78 liters R/hr = 6 CE/d2 (g,et)

I ft = 7.48 gal.

MISCELIR4EOUS CONVERSIONS Density = 6.2.4 lbm/ft 3 .

1 Curie = 3.7 x 1010dps Density = 1 gm/cm 3 1 kg = 2.21 lbm Heat of valorizations = 970 Itu/lbm I hp = 2.54 x 103 BTU /hr Heat of fusica = 144 Btu /lbm 6 1 Hw - 3.41 x 10 Btu /hr 1 Atm = 14.7 psi = 29.9 in. I'g. 1 Btu = 778 ft-lbf i

i I ft. Hy o = O,4333 lbf/in 2 1 inch = 2.54 cm F = 9/5 C + 32 C = S/9 ( F - 32) 1

L

• Secti en A Principles of Reactor Operation QUESTION A.3 Under- steady state conditionc:

Why is there no significant difference between critical control rod positions between 10 watts'and 100 watts? (1.0)

• ANSWER ,

10 watts and 100 watts: Because there is essentially no temperature change in moderator or fuel temperature to provide

negative reactivity. (1.0)

• REFERENCE General Physics Nuclear Theory II B.2.c OUESTION A.2 Following a scram there is an initial prompt drop in power level followed by a power decrease and a negative period of -80 seconds.

Why can't the power decrease at a rate Caster than -80 seconds'~

(1.0)

• ANSWER Power cannot decrease f aster than mean life time of longest lived precursor. (This is 1.44 x 55.sec T1/2 life of Br) (1.0)

• REFERENCE General Physics Nuclear Theory II B.2.c 1

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OUESTIO'N A. 3-cThe University of- Arizona TRIGA reactor has an Americium-Berylium j neutron source. -

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' a .' Why _ i s - an Americium-Berylium neutron source necessary 'in the University of Arizona TRIGA reactor? < (1.0)

b. What1 2s the process by'which the source produces neutrons 7 1 (0.5) j t

• ANSWER

a. The. source is need_for reactor startup to insure instrument response remains-on scale at lowest' power level and controlled approach to criticality. (1.0)

.: 'b. Am decays via' alpha emission. The alpha interacts with Be to

_ produce carbon and a neutron. (0.5) j l

i

• REFERENCE CHAPTER C UARR' FACILITY REFERENCE MATERIAL DUESTION.A.4 f a

The count rate has increased from 100 cps to 150 cps in a subcritical/ reactor'.

How much reactivity have you adoed to the reactor if i ni ti al value-of Keff'was O.95 7 (1.5)

• ANSWER cr1L/cr2 =~(1-Keff2) / (1-Keff1) [0.93 100/150' = (1-Keff2) / (1-0.95) CO.53

'1-Keff2 = 10/15 x 0.05 Keff2 = 0.967 CO.13 change in reactivity = L1-Keff2/Keff23 - El-Keffi/Keff13

= Keff2 - Keffi / Keffi x Keff2 CO.93

= 0.967 - 0.95 / O.95 x 0.967 [0.53  !

= 1.05 */. delta K/K EO.13  !

• REFERENCE C-E Reactor Theory pgs. 74-76

. Nuclear, Energy Training, Module 3 Rx Ops, Unit 5.5 General PhysicsNuclear Theory II B.1 i

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.I l l L QUESTION A.5 )

! s I Af ter achie'ving criticality you raise reactor power to 50 watts quickly, and'immediately stablize the reactor.by estab inhing an infinite period at the 50~ watts power level. You then erif.y that the power level indication is steady with no rod motion (rod control' remains in manual). .

WHY would you observe an increase in power after waiting a-few ,

minutes? (2.0) 1

• ANSWER (The rods-would have to be inserted when power reachis the 50 kw level to establish an infinite period.)

When rods were inserted only prompt neutrons were affected and

reactor power was stabilized. (1.0)

I

. Af ter. a f ew minutes delayed neutrons contributed to the overall i neutron population thus power will increase. (1.0)

• REFERENCE C-E-Reactor Theory pgs. 74-76 ,

Nuclear Energy Training, Module 3 Rn Ops, Unit 5.5 q General Physics Nuclear Theory II B.1 x

QUESTION A.6- ,

The reactor is operating at 100 Kw (100% full power) and the reactor scram is set for 110% full power.

What will be the power at the' time of the scram if a nuclear. U excursion creates a 100 millisecond period and the scram delay time is 0.1 seconds after 110% power is reached? (1.5)

(Assume no temperature or void effects. Show all work.)  ;

• ANSWER T=100 x 10(-3) sec=0.1 sec (0.25)

P(final) = ' P(initial) x ett/T) (0.5)

. P (final ) = 110 F49 x e(.1/.1) (0.5)

P(final) = 110 Kw x e = 110 Kw x 2.72 P (f i nal ) = 299 Kw (+ or - 5 Kw) (0.25) )

• REFERENCE l General Physics Academic Program for Nuclear Plant Personnel

{

. i O

QUESTION A.7 Why will the Core Delayed Neutron Fraction change as a function of core age (burnup)? (2.0)

{

• ANSWER .

