ML20153E789
| ML20153E789 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 04/21/1988 |
| From: | Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Bragdon P REED COLLEGE, PORTLAND, OR |
| References | |
| NUDOCS 8805100110 | |
| Download: ML20153E789 (24) | |
Text
. _ . ._ _ _ . .. . --
April 21,-1988 f Docket No. 50-288-Reed College !
Portland, Oregon 97202 f Attention: Dr. Paul Bragdon, President i
Gentlemen:
SUBJECT:
FXAMINATION REPORT ,
On March 25, 1988 the NRC administered a first' retake examination'to a member- !
of your college who had applied for a license to operate your Reed Reactor l Facility. At the conclusion of the examination on March 25, 1988, the i examination process and associated licensing issues were discussed with those i members of your staff identified in the enclosed report. -!
In accordance with 10 CFR 2.790(a), a copy of this. letter and enclosures _(1) y and (2) will be placed in the-NRC's Public Document Room. The results for ;
the individual applicant are exempt from' disclosure by 10 CFR 2.790(a)(6). j Therefore, enclosure (3) will not placed the NRC's Public Document Room. i Should you have any questions concerning this examination, please contact i Mr. Thomas Meadows at (415) 943-3867. .
Sincerely, a t
i l t
/5 i Robert J. Pate, Chief :
Operations 8 ranch
Enclosures:
- 1. Examination Report No. 50-288/0L-88-01 l
- 2. ExaminationsandAnswerKeys(SR0/R0) :
- 3. Grade Summary Report i i
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8805100110 880421 -l PDR ADOCK 05000288 V DCD ;
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Dr. Paul Bragdon 2 April 21, 1988 ccw/ enclosures (1),(2)and.(3):
Larry Ruby, Director, Reed Reactor Facility, cc w/ enclosure (3) only:
Janet Lanning, Management Assistant, NRR/LOLB cc w/ enclosure (1) only:
J. Hannon, Branch Chief, OLB
[ J. Martin, RV D. Kirsch, RV
! R. Pate, RV l J. Elin, RV T. Meadows, RV H. Berkow, NRR/PDSNP C. Thomas, NRR/PDISA H. North, RV M. Cillis, RV R. Cross, RV (2 copies) ccw/englosures,(1)and(2)only:
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- , KEY
'. Kt: 1, V.-S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Reed (Research)
Reactor Type: TRIGA Date Administered: 3/25/88 _
Examiner: Thomas R. Meadows Candidate:
INSTRUCTIONS TO CANDIDATE
' Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sr.eets. Points for each question are indicated 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
_ A. Principles of Reactor Operation B. Features of Facility Design C. General Operating Characteristics D. Instruments and Controls E. Safety and Emergency Systems F. Standard and Emergency Operating Procedures 15 100 G. Radiation Control and Safety 15 Final Grade %
All work done on this exam is my own. I have neither given nor rectived aid.
Candidate's Slgnature a rc- / t ur w i . L c-
~
- . k- '
S ES-201-1 Enclosure 2 l ATTACHMENT 1 (continued) !
Enclosure 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN 1.
'A single room shall be provided for completing the written examina .
as to prevent contact with all other facility during the duration of the written examination.
c and/!
t motel, or other building.should make arrangem1nts for the use of j the licensee. Obtaining this room is the responsibility of , j 2.
by the chief examiner. Minimum spacing is required toe ensure ex with a 3-ft space between tables. Minimum spacing should be one candidate p No wall charts, models and/or other training materials shall be present in the examination roo,m
- 3. .
Suitable arrangements shall be made by the facilitya ifesthe to have lunch, coffee, or other refreshments. are candid t comply with Item 1 above. These arrangements shall examiner and/or proctor. These arrangements shall be reviewed by the -
4.
The facility staff shall be provided a copy of the written on and examinati examination.
answer key after the last candidate vide formal written comments with supporting documentation on has encomple tion and chief. answer key to the chief examiner or to the regional m na- - offi ce section 5.
