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Exam Rept 50-288/OL-89-01 on 890516-19.Exam Results:Two Senior Reactor Operator Candidates Passed All Portions of Written Exam & Three Reactor Operators (Ros) Passed All Portions of Exam & Three ROs Failed Exam
	ML20245H225
Person / Time
Site:	Reed College
Issue date:	06/14/1989
From:	Meadows T, Miller L, Royack M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
Shared Package
ML20245H211	List: ML20245H207; ML20245H225;
References
	50-288-OL-89-01, 50-288-OL-89-1, NUDOCS 8906290430
	Download: ML20245H225 (150)
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-ENCLOSURE-(1)?

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U. S. NUCLEAR., REGULATORY COMMISSION

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-EXAMINATION REPORT Examination Report"No.il 5 288/0L-89-01) 1 jc 4 Facility Licensees

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. Reed Reactor Facility ,

a Reed College 3 Portland . .. Oregon- 97202. ' t

Facility Docket No.:- 50-288 Facility Li_ cense No.- , R-112 ..

_ Examinations administered at Reed College, Portland, Ore on <

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c. . Chief Examiner: "~

MichaeltJ. Roy)ck-

\ /,/.7 j j 6//7 / P7 Datfe Signed Examiner: EZw MM '

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,Thoma R. Meadows Date Signed Approved by:

L flie'r, Ch , perations Section Date Signed

SUMMARY

Written examinations were administered to six '(6) Reactor Operator (RO) candidates and two:'(2) Senior Reactor Operator (SRO) candidates on May 16,1989. . Two~ (2) of the Reactor Operator written examinations were one'(1)sectionretakeexaminations. The operating examinations were administered on.May 16 through 19, 1989.. The;two (2) SRO candidates-passed all portions l.of the examination. Three (3) R0 candidates passed all portions of their examinations. Three of the RO candidates failed the examination, two (2) of the candidates failed both the written and operating portions of the examinations and one of the candidates failed the operating portion of the examination, 8906290430 890615 PDR ADOCK 05000288 V PNU 1.

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REPORT DETAILS i

1. Examiners:

Michael J. Royack, RV, Chief Examiner '

Thomas R.-Meadows, RV, Examiner

2. Persons Attending Exit Meeting:

NRC: l Michael J. Royack, RV REED:

M. Cronyn, Reed Vice President / Provost L. Ruby, Director Reed Reactor Facility J. Pollock, Assistant Director Reed Reactor Facility C. Grant, Reed Reactor Facility Staff S. Herbelin, Reed Reactor Facility Staff

3. Written Examination and Facility Review:

Written examinations were administered at Reed College on May 16, 1989.

At the. conclusion of the examination copies of the SR0 and R0 examinations and associated answer keys were provided to Mr. J. M. Pollock for coordination of the licensee's examination review.

.On May 18, 1989 the Chief Examiner met with the facility reviewers to discuss 'their comments on the written examination.

The facility comments and NRC resolutions for the SRO, and for the R0 written examinations are included as Attachments A and B, respectively.

The resolutions to the facility comments were incorporated into the SRO and R0 written examination answer keys prior to the grading of the examination.

4. Operating Examination:

The SR0 and R0 operating examinations were administered from May 16 through May 18, 1989.

During the operating portion of the examination, three generic weaknesses in the operator training program were identified. The areas identified were:

a. Training of operators in the area of radioactive material transfer procedures and processes.

The operators need to be familiar with procedures for the transfer of radioactive material, specifically within the facility.

Most of the candidates were unfamiliar with the processes and the I location of procedures for the transfer of radioactive materials i when questioned in this area during the operating examinations.

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b.- . Training lof. Reactor Operators in the ared of reactor kinetics.

l .. 3: ; Safe reackor operators are required to be knowledgeable in the areas 'of reactor kinetics -in . order to prevent or. mitigate the-effectsLof potential reactor accidents.-

, Some of the' candidates examined;did not' appear adequately trained- ,

in the area of reactor, kinetics..' Examples of this condition were::

00ne off the candidates was unable to explain whatI" critical:

, operation" meant.-

. A candidate incorrectly . identified the reactor as critical a when it was well below the point of criticality dur.ing a -n reactor start up.-

c. . Training of reactor. operators.in the areas'.of radiological controls.

Operators are ' required to be aware of and conform to the proper.

, use of radiological-controls.-

Some of. the candidates. did not adequately understand proper measures to control radioactive contamination. This weakness.

was identified by'the following examples:

. One of the candidates tried'to leave.the reactor bay area without frisking. their. hands or feet as required by the Reed Reactor Facility procedures..

. A candidate placed a bare hand in the potentially contaminated

" rabbit" terminal box. After the candidate frisked the hand and put'on protective gloves the candidate touched his face and hair.with his potentially contaminated gloved hands that he had used .to demonstrate the operation of the'." rabbit" system.

'4. Exit Meeting: '

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!. At the conclusion,of the examination on May'19, 1989 an exit meeting was )

' held with the facility. During the exit meeting the generic training j problems identified in paragraph 3 of this report were discussed with the j facility representatives, who agreed to review these weaknesses.= q

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l ATTACHMENT A SR0 EXAMINATION REED REACTOR FACILITY COMMENTS AND NRC RESOLUTIONS ,

RRF Comment:

~ SRO Exam H.07: This problem concerns 2 reactors, designated as "A" which reached full power in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with some final rod adjustments, and "B" which reached full power 'in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , but with no final rod adjustment.

The question is, "Which of the following statements correctly describes the reasons for the differences in power stability at 100% power?

d. Reactor "B" required no adjustment since the delayed neutrons that are being produced are in a state of equilibrium.

We believe that the key answer of "d" is f ncorrect. Since both reactors achieve full power in a time large compared to the longest delayed-neutron half life, both reactors have delayed neutrons which are in essential equilibrium with the power at all times. However, the actual situation for reactivity correction is very complicated. Although both reactors experience the negative temperature coefficient from fuel-temperature increase, the situation'with respect to samarium burnout, and with xenon buildup (or burnout) is different in the 2 cases. There is insufficient information given to assess the effect of the latter poisons. The . reference given for the problem compares "very fast" rises to power, with rises over "several hours", but in this context, "very fast" would have to be of the order of a few minutes, or less, to observe a reactivity effect due to the temporary lack of delayed neutrons.

TRIGAS capable of square-wave operation, but not ours, can illustrate this.effect.

RRF Suggested Resolution:

Delete question H.07 from examination key.

NRC Evaluation:

NRC concurs with facility comment.

NRC Resolution:

Delete question H.07 from SRO examination key, i

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l ATTACHMENT B R0 EXAMINATION REED REACTOR FACILITY COMMENTS

.1 AND NRC RESOLUTIONS RRF Comment:

R.0. Exam D.01: Why is a neutron source needed for a startup if the reactor has been shut down for long period of time?

a. To ensure that there is a sufficient number of neutrons to start the nuclear reaction.

d. To ensure that nuclear power.can be accurately monitored during a start up from. low count rate.

While we agree that the key answer of "d" is correct, we suggest that "a" is equally correct, and, in fact may be an even more important reason.

Our training manual says on page 4-6, "These neutrons are used to start the chain reaction..... " and Glasstone and Sesonske say on page 322,."During startup, it is possible for the reactor to become critical, and for the reactor period to be very short while the neutron flux is still low. If this occurred, the power might increase so rapidly that dangerous levels would be reached before steps could be taken to reduce the fission rate."

RRF Suggested Resolution:

Delete question D.01 from examination key.

NRC Evaluation:

NRC concurs with facility comment, reference material is correct.

NRC Resolution:

Delete question D.01 from R0 examination key.

FC

% yqqf U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION As Gmsed Facility: REED COLLEGE Reactor Type: TRIGA MARK 1 Date Administered: Ma v 16. 1989 -

Examiner: Michael J. Royack Candidate: ******* KEY ******************

INSTRUCTIONS TO CANDIDATE 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 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.

1 Category % ,of Candidate's % of

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Value Total Score Cat. Value 14 A. Principles of Reactor 14.14[~ Operation 14 14.6 4 B. Features of Facility Design 14.25 14.b C. General Operating Characteristics 13 1.( n.15 c; Mbt 4-44 -1(.254 D. Instruments and Controls 14.5 NY '

E. Safety and Emergency Systems m .65 14.5 h F. Standard'$ndEmergency Operating Procedures 14.5 Y G. Radiation Control and Safety 99 w 100 Totals Final Grade KEY %

All wofk done on this examination is my own. I have neither given nor received aid.

- - - - KEY ************

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Candidate's Signature

ES-201 Rev 5 01/01/89 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS

1. A single room shall be provided for administration of the written examina-tion. The location of this room and supporting restroom facilities shall -

be such as to prevent contact with all other facility and/or contractor personnel during the written examination. If necessary,-the facility '3 should make arrangements for the use of a suitable room at a local school.l-motel, or other building. Obtaining this room is the responsibility of R the licensee. "

2. Minimum spacing is required to ensure examination integrity as determined k

by the Chief Examiner. Minimum spacing should be one applicant per table, with a 3 foot space between tables.

V L 3. Suitable arrangements shall be made by the facility if the applicants are j

( to have lunch, coffee or other refreshments. These arrangements shall f comply with Item 1 above and shall be reviewed by the examiner and/or ]

E proctor.

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4. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in completing the examination. The examiner shall distribute these pads to the applicants. ,

1 5.. Applicants may bring pens, pencils, calculators or slide rules into the I examination room. Only black ink or dark pencils should be used for I writing -inswers to questions. ,

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f p 6. -The licensee shall provide one set of steam tables for each applicant.

i- The examiner shall distribute the steam tables to the applicants. No wall k charts, models, and/or other training materials shall be present in the y examination room. No other equipment or reference material shall .be 9 allowed unless provided by the examiner.

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[ ES-201 R::v 5 01/01/89 t

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j PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS

1. Check identification badges.

2. Pass out examinations and all handouts. Rekind applicants not to review i

examination until instructed to do so.

READ THE FOLLOWING INSTRUCTIONS VERBATIM:

! During the administration of this examination the following rules apply:

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1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you.have not

L received or given assistance in completing the examination. This must be done after you complete the examination. -

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READ THE FOLLOWING INSTRUCTIONS -

1 1. Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examination

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room to avoid even the appearance or possibility of cheating.

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2. Use black ink or dark pencil only to facilitate legible reproductions,- !

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3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

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

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5. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON !

! THE BACK SIDE OF THE PAGE. - -

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! ' 6. If you write your answers on the examination question page and you neeo l

) more space to answer a specific question, use-a . separate sheet of the J paper provided and insert it directly after the specific question. DO NOT

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WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.

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) 7. Print your name in the upper right hand corner of the first page.of each" -

l l section of your answer sheets whether you use the examination question l ij pages or separate sheets of paper. Initial each page. . '

l 8. Before you turn in your examination, consecutively number each answer l sheet, including any additional pages inserted when writing your answers

,{ on the examination question page. i l ,

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? Examiner Standards w=_ =- - N

ES-201-Rev 5 01/01/89 J

9. - If you. are using separate sheets, number each answer as to' category and number (i.e. LO4, 6.10) and skip a~t least 3 lines between~ answers to allow space for grading. .

10. Write "End of Category " at the end of your answers to a category.

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11. Start each category on a new page.

12. Write "Last Page" on the last answer sheet. .

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- 13. Use abbreviations only if they are commonly used in facility literature. i Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.

[ 14. -The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.

3 15. Show all calculations, methods,'or assumptions used to obtain an answer.

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

17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is l worth one point and asks for four res points, and you give five responses, ponses, eachresponses each'of your of which iswill worth 0.25 be worth 0.20 points. If one of your five responses is incorreect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.

-18. If the intent of a question is unclear, ask questions of the examiner.only.

[. 19. When turning in your examination, assemble the completed examination with-( examination questions, examination aids and answer sheets. In addition, 7 turn in all scrap paper.

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20. To pass the ' examination, you must achieve an overall grade of 80% or greater and at least 70% in each category.

21. There is a time limit of (6) hours for completion of the examination.

l (or some other time if less than the full examination is taken.)

22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination l

1 is still in progress, your license may be denied or revoked.

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1 ' Examiner Standards G n 'e*g -" e' +*94+ ero . _ WN , ps "mem A wm~~***'w *~~*'*-=***'w-*~-'y , 39-

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j EQUATION SHF T-e f " 1** v =.s/t v = ag 2 . Cycle efficiency = Wet Work (out) j 8 = v,t +. hat Energy (in) '

E = aC2 a = (vg - vp )/t A = A e'A" IE = huv vf = v, + et A = AN PE = agh a = 6/t 1 = in 2/tg = 0.693/tg

* "AP T=I n / delta k 8 (*ff) " (t,)(ts)

AE = 931Am

, $ = delta k/ Beff Itg+t)b '

N" p 6T , ,-Ix ,

k=UAAT I=Ie0 .Ux

"f I=I -10

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E It) TVL = 1.3/y -

0 .

P = P,10 L P = P ,e*Ii . HVL = 0.693/u

. SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg) ,

f1*ggo \

k SUR = 26 g,, CR ,= S/(1 - K,ggx).

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'F T = '(1*/p ) + [(i 'p)/x,f,p] 1( eff}1 " 2 II ~ Keff)2 T = 1*/ (p - Ty M = 1/(1 - K,gg) = CR /CR0 g T = (I - p)/ 1 p eff f M = (1 - K,gg)D/CI ~ Keff)1 f.

P*I, aff"I)/Eeff " Eeff/K*ff -

t - SDM = (l'- Ketf)lKeff

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p= [ A*/TKygg] + [I/(1 + 1,ggT )] g* = 1 x 10 seconds

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h P = I$V/(3 x 1010) 1,gg = 0.1 seconds i I = No j . Idgy=Id22 WATER PARAMETERS Idg =Id 2 f 2

,} 1 gal. = 8.345 lba R/hr = (0.5 CE)/d (meters) 1 gal. = 3.78 liters R/hr = 6 CE/d (feet)

I 1 ft3 = 7.48 gal. MISCELIR.EOUS CONVERSIONS 3 O

f. . Density = 62.4 lbm/ft 1 Curia = 3.7 x 10 dps 3

f Density = 1 gm/cm ,

1 kg = 2.21 lba 3

{ Heat of valorization = 970 Itu/lba 1 br = 2.54 s 10 BTU /hr f Heat of fusica = 144 Btu /lba 1 N = 3.41 x 100Btu /hr 1 Ata = 14.7 psi = 29.9 in. I'g. 1 Btu = 771 ft-1bf '

2 I ft. H oy = 0.4333 lbf/in 1 inch = 2.54 cm F = 9/3'C + 32 "C = 5/9 ("F - 32) t prf A h-,eme.mg.ysse ip .g9af 9 e moy.m &fy, w -c+wu.+ p * * +

A huhm.fML.hLs.m. A- @ + 1 m. ?!

CATEGORY A PRINCIPLES OF REACTOR OPERATION,

DUESTION A.01 (0.75)

Multiple Choice, Select the correct response.

Reflectors are used in the TRIGA reactor as a method of helping to control the neutron population of the reactor.

What material is used as the PRIMARY reflector in the Reed College TRIGA reactor?

I- a. Water (H O).

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b. Graphite.

if c. Aluminum.

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d. Zirconium Hydride.

ANSWER A.01 (0.75) f b.

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REFERENCE RRF Training Manual , Module 12-6.

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QUESTION A.02 (0.75)

Multiple Choice, Select the correct response.

What are the.three (3) materials that are'specifically designed as moderators in the Reed college TRIGA reactor 7

a. . Water, Graphita, Zirconium Hydride.

b. Zirconium Hydride, Concrete, Graphite.

c. Graphite, Water, Al umi qum. -

d. Al umi nurr., . Concrete, Water .

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ANSWER.

I A.02.(0.75) f n

a.

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REFERENCE RRF Training Manual, Module 12-6 e

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DUESTION A.03 (1.0)

What is the purpose of neutron moderation in the Reed College TRIGA reactor? (1,0)

ANSWER A.03 (1.0) ,

To thermalize or slow down neutrons. (1.0)

REFERENCE RRF Training Manual, Module 12-6.

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QUESTION A.04 (1.5)

CALCULATION, show all . work. .

The Reed College' reactor is at a power level 'of one (1)'

watt and increasing with a parfod of 20' seconds.

.How long will .it take f or reactor power to '.ncrease by a factor off1000 (3 decades)?

Show All Work

-(1.25 pts. application)

(0.25 pts. answer)

ANSWER

A.04 (1.5)

T = 20 seconds-P/PO"

In 1000 = t/20 (0.25) t = 20 in 1000 = 20 (6.91) t = 138.2 seconds = 2.3 minutes (+ or - 3.0 sec or O.1 min)

(0.25)

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. SUR = 26.06/T = 26.06/20 = 1.3 dpm - ( 1. 0) 3 decades / 1.3 dpm = t (0.25)-

t = 2.3 minutes (+ or - 3.0 set or O.1 min) (0.25).

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REFERENCE F

RRF Training Manual.

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QUESTION A.05 (1.5)

CALCULATION, show all work.

The Reed College reactor is subcritical with a kef f of 0.94

and 20 counts per second (cps). After an experiment is installed the indicated count rate increases to 40 counts per second.

What is the new kef f f or the new count rate of 40 cps? (1.5)

Show All Work (1.25 pts.' application)

(0.25 pts, answer) h I

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ANSWER A.05 (1.5)

L corre.:t iormul a,

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C,R1/CR2 = (1 - keff2) / (1 -

keff1) (0.75) correct substitution, 20 cos / 40 cps = (1 - keff2) / (1 - 0.94) (0.25)

(0.5)(0.06) = (1 - keff2) h t-h correct answer,.

l' kef f 2 = 1 - 0. 03 = 0.970 (+/- 0.005) (0.25)-

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REFERENCE f Equation sheet, RRF Intro to Resctor Operations t

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QUESTION A.06 <2.0)

Cal cul ati on . Show all work.

The mean lifetime (I n) f al reactor neutrons.is calculated

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to be 9.2 x 10 seconds and the Rsed Reactor Facility (RRF) beta effective (B,jg) is 0.0075.

The reactor is. at power and a sixty (60) cents worth of reactivity is inserted.

O What will be the resulting steady state reactor period?

i (2.0) g -.

i Show All Work h- (1.75 pts application)

L (0.25 pts answer)

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ANSWER A.06 (2.0)

T=1- n / delta k. (0.75) o

$.= delta k /.B,jf (0.75)

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delta k = ($) B,jf

= (0.60)(0.0075) = 4.5x10 (0.25)

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T=I n

/ delta k = 9.2x10~ / 4.5x10 = 20.4 seconds

-(+ or 1 second) (0.25) ora i-

! SINCE T = In / delta. k is 'only f or a reactor with no delayed netrons also accept:

T = Beff - p / lamda x p = 1-$ / lamda x p=T (1.5) 1 - 0.60 / (0.1 SEC) (0. 60) (0._5) h = 6.67 SEC. (0.25)

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REFERENCE RRF Introduction to Reactor Operations, equation sheet.

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QUESTION A.07 ( 1. 5)

CALCULATION, show all work.

During a reacto- refueling a spent fuel element is removed from the reactor causing the the shut down margin (SDM) in the reactor pool to change to 0.12 delta R.

What is the new keff for this condition of 0.12 delta k SDM7 (1.5)

Show All Work (1.25 pts application)

(0.25 pts answer) 1

ANSWER A.07 (1.5)

Correct equation

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Keff = 1 - SDM (0.75) keff = 1 - O.12 (0.5) keff = 0.88 (+ or - 0.01) (0.25)

( ort h Accept: 1 - keff / keff = SDM (0.75) keff =1 / 1 + SDM = 1 / 1 + 0.12 (0.5)

= 0.893 (0.25)

REFERENCE RRF Training Material, Equation Sheet, l

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QUESTION A.OB (1.0)

Mul tiple Choice, Select the correct response.

What is the temperature in degrees Fahrenheit f or a thermometer that is reading 30 Celsius?

a. 112 degrees F

b. 86 degrees F

c. 49 degrees F

d. 77 degrees F F-K

ANSWER A.OB (1.0) b.

degrees F = 9/5 degrees C + 32

= 9/5 (30) + 32 F = B6 ;

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REFERENCE Equation Sheet, Physics, Resnick and Hallidy.

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QUESTION A.09 (1.0) J l

Short Answer.

Prior to starting up the Reed College reactor the Americium-Bery3ium neutron scurce is moved near the start up detectors in order to test a control rod safety interlock.

What control rod safety interlock is tested when the neutron source is moved near the start up detectors? (1.0) -

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ANSWER L A.09(1.0)

L b Control rod withdrawal is prevented if start up channel b indicates less than two counts per second, or source t interlock (which tests the positive response of the channel f to neutrons. (1.0)

REFERENCE RRF Training Manual, Module 12-1, SDP 01, pg. 6.

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QUESTION A.10 (1.0)

.y Multiple Choice, Select the correct response.*

Which of the f ollowing statements correct 1'y describes Thermal Neutrons 7

a. A neutron that experiences a linear decrease in energy as the temperature of the moderator increases.

b. A neutron at resonant epithermal energy levels that causes fission to occur in Pu-240 and U-238.

c. A neutron that experiences an increase in energy levels

. af ter collisions with larger. atoms of the moderator.

p b- d. A neutron that experiences no net change in energy f- after several collisions with atoms of the moderator.