Pu 239 builds in and is responsible f or a larger percentage of the fissions,.thus it's smaller fraction delayed neutron fraction decreases the overall fraction. (2.0) .

1

• REFERENCE General Physics Academic Program f or Nuclear Power Plant Personnel QUESTION A.B , /, i pnttuf l

Refer to Figure A-1 which shows an instantaneous T.cgao ve l reactivity insertion into an already critical reactor core at l time T = 0. After a stable period is reached an instantaneous- l removal of this negative reactivity occurs at time T = 1. Respond ,

to the f ollowing instructions, assuming source neutrons are not l significant. l l

a. Sketch t'.e reactor POWER level as a f unction of time on l Figure A-1 for these reactivity changes. (1.0)

b. Sketch the resulting reactor PERIOD as a function of time on Figura n-1 for these reactivity changes. (1.0)

• ANSWER

a. and b. see the attached drawing (2.0)

• REFERENCE GENERAL-ATOMIC REFERENCE MATERIAL

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(%ble Pcucr)o.2 8 P.

(promPE.Tump) 0.25

.o i

t:0 -

1irne  ; t=l J

y N ... ,

a

.' \

QUESTION ~b9 f

a.. Why is. period used to describe the rate of change in' power. M of;a reactor.instead of a unit like watts per-se ond? (1.0) i b., How cannyou make an accurate measurement of' reactor period-

-if the period meter is inoperative and you are allowed to operate with it out of service?

( 1. 0 L I

• ANSWER

a. Power. increases exponentially, not linearly. (1.0) .  !

b.- Measure doubling time or e - folding time. ( 1.0) )

.h

• REFERENCE General Physics Academic Program for Nuclear Power Plant

.: . Personn.el .)

QUESTION A.10 MULTIPLE CHOICE - SELECT THE BEST ANSWER

The symbol' b '(beta) and b(eff) (beta effective) both. denote the

' ' total fraction of delayed neutrons. The difference between these (1.0) two ist a.- b(eff) is samaller than b since delayed neutrons are born ,

with lower energy levels than prompt neutrons. l

b. b(eff) is larger - than b since delayed neutrons are born with lower energy levels than prompt neutrons.

I

c. b(eff) is smaller than b since delayed neutrons are born with higher energy levels than prompt neutrons.

..i

d. .b(eff) is larger than b since delayed neutrons are born with higher energy levels than prompt neutrons.

• ANSWER

.b. (1.0)

• REFERENCE General Physics Academic Program for Nuclear Power Plant Personnel i

l l

l t

l l

l l

e  :

l4 -

F ..

-, 4

$ f f '/ .

'b

- QUESTION'A.11 4

MULTIPLE CHOICE -- SELECT THE. BEST ANSWER

(

l

.How willipeak power vary as a function of prompt exceks

~

)

1

< reactivity inserted into the University of Arizona TRIGA reactor?

(0.5)

'a. Inversely 3

b. No change. ,

c.- Directly .

d. As the square -

• ANSWER

,: j' d..  : (0. 5 F j

-* REFERENCE GENERAL ATOMIC REFERENCE NATERIAL  ;

End of Section A Go on to Section B l

I l

1 l

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'n

E Section B Features of Facility, Design s

. QUESTION B.1 5

Regarding the Neutron Startup Source:

What is.the minimum strength (in counts per second) that the neutron source MUST exhibit on-the Startup Channel prior to a reactor.startup? (1.0)

L

• ANSWER The startup channel must exhibit a minimum of 1 CPS. (1.0)

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION B.2 Answer the-following about reactor fuel rods:

a. How and where are individual fuel rods identified? (1.0)

b. What has'been placed in the ends of the fuel rods to minimize neutron leakage and improve flux within the individual f uel rods? (1.0)

• ANSWER Top

a. Serial numbers on M end fitting.

(1.0)

b. Graphite slugs on either end act as top and bottom reflectors. -(1.0)

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL

. q

- f' E.' '... ]

~

.d i

' QUESTION B.3 .

What ar e' th'r ee - (3) . of the'four design f eatures of- the Universi ty of Arizona.TRIGA reactor that would prevent an operatcp from l accidentally pulsing the reactor inLthe steady state mode qf operation 7

~ (1.5)~

1

• ANSWER l

-(any 3't 0.5 each)

~

L. .

1. Air cannot be applied to transient ' rod unless it is f ully down.

,J l2 ., Interlock prevents pulsing operations above i KW. l l

3. Simultaneous withdrawal interlock prevents _ transient and  :

l

-shim / reg rods moving simultaneously.

4. Inter 1'ock requires switch in pulse' mode. @ Ne c  ;

• REFERENCE.

CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION. B.4

a. LWhere may NEW fuel be stored when not installednin the reactor?- (0.5) .,y

b. . Where may: IRRADIATED fuel be stored when not insta11ed'in

'the reactor 7: (0.5) 1

• ANSWER

a. Irradiated fuel may be stored in the Pool wall storage rack.'

(0.5)

b. . New f uel may be stored in the shipping containers and in the Pool . wall . storage rack. (0.5)

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL i

I

-ummmi__.__.__ _ _ _ _ _

ll* .. (d i

ji.

OUESTION B.5 What(are the following design' parameters for'the University of Arizona TRIGA reactor? (2.5)

( .i' Ja. ' Reflector. material

b. Fuel enrichment-

c. Length of active fuel

d. Fuel cladding material f '. - Control rod cladding material

• ANSWER,

. :: a. Graphite.(0.5)

b. 20% (0.5)

c. 15 inches (0.5)

d. Stainless steel (0,5)

f. Stainless steel;- g [d.E -

ransient rod and. regulating rod have aluminum cladding .

1

.( 0.25)- CAF (description.in reference material lacking) -

• REFERENCE l

~ CHAPTER ~C UARR FACILITY REFERENCE MATERIAL' j

)

QUESTION B.6 j How do youLadjust thefamount of reactivity inserted during a ]

pulse? (1.0)

]

J

• ANSWER' l Adjustment of the position of the pneumatic cylinder sets the ')

upper. limit of pneumatic piston travel, thus limiting the' , _ l reactivity. (1.0) 1

• REFERENCE l CHAPTER C UARR FACILITY REFERENCE MATERIAL l

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J. . ..

,[ 9 f. 'v.

QUESTION- B.7 Wh'at is'the. source of reactor : pool makeup water for the University of Arizona TRIGA reactor 7 (0.5) o e u f V?o Vuotrut; e w 5eYboYQi f

he . demineralized sysCem prov hes the makeup water f or the r eacth)

~

(0,5) pool by processing raw water f rom theddwatyrj<'ain.,I fxt [

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION D.8  :

What are four (4) of the five reasons excess reactivity is placed in the core of the University of Arizona TRIGA reactor? (2.0)

• ANSWER (1) Pulsing.

.(2) Burnup (3) Overcome-Xe (4) Overcome Sm (5)' Overcome neg temp coef f

'* REFERENCE GENERAL ATOMIC REFERENCE MATERIAL CHAPTER C UARR FACILITY REFERENCE MATERIAL

. QUESTION B.9 How is the bottoming impact reduced when a control rod f alls into the University.cf Arizona TRIGA reactor core following a scram? i (1.0)

'

• ANSWER (The ' lower porti~en of the contal rod barrel that extends below the water surface) has a series of holes that provide a dashpot action for the piston on the connecting rod (between the armature and the poison connecting rod). (1.0)

• REFERENCE General Atomic Reference Material CHAPTER C UARR FACILITY REFERENCE MATERIAL l

QUESTION B.10 What are the three (3) functions the water treatment system provides for the University of Arizona TRIGA reactor 7 (1.5)

• ANSWER

~

1. Reduce radioactivity in the water. (0.5)

2. Maintain low conductivity (f or corrosion protection). (0.5)

3. Maintain water clarity. (0.5)

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL GENERAL ATOMIC REFERENCE MATERIAL End of Section B Go on to Section C i

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Section C- i L

I -General Operating, Characteristics e

I

{.

'[ QUESTION- C.1 ,

What are the f ollowing' values f or the University of Arizona TRIGA-j

-reactors (2.0) ,

a.. Maximum SAFETY LIMIT steady state- power- level' (NOT licensed j power level). j b.- Overa11 ' steady state power coef ficient of reactivity.' ]

la

c. Excess reactivity presently loaded.

n b

d. Present Transient Rod worth._ Lj l

• ANSWER i

a. : 1000'kw (0.5) -

b. $ [CAF3.(0.5) (),(k$7'd/ / ,

c. $-[CAF3 (0.5) $2,61 " VM"O l

-d. $'2.48 [CAF]-(0.5) g,g") [y.p jo f}

1

• REFERENCE

' Chapter E UARR Facility Reference Material, Technical l Specifications. j 1

4 QUESTION C.2 i The reactor is operating steady state at high power when a large j air bubble passes up through the core. What effect(s) would this have on the reactor as the bubble rises through the core? (2.0) 4

• ANSWER The air bubble would displace moderator (0.5) and add negative ,

reactivity (0.5). Reactor power would decrease as the bubble  !

passed through the core (0.5), then increase once water replaces the air (0.5).  !

• REFERENCE GENERAL ATOMIC REFERENCE MATERIAL 1

)

g.-- -

, r h

I > ; 7,k.'i L

I QUESTION C.3-

What will you observe.on the' nuclear instruments to' determine lwhether or not'the reactor has. attained criticality?- (1.0L Y  :* ANSWER d

'The' reactor'is critical (actually a little super crit' ital) when the flux' level continues to increase with no further rod movement'. (1.0)

• REFERENCE GENERAL-PHYSICS ACADEMIC-PROGRAM QUESTION C.4 s i A :$2.00 pulse results in a 360 Mw peak pulse power and.12.0 i: Mw-seconds energy released.