The facility licensee shall provide pads of 8-1/2 .by 11 in lined paper in The examiner shall distribute these pads toon.the candid examiner.
All reference material needed to complete the examination s into the examination room, and no other equipment or reference m e
s shall be allowed. a erial 6.
Only black questions. ink or dark pencils should be used for writing o answers t l
i Examiner Standards 2_ -
, . -s ES-201-1 Enclosure 2 a ..
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 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.
1 Print your name in the blank provided on the cover sheet of the examination.
5.
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 each -
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.
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.
Show all calculations, methods, 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 00 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 yourthe completing own and you have not received or been given assistance in examination.
been completed. This must be done after the examination has Examiner Standards
.T , .. _-.
A ES-201-1 Enclosure 2 ,
a '
18.
When you complete your examination, you shall:
- a. Assemble your examic on as follows:
(1) Exam questions on top.
(2) Exam aids I figures, tables, etc.
(3) Answer pages including figures which are a part of the answer. ~
7 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 paper that you did not use for answering the questions.
d.
Leave the examination area, as defined by the examiner.
leaving If after in progr,ess, your license may be denied or revoked.you are found in o
- I s
l 1
Examiner Standards
i s
ES-201-1 I Enclosure 3 i l
9 e ATTACHMENT 1 (Continued)
Enclosure 3 Requirements for Facility Review of Written Examination .
- 1. .There shall be no review of the written examination by the facility staff
'before or during the administration of the examination. Following the administration of the written examination, the facility staff shall be '
provided a marked-up copy of the examination and the answer key.
- 2. The facility will have five (5) working days from the day of the written examination is given to provide formal comment submittal. The submittal ,
will be made to the responsible Regional Office by the highest level of corporate management for plant operations, e.g. , Vice President for Nuclear l Operations. A copy of the submittal will beforwarded to the chief examiner, as appropriate. Comments not submitted within five (5) working days will '
be considered for inclusion in the grading process on a case by case basis by the Regional Office section leader. Should the comment submittal dead-line not be met, a long delay for finalization of the examination results ,
may occur.
~3.
The following format should be adhered to for submittal of specific I comments: "
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- a. Listing of NRC Question, answer and reference.
)
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- b. Facility comment & Evaluation
- c. Supporting documentation ..
NOTES: 1. !
No change to the examination will be made without submittal of complete, current, and approved reference material, l l
- 2. Comments made without a concise facility recommendation will not be addressed.
I i
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Examiner Standards
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' EQUATION SHEET f=m v = s/t w = mg s = v,t + lsat 2 Cycle efficiency = liet Work (out) '
Energy (in)
E = mC' a = (vg - y )/t -
KE = b v f=vo +a A = AN A=Aeg
~
E PE = mgh w = 0/t A = In 2/tg = 0.693/t g W = vaP AE = 931am eq (eff) = (t,:)(ts)
( ,,)
Q = $C ST -fX
, P , I=Ieo Q = UAAT I.Ie-UX Pwr = W' g $
~
I=I 10-x/TVL P=P 10 SUR(t)
TVL = 1.3/u t
P=P e o HVL = 0.693/u
'SUR = 26.06/T ~
T = 1.44 DT
/A
- SCR = S/(1 - Kgg) ,
SUR = 26 gf',o) CR = S/(1 - K gg )
7 * '(1? /o ) + {(g _.' p ) f x g,p] 1(
~
eff}l " 2(l ~ Keff)2 ^
T = t*/ (p _ p) H = 1/(1 - K,,g) = CR /CR '
g
" 0
~# 0 eff p = (K M = (1 - Keg,)0 (1 ~ eff)1 eff -1)/Keff = AKeff /K eff SD>i = (1 - K,gg)/Keff ' / ~ ##*##
p= ~
[1*/TKygg .] + [H/(1 + A,ggT )] _
t* = 1 x 10 seconds P = E4V/(3 x 1010) 3 '
E = No eff = 0.1 seconds Idgg=Id22 WATER PAPRfETERS Id g =Id2 1 gal. = 8.345 lba 2 1 gal. = 3.78 liters R/hr = (0.5 CE)/d (meters)
R/hr = 6 CE/d (fect)
I ft = 7.48 gal.