,

ANSWER A.10 (1.0) d.

REFERENCE RRF Training Manual, Module 12-6.

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DUESTION A.11 (1.0)

Short Answer. .

Af ter a. reactor. scram there is_ an initial prompt drop in power level followed by a steady power decrease with a period of -80 seconds.

Why does the power decrease always have a period of

- 80 seconds? (1.0)

ANSWER A.11 (1.0)

Power cannot decrease faster _than the the mean life of the longest lived precursor. (mean life of'Br 1.44 x 55 sec).

REFERENCE Reactor Physics, Module 4 and 5 l

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QUESTION A.12-(1.0) 1[.

Multi pl e . Choi ce, Select the correct response.

Below is a. strip chart recorder representation of reactor

. power versus time f or a xenon f ree reactor at start up. A reactor. trip occurred.at 70, hours fallowed by. reactor.. start up'to 100% power at'BO hours.- Representation A.12 (attached) shows four (4) graphs of possible xenon transients.

100%'-I ----- --- - - - - - - - - - -----------~~~~~

, P ! I 1 g O I I I W l I i E I i 1 f R l- 1 I I

i ! i f' i 1 1 1 I I i 1 1 0% _!_ _______!_____!_______________________________

l i 1 1 70 80 100 150 TIME (hours)

I Which representation correctly defines the xenon transients f associated with with this operating history?

k b

a. A.12.a

b. A.12.b L

c. A.12.c

[ d. A.12.d

ANSWER A.12 (1.0) l C. <

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REFERENCE t Reactor Physi cs, Modul e 12-7.

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f END OF SECTION A CONTINUE ONTO SECTION B t

i l-5 12

k XENON REPRESENTATIONS Sheet 1 of 2 A.12.a i e .

I i i Equilibrium Xe l i l 'At 100% Power

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X i l l E l l 1 N Xe_ i i ! !

l. O Free

'l N O 70 80 100 150 F HOURS s

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v V l l l I 1 i T ! ! i y a *

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[. j , At 100% Power 0

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Free 1 0 70 80 100 150 i HOURS

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i XENON REPRESENTATIONS f Sheet 2 of 2 .l i I I A.13.c d q

l ! I I I l-1 I I i 1 l

1 I i - Equilibrium Xe 1

_l____ __________________________

1 1 I At 100% Power I I i i l i X l I I t E I i 1 N

Xe_i_____________I_____!__________I__________l __

D Free i-N O 70 80 100 150 HOURS R

E f A' C 1 1 I A.13.d T I I I I I I V i ! I I I I i T I i l Equilibrium Xe

, y g____________ ____j________ ______ __________

, I ! I At 100% Power i ! 1 I I I I I I I I I xe_ _____________I_____i__________!__________I___________

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w . - _ _ , _ . : -. .v----- - .- - -

s CATEGORY B FEATURES OF FACILITY DESIGN

QUESTION B.01 (1.0)

Short Answer On a' reactor scram the control rods are rapidly inserted into the core.

What is the design feature of the control rod assembly barrel that helps prevent the control rods from impacting on the bottom during a reactor scram?

(

ANSWER B.01 (1.0)

J t Grated vents or holes are provided in the bottom (providing h a dash pot action on a scram). (1.0)

REFERENCE G.A. TRIGA Mark 1 Maintenance and operating manual.

I$'

U I

1 1

l I

15

[

r

%=____m_______

i i

DUESTION B.02 (0.75)

Multiple Choice, Select the correct response.

During power operations of the RRF the neutron flux is not the same throughout the core. .

What is the position ' of the maximum neutron flux in the RRF i core during 100% power operations?

a. At the top of the core.

b. At the bottom of the core.

t

[ c. At the outside perimeter of the core.

[. d. At the center of the core.

k t.

r a

ANSWER B.02 (0.75) d.

REFERENCE ir GA TRIGA. Maintenance and Operating Manual, Pg. 1.

V

(;:

4 f

e g

l l i 1 L

b I.

16

..._m__,_mm. , ._m_ , _ m

1

QUESTION B.03 (2.0)

.Short Answer The Rotary Specimen Rack holds samples of material to irradiated _and surrounds the core. .There are forty evenly 1 spaced tubular containers, in the specimen rack, which serve as specimen receptacles.

i

a. What design f eature in1the specimen receptacles allows you to detect water or condensation in the rotary specimen housing? (1.0) h b. How is water or condensation removed from the rotary specimen housing? (1.0) k I

b['

r

ANSWER B.03 (2.0)

a. (To detect water or condensation in the rotary specimen housing), A (0.625 in.) hole is provided in the bottom of !

one of the (perf orated) tubes. (1.0) ;

i

b. Desiccant or a water absorbing material (placed in the

[

perforated specimen tube). (1.0)

^

(

[ *RareReNee b' GA TRIGA Maintenance and Operating Manual. f L I c >

)

1 l

1 1

l 17

I I

t

'}

QUESTION LB.04 (2.5)

Short' Answer. 1 There is a conductivity probe located at the inlet of the domineralizer. The conductivity probe will read high if'the .

reactor water is grossly impure. One (1) of the conditions I that could cause high conductivity is f uel. element f ailure.

a. What are TWO (2) other design failures that'could cause a high conductivity at the inlet to the demineralized? (0.75 points each max 1.5 pts) (1.5)

O b. Wh a': are TWO (2) reasons for maintaining a low reactor water conductivity? (0.5 each max 1.0) (1.0)

Y r

ANSWER B.04 (2.5)

L. a. Max 1.5 points

1. Experiment Failure (i ncor e ) . '(0.75)

2. Failure of cooling water heat exchanger (cooling water flow into the reactor water system). (0.75)

b. Max 1.0 points

[i 1. Prevent corrosion. (of reactor components, pe~ticularly (0.5)

); fuel elements).

n.

bl 2. Reduce radioactivity of the reactor coolant system.

(0.5)

[

REFERENCE GA TRIGA Maintenance and Operating Manual and RRF SAR.

N l

I

[.

L 1e

l 1

QUESTION B.05 (1.0) r t'

Multiple choice, Select the correct response. 1

-The. filter in the reactor water system removes insoluble particulate matter and is provided with a pressure gauge up and down stream of the filter.

What-will the effect of a high. differential pressure across.

the filter-have on the reactor water pump and the demineralized flows?

-a. . Increase reactor water. pump flowLand decrease demineralized flow.

F b. Decrease' reactor water. pump' flow'and decrease demineralized flow.

[ c. Increase reactor water pump. flow and increase b -- demineralized flow.

[ d. Decrease. reactor water pump flow and increase demineralized f l ow.-

ANSWER

.B.05 (1.0)

> b.

REFERENCE GA TRIGA Maintenance and. Operating Manual.

i 3-e I

L 3

I 19 b.' .- , . . .

0:

l I

1 I

'l l

QUESTION B.06 (1.0)

Short Answer.

'l The TRIGA reactor water system is provided with a "sks mmer" in,the reactor tank. When in operation the reactor tank water level' must be maintained so that air is not drawn into the skimmer and the reactor water system.

What effect will air'being drawn.in through the skimmer have.

- on the demineralized? (1.0) i-

ANSWER p B.06 (1.O) f.

h Air will deplete (degrade) the resin, or cause channeling (holes) in resin bed. (1.0)

[

h I

REFERENCE GA TRIGA Maintenance and Operating Manual.

E r

i 1

6 I

n i 20

i. _.j h -

.____._,_.m.m.._m2,__. . . _ _ . . . _ _ . _ _ _ __ _ _ _

'\.

?

>t

QUESTION B.07-(0.75) e Multiple Choice, Select the correct ~ response.

The RRF has three control rods which contain a powdered ineutron absorber, or poison to control reactivity in the-Core.

What is the name of the powdered neutron absorbing material used-in the. control rods?

a. Borated aluminum oxide.

l b. Borated . zirconium alloy.

c. Boron' graphite.

h, L .d. Boron carbide.

l

ANSWER B.07 (0.75)-

d.

REFERENCE

f. GA TRIGA Maintenance and Operating Manual.

k:p i

l l

l i i

1 f.

21 b,

l

i

QUESTION B.OB (0.75) -,.

Multiple Choice, Select the correct response.

.The three TRIGA reactor control rods are made of the same structural material, which contains the powdered neutron absorbing material or poison.

What is the name of the cladding material that the control rods are made of?

a. 304 Stainless Steel .

P! b. Aluminum.

[.

f. c. Zirconium Hydride.

d. Graphite.

4

ANSWER

( B.08 (0.75) b.

REFERENCE p

GA TRIGA Maintenance and Operating Manual.

, i, 18 22

-w=:=rs====- : -

- . -- -- ~

I

QUESTION B.09 (0.7"J Multiple Choice, Select the correct response.

The fuel loading of f uel elements can be determined by

. grooves machined into the the top end' fixtures of the fuel elements. Figure B.09 illustrates the groove patterns f or fuel-loading.

Which pattern correctly shows a DUMMY ELEMENT 7

a. E

b. A hI c. C r;

d. B

ANSWER B.09 (0.75) a.

REFERENCE b- GA TRIGA Maintenance and Operating Manual.

t.

[1 u

h A ,-

e 9

23

-a g-Il[ .

FIGURE B.09

! I i i I, - t l -- - l A

B k_

.!- C D E Li L- s 9

d4

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.- s b

f,-

1 s

1 1

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i a

.v -

f 4 4 5

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m.__. m___m.____,_- m..._ . .. - . . , _ ..

QUCSTION-B.10 (1.0) ,

Multiple Choice, Select the correct response.

Two f our inch pieces of graphite are inserted into each f uel

' element, one above and one below the fuel.

What is the purpose of the graphite' inserted above and below the 'f uel?

a. To serve as reflectors for the top and. bottom of the core.

(. b.. Act'as a radiation shield to reduce nitrogen 16 gamma l' radiation above and below the core.

c. Provide spacing to insure that the fuel i s properly positioned in the element..

g

d. - Act as a buffer to allow for the' thermal expansion and

{ contraction of the fuel.

ANSWER B.10 (1.0) k a.

L

- *REFEhdNCE GA TRIGA Maintenance and Operating Manual.

78 I

f 24 1

h.

k_ A. - o .- .m.. <e m. ~m m m . mm m.. , _ . - .>..m... a , _ _ _ _ _ _ _

_

__1_*__:__.___3.______________________________

i

QUESTION B.11 (0.75)

Multiple Choice, Select the correct response.

What is the material that the rotary specimen rack is made of?

a. 304 Stainless Steel,

b. Zirconium Hydride Alloy.

c. Aluminum.

, d. 302 Stainless Steel.

k-

[

ANEWER B.11 (0.75) .

F C.

REFERENCE GA TRIGA Maintenance and Operating Manual.

P g .-

)

[ 25

[_ 1

j l

i

QUESTION I B.12 (0.75)

Multiple Choice, Select the correct response.

What is the material that the housing of the rotary specimen rack is located in made of 7

a. 302 Stainless Steel.

b. 304 Stainless Steel.

c. Zirconium Hydride Alloy.

r.

k d. Aluminum.

?

ANSWER

!. B.12 (O.75) p S

d.

REFERENCE GA TRIGA Maintenance and Operating Manual.

26 r _ . . w__r _ __ -_ r _ - - '- - - -

DUESTION B.13 (1.0) .

Multiple Choice, Select the. correct response.

The high speed pneumatic transfer system moves samples in and out of the core rapidly.

I Which of'the following statements correctly describes the the pneumatic transfer systems exhaust path and operating' pressure?

a. The pneumatic transfer system exhausts to the reactor room and maintains the transfer system at a positive pressure..

?,

C b. The pneumatic transfer system exhausts to the reactor f room and maintains the transfer system at a negative-

'. pressure. .

f c. The pneumatic transfer system exhausts to the building exhaust and maintains the transfer system at a negative p pressure.

d. The pneumatic transfer. system exhausts to the building exhaust and maintains the transfer system at'a positive pressure.

p.

ANSWER

h. B.13 (1.0)

L

[

p c.

REFERENCE i

Reed College Reactor Facility Description and SAR, pg. 5-7.

END OF SECTION B CONTINUE ONTO SECTION C I

l 27 l

CATEGORY C GENERAL DPERATING CHARACTERISTICS-t

QUESTION C.01 (0.75)

Multiple Choice, Select the correct response.

The RRF reactor pool is a source of water f or cooling the fuel elements.

Which oF the f ollowing is the primary cooling mechanism normally used to cool the RRF reactor core 7

a. Natural Convection (Ci r tual t i on ) .

u.

p .b. Gamma Radiation.

c. Forced Convection (Circulation).

[

A d. Mechanical Conduction.

y

ANSWER C.01 ( 0. 75) a.

E ~

REFERENCE E TRIGA MARK 1 Reactor Mechanical Maintenance and Operating Manual.

s p

r

l i ,[

]

i g'

l 2B

' "cr_:::c___ __ _:' :::t r&.- r- ~ ~ -

~ - --

-- ~. ,

QUESTION C.02 (0.5)

N The water in the reactor pool is used to cool the fuel elements. There are TWO (2) flow paths the water takes to reach the fuel elements. One-(1) of which i s through 31 holes in the lower grid plate.

What is the other flow path that the majority of the reactor cooling water takes from the pool-to the fuel elements?

(0.5)

l.

ANSWER

- C.02 (0.5)

Flow between the (top) of the lower grid plate, and the

[ (bottom oF the) reflector. (0.5)

{'l

REFERENCE TRIGA' MARK 1 Reactor Mechanical Maintenance and Operating Manual, pg 11.

V -

4 h

h 8

i w.*

1 c

, 29

[ 2

k

QUESTION C.03 (1.0) .

+; ,_

.Short Answer.

After the reactor cooling water has removed the heat from the fuel elements it returns to the fuel pool.

What are the names of the TWD (2) components that f orm the gap which the reactor coolant must flow through in order to return to the pool? (0.5 pts each snax 1.0 pts.)

r

ANSWER C.03'(1.0) (0.5 pts ea. max 1.0 pts)

?

l

1. (Triangular) spacer block (f uel rod) (0.5)

Y'

2. (Circular holes in) upper grid plate. (0.5)

REFERENCE TRIGA MARK.1 Reactor Mechanical Maintenance and Operating Manual, pg 9.

V i

7 p

V 9

g, t

30

)f- -"'i_'r.__;r-*::~ T:'" T ::~- ~'~ . '~ -

QUESTION C.04 (1.5)_

Short Answer.

The RRF TRIGA has three control rods, the ' shim rod, the-safety rod, and the regulating rod..

a. What is the present reactivity worth of the Shim rod?

(0.5)

b. What is the present reactivity worth of the Safety rod?

(0.5) l c. What is the present reactivity worth of'the Regulating

[" rod? (0. 5) '

R

! ,.

ANSWER I .. C.04 (1.5)

L, f.I a. $4.25 (+/- $0.50) (CWF for actual $ 4.30) (0.5)

b. $O 25 (+/- $0.50) (CWF for actual $ 4.26) (0.5)

c. $1.50 (+/- $0.25) (CWF for actual $.1.67) (0.5) p

REFERENCE Facility Data.

L e

t

.e N*

i n

P f 31

h. .

w. -- ..

, ~ . - . . . -, -- .,

l r

QUESTION '

C.05 (1.0) ,

.-a

. Short Answer

One reason f or maintaining a minimum reactor pool level is for-the proper operation of the pool " skimmer".

What are TWD (2) other reasons f or maintaining a minimum reactor pool level during reactor operation?

(0.5 pts each max 1.0)

ANSWER

[ C.05 (1.0) (0.5 pts ea max 1.0 pts)

L F 1. Provide shielding (From the core). (0.5)

T

'. 2. Proper " Dash Pot" action (f or control rods) during a scram. (0.5)

F.

REFERENCE TRIGA MARK 1 Reactor Mechanical Maintenance'and Operating Manual.

7 L

g t

d' ms t

I' 32 L

1 - - _ ____ - _ -

r'

QUESTION .

C.06 (1.0) l Multiple Choice, Select the correct response.

At what . minimum reactor pool level must corrective action be taken, during operation, as required by Technical

. Specifications?

a.- When reactor pool l evel is 12 feet above the upper grid plate.

b. When reactor pool l evel is 12 feet above the active

. core center line.

c. When reactor pool l evel is 16 feet above the upper grid plate.

E d. When reactor pool level is 16 feet above the active

[ core center line.

ANSWER C.06 (1.0) c.

REFERENCE k

RRF Technical Specifications l

QUESTION C.07 (1.0) ..e'

~

Multiple Choice, Select the correct response.'

t.

RRF Technical Specifications require that the reactor be shut down if the temperature in the reactor pool exceeds a preset.value.

What is this temperature?

a. 110 F, read at the ion exchanger inlet.

b. 110 F, read at reactor pool bulk temperature.

I. c.- 120 F, read at the ion exchanger inlet.

d. 120 F, read at reactor pool bulk temperature.

ll

ANSWER

['.

C.07 (1.0) d.

REFERENCE RRF Technical Specifications I.

is c

L p.

l 4

4

".. ' ?a ,

I l 34 e

j

QUESTION C.08 (0.75) ,' ,

Multiple Choice, Select the correct response)

Fuel storage racks are provided underwater in the. reactor

' tank to provide temporary stor age.

What'is the maximum number of fuel or dummy elements that each fuel rack can hold 7

a. 5

b. 10 I.

, c. 15 r,

d. 20

ANSWER C.OB (0.75) b.

REFERENCE

TRIGA Mechanical Maintenance and. Operating Manual, Pg. 26a.

t v ,

y,' .

p pM" s'

l.

f 35

( ,

i 1

1

QUESTION )

C.09 (0.75) i y J 1

Multiple Choice, Select the correct response. ]

What is the maximum keff in the fuel racksi' under all -

conditions of moderation when fuel elements are stored in {

the fuel storage racks? ,]

a. keff less than O.8. .

I

b. keff lens than O.85. l

c. keff less than 0.9.

r L- d. keff equal to 0.85.

L 1 e

b g

ANSWER C.09 (0.75)

V t a.

REFERENCE RRF Technical Specification, pg. 4.

{

v.

p b

v..

F1 I

y I

I e

T4 t'

g.

p-l[

36 h..

9 7 , ,., -,:. . _ . . .

}

QUESTION C.10-(2.0)

Calculation, Show All Work. i The reactor is critical in the source range and is below the point of adding heat to the moderator (PDAH). Rod motion has added enough positive reactivity to increase kef f from 1.00 to 1.002.

Assumes (beta effective) Beff = 0.0072 and Lamda ( ) = 0.10.

! Do not consider source neutrons.

f.

I: - What will be the stable reactor period (in seconds) after the positive reactivity addition increased kef f to 1.0027 f'-' (2.0) 7 E SHOW ALL WORK!

(1.5 points for application)

(0.5 points for correct answer)

ANSWER g* C.10 (2.0) (1.5 pts correct application, 0.5 pts correct answer) p.= (keff-1)/keff (0.5)

(1.002 - 1) / 1.002 = 0.002. (0.25)

T= (Beff - p)/ Lamda (p) (0.5) i = (0.0072 - 0.002) / (0.1) (0. 002) (0.25) i T = 26 seconds (+/- 3 seconds) (0.5)

.l 1 i

REFERENCE RRF Training manual, Modules 12-3 thru 12-6.

i 1

r r

i l 37

QUESTION C.11.(1.0)

Multiple Choice, - Select the correct response.

The large " prompt" negative f uel temperature coef ficient (FTC) for TRIGA reactors is achieved by the effects of THREE (3) different phenomena, one of which is the properties of-

,the fuel element moderator.

Which of the f ollowing statements correctly describes the reason for the effect of the prcperties of fuel element moderator effect on the overall " prompt" negative f uel temperature coefficient?

'~

I a. With increasing fuel element moderator temperatures the I thermal neutron population is hardened (increased in

[ energy).

b. With increasing fuel element moderator temperatures the

('- ef f ect of fission product Samarium increases the number of prompt neutrons.

c. With increasing fuel element moderator temperatures the thermal neutron population is softened (decreaseo .n p

energy).

t

d. With increasing fuel element moderator temperatures the

effect of fission product Samarium increases the number of delayed neutrons.

t-

ANSWER C.11 (1.0) a.

REFERENCE Reed Reactor Physics, Module 12-6.

-l I

i e

p 3B i.p

h l

i

QUESTION ~

C.12 (1.0)

Multiple Chcice, Select the correct response The large " prompt" negative fuel temperature coefficient (FTC) f or TRIGA. reactors . is achieved by the ef f ects of THREE

-(3) different phenomena, one-of.which is the Doppler Effect.

Which one of_the following statements correctly describes the reason for the Doppler Effect?

a. The narrowing of the resonant neutron capture energy bands'of Xe 131 and Pu 239.

h b.- The' broadening of the resonant neutron capture energy bands of Xe 131 and Pu 239.

y c. The narrowing of the resonant neutron capture energy t bands of U 238 and Pu 240.

f f

) d.. The-broadening of the resonant neutron capture energy bands of U 230 and Pu 240.

