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Exam Rept 50-113/OL-88-01 on 880411.Exam Results:Candidate Passed Written Exam Covering Section G,Radiation Protection & Granted Waiver for Operating Exam & Balance of Written Exam
	ML20154G025
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Site:	05000113
Issue date:	04/29/1988
From:	Elin J, Johnston G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
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i Examination Report' No. 50-113/0L-88-01

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Facility:

University of Arizona Resear h Reactor '

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Docket No.

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Examinations administered. fat University of Arizona' TRIGA reactor, Tuscon,-

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Arizona.

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Chief Examiner:

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Gary, J/5hns1/Tn

6 D7te gied Operat Licensing Examiner 3

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, q Summary:

Examination on Aprd 11,1988.(ReportNo.50-113LOL-88-01)

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A written examination covering Section G Radiation Protection, was given to one candidate. The candidate passed the examination. The candidate had reapplied and was granted a waiver of the operating examination and the balance of the written examination.

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l REPORT DETAILS i

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Examiner:

G.Johnston,R'I(ChiefExaminer) r s

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Persons Attending the Exit Meeting:

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,7Q G. Johnston, RL J, i.edford, UA 3.

Written Examination and Facility Review:

The writteri examination was administered to one candidate on l

April 11, 1988.

l At the conclusion of the examination, the facility staff member was given copies of the written examination and the answer key for review.

No substantive coments were proffered other than minor coments about question structure. Therefore no resolution of coments was deemed necessary. The facility's comments will be used to correct the key l

prior to uploading the examination to the Examination Question Bank.

4.

Exit Meetingi i

The examiner met briefly with the facility representative denoted in Paragraph 2 on April 11, 1968. The examiner discussed the examination procen, including the forwarding of coments for the examination.

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.s' U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR I.ICENSE EXAMINATION OWCC C Facility:

University of Arizona g

Reactor Type:

TRIGA Mk. 1 Date Administered:

April 11, 1988 G

Examiner:

cary W. Johnston Candidate:

INSTRUCTIONS TO CANDIDATE Use separata 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 at least 70% in each category.

Examination papers will be picked up six (6) hours after the examination starts.

Category % of Candidate's

% of

_Value Total Score Cat. Value 15.0 100 G.

Radiation Control and Safety Final Grade All work done on this exam is my own.

I have neither given nor received aid.

Candidate's Signature i

1

, G EQUATION SHEET f = ma y = s/t 2

w = mg a = v,t +,Iat Cycle efficiency = _ Net Work (out) s E = aC Eng W

.a - (vI v )/t.

2 KE = lsmv "'

'v

-At f = v '+? at A = AN A = A,e o

PE = agh w = e/t A = In 2/tg = 0.693/tg W = v4P

~J-g(eff) = Teg)-(eg}--

AE = 931Am t

-(g

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V Q = m,C AT i

t. 7.4X P

Q = UAAT

. o --

.y y

ux Pwr = W a

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g r.7 t0

P=P 10SUR(t) '

TVL = 1.3/p ve.j.;.) ";t/T "

gyt.'O.693/u s..

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SUR*='.26.06/T

[=1.44'DT SCR = S/(1 - K,ff) fA 0

SUR = 26 f

CR

= S/(1

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A T = '(1*/p ) +

[(i i p)/x p}

CR (1 - Ke f f) 3 = C'.:2 (1

Keff)2 y

7. t*/ (p _ py M = 1/(1 - K,gg) = CR /CR g

0

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~ 0}! eff" M = (1 - Kef )C (1 ~ Keff)1

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8 " ( eff-1)/Eeff = AK,gfMeff SDM = (1 - Y f)/K,fg

[ L*/TK,gg ] + [B/(1 + 1,gg )]

t* = 1 x 10 seconds a=

T

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P = I$V/(3 x 10 0)

A,gf = 0.1 seconds

~

E = No Idgl"Id22 WATER PARAMETERS, Id =1d g

22 1 gal. = 8.345 lbm 2

R/hr = (0.5 CE)/d g,,t,,,)

1 gal. = 3.7B liters 3

R/hr = 6 CE/d'(feet)

I ft = 7.48 gal.

MISCELLANEOUS CONVERSIONS, Density = 62.4 lbm/ft3 1 Curie = 3.7 x 1010dps Density = 1 gm/cm 1 kg = 2.21 lbm Heat of varori:ation = 970 f tu/lbm I hp = 2.54 x 103 BTU /hr Heat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 106 Btu /hr i Atn = 14.7 psi = 29.9 in. Ig.

