ML20238D615

Exam Rept 50-089/OL-87-02 on 870804-05.Exam Results:All Candidates Passed Oral Exams & Two Candidates Passed Senior Reactor Operator (SRO) Written Exams.Two SRO Licenses Issued

ML20238D615
Person / Time
Site:	General Atomics
Issue date:	08/13/1987
From:	Elin J, Morrill P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20238D606	List: ML20238D604 ML20238D615
References
50-089-OL-87-02, 50-89-OL-87-2, NUDOCS 8709110286
Download: ML20238D615 (105)

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{{#Wiki_filter:_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ l U. S. NUCLEAR REGULATORY COMMISSION REGION V Examination' Report No. 50-89/0L-87-02 Facility: GA Technologies, Inc. - Mark I and Mark F TRIGAs Docket Nos: 50-89 and 50-163-l Examinations administered at the GA Technologies TRIGA Test Reactor Facilities, La Jolla, California O//3/87 Chief Examiner: PhilipyMo ill, Operator Licensing Examiner Uate Signed h 3/V7 Approved: ohn 0. Elin, Chief, Operations Secion pte Vigned Summary: Examinations on August 4 and 5, 1987. Written and oral examinations were administered to three SR0 candidates. All candidates passed the oral examinations and two candidates passed the SR0 written examinations. Two SR0 licenses were issued. R DO K 9

l l REPORT DETAILS 1. Examiners:

• P. Morrill, NRC J.Elin,NRC(Auditor)
• Chief Examiner 2.

Persons attending the exit meeting: P. Morrill, NRC W. Whittemore, GA Technologies J. Razvi, GA Technologies 3. Written Examinations and Facility Review Written examinations were administered as follows: 3 SR0 Exams - August 4, 1987. All sections. At the conclusion of the examination, the facility staff reviewed the examination. Based on this review, the facility staff had comments on the examination which were discussed with the Chief Examiner. Based on these discussions, appropriate revisions were made to the master examination key by the Chief Examination prior to grading the candidate responses. The examiner's resolution of the licensee's comments are documented in Attachment 1. During the grading of the written examinations the examiner observed that all the candidates appeared to have some difficulty answering questions on infrequent operations, such as emergency shutdown, crane operations, and response to fire. 4. Operating Examinations: Oral examinations and facility walkthroughs we're administered to three SR0 candidates on August 5, 1987. 5. Exit Meeting: On August 6, 1987, the Chief Examiner met with the licensee representatives listed in paragraph 2, above. The Chief Examiner observed that some of the candidates had difficulty explaining how the automatic make-up water supply for tne Mark F cooling tower operated. The Chief Examiner also discussed the grading process for the written examination and the schedule.

l ATTACHMENT 1 EXAMINATION REPORT - FACILITY COMMENTS GA TECHNOLOGIES SR0 EXAMINATION . AUGUST 4-5, 1987 ' Question: N/A Facility Comment: The equation sheet did not appear to be used for any of the examination questions. Resolution: The examiner will consider updating the standard examination sheet prior to the next examination. Question: H-1 Facility Comment: On Figure H-1 the " Reactor Power" scale should be more properly labled " Reactor Log Power". Resolution: The connient is correct, however no change to the key appears appropriate. Question: H-3 Facility Comment: In the question " delta K" should have been "K effective". Resolution: None of the candidates questioned this item. However, the examiner agrees. The correct answer then becomes 0.8 - 0.9, which is -0.10, answer "C". Since there is no single correct answer the question will be deleted. t

.1 P. ] 1 ' ATTACHMENT IL-C NTINUED Question: H-6 Facility Coment: .In parti (d).the, candidates ma'y also state-that:the xenon - peaking ;is.due to the fact' that the half. life of I-131 is less than the half: life of Xe-131. This is'an equally valid L answer.