ANSWER C.12'(1.0) p.

L d.

f

REFERENCE y- Reed Reactor Physics, Modul e 12-6.

o i

g 0

' l f !

i.- c k

39

=x= __ s ;_ , ,_ -_~r-~- . , - - - -- -

QUESTION

- C.13 (1. 0)

Short Answer.

.i The'three phenomena that achieve the large." prompt" negative

. fuel temperature coefficient (FTC) are:

1. Doppler Effect.

2. Core Leakage.

3. Properties of the fuel' element moderator.

I" a. Which one of the three phenomena has the LEAST effect on i the FTC7 ( 0. 5) -

F

[ b. Which one of the three phenomena has the GREATEST effect on the FTC7 (0.5)

[.

ANSWER C.13 (1.0).

a. Core Leakage (2). (0.5)

b. Fuel Element Moderator (3) (0.5)

(

F

REFERENCE

[.

Reed Reactor Physics, Module 12-6.

lh-F m

1 l

[f 40

x. >_ -w, - n. . n . :.n: : - . . - . . . .- -

i 1

l 1

1 I

QUESTION C.14 (1.0) / -,-

Multiple Choice, Select the correct response.

The Reed College TRIGA reactor is characterized as being slightly undermoderated.

Which of the f ollowing statements correctly describes the reactor. operating characteristic of "undermoderated"?

a. A decrease in core water temperature will ccuse a negative reactivity response.

y b. A decrease in core water density will cause a negative

[ ' reactivity response.

['

c. An increase in core water temperature will cause a positive reactivity response.

d. An increase in core water density will cause a negative 5 reactivity response.

ANSWER' C.14 (1.0)

W b.

r s

t

REFERENCE f Reed Training Manual, Modules 12-6 and 12-7.

i l

i-i l

END OF SECTION C CONTINUE ONTO SECTION D L i L

p-41 L- _ - - - - _ - - .

i CATEGORY D INSTRUMENTS AND CONTROLS

QUESTION

D.01 DELETED Multiple-Choice, Select the correct response.

The Reed TRIGA reactor is provided with a neutron source.

Why is a neutron source needed for a start up if the reactor has been shut down for a long period of time?

a. To ensure that there is a sufficient number of neutrons

to start the' nuclear reaction.

b. Provide a source of neutrons to overcome peak samarium after a long term shutdown.

u c. Provide a source of neutrons to overcome non fissionable daughter product and Pu neutron

['

absorption.

7

d. .To ensure that nuclear power can be accurately monitored during a start up from low count rates.

L

ANSWER

[ D.01 DELETED h

e d. (possible "a" answer.)

REFERENCE Reed Reactor Physics, Heed SAR, Reed Technical Specifications.

i 0

L 42 i

y _

QUESTION '

D.02 (0.75) j Multiple Choice,. Select the correct response.

The Reed Reactor Facility safety control rod is driven by a non synchronous, single phase, electrically reversible motor. Assume safety rod is halfway out of the core when a withdrawal signal is given by the operator.

What is the speed of the RRF reactor safety control rod, in inches per minute (i n/mi n) ?

E a. 14 in/ min.

19 in/ min.

-b.

c. 24 in/ min.

d. 29 in/ min.

ANSWER D.02 (0.75)

, b.

b

REFERENCE

[ RRF TRIGA Mechanical Maintenance and Operating Manual, Pgs.

J 20 - 22.

j l-.

e l

t r

43

'*QUESTION ,

D.03~(O.75) ' -

l Multiple Choice, Select the correct response.

The Reed Reactor Facility regulating control rod fs driven by a servo type motor. Assume the regulating control rod is half way ~ out of the core when a withdrawal signal is given by the. operator?

What is the speed of the RRF reactor regulating control rod, in inches per minute (in/ min)?

, a. 14 in/ min.

I b. 19 in/ min.

c. 24 in/ min.

d. 29 in/ min.

b

ANSWER D.03 (0.75) c.

k

REFERENCE-RRF TRIGA Mechanical Maintenance and Operating Manual, Pgs.

k 20'- 22.

1 i-1 h

1 g +-

.y 1

p-l- 44 o______________ - . __

QUESTION D.04 (0.76)

Multiple. Choice, Select the correct response".

The RRF control rod assemblies are stopped at the top and the bottom of their travel when they are being electrically driven.

What is the component that stops the control rod drive at the' top and bottom of their travel?

a. Limit switches.

. b. Piston in a narrowing chamber.

S.

p c. Pneumatic cylinder.

L ,

[; d. Mechanical stop at each end. i I-f

ANSWER D.04 (0.75)

' a.

REFERENCE RRF TRIGA Mechanical Maintenance and Operating Manual, Pgs.

20 - 22.

s i

t 45

.U *'* * '

I n

____3 _ .._

[ I' : E #'

l

)

1

QUESTION .

' D.05 (1.0) '

'Short Answer.

n The RRF TRIGA control. panel has a mode selector switch which is used to select- tne modes of steady state operation, Manual or Automatic. When in the automatic mode the comparator circuit in the servo amplifier'uses three sources.

of.information.

What are TWO of the THREE (3) inputs to the comparator circuit in the' automatic mode of operation?

(0.5 pts ea. max 1.O' pts.) j f.

F F

ANSWER

'D.05 (1.0) (0.5 pts. ea max 1.0 pts) r s '. 1. Power demand (from the demand pot).

t. .

2. Reactor power (f rom linear ' power channel).

3. Reactor Period (from period circuit).

REFERENCE E

f RRF TRIGA tiechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-15.

L u

1 k

t

t E

QUESTION D.06 (0.75)

Multiple Choice, Select the correct response.

When the RRF TRIGA reactor is selected to the automatic-

n. ode power. level,is contrelled by control. rod movement.

What control rod (s) can the automatic' control system adjust-to' control reactor power level?

(Operation in accordance with SDPs')

. a. Regulating,. shim and safety.

7 Il b. ' Regulating cod only.

c. Shim rod only.

E Regulating, and shim.

'r l d. ')

k l

ANSWER-D.06-(0.75) 6.

Y

REFERENCE RRF TRIGA Mechanical-' Maintenance and Operating Manual ,-

k. Appendix-B, Pgs. 1-15.

s..

g/ A, CA4 ^ a ep4 em 5 h

+

t f

47 )

- -_- - -__- _ _ _ _ - _ _ _ _ _ . - _ _ . - _ 1

QUESTION

.D.07 (0.75) ..

Multiple' Choice, Select the correct response.

Nuclear instrumentation provides input for reactor trips at the RRF TRIGA.

Which of the following nuclear channels provides'a signal f or, a reactor: power scram at 110%7

a. Log power channel.

. b. Count rate Channel, i

k c. Period channel.

V

j. d. Linear power channel .

p

.

ANSWER k D.07 (0.75) d.;

REFERENCE.

L RRF TRIGA Mechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-13 thru 1-15.

l.<

L I

i l

c t

?

t:

r

[

48

=m, -

. --m, .m m -- - , - - , - ~ , - - - -

'r 2

QUESTION

D.OB ~ (0.75)

Multiple Choice , Select the correct response.

The"RRF TRIGA reactor uses several types of nuclear instrumentation.

Which ' nuclear channel . uses a fission type neutron ' detector?

a. Count rate channel.

b. Linear. power channel.

h c. Log power channel, f:

[~ d.- Peri od ' channel .

g

ANSWER

[i f D.OB_(0.75) a.

REFERENCE l RRF TRIGA Mechanical Maintenance and Operating Manual, E- Appendix B, Pgs. 1-13 thru 1-15.

6, e

sA h d Y

L.

r .-

49 h[ :

.. d. .. .~ . , , ,, . , , . , , , _ .

6 1

,!- j 4e )

.i

QUESTION '

D.09 (0.75) g Multiple-Choice,' Select the correct response.

')

The RRF'TRIGA reactor uses several types' of . nucl ear. 1]

instrumentation. One.(1) provides the operator with power, 1 indication f rom ' just above the source level to the f ull ]

power level.

Which nucl ear channel provides this indication?

a. Count rate channel.-

b. -Linear power channel.

r L

c. Log' power channel .

E f-l d. Percent power channel.

a.

ANSWER D.09 (0.75) b.

L

REFERENCE l-k RRF.TRIGA Mechanical Maintenance and Operating Manual,

p. Appendix B, Pgs. 1-13,thru 1-15.

p#

t

~

k e

h 50 t

M:,_:: r:= ~ ~ - - - - - - -

.~ - - - - ~-

QUESTION ED.10 (0.75) .

Multiple Choice, Select the correct response.

The RRF TRIGA reactor.uses several types df nuclear instrumentation. .One of the channels provides the operator with a continuous record of neutron-flux from less then one

- watt to full power.

What channel provides the operator with a continuous record of neutron flux from less than one watt to full power?

a. Linear power channel.

I p b. Log power channel.

c. Period channel.

I p- d. Count rate channel.

p .. '

ANSWER D.10 (0.75) b.

REFERENCE RRF TRIGA Mechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-13 thru 1-15.

G L,'

r F. '

-l l

1 1

i a

N 7

r. '

t 51

i

..f,

QUESTION D.11-(0.75) ,

Multiple Choice, Sel ect' the correct' response.

One of the RRF TRIGA reactor nuclear instrumentation' channels provides the operator:with an indication of the rate of change of power per.second.

Which of _ the following channels provides the operator with indication of the rate of change of nuclear power per

-second?

l a. Linear power channel.

L-V

p. b. Log power channel.

f c. Period channel.

d. Count rate channel.

{

ANSWER D.11 (0.75) c.

l.

L

REFERENCE V

1[

[_

RRFlTRIGA' Mechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-13 thru 1-15.

I t

h i

f" i f

52 i

. . l

QUESTION D.12-(0.75)

~

Multiple Choice, Select the correct response'..

Fission chambers are used at the RRF for detecting neutron-radiation. ' Fissionable material is used to line the wall of the counter tube.

What is' the fissionable material that is used to line the counter tube of a fission chamber?

a. U 235 l- b. Pu 238-P y .c. Au 198 l- -l

[ 'd. NaI, (Thallium) ;

I b

ANSWER D.12 (O.75) .l 1

a.

REFERENCE

' RRF Introduction To Radioactivity, Pg. 12-1-25.

?;

l i g A --

1>

.n-h L

h~

b. 53 y

rm -* sud * " - - ,

,y+ , e * , g* e 3

g ._ ._

_.t 4

QUESTION D.13: (0.75) J' Multiple Choice, Select ' the correct response.

- Fission chambers are used at the RRF for detecting neutron radiation. - Fissionable material is used to line the wall of the counter tube.

What is'the region of the Pulse Size vs. Applied Voltage does the fission chamber operate in? -

a. Geiger. Muller.-

p l- b. - Limited Proportionality.

j;

[

L' -

c. Proportional.

E d. I oni z ati on. -

p b

e F

ANSWER 3 D.13 (0.75) c.

r

-

REFERENCE L

p, ,

RRF' Introduction To Radioactivity, Pg. 12-1-25 & 2-31 y: !

w h .

i t i L; ,

i 1

. 4 E

, 1 i

E l

r 54 i f' .,

e

J s

QUESTION D.14 (0.75) -

])

Multiple Choice, Select the correct response.1 Figure D.14 is a copy of the rack-and pinion' drive mechanism, and the control rod drive assembly. I Which of the f ollowing statements correctly describes the purpose of.the PULL ROD 7

a. Provides a means f or manually adjusting rod position.

b. Provides rod bottom indication.

i c. Provides rod full out position indication.

d. Automatically engages the control rod on a pull signal.

4

ANSWER '

D.14 (0.75) b.

REFERENCE i

RRF SAR, Pgs. 5-8 thru 5-12.

v v

L:

f.

I k

I' 55 I

l er FIGURE D.14 CABLE GU:DE t

b' DRIVE MOTOR

, s MICROSWITCHES ifSPRINGLOADED POTENTIOMETER ROD i- Pj9 %

1 C ..

S Q

&{l g ARMATURE

,, DRAW g ,

TUBE -

} '

h I:

4 TIP OF PUSH ROD :

p ELECTROMAGNET '

FOOT t

o ,

BARREL i i b

~ PISTON

%n /.

CONNECTING ROD

(- o'y i

9 il.

1.-

. "l

. --CONTROL ROD

'3 . :

4 f

9

QUESTION D.15 (0.75)

Multiple Choice, Select the correct response.,

Figure D.14 is a copy of the rack and pinion drive mechanism, and the control rod drive assembly.

Which of the f ollowing statements correctly describes the purpose of the PUSH ROD 7

a. Provides a means f or manually adjusting rod position by pushing the rod in, h b. Provides rod bottom indication.

h t c. Provides rod f ull out position indication.

8 e

I' d. . Automatically engages the control rod on a control rod in signal.

0

ANSWER D.15 (0.75) c.

REFERENCE L RRF SAR, Pgs. 5-B thru 5-12.

L, b

}.:.

L

g. .

i W

D I

t I

56 ,

M_ , :_= _x _2 - __ :r :o 1: ----~~ ~. -- - . . . -

QUESTION D.16 (1.0) 4 Multiple Choice, Select the correct response.

Figure D.14 shows' a potentiometer as part of the control rod drive system.

Which of the f ollowing statements correctly describes' the purpose of the potentiometer?

a. Provides position indication when electromagnet engages the iron armature.

L b. Provides potential voltage as required for'the engagement'of the electromagnet.

c. Provides the potential voltage for deenergizing the electromagnet on a scram signal.

k d. Provides a variable voltage to the rod drive motor f or k regulating control rod speed.

ANSWER D.16 (1.0)

L ..

L a.

1 k

REFERENCE V

RRF SAR, pgs. 5-6 thru 5-11..

e F

f,.

t I

+

w h

y 57

_1__c_____----- -- --

QUESTION D.17 (0.75) r Multiple Choice, Select the correct response.-

Compensated ion chambers are used f or nuclear instrumentation.

What type of radiation does a compensated ion chamber compensate for?

a. Neutron.

b. : Beta.

c. Gamma.

d. . Alpha.

c.

S[

ANSWER D.17 (0. 75) .

c.

REFERENCE.

RRF Introduction To Radioactivity, Pg. 12-1-25 84 2-31 i.

I Y

T' D

e r

.m r

I 58

.g ~, w_ _ ._, ,; _. . .

QUESTION

'D.18 ' (0. 75) .,

Multiple Choice, . Select the correct response.

Geiger. Muller'(G-M) counters are used in radiation detection equipment.

Which of the. f ollowing statements correctly describes the G-M counter.

.a. G-M counters, accurately measure dose rate in greater -

than 10 mr/hr fields. -

ll L b. G-M counters accurately measure exposure _ rate in greater than 10 mr/hr fields.

c. G-M counters only register the counts of whatever radiation that produces the ionization.

f4

/ .d. G-M. counters are used to accurately detect neutron b, radiation in fields of 10 mr/hr or greater.

ANSWER' D.18 (0.75) c.

REFERENCE RRF Introduction to Radioactivity, Pgs. 2-36 & 2-39.

f t

u L.

t:-

t i

1 A

I END OF SECTION D CONTINUE ONTO SECTION E.

r i I

E 59

I CATEGORY E SAFETY AND EMERGENCY SYSTEMS i l

QUESTION E.01 (0.75)

Multiple Choice, Select the correct response.

l" The Reed Reactor Facility (RRF) Technical Specifications-require that the maximum available reactivity not . be above a prescribed delta K/K while " experiments are in place".

What is this Technical Specification f or maximum available core excess reactivity, in % delta K/K, at the RRF7

m. 2.00 % delta K/K.

i-I

. b. 2.25 % delta K/K.

c. 2.50 % delta K/K.

d. 2.75 % delta K/K.

ANSWER E.01 (0.75) b..

L

[A

REFERENCE RRF Technical Speci fications, Pg. 3.

l l

b i

y. . -

6o l.

e*

k.y -.e. . . y, , ,w-~.,q..y,ymy,-.,,-__ .v... . - + - *- + - m , ,

- - - -. ~ -

{'

f.

4-

. s.

.* QUESTION

.i

-E.02 (O.75)

Multiple Choice, Select the correct response.

The RRF Technical Specifications set limitations on the reactivity worth of experiments.

What .is the maximum reactivity worth limit of any single in-core experiment?

a. $1.00

b. $1.35

c. $1.75 0

I a

d.- $2.00

~~l

";

ANSWER k E.02 (O.75) hr b.

REFERENCE k.

RRF Technical Specifications, Pg. 6.

E N'

e.

t n.

t

.a

. t l

L V

I 61

, ~ ~ . . . ,

.. ._,w.- .s

p., j... ...r, ,,-

'r

QUESTION E.03 (O.75)

Multiple Choice, Select the correct response.

The RRF Technical Specifications set limitations on the.

reactivity worth of experiments.

What is the total reactivity _ worth limit of all i n-core

-experiments?

a.- $2.00

b. $2.25 I. c. $2.50 .

C

[ d. $2.75 p.

N h *4NSWER-I'" E.03 (O.75)

I-a.

-

REFERENCE c- .

_ RRF Technical Specifications, Pg.'7.

e j;;

s-wr 1

&~

7, i

62

h. -_=_______ _-_

QUESTION-E.04 (0.75) ,

Multiple Choice, Select the correct response.

The RRF. Technical Specifications set limitations on the reactivity worth of experiments. When experiments meet a specific reactivity worth they.must be located or securely fastened to prevent inadvertent movement during reactor operation.

What is the reactivity. worth limit, that requires experiments to be securely f astened?

a. $1.00 h-

! b. $1.50 l.

!- c. $2.00 h

> d. $2.50 s.

ANSWER E.04 (0.75) a.

b

REFERENCE y

RRF Technical Specifications, Pg. 7.

p p

63 ;

f-

QUESTION E. 05 ' (O.'75) '

.g Multiple Choice, Select the correct response.

RRF Technical Specifications set a limit for the total inventory of iodine (131 through.135) and strontium - 90 isotopes in each f ueled experiment.

What isithe limit for iodine-(131 through 135) i sotope inventory in each fueled. experiment?

a. O.15 curies iodine.

b. 5.0 mil 11 curies iodine.

,c. 1.5. millicuries iodine.

i' . .

e d. 1.5 curies iodine.

t h

j

ANSWER L E.05 -(0.75) d.

t

REFERENCE RRF Technical Specifications, Pg. 7.

a p

p r-h'

!y p.;

5 64

[

h r&rr:: ::=:r _. .

k'

QUESTIDN-E.06 (0.75) 4 ..

'>.r 3 Multiple Choice, Select the correct response.

The RRF Technical Specifications allow operation of the i reactor at two dif f erent power levels. One power l evel is for steady state mode, the other is for testing of the full power safety circuits.

What is the maximum Technical Specification steady state mode power limit for the RRF7

a. 237.5 kilowatts..

.' b. 250.0 kilowatts.

v 1

c. 275.0 kilowatts.

(2 b d. 287.5 kilowatts.

h.

i

ANSWER E.06 (0.75)

b. f

REFERENCE RRF Technical Specification, Pg. 1. l C'

r l

, j i

l'

~

3 l

65 S.. y u' s c. ..

h

QUESTION

' E.07.(0.75)

' Mul ti pl e - Choi ce , Select'the correct response.

' The RRF Technical Specifications allow operation of'the reactor at two.different power levels. One power level is for steady state mode, the other is for testing.of the full power safety circuits.

What.is the maximum RRF Technical Specification power limit for testing.of the full power safety circuits?

a. 237.5 kilowatts.

~

b. 250.0 kilowatts.

h.-

L c. 275.0 kilowatts.

Y. '

I 4

d. 287.5 kilowatts.

f

ANSWER E.07 (0.75)

' d.

f

REFERENCE i-h RRF Technical Specification, Pg. 1.

+

Lise.

[_ % TS C%e C" +ok ot*A* Ow* - 250 tGu '

h r

t 66 L

L.i..-%.....g-...,._,,,...,7_...__7,,...

..c _, .. ,

i

'* QUESTION E.OB (0.75)

Multiple Choice, Select the correct response

'The RRF Technical Specifications state a dinimum shutdown margin for-a condition of cold xenon free and the most reactive control element fully withdrawn.

Whati is. the minimum Technical Specification shutdown margin limit for-these conditions?

a. O.2 % delta k/k.

b. O.4 % delta k/k.

i' c. 0.6 % delta k/k.

E:

b- d. 1.0 % delta k/k.

g !

k.

ANSWER .f

. E.08-(O.75) b.

REFERENCE RRF Technical Speci f i cati on , Pg. 3.e p:

i j

r , 1 I 67 b _e_m__--____ . - -

QUESTION E.09.(0.75) y Multiple Choice, Select..the correct response.

The RRF Technical Specifications state the maximum rate-of reactivity insertion associated with the movement of a-standard control rod?

What is' the maximum rate of reactivity insertion f or -the movement of a standard control rod?

i

a. 2.25 % delta k/k sec.

f") b. O.40 % delta k/k sec.

V f c. 1.12 % delta k/k sec.

p '

)- d.. O.12 % delta k/k sec.

[ -

.

ANSWER E.09 (O.75) d.

REFERENCE

?

RRF Technical Specification, Pg. 3.