..l

a. What is the. resultant peak pulse power in Mw if a $1.50 pulse is done? (1.0) s b.- What is the-resultant energy released in Mw-seconds from a

$2.25 pulse? (1.0)

• ANSWER

a. C$2.00 - $1.003 [$1.50 - $1.003

---

= ---------------- (0.5) 360 X e

LX = 360 * (0.5)~ (0.25)

.f X = 360

• O.25 .

-i l

X = 90 Mw (0.25) i t

i o b. .C$2.OO - $1.003 [$2.25 - $1.00] l

---

= --------------- (0.75' )

- 12 X X= 1.25

• 12 1

/

X = 15 Mw-seconds (0.25) 11 l

1

• REFERENCE UARR Requalification Examination May 24, 1985 l l

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ir l,

QUESTION C.5 How would each-of-the:following factors insertynegative -i reactivity-on a' prompt power increase such as a pulse L (3.0)

LM k , a. ZrH' disadvantage factor.

b. Doppler-effect

c. -Water displacement

• ANSWER

v. ~

a. ZrH disadvantage factor .f

.as temperature becomes less effective as a moderator.

raises the ZrH . (1.0) q

b. Doppler effects absorption cross. sections of resonance peal:s

~

i

broaden as temperature increases. (1.0) -

c. Water. displacements. water and-fuel- density decreases (f rom -

heating) and. fuel expands to' displace water which which j

decreases moderation. (1.0) 1

• REFERENCE GENERAL ATOMIC REFERENCE MATERIAL

. QUESTION'C.6 4 1 4

I How could the radiation level from an experiment sample be ]

greater'than one-half the original radiation level after-passage- i of-more than one half-life? (1.0) i l

• ANSWER

]

The parent. isotope decays to a radioactive daughter. ( 1. 0 ) : }

• REFERENCE i' Foster and Wright, Nuclear Engineering l

1 u

I l

.. ,/ .)!

4 s

l QUESTION C.7  !

JThe f ollowing questions relate to a control rod that is being.

pulled'from full in to full out,

a. 'How does the DIFFERENTIAL WORTH of a control rod vary with.

its: axial position in the core? < (1,0)

b. How does'the INTEGRAL WORTH of a control rod. vary with.its

-axial postion in the core? (1.0)

• ANSWER-

a. .It increases as it approches the center of the core, then decreases as it is pulled further out. (1.0) b.- .The integral worth is cumulative, and represents the worth 1 of the rod to that position. i.e. . full .IN = full worth. .

(1.0)

.

• REFERENCE GENERAL ATOMIC TRAINING MATERIAL QUESTION C.8 LYou have'Just brought the University of Arizona TRIGA reactor critical at a powewr level of 1' watt.

What effect on the reactor would you observe if you removed the source from its location? (2.0) 1

• ANSWER

< The reactor. is dependent at - low power levels. on . source neutrons to remain critical. (1.0)

The reactor will go subcritical and the power decrease (to source {

1evels). (1.0) i

• REFERENCE j GLASSTONE AND SESONSKE, NUCLEAR ENGINEERING l I

End of Section C Go on to Section D I i

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1 C_-______-___

, H m ,a l.

l Section D l Instruments and Control

)

QUESTION D.1 .

/

Answer'the following concerning the' nuclear instrumentation ]

calibration. l f

a. 'How is.the tank constant determined prior to the -]

calorimetric? (1.0)

b. ,Will changes to the pool water level affect the i determination of the tank constant? (YES ~ or NO) (0.5) j

c. How is the instrument system adjusted to agree with the i (0.5)  !

calculated core output?

• ANSWER

a. By'using an electrical heater and then calculating'the tank heat up rate (kw/deg/hr). (1.0)

'b. 'Yes. .0.5)

(  ;

c.- By positioning the detector. '(0.5)

• REFERENCE

'UARR125.  ;

OUESTION- D.2 .1 When in the pulsing mode various changes occur in the f unction of the instrumentation.

a.. What is recorded by the green pen on the chart recorder when in.the pulse mode? ( 0. 5)- l l

1

b. What is recorded by the red pen on the chart recorder when in the pulse mode? (0.5) 1 J

i

• ANSWER

.a. . Fuel temperature. (0.5)

Sh[L-

b. p Pulse power. (0.5) l

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL v

i

! OUESTION D.3' Which nuclear' instrumentation channel provides a control signal to the servo-controller for' automatic' control of the rpgul ating rod? I ( 1. 0) l .-

• ANSWER Linear power channel (1.0) eq d e, c

• V/ O .

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION D.4 What i s the appro>:imate normal count rate you would observe on

the Log Fower Channel when the reactor is cold subtritical?