I Btu = 778 fc.lbf 1 ft. H O = 0.4333 lbf/in 2

1 inch = 2.54 cm T = 9/5 C + 32 C = 5/9 ( F - 32)

SECTION G Radiation Control and Safety

QUESTION G.01 (2.5)

You are operating the fuel handling tool over the reactor pool during refueling operations, a SRO is with you by the pool. Both of you have just started to work (time 0). The SRO is 48 years old and has a total lifetime occupational dose of 100 Rem. You are 20 years old and have not received any occupational exposure to radiation over the present calendar quarter. You and the SRO are the only persons in the reactor room. All area radiation monitoring equipment is, unknown to you, out of service. The radiation level is a steady 10 Rem /hr.

I a.

How long can you remain (in hours) on the refueling platform without exceeding your 10CFR20 whole body quarterly exposure limit? (show all work!)

(0.5 for application)

(0.25 for value) (0.75) b.

How much radiation (Rem) can the SRO receive before exceeding his 10CFR20 lifetime limit for occupational exposure?

(Shcw all work!)

(0.75 for application)

(0.25 for value)

(1.0) c.

What is the name of the program outlined in 10CFR20, that must be implemented for the reactor facility, that would not have allowed you to work in the conditions described above?

(0.75)

(Answers on following page.)

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ANSWER G.01 (3.5) a.

Application:

time = 1.25 Rem /10 Rom per hr.

(0.5)

(or with NRC form 4 : 3 Rom / 10 Rem /hr)

Value:

I time = 0.125 (+/-.01) hours (7.5 min.)

(0.25) l (or NRC form 4 : 0.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months (18 min.})

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b.

Application:

exposure limit = 5 x (N - 18) Rem (0.25)

= 5 x (48 - 18) Rem (0.25) exposure left = 150 - 100 Rem (0.25)

Value:

exposure left = 50 Rom (0.25) c.

ALARA (As Low As Reasonably Achievable)

(0.75)

REFERENCE 10 CFR 20.101 s

QUESTION G.02 (1.5)

The damaging effects of ionizing radiation on tissue, at the same given energy level, varies depending on the type radiation.

Therefore, 10CFR20 specifies a Quality Factor (QF) must be applied to a given dosage in "Rads" to determine the equivalent biological damage in "Rem". The QF for (fast) neutron radiation is 10.

What is the QF for gamma type radiation?

(0.5) a.

b.

What is the QF for alpha type radiation?

(0.5) c.

What is the QF for beta type radiation?

(0.5)

ANSWER G.02 (1.5) a.

1 b.

20 1

c.

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REFERENCE 10CFR2 0. 4 (c) (2),

10CFR20. 4 (c) (4 )

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QUESTION G.03 (0.75)

MULTIPLE CHOICE (Select the correct response)

Which of the following correctly describes beta type radiation?

Radiation that has more penetrating power than fast neutron a.

radiation, b.

Radiation that is usually classified as having a positive

charge, Radiation that has less penetrating power than gamma c.

radiation.

d.

Radiation that is usually classified as having a neutral charge.

ANSWER G.03 (0.75) c.

REFERENCE Radiation Health Handbook

QUESTION G.04 (0.75)

MULTIPLE CHOICE (Select the correct response)

Which of the following correctly describes alpha type radiation?

Radiation that has more penetrating power than fast neutron a.

radiation.

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b.

Radiation that is usually classified as having a positive charge.

Radiation that has more penetrating power than gamma c.

radiation.

d.

Radiation that is usually classified as having a neutral l

charge.

ANSWER G.04 (0.75) b.

REFERENCE Radiation Health Handbook l

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QUESTION G.05 (1.0)

You are handling an experiment in the reactor room and nust work near an area radiation monitor located 5 feet from a point

-nource. The reading at the monitor is 100 mrem /hr from the point source alone. The point source is moved 2 feet further away.

What is the new dose rate (mrem /hr. ) at the area radiation monitor?

(0.75 pts for application)

(0.25 pts, for value) (1.0)

ANSWER G.05 (1.0)

Application:

R2 = R1 (D1/D2) ^2 (0.5) i R2 = 100 mrem /hr x (5/7)^2 (0.25)

Value:

R2 = 51 (+/- 1) mrem /hr at 7 f t.