NL PL g

L A g i

t t

\

l'

! 68

=- __.=__c, - ._+:, , , . - - .. n ., = - . . . .

.i i

QUESTION j E.10 (0.75)

Multiple Choice, Select the correct response, f 1

RRF Technical Boecifications set a l i .ni t for the total inventory of io'ine d (131 through 135) and strontium - 90 isotopes in each f ueled experiment.

What is the limit f or maximum strontium - 90 isotope inventory in each fueled experiment?

a. 0.5 millicuries strontium,

b. 1.5 millicuries strontium.

c. 0.5 curies strontium, h

d. 5.0 millicuries strontium.

ANSWER I E.10 (0.75) d.

REFERENCE RRF Technical Specifications, Pg. 7.

r .

t I- 69 Y

e _

W ti; r

g

QUESTION-E.11 (1.5)

'?

Short Answer.-

Of the six reactor scrams at the RRF.two are'high power (110%) scrams and one is the manual scram.

What are the THREE (3) other-reactor-scrams? 'l (0.5 pts. ea.) (1.5)-

ANSWER E.11 (1.5) (O.5 ea. max. 1.5 pts.) !

1. Reactor period (high). (0.5)

!? 2. Ion chamber power supply failure. (0.5) f . .

s

3. Console power (circuit)' failure (0.5) f- or external scram.

k Ti

REFERENCE RRF SAR, Pg. 5-16.

i r

R.

k

-i' F .-

I s

0 g.,_

b, w t

t

[

t>

r 70

- - ____ _ =_ ,._ - - _ __ -- -- - :__: _ ._ ___ _ _ . - _ _ _

EJ p.

QUESTION.

E.12 (1.0)

Short Answer.

RRF. Technical Specifications require that at a minimum THREE

'(3) reactor safety circuits be available prior to start'up.

One (1)'of the circuits is the-manual scram button'on-the ]

console.

What are the other TWO (2) safety. circuits?

(0.5 pts. ea.~) (1.0)

ANSWER y E.12 (1.0) (0.5 pts. ea. max 1.0 pts.)

y -1. Linear power (110%) (0.5)

2. Percent power ~(110%) (0.5)

REFERENCE

- RRF Technical Spe: ification, Table I.

s-2 L

kb g

c p

k i

4

.y.

L. ,

l I

71 i:

('

e.

QUESTION E.13 (1.0)

Short Answer.

RRF Technical Specifications require that at a minimum TWO interlocks be available prior to start up.

What are the TWO (2) interlocks?-(0.5 pts. ea.) ( 1. 0) -

'

ANSWER E.13 (1.0) i .

E ' 1. Control rod withdrawal with less than (2 cps) required I neutron' count rate per second on start up channel. ( 0. 5) '

s

?

p 2. Simultaneous manual withdrawal of two control rods. (0.5)

REFERENCE

[

RRF Technical Specification, Table II, pg. 9.

i:

?

k*

45-t

!, j

. i t

72

~ _ , . :--_ _~ . - _ ~ _ _ _ _ , _ . , _ - . .. . . . . - ,,.. . ,

1

. 4

QUESTION E.14 (0.75) ' c.

.y.

Multiple Choice, Select the correct response.'

The RRF has radiation monitors which actuate alarms and/or ventilation confinement when preset levels of radiation are-sensed by'the detectors.

Which of the following radiation. monitoring systems will cause a ventilation confinement actuation?

a. CAM b b. . RAM

f. .

c. ' Bulk water temperature, b d. Particulate stack monitor.

f5

ANSWER E.14 (0.75)

A.

REFERENCE b RRF Emergency Plan, Appendix D,'and SOP 65.

g9 b

f v':;

,}

4 r

N o

73 m

u --- -

i y

l

QUESTION E.15'(0.75) 3 Multiple Choict, oelect the correct response.

~

The RRF.has radiation monitors which actuate alarms an'/or d ventilation confinement when preset levels of radiation are sensed by the detectors. In accordance with RRF Emergency.

Plan, Appendix D.

What'is the alarm set point of the Continuous Air Monitor (CAM)?

h 'a. 400 CPM V b. 2 mR/hr

c. 1500' CPM

d. 2000 CPM j 1

7

ANSWER E.15'(0.75) j

, d.

.( '*REFERENCE !

RRF Emergency Plan, Appendix D, and SDP 30.

e - - ~a - ~ ns .

{:

M I

!~ - 74 I-r a _crrnur wrrrrr __ _ -r , 7 - --

QUESTION E.16.(0.75)

Multiple Choice, Select the correct. response.

The RRF has radiation monitors which actuate alarms and/or ventilation confinement when preset levels of radiation are sensed by the detectors. In accordance.with.RRF. Emergency Plan, Appendix D.

What is~ the alarm set point of the Radiation. Area Monitor.

(RAM)?

a. O.2 R/hr E

c b. 2 mR/hr

c. 150 CPM

[

h .d. 200 CPM L:

!a gs 1

ANSWER E.16 (0.75) b.

f:

REFERENCE k'

RRF-Emergency Plan, Appendix D, and SDP 70.

W 'r.

P j

-V r

I' h.

75 to m.=,= _. _ .-

iL t

QUESTION ,

E.17 (0.75) ,

ii; Multiple Choice, Select the correct response.

The secondary water system is operated at a pressure above that.of the reactor water (primary) system. In accordance with RRF Emergency Plan, Appendix D.

What is the' low pressure alarm ~ set' point for the. secondary

,_ system? (1.0)

.a. 35 psi.

i.

b.' 40 psi.

E c. 45 psi.

.d.. 50_ psi.

L

ANSWER E.17 (0.75) b.

k .* REFERENCE I .RRFL Emergency. Plan, Appendix D, and SDP'62.

I

=-

g N

f. 76 L- _ _ __- _ - ___-___-_-_-- _-__ _ _ -

QUESTION E.18 .(0.5)

Short. Answer.

The ' secondary water system is operated at a pressure above that of the reactor water (primary) system.

Why is the secondary water system operated at a higher pressure than the reactor water system?-

ANSWER E.18 (0.5) i

' Leakage will be from the. secondary to the primary, or.

L prevent reactor (radioactive) water f rom leaking to the environment. (0.5)-

{

e.

l .* REFERENCE-s' SOP. 62.

L p

o

.l END OF SECTION E CONTINUE ONTO SECTION F..

L.

77 h

~ m-Q - r . = - . . _

,* ~' , ~ " '

r i , 'k I i

CATEGORY F STANDARD.AND EMERGENCY DPERATIN

G. PROCEDURE

S

QUESTION F.01 (0.75)

Multiple Choice, Select the correct. response.

Reeds Emergency Implementation Procedures (EIPs) allow-limited-re'- entry of personnel'into an area that has been evacuated due to a radiological problem if the entry is to

. save a lif e or. prevent a serious accident.

I What is-the title of the person who can authorize this re - entry, in accordance with RRF EIPs 7 p: a. Senior Reactor Operator.

i.

k;, b." Reactor Operator l i

I c. Emergency Coordinator d.. Reactor Supervisor L

ANSWER k F.01 (0.75) 5 T- c.

p;

REFERENCE RRF Emergency Implementation Procedures, Appendix c.

P t

4 =

n 78 LE-~ _u____. . _ - . . . . . - . . !

a.

QUESTION F. 02 - (0.'75)

Multiple Choice, Select the correct response.

Reeds; Emergency Implementation Procedures (EIPs) allow limited re - entry of personnel into an area that has been evacuated due to a radiological problem if the entry'is to save a life or prevent a serious accident. The dose. rate and-personnel doses are limited during the entry.

What is the maximum allowable radiological dose rate for re - entery, in accordance with RRF EIPs?

[ a. 10 R/hr

[-

!< b. 25 R/hr-p L

c. 75 R/hr

% d. 100 R/hr'

(. .

ANSWER F.02 (0.75)-

L d. .

1

.

REFERENCE RRF Emergency Implementation Procedures, Appendix c.

I u

?

I p'-

79

QUESTION F.03-(0.75) A Multiple Choice, Select the correct response. l Reeds Emergency Implementation Procedures (EIPs)' allow limited re - entry of personnel into an area that has been l evacuated due to a radiological problem if the . entry is' to save.a life or prevent a serious. accident. The dose rate and-personnel doses are limited during the entry.

- What 'is the maximum personal dose allowed by RRF EIPs to save another persons life 7

a. 2.5 Rem k b. 25' Rem

c. 50 Rem

d. 100 Rem h

ANSWER F.03'(0 . 75) b.

REFERENCE-

[, RRF Emergency Implementation Procedures, Appendix c.

e_

s h .

j. -

L l.'

i:

m

I Y

+

QUESTION F.04 (2.0)

Short Answer.

An irradiated experiment containing Pu - 239 has been

. spilled 'in the radiochemistry lab. The evacuation' alarm is sounded.and all personnel. evacuate.-The Reactor Operator.is responsible'for taking.the console key,cand closing and /or

- locking specific doors upon evacuation. One of the doors is:

the reactor bay door between the reactor bay and the control-room.

a. Where are the TWO (2) locations that the evacuation alarm L. can be initiated f rom? (0.5 pts ea.) (1.0)

L

~ b..What'are the TWO (2) other doors the' Reactor Operator is responsible f orf closing and/or locking during an evacuation? (0.5 pts ea.) (1.0)

[.

[

ANSWER

?' F. 04 ' (2. 0)'

a.-Control consol (right. side red button). (0.5)

Reactor Bay (south wall). (0.5) b.

[ 1. Control room door (l ock ) . (0.5) 2, Radiochemistry Lab (between radiochemistry lab and exit corridor). (0,5)

i .

0~

J.-

p.

[

REFERENCE RRF Emergency Implementation Procedures, Appendix c.

4 t p

i-i x

01 L _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ . _ .

I

\ ,

QUESTION F.05 (0.75)

Multiple Choice, Select the correct response.

During an evacuation of the f acility a staf f person is required to pick up the emergency grab bag.

Where is the emergency grab bag located?

a. Emergency exit door reactor bay.

>b. Radiochemistry room.

, c., Control room.

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I d. Exit corridor.

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ANSWER F.05 (0.75) b d.

REFERENCE RRF Emerg'ency Implementation Procedures, Appendix c.

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i. 82

_________1__ ________.__:_.____ _ . _ . l

QUESTION F.06 (0.75) 4 Multiple Choice, Select the correct response.

RRF' Technical Specifications and administrative procedures establish' organizational reporting guide lines and position responsibilities.

What is the title of the person that.the Reed Reactor Facility Director. reports to and is directly responsible to?

a. Reactor Operations Committee Chairman.

[- b. . Radiation . Saf ety Committee Chairman.

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h c. President of Reed College.

i It d. Reactor Review Committee.

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ANSWER.

b F.06 (0.75) c.

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REFERENCE L

f) RRF Technical Specifications, and RRF Administrative

{ Procedures.

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QUESTION.

'F.07 (O.75)

Multiple Choice, Select the correct response.

RRF Technical Specifications and administrative procedures establish organizational reporting guide lines and position

-responsibilities.

What is' the title of ' the person who is responsible f or approving'all reactor experiments?

a. Director of Reed Reactor Facility.

+ b. Reactor Supervisor.

g.

'- ce Reactor Operations Committee Chairman.

d. Radiation Saf ety Committee Chairman.

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ANSWER F.07 (0.75)

- a .'

REFERENCE I RRF. Technical Specifications, and RRF Administrative Procedures.

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QUESTION '

F.OB (0.75)

Multiple Choice, Select the- correct response.

The Reactor Review Committee (RRC) is established to to

- provide f or a review and audit of reactor f acility operations.

How-often are the RRC sub committees required to meet? I

a. Once.a year.

b. .Twice'a year.

c. Three times.a year.

Monthly.

[

L d.

ANSWER i

F.OB (0.75) b.

REFERENCE RRF Technical Specifications, and RRF Administrative

~~;3 Multiple Choice, Select the correct response.~~

~~Start up and Core Excess Check procedure BOP 03 personnel~~

~~. requirements state that the reactor SHALL be operated by:or under the direct supervision of a person who holds a valid-Operator or Senior Operator license issued by the NRC.~~

~~What is the title of the person who is responsible for the selection of personnel to operate the Reed College Reactor?~~

~~a. Director RRF.~~
b:
i b. President of Reed College.
I;
~~, c. Reactor Safety Committee Chairman.~~
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~~d. Reactor Supervi sor.~~
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~~ANSWER F.09 (0.75) a.~~
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~~REFERENCE i~~
~~b RRF Technical Specifications, and RRF Administrative Procedures, and SDP 3.~~
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~~QUESTION F.10'(0.75)~~
Multiple Choice,- Select the correct response. '
As the reactor operator you are conducting a start up in accordance with " Start up and Core Excess Check" procedure-SDP 3.'Before pulling the safety and shim rods the regulating rod-is pulled in~ anticipation of future automatic operation.
How far out is the regulating rod pulled?
a.- '20 % of its rar.ge.
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F' b. 50 % of its range.
h c. 75 7. of.its range.
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~~d. 90 % of its range.~~
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~~ANSWER F.10 (0.75) b.~~
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~~REFERENCE k RRF SDP 3.~~
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~~QUESTION F.11 (0.75) /. i~~
d.
Multiple Choice, ' Select ' the correct response.
As the reactor operator you are conducting a start up in accordance with " Start up and Core Excess Check" procedure SOP 3. When performing a start up the period i s limited.
What is 'the minimum reactor:. period allowed during a start up?
~~a. 5 seconds.~~
~~b. 7 seconds.~~
I
~~c. 10 seconds.~~
~~d. 15 seconds.~~
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~~ANSWER F.11 (0.75) c.~~
~~REFERENCE l~~
[- RRF SOP 3.
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~~QUESTION ~~~
F.12'(0.75)
Multiple Choice..' Select- the correct response.
As the reactor.' operator you are conducting a start up in accordance with'" Start up and Core Excess Check" procedure SDP 3. When reactor power reaches a minimum preset point the-linear power range should be shifted.
What' is the minimum power at ' which the linear power range' can be shifted?
~~a. 35 %~~
~~b. 40 %~~
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~~c. 45 %~~
d.. 50 %
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~~ANSWER~~
~~- -F.12 (0.75) d.~~
~~REFERENCE i .:~~
~~RRF SDP 3.~~
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~~C . = _ _ _ . .- _.~~
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~~QUE.STION F.13 (0.75) .~~
Multiple Choice, Select the correct response.
RRF procedure SDP 04, Reactor. Operations, precautions the operator to not operate the reactor above 96 % reactor power.
What is the reason for not operating the reactor'above 96 %
power?
~~a. Account for fluctuations that may,take power above~~
, licensed limit.
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[ b. Account f or burnout of fission product poisons that increase. cladding temperature above limits.
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b' t c. Insure that the control rods are inserted to a point where they have sufficient bite.
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~~d. Precaution against f uel element swelling from continued-high power operations.~~
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~~ANSWER F.13 (0.75) a.~~
~~I N~~
~~REFERENCE 3~~
K RRF SDP 04.
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ - . )
- _ - _ _ _ - _ _ - - _ _ - - _ _ _ . _ - - - _ _ - - - - ___ _ _ _ . , . - - _ - _ . __ _-_ _. . _ _ - - - _ _ ____-_ -_ _ = - _
~~QUESTION '~~
F.14 (0.75)
Multiple Choice, Select the correct response.
As a licensed reactor oper.ator you are performing a reactor power calibration in.accordance with RRF procedure SDP 43.
Prerequisites require that the-reactor not be operated for a period of time bef ore the calibration to minimize the effects.of a fission product poison.
What is the fission product poison?
~~a. Thallium~~
~~b. Samarium~~
~~c. Cesium I-~~
~~d. Xenon~~
~~ANSWER F.14 (0.75) d.~~
I '- -* REFERENCE 8 L
b RRF SDP 43.
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~~QUESTION F.15 (0.75) . .c As a licensed reactor operator you are perf orming a reactor .~~
power calibration ' in accordance with' RRF procedure SDP 43.
Which'of the f ollowing statements correctly describes the l parameters'needed to complete the calibration? .
~~a. Time and reactor water pump flow'.~~
~~b. ' Reactor water pump flow and temperature.~~
~~c. Reactor water pump pressure and temperature.~~
d.. Reactor water temperature and time.
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~~ANSWER i- F.15 (0.75)~~
I d.
-
~~REFERENCE RRF SDP 43.~~
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~~DUESTION F.16 (1.0)-~~
.Short. Answer.
The RRF. Emergency Plan classifies THREE. credible Emergency Action Levels (EALs).
Wha't are TWO of the THREE (3> credible EALs f or the RRF7 (0.5 pts. ea.-max 1.0 pts) - (1.0)
~~ANSWER F.16 (1.0) (0.5 pts ea. max 1.0 pts.)~~
r
~~1. Non-Reactor Safety Related Event.~~
k 2. Noti fication of'. Unusual Event, (NOUE).
t E 3. . Alert.
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~~REFERENCE RRF EP.~~
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~~QUESTION F.17-(1.0)~~
Shortl Answer.
An. electrical and chemical' fire has causedan evacuation of the RRF in accordance with RRF Emergency Implementation Procedures (EIPs). You are required to -trip the main facility electric circuit breaker as part'of your duties..
~~a. What is the name of the hospital that injured RADIOLOGICALLY CONTAMINATED personnel are taken to?'~~
~~(0.5)~~
~~b. Where is the emergency key kept to allow. you to gain b access to the main facility electric breaker? (0.5)~~
~~F r~~
~~ANSWER L F.17 (1.0) i~~
~~a. Good Samaritan. (0.5)~~
~~b. (Emergency) Grab Bag. (0.5)~~
~~REFERENCE s~~
- RRF EIPs..
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END OF SECTION F CONTINUE ONTO SECTION G.
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1
7-.
CATEGCRY G RADIATION CONTROL AND SAFETY
~~QUESTION G.01 (0. 75)~~
' Multiple Choice, Select the correct response.
Quality factors.are used to convert. Roentgen per hour (R/hr) to Roentgen Equivalent Mammal per hour (Rem /hr).
What is the Quality Factor.used to convert a dose of gamma-rays in R/hr to Rem /hr?
r a. 1.
. b. 5.
~~c. 10.~~
[ d. 20. .
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~~ANSWER G.01-(O.75)~~
F: a.
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~~REFERENCE RRF ' Introduction to Radioactivity, Chap'2, 2-2 & 2-3.-~~
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~~QUESTION G.02 (0.75) e~~
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Multiple Choice, Select the correct response.
Quality factors are used to convert Roentgen per hour (R/hr) to Roentgen Equivalent Mammal per hour-(Rem /hr).
.- What L is the Quality Factor used to convert a dose of Beta particles:in R/hr'to Rem /hr?
~~a. -1.~~
~~b. 5.~~
~~g c. 10.~~
~~d. 20.~~
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~~ANSWER~~
~~l. G.02 (0.75) f.~~
a.
~~REFERENCE RRF Introduction to Radioactivity, Chap 2, 2-2 84 2-3.~~
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~~QUESTION G.03 (0.75)~~
Multiple Choice, . Select the correct response.
Quality factors are used'to convert Roentgen per. hour (R/hr) to Roentgen Equivalent Mammal per hour.(Rem /hr).
- What is the Quality Factor used to conver't. a - dose of Alpha -
particles in R/hr to Rem /hr'l
~~a. 1.~~
~~b. 5.~~
~~c. 10.~~
~~O d. 20. .!~~
~~ANSWER f.~~
~~G.03 (0.75) s i d.~~
~~REFERENCE RRF Introduction to Radioactivity, Chap 2,.2-2 & 2-3.~~
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- *QLJESTION G.04 (0.75)
.a Multiple Choice, Select the correct response?
- Quality factors are used to convert Roentgen per hour
- (R/hr) to Roentgen Equivalent Mammal per hour (Rem /hr).
What is'the Quality Factor used to convert a dose of fast neutrons in R/hr to Rem /hr?
~~a. 1.~~
~~b. 5.~~
~~c. 10.~~
~~d. 20.~~
~~f. ,~~
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~~ANSWER~~
~~i. G.04 (0.75)~~
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c.
~~REFERENCE RRF Introduction to Radioactivity, Chap 2, 2-2 84 2-3.~~
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~~QUESTION G.05-(0.75)~~
Multiple Choice, Select-the correct response.
The Code of Federal Regulations (10 CFR 20)' specifies quarterly occupational- radiation' dose standards f or individuals to the whole body. Whole' body defined-as; head and trunk, active blood forming organs, lenses of the eye,.
or gonads.
What is the 10 CFR 20 quarterly occupational radiation dose standard to the whole body?
~~a. 1.25 Rem.~~
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~~b. 3.'O Rem.~~
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~~c. 7.5 Rem s~~
d.- 18.75 Rem,
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~~ANSWER G.05 (0.75) a.~~
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~~REFERENCE r~~
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~~QUESTION G.06-(0.75) , ..s. .~~
Multiple Choice, Select the correct response..
The Code of Federal' Regulations (10.CFR 20) specifies quarterly occupational ~ radiation dose ~ standards f or individuals ' to the skin of ' the whole body.
What-is the 10 CFR 20 quarterly occupational radiation dose standard to the skin of the whole body?
~~a. 1.25 Rem.~~
4 b. 3.O Rem.
I.
~~c. 7.5 Rem i d. 18.75 Rem.~~
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~~ANSWER G.06 (0.75)~~
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~~REFERENCE p.~~
~~b. 10 CFR 20 (20.101)-~~
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~~QUESTION G.07-(0.75) -~~
- Multiple Choice, Select.the correct response.
The' Code of Federal Regulations (10 CFR 20) specifies-quarterly occupational radiation dose. standards for individuals to the hands and forearms.
What.is1the-10 CFR 20 quarterly occupational radiation dose standard to the hands and forearms?
~~a. 1.25 Rem.~~
L b .' 3.0 Rem.
c.- 7.5 Rem e-
~~d. 18.75. Rem.~~
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~~ANSWER G.07.(0.75)~~
L d.
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~~REFERENCE y~~
10 CFR 20 (20.101) s 1 f:
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~~QL'EST ION G.OB (1.O) '~~
A,.
Short Answer.
The Code of Federal Regulations'.(10 CFR 20) states that a licensed facility'may permit a radiation worker to exceed the standard' occupational dose if THREE (3) conditions-are met. One of'which.is.that the worker has a NRC' form 4 or
~
equivalent onfi1e.
What are'the two (2) other conditions? (0.75 pts each, max 1.0 pts.) (1.0)
I
[
~~ANSWER l' G.OB-(1.0)' (0.5 pts each, max 1.0 pts.)~~
s..
I 1. Dose (to the whole body) does not. exceed 3 rem during L the calendar quarter. - (0. 5) . ;
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~~2. Dose (to the whole body) does not.. exceed 5(N-18).(0.5)~~
~~REFERENCE-10 CFR 20 (20.101) r:~~
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~~QUESTION {~~
G.09 (1.25) 'l b
j: Calculation, Show All Work. l g A point source of radioactivity measuring 90 Rem /hr of gamma at DNE (1). meter has been detected. Assume 100% detector 3- ..
efficiency for gamma radiation.
. g.. How far away from the point source will you have to move to
,y.
reduce your exposure 20 Rem /hr? (1.25)-
SHOW ALL WORK 1 (1.00 application.)
L- (0.25 for answer) l
?-
1 .
~~ANSWER~~
,[ G.09~(1.25) h, applications D 3
/D 2 = (L 2
/ L )2 g
(0.75)
(80 / 20) 1 = (L ) (0.25) 2
'k L = 2 meters (0.25) 2 a
~~REFERENCE RRF Introduction to Radiation, Pg. 2-21.~~
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~~DUESTION G.10 (1.5)~~
Calculation, Shts All Work.
A radioisotope has been removed f rom a sample tube. The sample is reading 4 Rem /hr at one (1) foot. From the experiment data you find out that the radioisotope decays by-a 0.5 Mev gemma. . Assume the radiation is totally f rom the radioisotope and that the meter being used is 100%
efficient.
How many curies does the sample contain? (1.5) p SHOW ALL WORK
~~(1.25 f or application) i (0.25 for answer)~~
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~~ANSWER G.10 (1.5)~~
(1.25 pts application, 0.25 pts answer.)
R/hr = 6 CE n / L (0.5) 4 Rem /hr = 6 C (0.5 Mev)(1) / 1 (0.5)
(, ,. C = 4 Rem /hr (1 ) / 6 (1) (0,5) (0.25)
V C ='1.33 curies- (+/- O.1 curi es) (0.25)
~~REFERENCE F RRF Introduction to Radiation, Pg. 2-22.~~
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~~QUESTION G.11-(0.75)~~
Multiple. Choice, Select the correct response.
Reed Reactor Facility personnel are trained to use different types of portable radiation detectors, both for' daily survey 1 and emergency use.
Which of the f ollowing instruments would be used. to detect HIGH range Beta - Gamma radiation during an emergency condition?
~~a. Eberline Model E-140.~~
~~b. Model RD-2.~~
U I' c. CD V - 700 model '6B.
I d.- CD V - 715 model 1B.
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~~ANSWER~~
~~,. G.11 (0.75) d.~~
~~REFERENCE p~~
I- RRF Introduction to Radiation and Rad. Inst. Manuals.
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~~QUESTION -~~
G.12 (0.75) ;
, 4 l
Multiple Choice, Select the correct. response., 1 ci
,I Reed Reactor Facility personnel are trained to.use different '
types of. portable radiation detectors, both for daily survey-
, and emergency use. R
.. j Which. of the f ollowing instruments would is used as a frisker to detect contamination on personnel hands?
~~a. Eberline Model E-140.~~
~~b. Ludlum Model 3.~~
~~V f-~~
~~c. Ludlum Model 2.~~
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~~d. Model 177.~~
b.
~~ANSWER G.12 (0.75) d.~~
~~REFERENCE' L.~~
RRF Introduction to Radiation and Rad. Inst. Manuals, w
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~~QUESTION 1 G.13 (0.75)~~
Multiple Choice, Select the correct response.
Reed Reactor Facility personnel are trained to use different-types of portable radiation detectors, both f or daily survey and emergency use.
Which of the f ollowing instruments can be used to discriminate Beta from Gamma radiation?
. a. CD V - 715 model 1B.
E b. Eberline Model RO - 2.
~~2. Ludlum Model 2.~~
~
~~d. Model 177.~~
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~~ANSWER G.13 (0.75) b.~~
~~REFERENCE E RRF Introduction to Radiation and Rad. Inst. Manual s.~~
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~~QUESTION G.14 : (0. 75)~~
Multi ple Choice, Select the correct response.
Which of the statements correctly describes Alpha radiation?
~~a. Particles' that lose energy rapidly in any medium due to high ionization level.~~
~~b. Radiation that has a higher penetrating power than gamma radiation,~~
~~c. Radiation that requires a thin lead shield due to high penetration and low ionization level.~~
~~d. Particles that have a higher penetrating power than h~~
t' fast beta radiation.
I y