(1.0)

• ANSWER b.

n

~w__

e_ .n e. (1.0) / -lt> [R /D w) A 5 &bCD>*

/

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION D.5 What parameter is measured to provide an indication of bulk water purity? (0.5)

• ANSWER conductivity (0.5)

• REFERENCE

. CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION D.6 Why is the location of the fuel element that contains the f uel temperature thermocouple in the B-ring? (1.0)

• ANSWER To insure a representative indication of the highest fuel temperature. (1.0)

• REFERENCE TECHNICAL SPECIFICATIONS

.. s . . .  : l

~

1 f

a.

' QUESTION .D.7 q_

What will happen to the regulating rod when the' reactor mode control Lis 1.n; automatic,' and the reactor- is at 50 kw, g f the i following or, cur??(Consider each casr separately.) t .

p.

~ a. ;The'gammaicompensating voltage for the Linear' Power channel '

L compensated ion chamber fails (goes to :ero). .

(1.0)

b. 'The period output from the Log Power channel provides a:+3 second period to the Flux regulator circuitry. (1.0)

• ANSWER

a. The regulating rod will. drive.in slightly to (adjust flux to I a now percieved' higher output.from th,e CIC). . ( 1. 0 )  !

In I' b. The regulating rod should eet move et all, (the p=H mM in wcil L 1 w., U ,- ,,,i mi r.um o f 10 scc;nd; tich it thc 1 ; ...10) . i (1.0)

-* REFERENCE I CHAPTER-C UARR FACILITY REFERENCE MATERIAL

-QUESTION .D.8- q l

~

For'each of the.following types of' neutron sensitive detetl tors, )

what-iu'the type cef neutron wensitve' materi al used in the ]j detector chamber?

a. Log Power Channel detector. (0.5)

]

b. Linear Power Channel detector.. (0.5) 1

c. Saf ety Channel detector. (0.5) -)

I

• ANSWER .j

a. Uranium'235 (fission chamber) (0.5) l i'

.b.. Baron (coating inside CIC) (0.5)

c. Baron (coating inside UIC) (0.5)

• REFERENCE Foster and Wright, Nuclear Engineering CHAPTER C UARR FACILITY REFERENCE MATERIAL l

l

OUESTION D.9  ;

The reactor console has a series of backlighted pushbuttons for the operation of the control rods.

What functicanlly occurs to cause the CONT /ON light for thd control rods to illuminate? ,.

(1.0)

• ANSWER i The magnet is on and the control rod aramture have made contact.

(1.0)

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION D.10  ;

~-

a. What device provides indication of flowrate through the demineralized? (0.5)

b. What is the maximum expected flowrate that you would observe when the demineralized is in operation? (0.5)

• ANSWER FIou)nekeV (0.5)

a. A.rctameters

b. 12 gpm. (0.5)

• REFERENCE  ;

CHAPTER C UARR FACILITY REFERENCE MATERIAL 'l QUESTION D.11 Why can the Percent Power channel use an Uncompensated Ion Chamber rather than a Compensated Ion Chamber? (1.0)

• ANSWER The gamma flux over the signal range (2% to 100+%) of the Percent Power channel is insignificant making compensation unnecessary.

(1.0) j i

• REFERENCE )

RADIATION DETECTION INSTRUMENTATION 1

End of Section D  ;

i Go on to Section E l

. _ _ _________a

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i OV b< Section E n

-Safety 1and Emergency Systems-f . l f QUESTION: ~E.1 <

When conducting pulsing operations: ..

Howiis theimaximum reactivity addition of'the transient rod physically limited?- (1.0)

-* ANSWER-I

'A p1'ug.(mechanical block) is. inserted to limit transient rod motion. (1.0) i i

• REFERENCE.  ;

CHAPTER C UARR. FACILITY REFERENCE MATERIAL g QUESTION E.2-  ;

I For ' the f ollowing backlighted : pushbutton control rod drive switch conditions:

What normal.or abnormal condition exists?

l

a. UP LIGHT -

OFF (1.0) ,.i DOWN LIGHT -

ON ,

. CONT /ON LIGHT --

DN

b. UP LIGHT -

OFF (1.0)

DOWN LIGHT -

.ON l CONT /DN LIGHT -

OFF

• ANSWER-a .- Normal , ' rod is at lower limit , -armature all the way down.

(1.0)

.b. Abnormal, red and drive completely down. (1.0)

• REFERENCE  !

GENERAL ATOMIC REFERENCE MATERIAL i

l 1

I 2:__-___-

-QUESTION E.3 Deside the two Safety Channel scrams, the manual scram, and the 110% Peak Power scram for the pulse mode, there are sir, other scrams associated with the reactor protection functioq.

What are those six (6) other scrams associated with re. actor protection? (3.0)

• ANSWER

1. Pool water level.

2. Magnet supply failure.

3. Safety channel switched to " calibrate" or "zero".

4. Power failure.

5. Earthquake.

6. Agustat t mer after pulse. (0.5 each)

'7 #/o ved. b A fl,\) , e e 5 c[.m es ,

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL QUESTION E.4 What are the two (2) interlocks associated with the Log Power Channe17 (2.O)

• ANSWER The reactor cannot be started up without at least 2 cps.