MISCELLANEOUS CONVERSIONS Density = 62.4 lbm/ft 3 y 1 Curic = 3.7 x 1010d p s /. 7 "O ##
Density = 1 gn/cm 1 kg = 2.21 lbm Heat of va}orizationi = 970 Etu/lbm I hp = 2.54 x 10 BTU /hr Heat of fusica = 144 Btu /lbm 6 1 N = 3.41 x 10 Btu /hr 1 Atm = 14.7 Psi = 29.9 in.1 3 1 BLu = 778 ft-lbf I ft. H yo = 0.43D lbf /in 1 inch = 2.34 cm F = 9/5 C + 32 "C = 5/9 ( F - 32)
g .
Y SECTION G Radiation Control and Safety
- QUESTION G.01 (3.0)
You are operating the fuel handling tool over the reactor pool during refueling operations. Your shift SRO is with you by the pool, verifying the storage spent fuel. Both of you - have -j ust started the shift (time into shift: is O seconds). Your shift SRO is 48 years old.and has a total lifetime occupational dose of 100 Rem. You are 30 years old and have not received any occupational exposure to radiation over the present calendar quarter. Due to a management error, both of you took the. shift without a shift turn over, and are the only persons in the reactor building. All area-radiation monitoring equipment was placed out of service by gross calibration errors last shift. The background radiation level is ;
a steady 10 Rem /hr. The 10CFR2O whole body quarterly exposure ,
limit is 1.25 Rem.
- a. How long can you remain (in hours) on the refueling
! platform without exceeding your 10CFR2O whole body quarterly exposure limit? (Show all work!) (0.5 for application)
(0.25 for value) (0.75) ,
- d. How much radiation (Rem) can your Shift SRO receive before exceeding his 10CFR2O lifetime limit for occupational exposure? (Show all work!) '(0.75 for application)
(0.25 for value) (1.0)
- e. What is the name of the program required by 10CFR20, to be !
implemented at Reed Reactor Facility, that would not have j allowed you to work in the conditions described above?(0.25) l l
(see next page for answer key) l 1 l L
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- ANSWER G.01'(3.0)
- a. Application:
time = 1.25 Rem /10 Rem-per hr. (0.5) l Value:
time = 0.125 (+/- .01) hours (7.5 min.) (0.25) b.- 7.5 Rem :(0.5) ,
- c. 18.75 Rem (0.5)
- d. Application:
exposure limit = 5 x (N - 18) Rem (0.25) l
= 5x (48 - 18) Rem (0.25) exposure'left = 150 100 Rem (0.25)
Value:
exposure left = 50 (+/- 2) Rem (0.25)
- e. ALARA (As Low As Reasonably Achievable). (0.25)
- REFERENCE 10 CFR 20; 4 ,
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-* 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, a Quality Factor (DF) must be -applied to a given dosage in "Rads" to determine the equivalent biological damage in.
"Rem". The OF for (fast) neutron radiation is 10.
- a. What is the OF for gamma type radiation? (0.5)
- b. Wha t is the QF f or alpha type radiation? (0.5)
- c. What is the QF for beta type radiation? (0.5) i
,
- ANSWER -
G.02 (1.5)
- a. 1
- b. 20
- c. 1 tREFERENCE !
Reed Training Manual, Chapter 2, pp. 2-3:
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- s 0
- OUESTION
.G.03 (0.75)
MULTIPLE CHOICE (Select the correct' response)
Which of the following correctly describes beta type radiation?
- a. Radiation that'has,more penetrating power than fast neutron radiation.
- b. Radiation that is usually classified as having a positive charge.