~~ANSWER f- G.14 (0.75) y s~~
a.
~~REFERENCE h RRF Introduction to Radioactivity, pg. 2-23.~~
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~~QUESTION G.15 (1.0)~~
Multiple Choice, Select the correct response.
Which of the f ollowing statements correctly describes neutron radiation?
~~a. The energy loss by neutron radiation is mainly due to~~
~~. the ionization of other atoms as it passes by,~~
~~b. Neutron radiation is redirected in direction due to the repulsion of negatively charged atoms.~~
? c. Neutrons lose _ energy as they pass through matter by elastic and inelastic scattering with nuclei.
1 s d. Neutrons cause the direct opposite ionizing ef fect as f alpha radiation due to the opposite charge .
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~~ANSWER G.15 (1.0) c.~~
~~REFERENCE~~
[ RRF Introduction to Radioactivity, pg. 1-25.
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~~QUESTION G.16 (O.75)~~
Multiple Choice, Select the correct response.
Ingestion of radioactive materials is a major concern. For the'same curie amount different types of radiation cause different amounts of biological damage.
Which of the following types of radiation will cause the-greatest biological damage f or the same curie amount when-ingested?
~~a. Alpha.~~
p b. Beta.
I c. .G?mma.
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~~d. X-ray.~~
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~~r4NSWER j G.16 (0.75) a.~~
~~REFERENCE~~
(' RRF Introduction to Radioactivity, Chap 1.
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~~QUESTION-G.17 (0.75) < -~~
Multiple Choice, Select the correct response.
A. radioactive materials transfer is being made from the RRF to an. experimenter. You are requested to check the recipients licenne to make sure that it is current.
Where are copies of recipients current licenses kept?
~~a. Console room file cabinet.~~
~
~~b. RRF, Health Physicist office file cabinet.~~
~~c. RRF, Associate Directors of fice files.~~
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~~ANSWER G.17 (0.75) a.~~
~~REFERENCE r~~
e RRF SDP - 52.
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e END OF SECTION G END OF WRITTEN EXAMINATION
(
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C- _ _;_ _. _ _ _ _ . _ _ . _ . .
-?
As biVen b As hecded (C.eD U.S. NUCLEAR REGULATORY COMISSION SENIOR REACTOR OPERATOR LICENSF EXAMINATION' . .
Facilityi REED COL 1.EGE -
Reactor Type: TR:GA MARK 1 Date Administered: Mov 16, 1989 Examiner: Michael J. Royack.
Candidate: * * * " " " " % t. I ' ' ' ' ' - ~ ~ ~ 6 INSTRUCTIONS TO CANDIDATE 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 -
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 , Applicant's % of Category Value Total Score Cat. Value wN M H. Reactor Theory 70 20.14 1. Radioactive Materials Handling Disposal and Hazards -
20 20. 6 J. Specific Opera *,ing Characteristics 20 20.t 4-K. Fuel Handling and Core Parameters 20 2M 4 L. Administrative Procedures, Conditions and Limitations d@ 100
, Totals Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
KEY *********
Candidate', Signature 9
_m____.__.__ _ - . . _ _ _ _ i
l l k
ES-201 !
Rev 5 01/01/89 1 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
1. A single room shall be provided for administration of the written examina-tion. The location of this room and supporting restroom facilities shall - i be such as to prevent contact with all other facility and/or contractor !
personnel curing the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee. '
~~2. Minimum spacing is required to ensure examination integrity as oetermined i by the Chief Examiner. Minimum spacing should be one applicant per table, !~~
? with a 3 foot space between tables.
> l
> 3. Suitabic arrangements shall be made by the facility if the applicants are L !
to h ne lunch, coffee or other refreshments. These arrangements shall
~~comply with Item 1 above and shall be reviewed by the examiner and/or f~~
~~proctor.~~
4. The facility licensee shall provide pads of.8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in completing the examination. The examiner shall distribute these pads to the applicants.
5. Applicants may bring pens, pencils, calculators or slice rules into the examination room. Only black ink or dark pencils should be used for f writing inswers to questions. ,
[ 6. The licensee,shall provide one set of steam tables for each applicant.
j~ The examiner shall distribute the steam tables to the applicants. No wall j charts, models, and/or other training materials shall be present in the ;
examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
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Examiner Standards
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Rev 5 01/01/89 3
Y PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
~~1. Check identification badges.~~
~~2. Pass out examinations and all handouts. Remind applicants not to review examination until' instructed to do so.~~
.x READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this examination the following rules apply:
~~1. Cheating on the examination means an automatic denial of your application i and could result in more severe penalties.~~
~~I" 2. ' After the examination has been completed, you must sign the statement on the cover sheet indicating.that the work is your own and you.have not~~
~~received 3r given assistance in completin~~
~~[ done; after you complete the examination. g the examination. This must be READ THE FOLLOWING INSTRUCTIONS~~
1. . Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone.outside the examination g; room to avoid even the appearance or possibility of cheating.
J 2.
h Use black ink or dark pencil only to facilitate legib'le reproductions.
~~3. Print your name in the blank provided in the upper right-hand corner of 7 the examination cover sheet. . .~~
~~f,L 4. Fill in the date on the cover sheet of the examination (if.necessary).~~
~~5. You may write your answers on the examination question page or on a 6 separate sheet of paper. USE ONLY THE PAPER PROVIDED AND 00 NOT WRITE ON~~
[r THE BACK SIDE OF THE PAGE. .- .
j $ 6. If you write your answers on the examination question page and you need g more space to answer a specific question, use.a . separate sheet of the
, paper provided and insert it direct-ly after the specific question. DO NOT
, 6 WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
l- . . . . y. .
.y. .
. ~~c.
t 7. Print your name in the upper right nand corner of the first page..of eache- -
i section of your answer sheets whether you use the examination question p pages or separate sheets of paper. Initial each page. .
~~8. Before you turn in your examination, consecutively nustAr each answer I sheet, including any additional pages inserted when writing your answers~~
{ on the examination que,stion page.
j
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Examiner Standards
~
4 -,_--u-a_--_ _=,.,,m,,--awaw>,.m+.- . s seu i e-s
ES-201 Rev 5 01/01/89
9. If you are using separate sheets, ntsaber each answer as to category and number (i.e. 1.04,6.10) and skip at least 3 lines between answers to allow space for grading. ,
~~10. Write "End of Category " at the end of your answers to a category.~~
~~11. Start each category on a new page.~~
~~12. Write "Last Page" on the last answer sheet. .~~
~~13. Use abbreviations only if they are commonly used in facility literature.~~
~~Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out..~~
h. 14. The point value for each question is indicated in parentheses after the k question. The amount of blank space on an examination question page is I NOT an indication of the depth of answer required.
k
~~15. Show all calculations, methods, or assumptions used to obtain an answer.~~
~~! 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION p AND DO NOT LEAVE ANY ANSWER BLANK.~~
17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth
[, 0.20 points. If one of your five responses is incorrect, 0.20 will be
[ deducted and your total credit for that question will be 0.80 instead of E 1.00 even though you got the four correct answers.
~~18. If the intent of a question is unclear, ask questions of the examiner only.~~
~
~~19. When turning in your examination, assemble the completed examination with examination questions, examination sids and answer sheets. In addition, turn in all scrap paper.~~
~
~~20. To pass the examination,.you must achieve an overall grade of 80% or greater and at least 70% in each category.~~
~~21. There is a time limit of (6) hours for completion of the examination.~~
~~(or some other time if less than the full examination is taken.)~~
~~. 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination l~~
3 is still in progress, your license may be denied or revoked. ,
h ,
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Examiner Standards -
L _ __ _ ___ _ _ _ _ _ _ _______-_ _ ._ _ __ _ - - = - -- -
c h .
EQUATION SHEET
?
t, f"M v =. s/t
'"4 s = v t +. hat2 Cycle efficiency = Net W rk (out)
Energy (in) 2 E = aC a = (vg - vp)/g ,
E"N vf = v, + at A = AN A = i pe"At PE = agh a = 8/t 1 = in 2/tg = 0.693/tg ,
W = v&P (ti;)(ts)
T=I n / delta k ,bg,gg) ,
AE = 931Am
$ = delta k/ Beff * (* * *b) ,
6-5C,AT , y . y
- Ix ,
6=UAAT y . y vx ,
Pwr = Wg E I=I 10'*
r . P = P ,10 M(t) TVL = 1.3/u P=y et/T , EVL = 0.693/g SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg) ,
sUR = 26 fa*fr )
p CR, = S/(1 - Kefh),
g,,
2 C ~
eff)1 " 2(1 *K,gg)2 T = '(1*/o ) + [(i-' p)/A,ffp ]
7 . g*f (, _ p M = 1/(1 - K,gg) = CR /CR0 g T = (3 - p)/ A*gg o M = (1 - K,gg)D/Il ~ Eeff)1
'" eff~I) Eeff " #eff/K,gg s.
, sm , (l - K,gg)/K,gg
~
P= [1*/TK,gg ] + [I/(1 + A,ggT )] 1* = 1 x 10 seconds g
P = I(V/(3 x 1010) aff = 0.1 seconds" i I = No -
Idgg=Id22 WATER PARAMETERS Id =Id y f ,
g l 1 gal. = 8.345 lba R/hr = (0.5 CE)/d (meters) i 1 gal. = 3.78 liters R/hr = 6 CE/d (feet) 1 ft = 7.48 gal. MISCELLANEOUS CONVERSIONS 3 1 Curie = 3.7 x 10 dps O
. Density = 62.4 lbm/ft i 3 Density = 1 gm/cm 1 kg = 2.21 lba
. Heat of vaporization = 970 Etu/lba 1 bp = 2.54 s 103BTU /hr Heat of fusica = 144 Btv/lba I N = 3.41 x 10 Btu /hr
, 1 Atm = 14.7 psi = 29.9 in. I's. 1 Btu = 778 ft-lbf 2
f 1 ft. H o = 0,4333 lbf/in y 1 inch = 2.54 ca
~~F = 9/$ C + 32~~
{ C = 5/9 ( F - 32) i -
b _ _ _ _ _ __.__ _._ _ __ _ _ _ _
.y. +
OATEGORY H REACTOR THEORY
< ^nf
~~QUESTION H.01 (0.75)~~
Multiole Choica, f Select the correct response.
Reflectors are usrd in the TRIGA reactor as a method of helping to control the neutron population of the' reactor.
What material is used as the PRIMARY reflector i n the Reed College TRIGA reactor?
f a. Water (H O).
2 i b. Graphite.
r 7 c. Aluminum..
~~d. Zirconium Hydride.~~
~~ANSWER H.01 (0.75) i b.~~
~~0 g~~~
~~REFERENCE RRF Training Manual, Module 12-6.~~
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~~QUESTION-H.02 .O.75) 4 Hultiple Choice, Select the correct response.~~
~~What are the three (3) materi als that.. are 'specifically designed as moderators in the Reed college TRIGA reactor?~~
~~a. Water, Graphite, Zirconium H dride.~~
-Zirconium Hydride, Concrete, Graphite,
~
b.
~~c. Graphite, Water, Aluminum. ;~~
~~d. ~ Aluminum, Concrete, Water.~~
~~ANSWER H.02 (0.75),~~
a.
~~REFERENCE RRF. Training Manual, Module 12-6 b~~
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~~QUESTION H.03 (1.0)~~
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What is the purpose of neutron moderation in the Reed College TRIGA reactor? (1.0)
~~ANSWER H.03 (1.0)~~
~~To thermalize or slow down neutrons. (1.0) !~~
~~REFERENCE RRF Training Manual, Module 12-6.~~
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~~QUESTION H.04'(1.5)~~
CALCULATION, show all work. I5-The Reed College reactor is at a power l evel of one (1) watt and increasing with a period of 20 seconds.
How long will it take f or reactor power to increase by a factor.of 2000 (3 decades)? . ( 1. 5) .
Show All Work (1.25 pts. application)
(0.25 pts. answer)
e.
~~ANSWER H.04 (1.5)~~
[ T = 20 seconds 9' - t/20 P/P O = 1000 = et /T = e (1.0)
'In 1000 = t/20. (0.25)
.t = 20 In 1000 = 20 (6.91) t= 138.2 seconds = 2.3 minutes (+ or - 3.O'sec or O.1 min)
(0.25)
OR SUR = 26.06/T = 26.06/20 = 1.3 dpm (1.0)
L sc 3-decedes/ 1.3.dpm = t (0.25) t = 2.3 minutes (+ or - 3.0 see or O.1 min) (0.25)
[
~~REFERENCE RRF Training Manual.~~
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~~QUESTION H.05 (1'5) .~~
1
-CALCULATION, show all work.
The Reed College reactor is subtritical with~a keff of 0.94 and 20 counts per second (cps). .After an experiment is installed the indicated count rate increases-to 40 counts per second.
What ~is the new kef f f or the new count rate of 40 cps? (1.5)-
Show All Work (1.25 pts. application)
(0.25 pts. answer)
!
~~ANSWER H. 05 71. 5)~~
~~{ correct formula,~~
. p. CR1/CR2 = (1 - keff2) / (1 - keff1) (0.75) correct substitution, 20 cps'/ 40 cps = (1.- keff2) / (1 - O.94) (0.25)
.F
'k (0. 5) (0. 06) = (1 - keff2) k correct answer, Ib keff2 = 1 - 0.03 = 0.970 (+/- 0.005) (0.25)
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~~REFERENCE Ef Equation sheet, RRF. Intro to Reactor Operations i.~~
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~~QUESTION H.06 (2.0)~~
" W Cal cul ati on , Show all work.
The mean lifetime (I n) f all reactor neutrons is calculated to be 9.2 x 10~ seconds and the Reed Reactor Facility (RRF) beta effective (Beff) is 0.0075.
The reactor is at power and a sixty (60) cents worth of reactivity is inserted.
What will be the resulting steady state reactor period?
(2.0) i ~~
Show All Work (1.75 pts application)
(0.25 pts answer)
~~ANSWER H.06 (2.0)~~
T=1 / delta k (0.75) n
$ = delta k / B eff (0.75) delta k = ($) B = (0.60)(0.0075) = 4.5x10 (0.25) eff
~
T=I n
/ delta k = 9.2x10 / 4.5x10~ = 20.4 seconds
(+ or - 1 second) (0.25) or T = In / delta k i s f or a reactor with no delayed neutrons.
accept: 1 -$ / lamda $ = T (1.5) 1 - 0.60 / (0.10) (0.60) (0.25)
= 6.67 sec (0.25) f
~~REFERENCE RRF Introduction to Reactor Operations, equation sheet.~~
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~~QUESTION~~
.H.07 DELETED
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Multiple Choice, Select the correct response."
Two identical reactors are increased in power from 20% to 100% percent"by pulling control rods. Reactor "A"s power is increased over a one (1) hour period while reactor "B" power increase is made over a period of ten hours. After reactor "A" reached 100% power.the operator had to adjust the control rods to maintain 100% power. Reactor "B"s operator did.not have to make any rod adjustments once the reactor was at 100% power.
Which of the following statements correctly describes the g-reasons for the differences in power stability at 100%
6 power?
r
~~a. Reactor "A" required adjustment to compensate for the~~
[,' --
'7'nitial 1 high rate of samarium build up and then burn 6 out after it reached 100% power.
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~~b. Reactor "A" required control rod adjustment out to compensate for a. decrease in delayed neutrons after reaching 100% power,~~
~~c. Reactor "B" required no adjustment because the burnout of. samarium is faster than it is produced during a slower power increase.~~
[- d. Reactor "B" required no adaustment since the delayed U neutrons that are being produced are in'a state of equilibrium.
h.
~~ANSWER H.07 DELETED~~
{ _
d.
RRF Reactor Physics Module 12, Pg. 5-16.
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~~QUESTION ;~~
H.08 (1.5) I i
1 ,x CALCULATION, show all work.
During a reactor refueling a spent fuel element is removed f rom the reactor causing the the shut down margin (SDM) in the reactor pool to change to 0.12 delta k.
What is the new keff for this condition of 0.12 delta k SDM7 (1.5)
Show All Work (1.25 pts application)
(0.25 pts answer) f
~~ANSWER H.OB (1.5) t Correc't equation Keff = 1 - SDM (0.75) r l~~
keff = 1 - 0.12 (0.5) keff = 0.88 (+ or - 0.01) (0.25)
. or:
[ SDM = 1 - keff / keff (0.75)
Keff = 1 / 1 + 0.12 (0.5)
Keff = 0.893 (0.25) g..
~~REFERENCE RRF Training Material, Equation Sheet.~~
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~~QUESTION H.09 (1.0)~~
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Multiple Choice, Select the correct response.-
What is the temperature in degrees Fahrenheit f or a thermometer that is reading 30 CelFiuG7
~~a. 112 degrees F~~
~~b. 86 degrees F~~
~~c. 49 degrees F~~
~~d. 77 degrees F c~~
~~ANSWER H.09~C1.0) l b.~~
degrees F = 9/5 degrees C + 32
= 9/5 (30) + 32 F = 86 F
~~REFERENCE Equation Sheet, Physics, Resnick and Hallidy.~~
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~~QUEST I Ob' ;~~
H.10 (1.0)
Short Answer.
Prior to starting up the Reed College reactor the Americium-Berylium neutron source is moved near the start up detectors in order to test a control rod safety interlock. !