(0.25)

REFERENCE Radiation Health Handbook I

QUESTION G.06 (1.5)

Attached Figure G.06 is an illustration of the floor plan of the U of A TRIGA Reactor Facility. The general background radiation levels are indicated for the Reactor room. 10CFR20 requires specific types of "CAUTION" signs for each area containing radioactive materials or presenting a radiation hazard, j

What must the "CAUTION" sign read that is hung over the a.

reactor pool?

(0.5) b.

What must the "CAUTION" sign read that is posted on the reactor room door?

(0.5)

What must the "CAUTION" sign read that is posted on the c.

storage area containing radioactive sources?

(0.5)

ANSWER G.10 (1.5)

(CAUTION / DANGER) HIGH RADIATION AREA (>100 mrem /hr)

(0.5) a.

b.

(CAUTION / DANGER) RADIATION AREA (5 mrem /hr or 100 mRom/5 days)

(0.5) c.

(CAUTION / DANGER) RADIOACTIVE MATERIAL (S) (10 times Appendix C levels)

(0.5)

REFERENCE 10 CFR 20.203

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QUESTION G.07 (1.0)

When would you be required to wear a finger ring dosimeter? (1.0)

ANSWER When handling radioactive material shields) with dose rates in excess o(samples or neutron absorbing inch).

f 5 mrem (at a distance of 1 (1.0)

Partial credit:

When handling radioactive materials.

(0.75)

REFERENCE UARR 110 Pg.

2, Irradiation Procedure e

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QUESTION G.08 (1.0)

During normal operation of the University of Arizona TRIGA reactor radioactive Nitrogen-16 gas is produced.

What is the source of the Nitrogen-16?

(0.5) a.

b.

Where is the Nitrogen-16 produced?

(0.5)

ANSWER a.

Conversion of Oxygen-16 (n,p reaction).

(0.5) b.

The water (H2O) in the reactor pool (and experimental facilities (lazy susan, rabbit)).

(0.5)

REFERENCE UARR Reactor Description pgs. 20 to 24.

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QUESTION G.09 (1.0)

The survey instrument used for personnel frisking at the University of Arizona Research Reactor is an RM-14 using a Geiger-Mueller detector. Why is the detector used for the purpose of frisking personnel a Geiger-Mueller type rather than an ionization chamber?

(1.0)

ANSWER The G-M detector is used to provide a sensitive detector of the presence of radioactive contamination, not for determining the l

i dose rate.

(1.0)

REFERENCE Radiation Health Handbook l

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QUESTION G.10 (1.5) l During the removal of a sample from its lazy susan capsule an experimenter spills the dry powdered contents, activated sodium bicarbonate (NaHCO3), on the floor of the reactor room. A selected portion of the ' Chart of the Nuclides' is included on the following page.

How long would it take for the material, considering only the activation product of sodium (Na-24), to decay away to less than 2% of it's original activity?

(1.5)

ANSWER A = Ao^e-(lambda)t (0.75) lambda = In 2/t1/2 = 0.693/15.02h = 0.0461 h^-1 (0.5) 0.02 = (1)e^-0.0461(t) ;

in (0.02) = -0.0461(t) t=

In (0.02)/-0.0461 = -3.912/-0.0461 =

= 84.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (+ or - 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months )

(0.25)

REFERENCE Reference Sheet, Radiation Health Handbook, Chart of the Nuclides.

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QUESTIOli G.11 (1.5)

There are four specific instructions for the uso of the Friskor.

a.

What scale (i.e. X1, X2, X10, X100 etc.) must the Friskor be set to prior to use?

(0,5) b.

What part of the body do you check first?

(0,5)

What do you do if you detect some counts just above c.

background (50 counts per second above)?

(0,5)

AliSWER a.

X1 (0.5) b.

Hands.

(0.5) c.

Report to the Senior Operator.

(0,5)

REFERE! ICE Posted liotice 11/2/81.

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QUESTION G.12 (1.0)

Concerning 10CFR20 exposure limits; What is the 10CFR20 quarterly exposure limit (Rem) for the a.

skin of your whole body?

(0.5) b.

What is the 10CFR20 quarterly exposure limit (Rem) for your hands and forearms?

(0.5)

ANSWER a.

7.5 Rem (0.5) b.

18.75 Rom (0.5)

REFERENCE 10 CFR 20 END OF SECTION G END OF EXAM

ML20154G025

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