- c. Radiation that has less penetrating power than gamma' ,
radiation. '
- d. Radiation that is usually classified as having a neutral charge.
- ANSWER G.03 (0.75) c.
tREFERENCE Reed Training Manual, Chapter 1, pp. 7; i
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- QUESTION G.04 (0.75)
MULTIPLE CHOICE (Select the correct. response)
Which of the following correctly describes. alpha type radiation?
- a. Radiation that has more penetrating power than fast neutroit radiation. ,
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- b. Radiation that is usually classified as having a' positive charge.
- c. Radiation that has more penetrating power than gamma radiation.
- d. Radiation that is usually classified as having a neutral charge.
- ANSWER G.04 (0.75) 6.
- REFERENCE Reed Training Manual, Chapter 1, pp. 16-18; j
b.
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- QUESTION G.05 (1.0)
You are assisting with an experiment in the reactor room and must work on the RAM located 5 feet from a point source. The reading at the RAM 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 RAM 7 (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)
R2 = 100Meem/hr x (5/7)^2 (0.25)
Value:
R2 = 51 (+/- 1) Mrem /hr at 7 ft. (0.25)
- REFERENCE Reed Training Manual, Chapter 2, pp. 20-28; ;
6
a
- OUESTION G.06 (2.0)
You are irradiating afspecimen in the Chemistry lab. The radiation source that you are using is a sample from the reactor, that is kept in a shielded container mechanism fitted with an open window. The source is transmitting a cattgts beam of 0.1 Mev gamma radiation at a. negligible distance from the specimen. You would like to reduce the beam's intensity by 10% using an Aluminum shield. Using the equation sheet provided with this examination, and Figure G.06 (Attached):
- a. What is the thickness (cm) of the required aluminum shielding? (Show all work!)
(1.0 pts. for correct application)
(0.25 pts. for correct value) (1.25)
- b. Which one(1) of the substances listed on Figure G.06 would make the most effective radiation shielding (in terms of reducing personal exposure) for O.1 Mev gamma? (0.75)
- ANSWER G.06 (2.0)
- a. Application:
I =,f,o e^-ux (0.25)
, p berc = e^-(0. 435 cm^-1) (x cm) (0.25)
I nPP - In10 = In[e^-0.435(x)] (0.25) 24 Ar- 2.3 = .435x (0.25)
Value:
0./J t = Jrff (+/- O.1) cm (0.25)
- 6. Pb (l ead ) (0.75)
(relationship between density and attenuation) 4 REFERENCE Reed Training Manual, Chapter 2, pp. 20-28:
, . ~ . - -, ,--
- , - . a nn w , , . . -,- - , . , , ,,--y, - - , , , , ,
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. .4 Linear Attenuation Coefficients, CM'I ,
Quantum Energy, MeV 3
o, g/cm 0.1 0.15 0.2 1
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C 2.25 0'.335 0.301 0.274 Al 2.7 0.435 0.362 0.324 Fe 7.9 2.72 '
1.445 1.090 Cu 8.9
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3.80 1.830 1.309 a
Pb 11.3 59.7 20.8 10.15 1.29 x 10 -3 Air -
1.95 x 10 " 1.73 x 10 " 1.59 x 10' HO {
2 1 0.167 0.149 0.136 l Concrete 2.35 0.397 0.326 0.291 1
4 l'.
F i s c/ A E . G, O f I
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- QUESTION G.07 (0.75)
You have counted an air sample filter that was just obtained from the Reactor room. You are using the Ludlum MODEL 177 ratemeter with the hand monitor attachment to obtain your data. To be conservative, the Reactor Director wants you to assume that all of the airborne contamination in the Reactor room is due to insoluble Iodine 131 (I-131) isotope. Using the attached Figure G.07 (10CFROO Appendix B):
- a. What is the 10CFR2O airborne contamination limit for insoluble I-1317 (0.25)
- b. How many hours por week working period does 10CFR2O assume for the airborne contamination limits specified on Figure G.07? (0.5)
- ANSWER g G.07 (0.75)
- a. 3x 10^-7 uCi/ml (f rom Figure G.07, 10CFR2O Appendix B Table I) (0.25)
- b. 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (0.5)
- REFERENCE Reed Training Manual, Chapter 1, pp. 13-14; 10CFR2O i
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- o. / xid " : - %-lY = [p.,gj~)
(pesoerazowa>FM &
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Nuclear Regulatory Commission Part 20, App. B APPEN0lX B--CONCENTRATIONS IN AIR AND WATER A90VE NATunat. BACKGR -
(See footnotes at end of ApperJu R1 .