What control rod saf ety interlock is tested when the neutron source is moved near the start up detectors? (1.0)
/
~~ANSWER H.10 (1.0)~~
( Control rod withdrawal is prevented if start up channel indicates less than two counts per second or source 1-
) interrock ( positve source channel response to neutrcns).
(1.0)
~~REFERENCE RRF Training Manual, Module 12-1 ;~~
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~~QUESTION H.11 (1.0)~~
Multiple Choice, Select the correct response.
Which of the following statements correctly describes Thermal Neutrons 7
~~a. A neutron that experiences a linear decrease in energy as the temperature of the moderator increases.~~
~~b. A neutron at resonant epithermal energy levels that causes fission to occur in Pu-240 and U-238.~~
~~c. A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator.~~
~~d. A neutron that experiences no net change in energy~~
!, after several collisions with atoms of the moderator.
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~~ANSWER H.11 (1.0) d.~~
~~REFERENCE RRF Training Manual, Module 12-6.~~
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~~QUESTION j H.12 (1.0)~~
Short Answer. 'iM l
Af ter a ' reactor scram there is an initial, prompt drop in j power level followed by a steady power decrease with a period of -BO. seconds.
Why does the power decrease always.have a period of
- 80 seconds? (1.0)
~~ANSWER H.12 (1.0)~~
~~' Power cannot decrease f aster than the the mean lif e of the e' longest lived precursor. (1/2 life of Br 1.44 x 55 sec).~~
~~REFERENCE Reactor Physics, Module 4 and 5 T~~
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~~OUESTION H.13 (1.0)~~
Multiple Choice, Select the correct response.
Below is a strip chart recorder representation of reactor power versus time for a xenon free reactor at start up. A reactor trip occurred at 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months followed by reactor start up to 100% power at 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months . Representation A.13 (attached) shows four (4) graphs of possible xenon transients.
100% -1 - - - - - - - - = - ----------------------------
P 1 1 I O I 1 i W l i I E 1 1 I 3'
R I I I I I I
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1 l 1 0% 1 i !
! 1 ! l 70 00 100 150 TIME (hours) j Which representation correctly defines the xenon transients
~~- associated with with this operating history?~~
~~b b 1 b~~
~~c. A.13.c~~
~~d. A.13.d~~
~~ANSWER H.13 ( 1. O)~~
~~c. ',;~~
~~REFERENCE Reactor Physics, Module 12-7.~~
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XENON REPRESENTATIONS Sheet 1 of 2 I I I A.13.a i a 1 i i 1 1 I i 1 i i 3 i ! Equilibrium Xe
~~___________ ____g_______________ _________________~~
1 1 I At 100% Power i i i I I X i i !
E J. I I N Xe_ _____________l_____1__________!__________!_________ _ _ l D Free N- O 70 80 100 150 HOURS R
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A, i C !
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T I I I A.13.b I i i i I V i 1 1 I i I i
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". - Y I I I Equilibrium Xe i 3____________ _____g_____ - - = - _ _ _ _ _ _ _ _ _ _ . __-______
1 l 1 At 100% Power i i !
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I i 1 X e _ __ __ _ __ _ _ __ _ _ ! _ _ _ __ l _ _ _ _ __ _ __ _ l ' I <
^ Free O 70 80 100 150 HOURS
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~~L, XENON REPRESENTATIONS Sheet 2 of 2 I I I A.13.c~~
- I I i l I 8-1 I I I I I I I Equilibrium Xe
! I I At 100% Power I i 1 I I i X l I i
! E _l, I I N Xe_I i l_____ __!__________I___________
D Free N O 70 80 100 150 t
HOURS R
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[. C 1 i 1 A.13.d-L T- 1 1 I i's I i i 3
J - V i i !
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{'; T i I ! Equilibrium Xe y ___________
____3________..___ _____ ___________
L i ! ! At 100% Power I ~
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Free Li O 70 80 100 150 HOURS ?
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~~QUESTION H.14-(2.0)~~
~~Calculation, Show all work!~~
~~While ref ueling the RRF TRIGA reactor the conditions -in the reactor. pool changed causing the keff to change from 0.88 to 0.963.~~
How much reactivity was added to the reactor pool? (2.0)
Show All Work.
(1.75 pts application.)
(0.25 pts answer)
[
~~ANSWER i~~
H .14 -02. 0 )
I Application r rho (p) = keff - 1 / keff. (0.75) pg = 0.88 - 1 / O.88 = - O.136'(+/- 0.001) (0.25) p2 = 0.963 - 1 / O.963 = -0.038 (+/- 0.001) . (0.25) p = 0.136 - 0.038 (0,5) added P1 ~P2 fe '
4 answer padded " * +~ '
~~17.~~
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~~REFERENCE-c 3~~
RRF Training Manual, Modules 12-4 and 12-5.
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~~QUESTION H.15 (2.O) n' . ..%' ,,~~
Calculation, Show All Work!
The reactor is critical' in the source range and is below the point of adding heat (PDAH) to the moderator. Rod motion has added enough positive reactivity to increase kef f. f rom 1.000 to 1.002.
Assume:
Bef f - (beta ef f ective) = 0.0072 and Lamda (b)= 0.10 DO NOT CONSIDER SDURCE NEUTRONS.
What'will be the reactor period (in seconds) after the positive reactivity addition increased keff to 1.0027 (2.0)-
! SHOW ALL WORK (1.5 Pts. application)
L (0.5 pts. correct answer)
~~ANSWER H.15 (2.0)~~
(1.5 pts correct application, 0.5 pts correct answer.)
E p= (keff - 1) / keff (0.5) k (1.002 - 1) / 1.002 = 0.002 (0.25) n i
T= (Beff - p) / Lamda (p) (0.5)
A. = (0.0072 - 0.002) / (0.1) (0. 002) (0.25)
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' T = 26 seconds-(+/- 3 seconds) (0.5)
~~REFERENCE RRF Training Manual, Modules 12-3 through 12-6.~~
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~~QUESTION j H.16 (1.0) J i~~
Multiple Choice, Select the correct response.
I The reactor has a core configuration of keff equal to 0.990.
What is the value of the e>: cess multiplication f actor?
~~a. -0.010~~
~~b. O.010 j~~
~~c. -0.991~~
~~. d. O.991 1~~
~~ANSWER H.16 (1.0) a.~~
(delta k) = keff - 1
-0.010 = 0.99 - 1
~~REFERENCE RRF Training Module 12-5, pg. 5-4.~~
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CATEGORY I RADIOACTIVE MATERIAL HANDLING, DISPOSAL AND HAZARDS
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~~QUESTION I.01 (0.75)~~
Multiple Choice, Select the correct response.
1 Quality factors are used to convert. Roentgen per hour (R/hr) to Roentgen Equivalent Mammal per. hour (Rem /hr).
What is the Quality Factor used to convert a dose of -gamma rays in R/hr to Rem /hr?
~~a. 1.~~
s
~~b. 5.~~
~~c. 10.~~
~~d. 20.~~
~~ANSWER~~
.I.01 (0.75) a..
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~~REFERENCE~~
.s RRF Introduction to Radioactivity, Chap.2, 2-2 84 2-3.
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~~QUESTION I.02 (0.75).~~
Multiple. Choice,' Select the correct response.
Quality factors are used to convert Roentgen per' hour (R/hr) to Roentgen Equivalent Mammal per hour-(Rem /hr).
What'is the Quality Factor used to convert a dose of Beta particles in R/hr _ to Rem /hr?
~~a. 1.~~
~~b. - 5.~~
~~c. 10.~~
~~d. 20.~~
~~ANSWER I.02 (0.75) l a.~~
~~REFERENCE RRF Introduction to Radioactivity, Chap-2, 2-2 & 2-3.~~
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~~QUESTION I.03 (0.75)~~
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Multiple Choice, Select the correct response.
Quality factors are use'd to convert Roentgen;per hour (R/hr) to Roentgen Equivalent Mammal per hour (Rem /hr).
What is the Quality Factor used to convert a dose of Alpha particles in R/hr to Rem /hr?
e
~~a. 1.~~
~~b. 5.~~
~~c. 10.~~
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3 d. 20.
~~ANSWER~~
~~" - I.03 (0.75) d.~~
~~REFERENCE RRF Introduction to Radioactivity, Chap.2, 2-2 t< 2-3.~~
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~~QUESTION I.04 (0.75)~~
.s Multiple Choice, Select the correct response.
Quality 'f actors are used to convert Roentgen 'per hour (R/hr) to Roentgen Equivalent Mammal per. hour (Rem /hr).
What is the Quali;y Factor used+ to convert a dose of fast I
neutrons in R/hr to Rem /hr?
~~a. 1.~~
~~b. 5.~~
~~c. 10.~~
i d. 20.
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~~ANSWER-t I.04 (0.75)~~
~~C .' .~~
~~REFERENCE RRF-Introduction to Radioactivity, Chap 2, 2-2 84 2-3.~~
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~~QUESTION~~
< I.05 ( 0. 75 ) -
Multiple Choice, Select the correct response.
I
' The Code ofl Federal. Regulations (10 CFR 20) specifies quarterly' occupational radiation dose standards f or individuals to-the whole body. Whole body defined as; head end trunk, active blood f orming organs, lenses of the eye, 7
or gonads.
l What is the 10 CFR 20 quarterly occupational radiation dose standard to the whole body?
- a. 1.25 Rem.
~~b. 3.0 Rem.~~
~~p . c. 7.5 Rem~~
~~d. 18.75 Rem.~~
~~ANSWER I.05 (0.75) a.~~
~~REFERENCE 6,~~
10 CFR 20 (20.101)
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~~QUESTION I.06 80.75)-~~
n V; Multiple Choice, ' Select the correct response.
The Code of Federal Regul ati ons (10 CFR 20) specifies quarterly occupational radiation dose standards for individuals to the skin of the whole body.
What is the 10 CFR 20 quarterly occupational radiation dose standard to the skin of the whole body?
~~a. 1.25 Rem.~~
~~b. 3.0 Rem.~~
~~c. 7.5 Rem d.~~
-.8.75 1
Rem.
~~ANSWER I.06 (0.75) c.~~
~~REFERENCE' 10 CFR 20 (20.101) k s.~~
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~~QUESTION' I.07. (0.75)~~
Multiple Choice, Select the correct response". .j y
The Code of Federal Regulations (10 CFR 20) specifies !
quarterly occupational radiation dose standards f or individuals to. the hands and L f orearms.
What'is.the 10 CFR 20 quarterly occupational radiation dose standard to the hands and forearms?
~~a. 1.25 Rem.~~
~~b. 3.0 Rem.~~
~~c.. 7.5 Rem i~~
~~'d. 18.75 Rem.~~
~~r r-~~
~~ANSWER I.07 (0. 75) '~~
d.
~~REFERENCE 10 CFR 20'(20.101) s:,~~
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~~QUESTION I.08 (1.5) ,~~
a i
in . 1 Short Answer. l' % ' < -
l The Code of Federal ' Rec 21ations (10 CFR 20) states - t hat a .
I licensed facility may permit a radiation worker to exceed the standard occupational dose if THREE (3) conditions are
. met. One of which is that the. worker has a NRC form 4 or equivalent' on file.
What are the two (2) other conditions? (0.75 pts each, max 1.5 pts.) (1.5)
~~ANSWER I I.08 ( 1. 5 ) ' (0.75 pts each, max 1.5 pts.)~~
~~1. Dose (to the whole body) does not exceed 3 rem during~~
~~the calendar quarter. (0.75)~~
~~U Dose (to the whole body) does not exceed 5(N-18).(0.75) 2.~~
~~REFERENCE 10 CFR 20 (20.101)~~
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~~QUESTION 1.09 (1.25)- ...<~~
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Calculation, Show All Work. .
A point source of radioactivity measuring'OO Rem /hr of gamma at,DNE-(1) meter has been detected. Assume 100% detector efficiency.for' gamma radiation.
How far away from the point-source will you have to move to reduce your.. exposure'20 Rem /hr? (1.5)
SHOW ALL. WORK (1.00 application.)
(0.25 for answer)
~~ANSWER~~
- I.09 (1.25) application: D /D = (L /L)1 (0.75) 3 2 2 (80 / 20) 1 = (L ) (0.25) 2 L = 2 meters (O.25) 2
~~REFERENCE RRF' Introduction to Radiation, Pg. 2-21.~~
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~~QUESTION I.10 (1.5) t e Cal cul ati on , Show All Work.~~
A radioisotope has been removed from a sample tube.'The sample is reading 4 Rem /hr at one (1) foot. From the experiment data you find out that the radioisotope decays by a 0.5 Mev gamma. - Assume the radiation is totally f rom the radioisotope and that the meter being used is 100%
efficient.
How many curies does the sample contain? (1.5)
SHOW ALL WORK (1.25 f or application)
(0.25 for answer)
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~~ANSWER r: I.10 (1.5) t (1.25 pts application, 0.25 pts answer.)~~
R/hr = 6 CE n / L (0.5) 4 Rem /hr =6C (0.5 Mev)(1) / 1 (0.5)
C = 4 Rem /hr (1 ) / 6 ( 1 ) (0,5) (0.25)
C = 1.33 curies (+/- O.1 curies) (0.25)
~~REFERENCE s~~
RRF Introduction to Radiation, Pg. 2-22.
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~~QUESTION l~~
. I .11 ' (0. 75) '
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Multiple Choice, Select the correct response.
Reed Reactor Facility personnel.are trained to use different types of portable radiation detectors, both for. daily survey j and emergency use.
Which of the f ollowing instruments would be used to detect HIGH range Beta - Gamma radiation during an emergency condition?
~~a. Eberline Model E-140.~~
L b. Model RD-2.
[~ c. CD V - 700 model 6B.
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~~d. ~C"D V - 715 model 1B.~~
~~ANSWER~~
~~-I.11 (0.75) d.~~
~~REFERENCE.~~
'RRF Introduction to Radiation and Rad. Inst. Manuals.
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~~QUESTION I.12 (0.75)~~
Multiple Choice, Select the correct response.'
Reed Reactor Facility personnel are trained to use different types of portable radiation detectors, both for daily survey and emergency use.
Which o'r the following instruments would is used as a
~~3. frisker to detect contamination on personnel. hands?~~
6
~~a. Eberline Model E-140.~~
~~b. Ludlum Model 3.~~
L i c. Ludlum Model 2.
d .- Model 177.
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~~ANSWER I.12 (0.75) d.~~
~~REFERENCE RRF Introduction to Radiation and Rad. Inst. Manuals.~~
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~~QUESTION.~~
I.13 (0.75) l Mul ti pl e ' Choi ce, Select the correct response.
Reed Reactor' Facility personnel are trainedfte use different types of portable radiation detectors, both for-daily survey and emergency use.
Which of1the following instruments can be used to discriminate Beta from Gamma radiation?
~~a. CD V - 715 model 1B.~~
~~b. Eberline Model RO - 2.~~
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~~c. Ludlum Model 2.~~
~~d. Model 177.~~
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~~ANSWER I.13 (0.75) b.~~
~~REF'ERENCE RRF Introduction to Radiation and Rad. Inst. Manuals.~~
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~~QUESTION-I.14 (0.75)-~~
Multiple Choice, Select the correct response.
Which of the statements correctly describes' Alpha radiation?
~~a. Particles that lose energy rapidly in any medium due to high ionization: level.~~
~~b. Radiation that has a higher penetrating power than gamma radiation.~~
~~c. Radiation that requires a thin lead shield due to high penetration and low ionization level.~~
~~d. ' Particles that have a higher penetrating power than~~
' fast beta radiation.
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~~ANSWER I.14 (0.75)~~
~~L a.~~
~~REFERENCE RRF Introduction to Radioactivity, pg. 2-23.~~
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~~QUESTION 1 I.15 (1.0) -~~
]1 Multiple Choice, Select the correct response.'
Which of the following statements correctly describes neutron radiation?
~~a. The energy loss by neutron radiation is mainly due to the ionization of other atoms its it passes by.~~
~~b. Neutron radiation is redirected in direction due to the repulsion of negatively charged atoms.~~
~~c. Neutrons lose energy as they pass through matter by elastic end inelastic scattering with nuclei.~~
~~d. Neutrons cause the direct opposite ionizing ef f ect as a1pha radiation due to the opposite charge.~~
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~~ANSWER I.15 (1.0)~~
~~.c.~~
~~REFERENCE~~
~~RRF Introduction to Radioactivity, pg. 1-25.~~
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~~QUESTION I.16 (0.75)~~
Multiple Choice, Select the correct response.
Ingestion of radioactive materials is a majo'r. concern. For the same curie amount different types of radiation cause different amounts of biological damage.
Which of the f ollowing types of radiation will cause the greatest biological damage for the same curie amount when ingested?
~~a. Alpha.~~
~~b. Beta.~~
~~c. Gamma.~~
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b
~~ANSWER I.16 (0.75) a.~~
~~REFERENCE RRF Introduction to Radioactivity, Chap 1.~~
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~~QUESTION~~
- I.17 (0.75)
C-Multiple Choice, Select the correct response.
A radioactive materials transfer is being made from the RRF' to an experimenter. You are requested to check the recipients license to make sure that it is current.
Where are copies of recipients current licenses kept?
~~a. Console room file cabinet,~~
~~b. RRF, Health Physicist office file cabinet.~~
~~c. RRF, Associate Directors of fice files.~~
~~d. RRF, Reactor Supervisors of fice files.~~
~~ANSWER I.17 (0.75) a.~~
~~REFERENCE RRF SDP - 52.~~
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~~QUESTION~~
- I.18'(0.75)
~
. Multiple Choice, belect'the correct response.