(TS >lcp) 1.-

(1.0)

2. The reactor cannot be pulsed if power is greater than i Kw.

(1.0)

• REFERENCE h&

CHAPTER C UARR FACILITY REFERENCE MATERIAL

l "3

. .m l6 of QUESTION E.5 i

.The Uni.versity.of. Arizona TRIGA react'or is determined by you to  !

be subcritical by;$0.30 with~one control rod stuck in gthe f ully.

L 1 withdrawn position. .

Why;is the the reactor not considered " shutdown" as d,e~ fined by ,

the Technical Specifications? (1.0) l I

r

• ANSWER The T. S. require that~the reactor to be " shutdown" must be shutdown'by more than-$4L4XA (1.0) ly 0

• REFERENCE T. S. 3.1'. a .

Jl QUESTION E.6  !

.7 Why in'the reactivity worth of removeable experiments limited to  ;

less'than $1.007 ( 1. 0 ) -

• ANSWER

'The sudden removal of an experiment of $1.00 or less will not- j violate any fuel temperature limits when the reactor is operating  ;

at full power. (1.0) l

• REFERENCE T. S. 3.1 Bases QUESTION E.7 .

What indication is provided, while operating the University of Arizona TRIGA reactor, that aids you in determining that a fuel element / cladding failure may have occured? (1.0) j I

• ANSWER j i

A radiation monitor (GM detector) is installed in the line  !

leading to the purification system. It alarms and providec  ;

indication at the console. The PAM may also alarm indicating the l prescence of particulate daughters of escaping fission products. l (1.0) i i

I

• REFERENCE CHAPTER C UARR FACILITY REFERENCE MATERIAL f i

r ,

l L  !

p

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kkh':- '

Jps -QUESTION E.8 g"%

^

~

. --Procedure;UARR104' states that the " normal" setpoint . f or ' the al arm on.the Continuous.. Air Monitor is'fu11-scale.(5' units)lwith.the.

. range-selectoriset to X.10. 4:

What count rate.does that represent?. .'- ( 1. 0 ) .

a'. . 1 i

b. .What immediate'actionsfmust you take'if.this alarm level is reached'during' operation of-the University of Arizona TRIGA' reactor? (2.0) ,

• ANSWER.

m .a. 50# ounts per' minute. (1.0)

'b. Scram reactor. .

( 0. 5). ,

7: Evacuate reactor' room. (0.5)  !

Window 1 fan off. (0.5)

,,U Stack fan on.. (0.5) 1

• REFERENCE

.UARR100 and UARR1041

. . l End of Section E Go on to Section F ,

i l

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4

Y + r' [ *]

(* >

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.s Section F-Standard-and' Emergency Operating Procedures 1

QUESTION F.-1: ,- .]

-l

When conducting pulsing operations

:?

n' .

u

/ 4 a.: What is.the--maximum reactivity addition' allowed?-

^

(1.0)'

1 i

What . is the maximum: permitted initial,. steady l state power f or

~

lb. '

'a: pulse'(less than. licensed steady state power)? (0.5)

.c. Why-is there a limit onithe power the reactor-can be at' prior to a' pulse? (1.O) -

1 1

• ANSWER- ..

2,$~b . ..

a.' Current limit i s - about $3,-tif ( which is experimentally derived based on max fuel.itemp. of 830 degrees C.) (0.5) b.

joW iho^ watts (1.0)

\

1 c.- The heat added by the pulse a power levels above the. limit .

'could exceed.the. design l evel s f or.' the- f uel .

(1.0) 1

• REFERENCE Technical Specifications'3.3 l I

-)

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~.0UESTION1 F.2-F ,

1 t

Answer-. True or False ' f or the f oll owi ng: ,

1

-a; lThemaximumexper,iment_ reactivity'which'maybe1kaded,into f

• 'the core at any given time shall not exceed $5.00.- (0.75)

b. All' fuel elements shall be' stored such.that Keff'is less than 0.9 under-all conditions of moderation. (0.75) c.- The scram time measured from the time a rod starts in motion to the time the red reaches a .f ully inserted position shall not exceed 1.2 seconds for the slowest standard control rod.

n (0.75)

.y' t

• ANSWER  !

l

a. .

(0.75) ,

. .I

c. False (0.75)- o j

l

. d. False

( 0. '7 5 ) - j 1

• REFERENCE. i LTechnical Specifications 3.1 I

n b

4 1

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n-L ,

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p

< QUESTION-- F.3' ,.