Isotope
- Table i
- Table II Dement (atornic number)
Col 1-AJr M 2- Col 1- Air Col 2-haQ/mQ *'
([C m0 D'U#8'd) g loone (53) I125 S 5 x10** 4 x 10-8 ax10.n 2x 10*8 1 2x 10" 8 x10" ex10*' 2x10" 1128 5 8 x10** 5 x 10*
- 9 x 10*" 3 x10-'
- 1 3 x10*' 3 x 10*' 1x10 e 9 x t0" 1129 S 2x10**
l 1 x 10*
- 2x 10*" 8 x10"
- 7x 10-' 8 x 10*
- 2x10" 2 x 10-*
8131 S 9 * -"
8 x 10*
- 3 x10" I 2x10** g.
1132 S 1 x10" 8 x 10* *
- 0-' 2x10-8 4 x10-*
I 9 x 10-' 5 x 10*
- 3 x 10*
- 1133 _ S 2x 10-'
I 3x 10-8 2x10" 4 x 10*
- 1 x 10**
2x 10*' 1x10-8 7x10*
- 4 x10-*
1134 S Sx10-'
, 4 x 10" 8 x10" 2x10-8 1 3x1T* 2x10-8 1x 10*' 8x10"
. 5135 S 1 x 10-' 7x 10*
- 1 x 10-' 4 x 10-'
I 4 x 10-' 2x10 s tridium p71 Ir190 S 1x10o 7x t0-s 1 x10-8 6x10-s 4xwe 2x10" l 4 x 10-' 5xtr;" 1x ig-*
tr192 S 2x 10's 1 x 10-' 1 x10-s extrf
- 4 x 10*
- I 3 x 10-'
tr 194 S 1 x10*
- ex te-" '
4 x10-8 2x10" 1 x 10-8 8xW8 3xto* , -
8 1 2 x 10*'
Iron (26) Fe 55 9 x 10" 5 x 10*
- 3 x10 I S 9x10" 2x 10-8 3 x 10*
- 8xt0" l 1 x 10" Tx 10*
- Fe E1 S 3x10-e 2 x10-'
- 1x10" 2x10" 5 x 10-8 8 x 10*
- Krpton (36?