Part 20.105 of the Code of Federal Regulations-(10 CFR 20) specifies permissible dose limits f or unrestricted areas.
The dose.shall not exceed the limit for any' period of one cal endar . year.
What is the radiation dose limit f or unrestricted ' access?
~~a. O.1 mrem.~~
~~b. O.1 Rem.~~
~~c. 0.5' mrem.~~
~~d. 0.5 Rem.~~
~~ANSWER I.18 (0.75) d.~~
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~~REFERENCE 10 CFR 20 (20.105) k o~~
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~~QUESTION' I.19.(0.75)~~
Multiple Choice, Select the correct response.
.Part 20.105 of.the Code of Federal Regulations, 10.CFR 20, identifies a dose limit a person can not exceed if that person is in a " unrestricted area".
What is the dose limit'that can not be exceeded in one.(1) hour in an unrestricted area 7
~~a. O.2 Rem 1 i~~
~~b. 20.C mrem i~~
p c. 2.0 mrem h d. ~O.2 mrem V l F
~~ANSWER l' I.19 (0.75) c.~~
~~REFERENCE 3~~
10 CFR 20., 20.105
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~~DUESTION ;~~
I.20 (0.75) .]
Multiple Choice, Select the correct response.' l Part 20.105 of the. Code of Federal Regul at i ons , 10 CFR 20, !
identifies a dose limit a person can not exceed if that person is in a " unrestricted area".
What- is the dose limit that can not be exceeded in a
- seven (7)' day period for a unrestricted arei a.. 10 mrem. j
~~b. 20 mrem. )~~
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~~rr- c. 50 mrem.~~
~~. d. 100 mrem.~~
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~~ANSWER I.20 ( 0. 7 5 ) '~~
d.
~~REFERENCE I 10 CFR 20, 20.105.~~
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~~QUESTION 1.21 (1.0) ,_~~
. c ij Multiple Choice, Sel ect the correct response.'l;1,-.
Part 20.104 of 10 CFR 20 sets limits on the'whole body radiation dose a person under the age of -18 years of age is allowed to receive in a calendar quarter when that person is in a restricted area.
What is .the radiation dose limit?
~~a. 1.875 Rem.~~
~~b. O.125 Rem.~~
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~~e. ' 10.O mrem.~~
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~~d. 7.50 mrem.~~
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~~ANSWER I.21 (1.0) b.~~
(10 % of 1.'25 Rem /Qtr.)
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~~REFERENCE P~~
10 CFR 20, 20.101 & 20.104.
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~~QUESTION I.22 (1.75)~~
Calculation, Show All Work. 3 An ' irradiated sample is' emitting a narrow beam of 0.15 Mev gamma radiation at the surface of a capsule. You:want to reduce the beams intensity by 50% using a lead shield.
(Use Figure I.22 and equation sheet.)
What is the thickness of lead, in centimeters, that is required to reduce the intensity of the beam by 50%7 (1.75)
Show All Work.
(1.5 for application.)
(0.25 for correct answer.)
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~~ANSWER I.22 (1.75)~~
Application e "*
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I=1 (0.5) 0
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~~C*^~ } * '*' (0.5)~~
, 0.5 = e n
f i n 0. 5 = I n (e~ *
~~'} (0.25) i r -0.69 = -20.8 (x) (0.25) g:~~
I~ Correct answer x = 0.03 cm (+/- 0.003) (0.25)
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~~REFERENCE RRF Training Manual, Chapter 2, pgs. ,20 t o 28.~~
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j' END OF SECTION I CONTINUE ONTO SEC ION J uw l-h L
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Quantum Energy, MeV
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CATEGORY J SPECIFIC OPERATING CHARACTERISTICS f
~~QUESTION J. 01. (2. 5)~~
Short Answer.
RRF SOP 03 requires that Core Excess checks be performed as the first reactor operation of each calendar day. The
. operator will use TWO (2) types of rod worth curves to perform.the core excess calculation.
~~a. What are the names of the TWO (2) rod worth curver used?~~
~~(0.5 pts ea.) (1.0) h p b. What is the name of the specific control room document~~
that the control rod worth curves are kept in? (0.5) i j c. WhWt is the scale that the range switch is selected to (in Watts) when starting the core excess check? (0.5)
~~d. What is the name of the control rod that is withdrawn first when performing a core excess check? (0.5)~~
~~ANSWER J.01 (2.5)~~
~~a. Dif f erenti al (rod worth) (0.5) o Integral (rod worth) ~(0.5)~~
~~I b b. Log Book (inside back cover) . (0.5) k~~
~~c. O.1 Watt (0.1-W scal e) (0.5)~~
~~d. Regulating. (0.5)~~
~~REFERENCE RRF SDP 03 Start Up and Core Excess Check. l i~~
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~~QUESTION J.02 (0.75) ]~~
' Multiple Choice, Select the correct response. -
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" Start up.and Core Excess Check", procedure SDP 3 is being performed. The procedure states.that when reactor power r eaches a minimum preset point the linear power range should be shifted, but not before. , f t
What is the minimum power at'which the linear powei range can be shifted? .
~~a. 35 %~~
!, b. 40 %
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~~c. 45 %~~
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~~ANSWER J.02 (0.75) d.~~
~~REFERENCE I. RRF SDP 3.~~
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~~QUESTION J.03 (0.75) 1.,~~
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Multiple Choice, Select the correct response'.' - !
RRF procedure SDP 04, Reactor Operations, precautions the operator to not operate the reactor above 96 % reactor power.
What is the reason f or not operating the reactor above 96 %
power?
~~a. Account f or fluctuations that may take power above licensed limit.~~
~~b. Account f or burnout of fission product poisons that increase cladding temperature above limits.~~
~~p c. Tnsure that the control rods are inserted to a point 3 where they have sufficient bite,~~
~~d. Precaution against fuel element swelling from continued high power operations.~~
~~ANSWER J.03 (0.75) f~~
~~[ a.~~
~~REFERENCE I- . RRF SDP 04.~~
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~~QUESTION ,,~~
.J.04 (1.0) l
. 2; 4 . ,
Short Answer. {
" Start up and Core Excess Check", procedure SOP'3 is being performed.- The procedure states that when reactor power .
reaches a minimum preset point TWO (2) of the control rods are adjusted to establish Equilibrium.
What are the names of the'TWO (2) control rods that are adjusted to. establish equilibrium? (0.5 pts ea.) (1.0)
~~ANSWER L- .J.04 (1.0) f;~~
~~1. Shim rod. (0.5)~~
E
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~~7. Saf ety rod. (0,5)~~
~~REFERENCE RRF SDP 03.~~
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~~QUESTION 'l J'05-(0.75) g.-~~
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Multiple Choice, Select the correct response.:
" Start'up and Core Excess Check",' procedure BOP 3 is'being,
~
performed.-The procedure states'that.when reactor power reaches m~ minimum preset point TWO '(2) of the control rods are adjusted.to establish Equilibrium.
What is the power level, in Watts,-that the reactor is leveled out at to establish equilibrium?
~~a. 2 Watts.~~
Le
~~p. ' b. 5 Watts.~~
~~t i c. S Watts.~~
~~d. 10 Watts.~~
9
~~e. -~~
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~~ANSWER J.05 (0.75)~~
~~,, b.~~
~~REFERENCE N.~~
=, RRF SDP 03 l l Y
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~~QUESTION l J.06 (0.75) g~~
-) i Multiple Choice, Select the correct response. ;
" Start up'and: Core Excess Check", procedure SDP 3 is being perf ormed. .The procedure states that- when reactor. power reaches. a - minimum preset point TWO (2) of the control rods are adjusted to establish Equilibrium.
How long must the reactor be maintained in- the equilibrium condition?
~~a. 2 min.~~
~~b. 4 min.~~
c.-6 min.
e -.
~~d. O mi n.~~
~~ANSWER J.06 (0.75) a.~~
,
~~REFERENCE f~~
L-RRF SDP 03..
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~~QUESTION I~~
' J.07:(0.75) , , . , .4 ' .l
. ... . .q. J Multiple Choice, Select the correct response;* ,
A reactor operator conducting a start up in: accordance with
" Start up and Core Excess Check" pro edure. SOP 3. When
. perf orming a start up the period. is limited.
What is the minimum reactor pariod allowed during a start' up?
~~a. 5 seconds.~~
~~b. 7 seconds.~~
~~c. 10 seconds.~~
f d. 15 seconds.
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~~ANSWER~~
' J . 07 . (0. 75)
C.
~~REFERENCE RRF SDP 3.~~
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~~QUESTION "J . OB ' ( 0. 75) _~~
~~r Multiple Choice, Select the correct response.'~~
- RRF procedure-SOP 04, Reactor Ope 3tions, precautions the operator to not operate the reactor above 96 % of licensed reactor power.
What -is the reactor power, in Kilo. Watts, that. corresponds to 96% power?
~~a. 230 Kilo Watts,~~
~~b. 240 Kilo Watts.~~
f- c. 250 Kilo Watts.
['- d. '260 Kilo Watts.
E' L
~~ANSWER~~
~~'J.08 (0.75) b.~~
~~REFERENCE RRF SDP 03 and 04.~~
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~~QUESTION i J.09 ( 2. 25 ) .~~
J,\
Short Answer.
The RRF TRIGA has three control rods,_the' shim rod, the safety. rod, and the regulating rod.
a.- What is the present reactivity worth of the Shim rod?
(0.75)
~~b. What is the present reactivity worth of the Safety rod?~~
~~(0.75)~~
~~c. What is the present reactivity worth of the Regulating~~
~~g. rod? (0.75)~~
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!- .*ANSWER J.09-(2.25)
~~a. $4.25 (+/- $0.50) (CWF for actual $ 4.30) (0.75)~~
~~b. $4.25 (+/- $0.50) (CWF for actual~~
~~4.26) (0.75)~~
~~c. $1.50 (+/- $0.25) (CWF for actual $ 1.67) (0.75)~~
~~REFERENCE Facility Data.~~
~~c. .~~
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~~QUESTIDN' J.10 (1.0). .~~
%{:!! s SOP. 03 states that af ter core excess has been ;~;etermined it
- must be consistent with TWO (2) prior conditions,'one of which is previous power histcry. *
'I 11 What is the other operational ' condition that can have an effect-on' core excess reactivity?
~~ANSWER' J.10,(1.0)~~
~~Experiment Loading. (1.O) f~~
~~REFERENCE k,. RRF SDP 03.~~
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~~QUESTION J.11 (0.75)~~
Multiple Choice , Select the correct response.
- The RRF TRIGA reactor uses several types of nuclear instrumentation.
Which nuclear channel uses a fission type neutron detector?
a.- Count rate channel.
~~b. Linear power channel.~~
~~c. Log power channel.~~
P
~~d. Period channel.~~
e
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~~ANSWER~~
~~J.11 (0.75) a.~~
~~REFERENCE RRF TRIGA-Mechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-13 thru 1-15.~~
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~~QUESTION I J.'12 (0.75) l J~~
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. Multiple Choice, Select the correct r esponse.;
+t The RRF TRIGA reactor uses several types of nuclear instrumentation. One (1)1 channel provides power level indication' f rom Just above the source level to full power.
Which' nuclear channel provides the operator with power indication from just above the source level to the full power level?
~~a. Count rate channel .~~
~~[ b. Linear power channel.~~
~~c. Log power channel, i~~
!, d. ~Fercent power channel.
f' f-1--
.
~~ANSWER J.12 (0.75) b.~~
~~REFERENCE t RRF TRIGA Mechanical Maintenance and Operating Manual,~~
'. AppendiR B, Pgs. 1-13 thru 1-15.
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~~QUESTION' J.13 (0.75) , ,~~
Nc' tiple Choice, Select the correct response.~ ~ "
4%
The RRF TRIGA reactor uses several-types of nuclear instrumentatir- D e of the channels provides the operator ,
with a continuout record of neutron flux from less then one watt to full power.
What channel providet the operator with a continuous record- ~
of neutron flux from less than one watt to full power?
~~a. Linear power channel.~~
~~b.- Log power channel, i c. Period. channel.~~
~~d. -Count rate channel.~~
~~F 4~~
~~ANSWER J.13 (0.75) b.~~
~~REFERENCE h- RRF TRIGA Mechanical Maintenance and Operating Manual, i..~~
Appendix B, Pgs. 1-13 thru 1-15.
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~~QUESTION J.14 - (0.75)~~
J Mult'iple Choice, Select the correct response.
One of'the RRF TRIGA reactor nuclear instrumentation channels provides the operator w3 th an ' indication of the rate of' change of power per second.
Which of the f ollowing channels provides. the operator with indication of the rate of change of nuclear power per secon:17 '
~~a. . Linear power channel.~~
7
~~b. Log power channel.~~
~~ff c. Period channel.~~
~~s. d. Count rate channel.~~
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~~ANSWER J.14 (0.75)~~
C.
~~REFERENCE f.~~
/ RRF TRIGA Mechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-13 thru 1-15.
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~~QUESTION 'l J.15 (0.75)~~
Multiple Choice, Select the correct respon eb ~
, 4, Fission chambers are used at the RRF f or deteeting neutron radiation. Fissionable material is used to line- the wall of the counter tube.
What.is the region of.the Pulse Size vs. Applied Voltage does the fission chamber operate in? -
~~a. Geiger Muller.~~
b ~. . Limited Proportionality.
[ c. Proportional,
!1 d. Ionization.
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~~ANSWER.~~
P' J.15 (0.75)
C.
~~REFERENCE RRF Introduction To Radioactivity, Pg. 12-1-25 & 2-31 p.~~
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~~QUESTION, J.16 (0.75) ,~~
Multiple' Choice, Select the correct response.T 3
The excess reactivity of the core is the sum.of the-remaining worth of all of the control rods.
' What. is the maximum core excess reactivity worth in doll ars . ($) allowed by ' Technical Specifications?
~~a. $1.00~~
~~b. $2.00 O c. $3.'00~~
~~d. $4.00 6" ' .~~
~~ANSWER J.16-(0.75) c.~~
~~REFERENCE !~~
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~~QUESTION J .17 ' (1. 0) 4~~
p.: " a Short Answer. f You are the Senior Reactor Operator (SRD) on. duty during an experiment.. Upon verifying your calculations, you discover that the maximum core excess reactivity worth limit is exceeded.
What are the TWO'(2) immediate actions that must be taken.if the maximum core excess reactivity worth is exceeded?
(0. 5 pts ea. ) (1. 0) i
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~~ANSWER~~
. J.17 (1.0)-
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[ ~1~. Shut down the reactor. (0.5)
[. 2. Notify Reactor Supervisor. (0.5)
~~REFERENCE RRF SDP 03.~~
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~~QUESTION J.18 (1.0) . .~~
Multiple Choice, Select the correct response. ,y Which of the.following statements correct 1'y describes core excess reactivity after a extended high power reactor run?
~~a. Core excess reactivity will be be lower due to samarium build up.~~
~~b. Core excess reactivi.ty will be be higher due to samarium build up.~~
~~c. Core excess reactivity will'be higher due'to xenon build up. .~~
~~d. Core excess reactivity will be lower due to xenon g~~
~~build up.~~
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~~ANSWER I' J.18 (1.0) d.~~
~~REFERENCE RRF SDP 03 and RRF Training Material, b~~
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'* QUESTION J .19 - (0. 75) s Multiple Choice, Select the correct response.
When the RRF TRIGA reactor is selected to the automatic mode power level is controlled by control rod movement.
What' control rod (s)'can the automatic control system adjust to control reactor power leve17
~~a. Regulating, shim and safety.~~
~~b. Regulating rod only.~~
~~c. Shim rod only.~~
~~d. Regulating, and shim.~~
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~~ANSWER l- J.19 (0.75) b.~~
~~REFERENCE' RRF TRIGA Mechanical Maintenance and Operating Manual, Appendix B, Pgs. 1-15.~~
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~~QUESTION J.20 (0.75)~~
Multiple Choice, Select the correct response.
Nuclear instrumentation provides input for reactor trips at the RRF TRIGA.
Which ONE (1) of the following nuclear channels provides a signal for a reactor power scram at 110%?
~~a. Log power channel,~~
~~b. Count rate Channel.~~
~~j c. Period channel, i'~~
~~d. Linear power channel.~~
~~ANSWER~~
. J.20 (0.75)
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d.
~~REFERENCE RRF TRIGA Mechanical Maintenance and Operating Manual, j Appendix B, Pgs. 1-13 thru 1-15.~~
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~~QUESTION J.21 (0.75) y~~
. Multiple Choice, Select the correct response.'
A rabbit'has been returned from the' reactor'after being irradiated in accordance with SDP 51, Performing Rabbit Irradiations. SDP 51 requires'that the dose rate from the rabbit be below a given limit before it can be removed from the terminal.
What is this limit?-
~~e. 5 . mrem /hr.~~
h- b. -0.5 Rem /hr.
t' f c. 1.0 Rem /hr.
p., d. ~f0 mrem /hr.
~~ANSWER J.21-(O.75)~~
~~. d.~~