Regarding-the. Neutron Radiography Tubes j

a. .WHAT must be done IF the Neutron Radiography Tub is placed_

in -the storage ' position without the interior sheilding plugs in' place and it is desired'to operate'the reactore at power? '

(1.0) b.- Where are the sheilding plugs to be placed when.they are not in the Neutron Radiography-Tube? -( 1. 0)

• ANSWER

' ' - ' (1,Q)

'a' Th= h==- - -n muut ha 4 m ni - - - - e i GM5 +I'M Ge rpe fe d d3/3 55;e'ldfkh ["'pke t .

'b. More than three feet from the reactor pool. (1.0)

.:- i

• REFERENCE-UARR113 1

QUESTION' F.4 i

)

The following questions' apply to fuel inspection. f 1

Why is the instrumented f uel element (containing the fuel- j

a. -

-temperature thermocouple) not subject to the fuel j l

inspection requirements that apply to the standard fuel elements? (0.755

b. What other two-(2) fuel element types are not subject to the f uelf inspection requirements? (1.0) l

• ANSWER

a.

jncoSane &a.fyn .

.It cannot be pl:ced 4n +ha i n spmm t i cr. --- t eel to h ====' rad-(0.75)

b. Fuel f ollower elements f or the control rods, and the ')

I demountable f uel element. (1.0) r

• REFERENCE UARR121  !

l 1

l I

J

m- .

, -; ; - s b' 1

. l' ' if , i W.c l

,j l

, QUESTION 1 F. 5' -

i l

b j

i

-Whatiare the differences in_ control. rod manipulations and reactor-

~

power manipulations.for a steady state startup_to progeed to a . ]

' power / of ' 50 kw1versus a .startup f or pul sing operations? ( 1'. 0) - 1 1

l

• ANSWER ~

' During 's startup f or pulsing the transient . rod is not. used to l attain criticality:and. power isirestrictedLto 1 KW. (1.0)

• REFERENCE- )

.UARR100- ,

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' QUESTION F.6.

1

! . MULTIPLE. CHOICE.- CHOOSE THE BEST ANSWER Which of the f ollowing occurances is NOT an unusual Event?

(1.0) a.L ' A student. participating in an experiment while in the 'j

, Nuclear Reactor. Laboratory trips and suffers a severe cut i requiring medical aid. ]

i:

b. ?A fir'e.in:the-Engineering building immediately adjacent to

" --the Nuclear l Reactor Laboratory requires the assistance of-the Tucson Fire Department.

-c.- A' phoneJ caller with a v'oice of. flippant quality' states that.

la paperfsack in the-hallway outside the entry to the Nuclear-Reactor _ Laboratory.has a bomb in it. '!

1

d. .The water level in the reactor pool'is determined to be decreasing at.a. rate in excess of 10 centimetres an hour (100' gallons per minute)..

'

• ANSWER l

a.- - ( 1. 0 ) -

• REFERENCE

,. UARR101 l

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_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ._____.___1_

~ ~ - - ~ ~ - ~-^---- - -- ~~

g; :3T - ~- R 1 . m N_' _t'. -Q '.

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QUESTION: F.7  ;

'What three.(3)cconditions would require the reactor'to be shut. _

( 1. 5) ~

. down and the .deminerali::er turned of f ? {

• ANSWER ~- '

l

. ,\:,

. ' 1. 1 Release. of dission products f rom a f uel' element. . (0.5)

W :2. Dropping of"anLirradiated sample that is soluable into the reactor pool.. ,

-( 0. 5) .

3.- Pool. activity: exceeds water activity' monitor setpoint.

- ( O'. 5 ) .]

-s

• REFERENCE

, 4 , UARR100.pg.,1'O 7 >

f: , [ }

--QUESTION F.8 ,-J y '

- What are the three,(3); actions req'uired of the Reactor Operator: l if:the reactor room must be evacuated due to a.high alarm. j l

. indication on-an area radiation' monitor?

(1.5)

• ANSWER Direct personnel'in the reactor room to go into the-control room. l

- (O. 5) .' '!

ake the frisker'into the control room nd close the. j Interconnection'g door'.

(0,5)L l 1<

.' Frisk the : personnel f or removeable contamination. (0.5) j i

• REFERENCE UARR101 pg'13.

.I

., End of Section F

-l Go on to Section G l l

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.' 's o 1 Section G j i

Radiation Control and Safety -j

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QUESTION. G.1 l

What.are three (3) principle sources of low level' liquid radioactive waste at the University of Arizona TRIGA facility?

• ANSWER .<

'1. h

'2. Demineralized filter and ion exchanger bed. (0.5)

3. M e_[rnm s. W (CAF for other possibilities)- j

• REFERENCE 1 CHAPTER C UARR FhCILITY REFERENCE MATERIAL AND CAF QUESTION G.2 10 CFR'2O_ specifies.the maximum doses that a radiation worker.can recieve.-

I What are the allowable dose per calendar quarter for each of. the following? i

-a. The whole body. (0.5) l (0,5) '

b. The hands and feet.

c. 1The skin of the whole body. (0.5)

• ANSWER a.- 1.25 Rem (0.5)

b. 18.75 Rem (0.5)

I

c. 7.5 Rem (0.5) l

• REFERENCE UA Requal Exam May 14, 1986.