Kr 85m -
1 5 x 10*
- 2x10" 2 x 10** 5x10"
- Kt B4 Sub 6x 10" 1 x 10-'
_. Sub 1 x 10-8 Kr 87- 3 x10" 8 Kr 88 Sub 1x ifr* 2x 10*
- Luthanum (57)
Sub 1X10" 2x 10" La *. 0 -- S 2x 10" 7x 10"_ . _ _ 5 x 10" 2x 10" I 1 x 10" 7x 10" Lead (62) Pb 203 S 4 x 10*
- 2x 10" 3 x 10" 1x10" 9 x 10-* 4 x 10*
- i 2x 10" Pb 210 S 1 x 10* 8 8 x 10-* 4 x10"
" 1 x 10-" 4xto", 4 x 10*" 1 x t o-'
l 2 x 10*
- 5 x10-8 8x10"8 2 x10"
, Pb 21? _ S 2x1C** 8x10"j 8 x 10*
- 2 x10*
- I 2x10**
LuetutF1)- Lu 177 S 5 x 10" 7x 10*
- 2x10" 8x10" 3 x 10" 2x 10" 1xto" l 5x 10" 3x 10's Man 9anese (25) Mn 52 S 2x 10-e j x109 -
2 x 10*' 1 x 10** 7 x 10" 3 x 10-a I 1 x 10*
- 9x 10" 5 x 10" {
Mn 54 S 3 x10" 4 x 10*' 4 x 10 1x 10" 1 x10" '
Mn 58 1
4 x 10*
- 3 x 10."e gx10** 1x10** I S 8x10" 4 x 10" 3x 1;-s 1 x10" i
Mercury (so) l $ x 10-' 3x 10" Hg 197m S 2x tC** 1 x 10" l 7x10" 8 x 10" 3x 10" 2x 10" 1
I 8 x 10" 5 x 10" Hg 197 S J x10** 2 x ttt" ,
1 x 10" 9 x 10" 4 x 10*
- 3 x t0" l 3 x 10" 1x10" ,
H3 203 S 9 x 10* * $ x t0" 7x 10" 5x10" 2 x t0" 2 x10* 8 Motyt4enum (42)
, i 1x 10" Mo 99 S 3 x 10* 8 4 x 10" 1 x 10"
,, 7 x to" 5x10" 3 x 10*
- 2 x 10" Noodymun (60) l 2x10 1 x 10*
- NJ 144 - 7 x 10*
- 4 x 10*
- S 8 x 10."u 2x 10" 3x t0*" 7x10" l 3 x 10"'
Nd141 S 2x 10*
- 1x t0*" 8 x t 0" 4 x 10" 2x10" 1 x 10-'
l 2x10" 8 x 10" Nd149- S 2x 10" 8x10" 6 x 10" 2 x 10" 8 x 10*
- 8xt0 e 3 x 10" NeptunuW(93)--
i i 1 x 10" 8 x 10" Np237- S 5 x 10" 3 x 10" 4 x 10* " 0x t0" 1 x 10*"
i 1x10** 3 x t0" Np 239 3 8 x t0" 4 x t0*" 3 x 10" 4
- 8 x 10* ' 4 x 10's 3xtoo gxgg e I 7 x 10' Noel (28) N159 3 4 x 10" 2 x 10.s g x t09 5x10" 8 x 10" 2x10 e 2 x 10" e
4 f i c. w r G. 0 7 *
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- QUESTION I I
'G.OB (1.5)
The types of radiation detectors can be characterized by the~ mode of the interaction with radiation. For example, one(1) of the two(2) types of detectors that the Ludium Model.177 ratemeter was designed to be used with is the scintillation type. . Lising this type of detector the Ludlum can reach up to 1007. detection efficiency for gamma radiation.
l
- a. What is the other. detector type designed to be used with.the Ludlum Model 177 ratemeter? (0.5) R
- b. What are the other two(2) kinds of radiation that can be i counted by the Ludlum? (0.5 pts. each) (1.0)
- ANSWER G.08 (1.5)
- a. Geiger-Muller (GM) (0,5) u , ,, n r.c esi*
- b. 1. alpha (c.s" / ) (0.5)
- 2. beta (0,5)
- REFERENCE Reed Training Manual, Chapter 2, pp. 34-38:
Instruction Manual, Model 177 l
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- QUESTION G.09 (1.75)
Attached Figure G.09 is a drawing of the Model E-140 counter used at Reed College. The "probe connection" is usually connected to an Eberline HP-270 or HP-190 detector ("frisker") when being used for personal contamination monitoring. Notice that the "Range" switch is marked off in three(3) multipliers 1, 10, and 100, yielding 600, 6k, or 60k counts per minute (cpm) full scale on the indicator face. These three(3) full scale readings also correspond to an equivalent exposure reading in mR/hr. There are two(2) specific functions for the "Reset" pushbutton.
- a. What are the three(3) equivalent exposure readings (mR/hr) that correspond to the full scale indications?