~~REFERENCE-y RRF SOP 51.~~
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END DF SECTION J CONTINUE ONTO'EECTION K vy y; ,
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CATEGORY K FUEL HANDLING AND CORE PARAMETERS
~~QUESTION K.01 (1.0)~~
Short Answer On a reactor scram the control rods are rapidly inserted into the core.
What is the design feature of the control rod assembly barrel that helps prevent the control rods from impacting on the bottorn during a reactor scram? (1.0)
.
~~ANSt 'ER K.01 (1.0)~~
~~Grated vents or holes are provided in the bottom (providing a dash pot action on a scram). (1.0)~~
~~REFERENCE G.A. TRIGA Mark 1 Maintenance and operating manual.~~
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~~QUESTION-K.02 (0.75)~~
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Multiple Choice, Select the correct response.
During power. operations of 'the RRF the neutron flux is not the same throughout the core.
What is the position of the maximum neutron flux in the RRF core during 100% power operations?
~~a. At the top of the coro.~~
~~b. At the bottom of the core.~~
~~c. At the outside perimeter of the core.~~
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~~d. At the center of the core.~~
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~~ANSWER K.02 (0.75) d.~~
~~REFERENCE GA TRIGA Maintenance and Operating Manual, Pg. 1.~~
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~~QUESTION.~~
K.03-(2.5)
Short Answer.
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There is a conductivity probe located at thE inlet of the
~
demi neral i z er. .The conductivity probe will"reud high if the reactor water is grossly impure. One (1) of the conditions that could cause high conductivity is f uel element failur'_. q
a. What are TWD (2) other design failures that could cause a high conductivity.at the inlet to the demineralized? (0.75 points each. max 1.5 pts) (1.5)
b. What-are TWO (2). reasons for maintaining a low reactor' water conductivity?-(0.5 each max 1.0) (1.0)
(:
~~ANSWER K.03 02.5)~~
~~a. . Max 1.5 points~~
~~1. Experiment cail ure (incore). (0.75)~~
2. Failure of cooling water heat exchanger (cooling water iflow into the reactor water system). (0.75)
~~b. Max 1.0 points !~~
7 r 1. Prevent corrosion (of reactor components, particularly fuel elements). (0.5)
~~2. Reduce radioactivity of the reactor coolant system.~~
~~(0.5) f fI-~~
~~REFERENCE GA TRIGA Maintenance and Operating Manual and RRF SAR.~~
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~~QUESTION K.04'(0.75) . ,,~~
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Multiple Choice, Sel ect the correct response'.*
... . I "The RRF has three control rods which contain'a powdered, neutron absorber, or poison to control reactivity in the core.
What is the name of the powdered neutron absorbing material-used in the control rods? j
~~a. Borsted aluminum oxide.~~
~~h b. ~ Borated zirconium alloy.~~
~~c. Boron graphite.~~
I i d. ~ Boron carbide.
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~~ANSWER K.04 (O.75) l d.~~
~~REFERENCE GA TRIGA Maintenance and Operating' Manual.~~
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~~QUESTION K.05 (0.75) .~~
Multiple Choice, Select the correct response.
The three TRIGA reactor control rods are made of the same structural material, which contains the powdered neutron absorbing material or poison.
What is the name of the cladding material that the control rods are made of?
~~a. 304 Stainless Steel .~~
~~b. Aluminum.~~
f c. Zirconium Hydride.
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~~d. ' Graphite.~~
~~ANSWER K.05 (0.75)~~
~~6. ,~~
~~REFERENCE GA TRIGA Maintenance and Operating Manual.~~
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~~QUESTION K.06-(0.75)~~
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Multiple Choice, Select the correct response. i
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The fuel loading of fuel elements can be determined by grooves machined into the the top end fixtures of the f uel elements. . Figure K.06 i11ustrates the -grcove patterns f or fuel loading.
Which patterns correctly shows a DUMMY ELEMENT'i
~~a. E.~~
~~b. A.~~
L.
~~c. B.~~
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~~d. C .~ ~~~
~~ANSWER K.06 (0.75) a.~~
~~REFERENCE F GA TRIGA Maintenance and Operating Manual, t~~
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~~QUESTION l K.07 (1.0) k Multiple. Choice, Select the correct rea ar s e .'~~
y Two f our inch pieces of graphite are inserted into each f uel
! element , J one above and one bel ow the f uel .
What is the purpose of the graphite inserted above and below the f uel?-
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~~a. To serve as reflectors for the top and bottom of the Core.~~
g b. Act as a radiation shield to reduce nitrogen 16 gamma radiation above and below the core.
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~~c. Provide spacing to insure that the fuel is properly positioned in the element.~~
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~~d. Act as a buf f er to allow f or the thermal expansion and y[ contraction of the fuel, f-~~
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~~ANSWER K.07 (1.0) a.~~
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~~REFERENCE.~~
GA TRIGA Maintenance and Operating Manual.
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~~QUESTION K.OB (1.0)~~
Multiple Choice, Select the correct responset. - r The high speed pneumatic transf er system moves samples in and out of the core rapidly.
Which of the following statements correctly describes the the pneumatic transfer systems exhaust path and operating pressure?
~~a. The pneumatic transfer system exhausts to the reactor room and maintains the transfer system at a positive pressure.~~
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p b.. The pneumatic' transfer system exhausts to the'reactcy room and maintains the transfer system at a negative
_,ressure.
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' c. The pneumatic transfer system exhausts to the building
( exhaust and maintains the transfer system at a negative pressure. s
~~d. The pneumatic transfer system exhausts to the building axhaust and maintains the transfer system at a positive pressure.~~
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~~ANSWER P- K.OB (1.0) b~~
);l c.
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~~REFERENCE Reed College Reactor Facility Description and SAR, pg. 5-7.~~
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~~QUESTION K.09 (0.75)~~
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The RRF reactor pool. is~ a source of water [for cooling the fuel elements. " ? .-
Which of the. f ollowing is the primary cooling mechanism normally used to cool the RRF reactor core?
~~a. Natural Convection (ci rcul ati on) .~~
~~b. Gamma Radiation.~~
~~{ c. Forced Convection (ci rcul ati on ) .~~
~~d. Mechanical Conduction.~~
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~~ANSWER r~~
K.09 (0.75)
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a.
~~REFERENCE TRIGA MARK 1 Reactor Mechanical Maintenance and Operating Manual.~~
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~~QUESTION K.10 (1.0) &~~
u.
Shcrt Answer. 4 After the reactor cooling water has removed the heat from the reactor core fuel elements it returns to the bulk volume of the fuel pool.
What are the names of the TWO (2) components that f e:rm the gap which the reactor coolant must flow through in order to return to the bulk volume of the reactor pool 7 (0.5 pts each max 1.0 pts.)
l
~~ANSWER P K.10 (1.0) (0.5 pts =a. max 1.0 pts)~~
~~~1'. (Tri angul ar) spacer block (fuel rod) (0.5)~~
~~2. (Circular holes in). upper grid plate. (0.5)~~
~~REFERENCE TRIGA MARK 1 Reactor Mechanical Maintenance and Operating Manual, pg.9.~~
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_ _ _ _ _ _ _ _ _ _ _ - - _ _ - = _ - - - . _ - - - . _ _ _ _ - - _ . . - - . , - .
~~QUESTION:~~
K.11 (1.0)
'j- 2 Short Answer. U^ #F The three phenomena that achieve the large'," prompt" negative fuel temperature coefficient (FTC) are:
1.-Doppler Effect.
~~2. Core Leakage.~~
~~3. Properties of the fuel element moderator.~~
~~a. Which one of.the three phenomena has the LEAST effect on the FTC7 ' (0.5)~~
[ b.lWifi'ch one of the three phenomena har, the GREATEST effec'.
L on the FTC? (0.S)
~~ANSWER K.11'(1.0)~~
a. Core Leakage (2). (0.5) i b. Fuel Element Moderator (3) (0.5) r.
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~~REFERENCE Reed Reactor Physics, Modul e 12-6.~~
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QUESTION K.12 (1.O) ,- j l .
jph i While moving. f uel in the reactor you notice _that'_one of.the operators is winding the fuel handling tool , control cable in {
c a tight coil (less .than two (2) feet in diameter).
What i s. the reason f or not coiling the f uel handling coil in j a less than TWD (2) foot diameter coil'while handling fuel? .,
(1.0) 1 r
~~ANSWER K.12 (1.0)~~
L, Could' drop a f usi element. ,
(1.0)
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~~REFERENCE g RRF~TRIGA Maintenance and Operating Manual.~~
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~~QUESTION )~~
K.13 (0.75) l Multiple Choice, Select the correct response.
The RRF control rod assemblies are stopped at the top and ;
the bottom of their travel when they are being electrically l driven. l,
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What is the component that stops the control rod drive at j the top and bottom of their travel? i 1
1
~~a. Limit switches. )~~
~~b. Piston in a narrowing chamber.~~
~~k c. Pneumatic cylinder,~~
~~d. Mechanical stop at. each end.~~
~~ANSWER K.13 (0.75) a.~~
~~REFERENCE RRF TRIGA Mechanical Maintenance and Operatirg Manual, Pgs.~~
, 20 - 22.
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~~QUESTION K.14 (1.0) q~~
..; i Short Answer. q The RRF TRIGA control panel has a mode selector switch which is used to select the mode of steady state operation, Manual or Automatic. When in the automatic mode, the comparator circuit in the servo amplifier uses three (3) sources of information one of which i s reactor power. !
What are the TWO (2) other inputs to the comparator circuit in the automatic mode of operation?
(0.5 pts ea. max 1.0 pts.)
59
~~ANSWER K.14 (1.0)~~
~~1. Power demand (f rom the demand pot) . (0.5)~~
~~2. Reactor Period (from period circuit). (0.5) {~~
~~REFERENCE RRF TRIGA Mechanical Maintenance and Operating Manual ,~~
Appendix B, Pgs. 1-15.
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'* QUESTION K.15 (0.75) <
'dt, an Multiple' Choice, Select the correct responise? %
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< ,> i The RRF-Technical Specifications state the maximum rate of I
reactivity insertion associated with the movement of a' standard control roo?
l What is the maximum rate of reactivity insertion f or the i movement of a standard control rod?
~~a. 2.25 % delta k/k sec. ,~~
~~b. O.40 %-delta k/k sec. i~~
/ -c. 1.12'% delta k/k sec.
$ d. 7.12 % delta k/k sec.
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~~ANSWER K.15 (0.75) d.~~
~~REFERENCE-~~
.- RRF Technical Specification,~Pg. 3.
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~~QUESTION' i K.16 (1.5)~~
Short Answer.
Of the six reactor scrams at.the RRF two (2) are (110%) high power scrams and one (1)is the manual scram.
What ar e the other three reactor scrams?. (1.5)
~~ANSWER K.16 (1.5) (0.5 em. max. 1.5 pts.)~~
~~1. Reactor period (high). . (0.5)~~
~~2. Ion. chamber power supply iailure. (0.5) r ..~~
[ 3. Console power (circuit) failure or-external scram.(0.5) f.-
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~~REFERENCE RRF SAR, Pg. 5-16.~~
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~~QUESTION K.17 (1.0)~~
Short Answer. ;.
RRF Technical Specifications require that ? at'a minimum THREE (3) reactor safety circuits be available prior to start up. One of the circuits is the manual scram button on
.the console.
What'are the other TWO (2) safety circuits? (1.0)
~~ANSWER K.17 (1.0) (0.5 pts. ea. max 1.0 pts.)~~
2 1. Linear. power (110%) (0.5)
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~~- 2. Percent power (110%) (0.5)~~
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~~REFERENCE RRF Technical Specification, Table I.~~
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~~QUESTION K.18 (1.0)~~
Short Answer.
RRF Technical Specifications require that at.a minimum TWO (2) interlocks be available prior to start up.
What are the TWO (2) interlocks? (1.0)
~~ANSWER K.18 (1.0)~~
~~1. Control rod withdrawal with less than (2 cps) required neutron count rate per second on start up channel. (0.5) j 2. Simultaneous manual withdrawal of two control rods. (0.5)~~
~~T :~~
~~REFERENCE l RRF Technical Specification, Table II, pg. 9.~~
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~~QUESTION~~
- K.19 (0.75) .
c.
Multiple Choice, Select the correct response. ,
.g The RRF has radiation monitors which actuate' alarms and/or ventilation confinement when preset levels of radiation are
- sensed by the detectors.
Which of the f ollowing radiation monitoring systems will cause a ventilation confinement actuation?
~~m. CAM~~
~~b. RAM~~
~~c. Bulk water temperature.~~
. d. Particulate stack monitor.
F.
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~~ANSWER~~
~~'- K.19 (0.75) a.~~
~~REFERENCE.~~
I RRF Emergency Plan, Appendix D, and SDP 65.
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~~QUESTION K.20.(1.0)-~~
Short Answer. bj The secondary water system is operated at a -pressure above
.that of the reactor water (primary) system.
Why is the secondary water system operated at a higher pressure than the reactor water system? (1.0)
~~ANSWER K.20 (1.0)~~
~~Leakage will be f rom the secondary to the primary, or prevent reactor (radioactive) water from leaking to the~~
~~environment. ( 1, 0 )~~
~~REFERENCE GDP 62.~~
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, 3.,a N END OF SECTION K CONTINUE DNTO SECTION L
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L y CATEGDRY L ADMINISTRATIVE PROCEDURES, CONDITIONS.AND' LIMITATIONS
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~~QUESTION MYY' '?~~
L.01 (2.0)
Short Answer.
An irradiated experiment containing Pu - 239 has been spilled in the radiochemistry lab. The evacuation alarm is sounded and all personnel evacuate. The Reactor Operator is responsible for taking the console key, and closing and /or
, locking specific doors upon evacuation. One of the doors is
[ the reactor bay door between the reactor bay and the control
.- room.
m a. Where are the TWO (2) locations that the evacuation alarm
! cin' be initiaced f rom? - (0.5 pts ea.) (1.0)
b. What are the TWO (2) other doors the Reactre' Operator is responsible f or closing and/or locking during an evacuation? (0.5 pts ea.) (1.0)
~~ANSWER L.01 (2.0)~~
~~a. Control console (right side red button). (0.5)~~
L Renctor Bay (south wall) .- (0.5) k, b.
L 1. Control room door (l oc k) . (0,5)
~~2. Radiochemistry Lab (between radiochemistry lab and exit corridor). (0.5)~~
~~REFCRENCE RRF Emergency Implementation Procedures, Appendix c.~~
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~~QUESTION L.02 (0.75)~~
Multiple Choice, Select the correct response.' !
During an evacuation of the facility a staff person is required to pick up the emergency grab bag.
Where is the emergency grab bag. located?
~~a. Emergency exit door reactor bay.~~
~~b. Radiochemistry room.~~
~~c. Control room.~~
~~d. Exit corridor.~~
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~~ANSWER L.02 (O.75) d.~~
~~REFERENCE f~~
RRF Emergency Implementation Procedures, Appendix c.
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~~QUESTION L. 03 ' (O. 75) ,~~
-Multiple Choice, Select the correct response. ,
RRF Technical Specifications and administrative procedures establish organizational reporting guide lines and position responsibil i ti es.
What is the title of the person that the Reed Reactor Facility r,irector reports to and is directly responsible to?
~~a. Reactor Operations Committee Chairman, i:- b. Radiation Saf ety Committee Chairman.~~
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L c. President of Reed College.
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' d. Reactor Review Committee.
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~~ANSWER L.03 (0.75)~~
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REFERENCE p RRF Technica) Speci-F i cati ons , and RRF Administrative i Procedures.
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~~QUESTION L.04 (2.O) x.<.c- , ,~~
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There are TWO (2) conditions that require that the NRC review and approve. changes to the facility Safety Analysis Report (SAR), related procedures, tests, and experiments; These conditions are stated in 10 CFR 50.59," Changes, Tests, and Experiments.
What are the TWO (2) conditions that require NRC approval?
ANSWER L.04 (2.0) f 1. Changes to the Technical Specifications (i incorporated ' i n r the license). (1.0) l 2. Unreviewed saf ety question. (1.0) i
~~REFERENCE 10 CFR 50.59, Changes, Tests, and Experiments.~~
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~~QUESTION L.05 (0.75)- y~~
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Multiple Choice, Select the correct response.:
1 The RRF Technical Specifications set limitations on the '
reactivity worth of experiments.
What is'the maximum reactivity worth limit of any. single in-core experiment?
~~a. $1.00~~
~~b. $1.35~~
~~[ c. $1.75 I~~
~~d. $2.00 l; . _ .~~
~~ANSWER L.05 (0.75) b.~~
~~REFERENCE RRF Technical Specifications, Pg. 6.~~
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~~QUESTION L.06 (0.75)~~
~~c-Multiple Choice, Selectthecorrectresponse[. , , -~~
The RRF Technical Specifications set limitations on the reactivity worth of experiments.
What is the total reactivity worth limit of all in-core experiments?
~~a. $2.00-~~
~~b. $2.25 L ,~~
't. $2.50
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~~d. $2.75 1- _.~~
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~~ANSWER L.06 (0.75) a.~~
~~REFERENCE RRF Technical Specifications, Pg. 7.~~
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~~QUESTION L.07'(0.75)~~
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Multiple Choice,, Select the correct respons:e.
The RRF Technical Specifications set limitations on the reactivity worth of experiments. When experiments mest a specific reactivity worth they 'must be located or securel y fastened to prevent inadvertent movement during reactor operation.
What is the reactivity worth limit, that requires experiments to be securely fastened?
[- a. $1.00
. b. $1.50
~~c. ~~i2. OO i~~
~~(. d. *2.50~~
~~ANSWER L.07 (0.75) a.~~
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~~REFERENCE~~
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RRF Technical Specifications, Pg. 7.
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~~QUESTION~~
~~1. 08 AO'75) ,.~~
Multiple Choice, Select the correct response.
RRF Technica1' Specifications set a limit f or' the total ;
inventory of iodina (131 through 135) and strontium - 90 '
irotopes in each~ f ueled experiment.
What is the limit f or iodine (131 through 136) isotope 4.nventory in each f uel ed experiment?
~~a. O.15 curies iodine.~~
, b. 5.0 millicuries iodine.
k p c. 1.5 millicuries iodine.
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~~d. _.1 5 curies iodine.~~
~~ANSWER L.08 (O.75) d.~~
~~REFERENCE RRF Technical Specifications, Pg. 7.~~
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~~QUESTION L.09 (O. 7 5) 7. . _~~
Multiple Choice, Select the correct response.
The RRF Technical Specifications allow operation of the reactor at two different power levels. One power l evel is for steady state mode, the other is for testing of the full power safety circuits..
What is the maximum RRF Technical Specificati on power limit !
for testing of the full power safety circuits?
~~a. 237.5 kilowatts.~~
~~b. 250.0 kil owatts.~~
~~c. 275.0 kilowatts.~~
~~d. 787.5 kil owatts.~~
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~~ANSWER L L.09 (0.75) d.~~
~~REFERENCE RRF Technical Specification, Pg. 1.~~
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~~QUESTION L.10 (0.75) ,~~
Th; Multiple Choice, Select the' correct response.-
- The RRF Techr.*al Specifications state a minimum shutdown margin f or a condition of cold xenon f ree and the most reactive control element fully withdrawn.
What is the minimum Technical Specification shutdown margin
. limit for these conditions?
~~a. O.2 % delta k/k.~~
. b. O.4 */. delta k/k.
~
~~c. 0.6 % delta k/k.~~
~~s d. _1. 0 % delta k/k.~~
~~ANSWER L.10 (O.75) r~~
~~b. ;~~
~~REFERENCE g RRF Technical Specification, Pg. 3.~~
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~~QUESTION L.11 (0.75)-~~
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Multiple Choice,' Select the correct response./
RRF Technical Specifications set a limit for?the total inventory of iodine (131 through 135) and strontium - 90 isotopes.in each fueled experiment.
What is the limit f or maximum ' strontium - 90 isotope inventory in each fueled experiment 7
~~a. 0.5 mil 11 curies strontium,~~
~~b. 1.5 mil 11 curies strontium.~~
~~c. 0.5 curies strontium,~~
~~d. 5.O mil 11 curies stront!"*.~~
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~~ANSWER L.11 (0.75) d.~~
~~REFERENCE RRF' Technical Specifications, Pg. 7.~~
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~~QUESTION L.12 (0.75)~~
Multiple Choice, Select the correct response. , ,
RRF Technical Specification and admi nistrative procedures establish organizational reporting guide lines and position responsibilities.
What is the title of the person who i s responsible f or approving all reactor experiments?
~~a. Di rector of Reed Reactor Facility.~~
~~b. Reactor Supervisor.~~
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! c. Reactor Operations Committee Chairman.
~~d. Radiation Safety Committee Chairman.~~
~~ANSWER L.12 (0.75) a.~~
~~REFERENCE i RRF Technical Specifi:ations, and RRF Administrative t- Procedures, k~~
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~~QUESTION L.13 (0,75). . . , _~~
4 - .+ Y .j g.7 Multiple Choice, Select the correct response.f
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The Reactor Review Committee (RRC) is established to to provide for a review and audit of reactor -f acility operations.
How.often are the RRC sub committees required to moet?
~~a. Once a year. .~~
~~b. Twice a year.~~
p c. Three' times a year.
.5 d. Monthly.
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~~ANSWER L.13 (0.75) b.~~
~~REFERENCE~~
~~g. RRF Technical Specifications, and RRF Administrative Procedures.~~
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~~QUESTION L.14 (0.75) , ,~~
Multiple Choice, Select the correct respons'e.~
Start up and Core Excess Check procedure SDP '03 personnel requirements state that the reactor SHALL be operated by or under the direct supervision of a person who holds a valid Operator or Senior. Operator license issued by the NRC.
-What is the title of the - person . who is responsible f or the sel ecti on - of personnel to operate the Reed College Reactor?
x a. Director F.RF.
~~b. President of Reed Col l ege.~~
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I c. _,eactor R Safety Committee Chairman.
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~~d. Reactor Supervisor.~~
~~ANSWER L.14 (0.75) a.~~
~~REFERENCE~~
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~~QUESTION~~
- L.15 - (1. 5) ., ,
y.p Short Answer.
The. RRF Emergency Plan classifies THREE credible Emergency Action Levels (EALs).
g What are the THREE'(3) credible EALs for the RRF?
(0.5 pts. ea. max 1.5 pts) (1.5)
~~ANSWER L.15 (1.5) (0.5 pts ea. max 1.5 pts.)~~
!. 1. Non-Reactor Safety Related Event. (0.5)
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~~2. Notification of Unusual Event, (NOUE). (0.5)~~
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~~3. ~41ert. (0.5) h r~~
~~REFERENCE RRF- EP.~~
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~~QUESTION L.16 (1.0)~~
,, 3 Short Answer. f*
a An electrical and themical fire has caused an evacuation of the RRF in accordance with RRF Emergency Implementation Procedures (EIPs). The main facility electrac circuit j br eaker is required to be tripped as part of duties duties. '
~~a. What is the name of the hospital that injured RADIOLOGICALLY CONTAMINATED personnel are taken to?~~
~~(0.5)~~
~~b. Where is the emergency key kept to allow the operator i to gain access to the main facility electric breaker?~~
(0.5) i
?
~~ANSWER L.16 (1.0)~~
~~a. Good Samaritan. (0.5)~~
~~b. (Emergency) Grab Bag. (0.5)~~
<I;EFERENCE RRF EIPs.
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.* QUESTION L.17 - (0.75) pm.
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Multiple Choice, Select the correct respon.se.-
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The'RRF has radiation m'onitors which actuate alarms and/or ventilation confinement when preset levels- of ' radiation are sensed by the detectors, in accordance with RRF emergency plan, Appendix D.
=What is the alarm set point of the Continuous Air Monitor (CAM)?
i' , a. 400 CPM o b. 2 mR/hr ,
I Lh c. -1500 CPM t'
~~d. 2000 CPM i~~
~~ANSWER L.17 (0.75)~~
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~~REFERENCE j RRF Emergency Plan, Appendix D, and SDP 30.~~
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~~QUESTION L.18 (0.75)~~
Multiple Choice, Select the correct response.
. . . , 3 The RRF has radiation monitorb which actuate alarms and/or ventilation confinement when preset levels of radiation are sensed by the detectors, in accordance with RRF emergency plan, Appendix D.
- What is the alar.n set point of the Radiation Area Monitor (RAM)?
~~a. O.2 R/hr~~
~~b. 2 mR/hr~~
~~c. -.50 1~~
~~CPM~~
~~d. 200 CPM~~
~~ANSWER L.18 (0.75) b.~~
~~REFERENCE RRF Emergency Plan, Appendix D, and SDP 70.~~
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~~QUESTION~~
' ~
L.-19 (0.75)u pg % . 4 . !
, 1" 4 Multiple' Choice, Select the r.errect respon" sed 4
4gy l Reeds Emergency Implementation Procedures';-IEIPsf allow
~
~
limited re - entry of personnel into an area that has been evacuated due to a radiological problem if the entry is to save a lif e or prevent a serious accident. The dose rate and personnel doses are limited during the entry.
What is the maximum allowable radiological dose rate f or re - entry, in accordance with RRF EIPs?
.- a. 10 R/hr
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F b. 25 R/hr f- c. 75 R/hr
~~d. 100 R/hr '~~
c'J L CR L.19 ( 0. 7 5 )
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~~REFERENCE L.~~
RRF Emergency Implementation Procedures, Appendix c.
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~~QUESTION L.20 (0. 75) ' y z~~
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Multiple Choice, Select the correct response.
Reeds Emergency-Implementation Procedures 1(EIPs) al l ow limited re - entry of personnel into an area'that has been evacuated due to a radiological problem if the entry is to save a lif e or prevent a serious accident. The dose rate and personnel doses are limited during the entry.
What is the maximum personal dose allowed by RRF EIPs to save another persons lif e?
~~a. 2.5 Rem~~
~~b. 25 Rem c.~~
50 Rem
- d. 100 Rem k
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~~ANSWER L.20 (0.75) b.~~
~~REFERENCE RRF Emergency Implementation Procedures, Appendix c.~~
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~~QUESTION: l L. 21 " :(1. 5) - 7 7, . ,~~
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RRF Technical Specifications establish THREE"$ (3)' criteria )l
.for'when experiments shall'be' doubly encapsulated. l
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What are the THREE - (3) ' times - when experiments shall be j doubly encapsulated? (0.5 pts. ea. max. 1.5 pts.) . (1.5)
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~~ANSWER~~
~~j. L.21 (1.5)~~
- ( O'. 5 p t 's'. ea. max 1.5 pts.)
Experiments that are:
.=
~~1. corrosive to reactor components, (0.5) ,~~
~~i '-~~
~~2. compounds (highly)-- reactive with water, (0.5)~~
~~3. liquid fissionable materials. .(0,5).~~
~~REFERENCE~~
~~RRF Technical Specification,.Pg. 7. ,~~
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END OF SECTION L "y,ya ; "
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END OF WRITTEN EXAMINATION " *-
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100
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_ . _ _

ML20245H225

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SUMMARY

G. PROCEDURE

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