1 I

8

{ '.

QUESTION G.3 The production of radioactive gasses due to neutron activation of dissolved air and water is a potential hazard from the operation of a TRIGA reactor. {

a.- What radioactive gas is produced from neutron activation of the reactor coolant'(water)7 (0.5)

b. What radioactive gas is produced from neutron activation of (0,5) dissolved air in the reactor coolant?

• ANSWER

a. Nitrogen 16 (0.5)

b. Argon 41 (0.5)

• REFERENCE GENERAL ATOMIC REFERENCE MATERIAL QUESTION G.4 MULTIPLE CHOICE - Select the correct answers.

Which of the following types of radiation will be e>tpected at the Neutron Radiography Tube when operating at power? (More _ th an one answer possible.) (1.0)

a. Fast neutrons.

b. Slow neutrons.

c. Beta particles.

d. Gamma radiation.

e. Alpha particles.

• ANSWER

a. , b. , and d. (3 at 0.33 each)

• REFERENCE RADIATION-HEALTH HANDBOOK

if  % -..

, 5 N' $-

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. QUESTION G.5 MULTIPLE CHOICE - SELECT THE BEST ANSWER JA point source of gamma radiation measures'32.R/hr at a distance

< of 2-feet.

'Which of the .f ollowing is the best estimate of the ra'diation dose rate from the gamma' source at a distance of 16 feet? . ( 1. 0 )

. a. -500 R/hr

b. 2 R/hr c.- 1000 mR/hr d.' 500 mR/hr

• ANSWER

d.- -(Dose. rate inversely proportional to distance squared.)

~

( 32 R/hr ) ( 2/16.)E2 = 32-* 1/64 .= 500 mR/hr

• REFERENCE STD Time, Distance, Shielding calculation I

QUESTION G. 6' Two terms' describe the nature of the elimination of a' radioactive nuclide that a. person may have~ ingested into his body. Those {

terms are: Bi ol ogi cal Half-life and Effective Half-life.

What is the distinguishing difference between these two terms?

(1.0) ]

i

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• ANSWER-

't The' ef f ective half-lif e includes the biological elimination of )

the nuclide AND radioactive decay of the nuclide. The biological J half-lif e concerns only natural elimination. (1.0)

• REFERENCE WJE 297 l

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' QUESTION'. G . '7 .

l AssumingLa point' source.of radiationss I

What three (3): factors can you utilize ~to minimize the dose you ,

could receive f rom' a source of radiation? -(1.5) i

~*A'NSWER-i 1.- Minimize, time of-exposure. (0.5) a

2. Maximize distance from source. (0.5) {

.3. Provide shielding from source. (0.5)

(Will accept Time, Distance, Sheilding for full credit.)

• REFERENCE BASIC RADIATION' PROTECTION, RADIAT. ION PROTECTION HANDBOOK i i

i l'  !

QUESTION G.8 MATCHING a

. Match-a-Quality Factor to each Radiation Type. (Each DF-may be.

used more than once-or not at all) Consider ONLY EXTERNAL exposure. ' (3. O) ~

a '. - Gamma, rays. 1. 20

b. Thermal Neutrons. 2. 15 c.- Fast' Neutrons. 3. 10

,; 'd. . Alpha particles. 4. 2.3 2

_i e. X-rays. 5.

d. Beta particles. 6. 1

7. O

• ANSWER 3;

a. 6

.,. :b. 4 Y c. 3 j!:

. d, 7 or I he 4+t 'h

.6

'e.

f. 6 (0.5 each)

• REFERENCE

l. BASIC RADIATION PROTECTION, RADIATION PROTECTION HANDBOOK i

10CFR2O l

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'Y g.,',

QUESTION G.9 You are using a beta-gamma survey instrument to check a samrie recently retrieved f rom the rabbit terminus. A window ppen reading shows 12 mR/hr, and with the window closed thel reading is 8 mR/hr. The instrument has a beta corection factor of< 4.5.

What is the TOTAL dose rate at the surface of the sample? (2.0)

• ANSWER gamma = 8 mR/hr (0.5) beta = (W.O. - W.C.)

• BCF (0.75) beta = ( 12 - B )

• 4.5 = 18 mR/hr (0.25)

total = 18 + 8 = 26 mR/hr (0.5)

• REFERENCE HEALTH PHYSICS HANDBOOK QUESTION G.10' When you are handling samples "emoved from the Lazy Susan after irradiation there are some precautions you must take to reduce exposure.

a. How must the finger ring dosimetry be worn when handling radioactive material? (0.5)

b. How can reduce raoiation exposure to your hands and forearms when handling radioactive samples? (0.5)

• ANSWER

a. With the radiation sensitive side toward the material. (0.5)

6. Use of tongs to handle the sample, minimize time of handling. (0.5) i

• REFERENCE UARR FACILITY REFERENCE MATERIAL UARR110 End of Section G End of Examination