(0.25 pts. each) (0.75)
- b. What does the indicator label marked "xx" on Figure G.09 actually say on the E-140's used at Reed College? y(0.5)
- c. What are the two(2) specific functions of the "Reset" pushbutton? (0.25 pts, each) (0.5)
- ANSWER G.09 (1.75)
- a. (any order, 0.25 pts. each) (0.75)
- 1. O.S mR/hr
- 2. 5 mR/hr
- 3. 50 mR/hr
- b. BATT OK (battery OK) (0.5)
- c. (any order, 0.25 pts, each) (0.5)
- 1. Reset after full scale (alarm)
- 2. Operational checks (calibration)
- REFERENCE Instruction Manual, Model E-140 10
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- QUESTION G.10 (2.0)
Attached Figure G.10 is an illustration of the floor plan of the Reed Reactor Facility. The general background radiation levels are indicated for the Reactor room, the Laboratory, the Mechanical room, and the Counting room. Radioactive sources are kept in the Laboratory for instrument calibration and certain experiments. 10CFR2O requiren specific types of "CAUTION" signs for each of these four(4) areas, for the specific conditions identified on Figure G.10. Using Figure 6.10 and the previcus Figure G.07 (10CFR2O Appendix B):
- a. What must the "CAUTION" sign read that is hung over the counting room? (0.5)
- b. What must the "CAUTION" sign read that is posted on the reactor room door? (0.5)
- c. What must the "CAUTION" sign read that is posted on the l cabinet containing radioactive sources in the lab? (0.5)
- d. What must the "CAUTION" sign read that is posted on the mechanical room dcor? (0.5) !
- ANSWER G.10 (2.0) 4
- a. (CAUTION / DANGER) RADIATION AREA (0.5)
- b. (CAUTION / DANGER) HIGH RADIATION AREA (0.5)
- c. (CAUTION / DANGER) RADIOACTIVE MATERI AL (S) (0.5)
- d. (CAUTION / DANGER) (0.5)
AIRBORNE (RADIOACTIVITYAREA) tREFERENCE i 10 CFR 20 I
i END OF SECTION G END OF EXAM i
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Nuclear Regulatory Commission Part 20, App. B -
APPENDIX B--CONCEhTRATIONS IN AIR AND WATER ABOVE NATURAL. BA *
(See footnotes at end of Appende B) .
isotope
- Table i Tata u '
Bement (atomic number) - . . -
Col.1 4 Col. 2- M 2-4Wml) * ) Col.1.-Air g[g 0.GM ((,n loene (53) i125 5 5x 10*
- 4 x10" I 8 x 10*" 2 x10*'
2 x 10*' S X 10" 8 x 10*
- 1 128 5 2x10" 8 x 10*' S X 10" 9x10 u 3xggn
- I 3 x 10* ' 3x 10**
1 129 1 x 10*
- 9 x 10*
- S 2x 10" 1x 10**
I 2x 10*" 8 x10* *
- 7x10" 8x10" 2 x 10*
- axt0**
1131 S 9X10** 8x 10** 1 x 10*
- 3xt0" I 3x10" 2x 10" g.
3132 1 x 10** 4 x 10*
- S 2x 10*' 2x10
. I 8 x 10*'
3 x 10** 8x!0**
l133 5x 10" 3 x 10** 2xto" S 3 x 10*
- 2x 10*
- 4 x 10*
- 1 x10**
i 2x 10*' 1 x 10*
- 7x10" 1134 S 4 x 10**
wx 10*' 4x10 a Ox10** 2x 10*
- I 3x t0** 2x M*'
.,. 1135 S 1x10" 4 x10**
1 x 10*' TX10" 1x 10" 4 x10-e Irida,rn R 4 x 10*' 2x 10*
- 1x10-e 7x 10" h 190 S 1 x 10** 8 x 10*
- 4 x 10*
- 2 x 10**
I 4 x 10*'
1r 192 P 5 x 10*
- 1 x t0" 2x10" 1 x 10" 1 x10's 4 x t0-e 4 x10*
- s 3x 10" 1x 10*
- 9x 10*
- 4 x 10**
1r 194 e 2x10" 1 x 10*
- 8 x 10" 3 x 10*
- 8 Iron tY 1 2 x 10*' 9x 10" $ x 10*' 3xt0" Fe 55 S 9x 10" 2 x 10*
- 3x10" 8x10" 1 1x10" 7x 10*
- 3 x 10" 2 x t0*'
Fe 59 S 1 x 10*' 2x 10*
- S x 10" 8 x 10**
Krypton (36)
Kr85m I $x10" 2x 10*
- 2x 10*
- Ex10"
- Sub 6 x 10*
- Kr 84 Sub 1x10" 1 x 10" 3 x 10" '
Kr 87 Sub Kt 48 -
1x10" 2x10" Sub 1 x 10" Lanmanum (57) La 140- - 2 x 10*
- S 2xIL" 7x 10" .
I 1x10" 5 x 10" 2x60" Lead (82) Pb 203 7x 10" 4 x 10" Pv10**
S 3x10" 1 x 10*
- 9 x 10-
- 4 x t0" l 2 x 10*
- 1 x 10* s Pb 210 4 x 10*
- 4 x 10**
- S 1xt?"*
. 4 x 10-8 4 x 10"' 1 x 10*'
+ I 2 x 10*"
Pb 21' * $ x 10" 8x10ns 2x10"
' S 2 x 10" 8x10" I
8 x 10*" 2 x to" Ladetum (71)
Lu 177 -
2 x 10* * $x 10" 7 x 10*
- 2 x t0" S 6 x 10" l
3x1c" 2x 10" 1 x 10" Manganese (25)- 5 x 10" ' 3 x 10*
- 2x10" 1x10**
lh 52 S 2 x 10*' 1x10 a 7x 10" 3 x 10*'
i 1x10" 9 x 10" Mn 54 5 $ x 10** 3 x 10*
- 4 x10" 4 x 10" 1 x 10*
- 1 x 10"
- I 4 x 10*
- 3 x 10* a Mn 58 S 1x10** 1 x10" 8 x 10*' ' 4 x 10" 3 x 10" 1x10" Mucury (60) l 5 x10" 3 x 10" Hg 197m 2 x 10*
- 1x10**
S 7 x 10" 8x 10" 3 x 10" 2 x 10" l B A 10" 5 x 10" Hg 197 - S 3x10 e 2x10" 1x10" 9x t0*
- 4 x t o" 3 x 10" 1 3 x 10* * ,
H3203 - -- 1x10" 8x10" $ x 10" S 7 x 10" S x 10" 2xto" 2 x 10" odemm (4';_
, i 1x10" 3 x 10*
- I
- Mo&9 S 4xts" l x 10**
,, 7 x 10" 5 x 10" 3 x 10*
- 2 x 10" i
odymrum (" i 2x10" 1xt0 s )
Nd 144, - S 7x10** 4 x 10" 8 x 10* " 2 x 10" 1 3 x1 * *"
3 x 10*" 7x t0" 2 x 10*
- 1 x 10"' 8 x 10" Nd 147 3 4 x 10 2 x 10 *
- t x t0" 8 x 10" 1 1 2x 10" 2x10" 8 x 10"
- Nd148 3 2 x 10" 8 x 10 *'
- 1 l
8 x 10" 8k t0" 3 x 10" '
e t 1 1 x 10" 8 x 10* * $ x t0**
Np 237 5 4x10"a 3 x t0" 9 x 10" 1 x t0*" 3 x 10" l 1 x 10"' 4x '0" Np 239 S 4 x 10"' 3 x 10"
' -
- 11P '
4 x 10
I 3 x 10* ' 1 x t0" Nost fM 7 x 10" 4 x 10" 2xto"
.. . Hl 58 3 5 x 10*' 1 x *0" I
- 8x10". 2x10' 2x10" l
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