Resolution:

The examiner-. agrees this'is'also'a correct answer and will add this response to the key.. Question: H u Facility Coment: i In part (a)'the answer. given is for low enriched fuel with stainless' steel cladding. The correct answer should be that: "The cell effect is much more significant to the NTC in FLIP fuel-due-to the short neutron range or due to'the large absorber.(erbium and U-235) cross section in the fuel." Reference is on page 23 of Chapter VI. Resolution: . The examiner. agrees. The key will be appropriately modified and the reference added.- Question: H-16 Facility Coment: Fuel can pressure is not very important, since it never gets above several PSI during pulses and the bur:;t pressure is much' higher. Resolution: No change to the. key was requested, nor does one appear appropriate. 1 ~

i ATTACHMENT 1 - CONTINUED I Question: I-7 i i Facility Comment: In the question the word " radiation" should be " source radiation". This is due to the fact that some beam ports use boron as part of the shielding material and boron will interact with neutrons to form alpha particles. 4 Resolution: No change to the key was requested, nor does one appear appropriate. The examiner will consider rephrasing the question in the future. Question: 1-11 Facility Coment: Theanswertopart(c)couldalsobe"toallowthedetector to operate". Without the holes in the attenuator, no neutron would get through and the detector would not work. Resolution: After rereading the reference material the examiner agrees. The answer will be changed to read " Holes in the attenuator allow some of the thermal neutrons (from the outer moderator) to pass into the inner moderator (and mix with neutrons thermalized in the inner moderator to provide a neutron field proportional to the dose rate in tissue)." Question: J-4 Facility Comment: The facility personnel consider "a. incore, hollow eleuent" and "d. dry irradiation facility" to be the same irradiation device (ie, a dry tube). Thus, the correct answer to J-4(a) is either "a" or "d", and there is no correct answer to J-4(b). Resolution: The examiner agrees that the four options presented could have been worded better. However, none of the candidates questioned the examiner regarding this point. "a" or "d" will be accepted for part (a) and part (b) will be deleted.

m-V LATTACHMENT 1 - CONTINUED . Question: J-6 Facility. Comment: b The question should state.which reactor, since the void tank-would be the preferred test facility for fast neutrons in the Mark F.. Resolution:- i None of the candidates had any questions regarding this Litem. The question was not. reactor specific -therefor the best. choice'is still'"d". No change will.be'made.to the key. ~ (Question:'J-8' -t Fa'cility Comment: ~ The correct answer is "c". Typographical error. Resolution: LThe examinerf agrees and ~will change the key. ../ Question:'J-11 FacilityLComment: 'A more appropriate alternative would have been "e. An alternative source of secondary water can be supplied thrbugh the cooler access plate." Resolution: The facility comment may be used for future questions, _however, the comment does not change the key. 4 1 l

L 1 ( ATTACHMENT 1 - CONTINUED Question: J-16 Facility Comment:

The question does not state whetber steady state or pulse mode is being considered. More importantly, the reference material is out of date. Consequently, the correct SCRAM setpoint for the Mark F K-1 linear power channel is 1650 Kw or 110% and the Mark F T-2 fuel temperature SCRAM is set at 650.C. The reference material will be corrected.

Resolution: The ' examiner confirmed that the setpoints for SCRAMS were as stated. The examiner also confirmed that these settings were . consistent with the Technical Specifications. The key will be changed as requested. Question:'K-1 Facility Comment: The words " basic limit" in the question should be " basic safety limit", which for TRIGA fuel is 1150 C. The ultimate limit is 1350 C, at which point the zirconium hydride would decompose violently. As a practical matter the facility limit for fuel temperature is 800 C. The limits for fuel temperature for the Mark F in the Technical Specifications are for transient operation. Resolution: The facility personnels' comments have merit, however, the reference material clearly indicates an operational limit for steady state operation in the 650 to 700 C range. No change will be made to the key.

7 ~ ATTACHMENT 1-- COT <TINUED l Question: K-5 j Facility Comment: Pulses are started from low power. Thus, the initial' statement is confusing. All of the choices are reasons why . pulses are startedffrom low power. Resolution: i The examiner agrees that the initial statement could be stated more clearly. However, none of the candidates questioned the examiner regarding this item. It is clear from the reference material that three of the four items listed are concerns if pulsing were started from high power, -consequently the key will not be changed. l Question: K-13 Facility. Comment: In K-13(a) the lead-in statement should state "very low power" in place of " low power" since the linear increase due to source neutrons will not be seen in the mill-watt range, which we consider " low power". Also, in the choices to K-13(b) the word " logarithmic" should be "expoential". Resolution: The facility comments would improve the questions' clarity. None of the candidates asked for any clarification of these l two points. No change appears appropriate for the key. j l Question: L-9 Facility Comment: The annual and semi-annual calibrations conducted by the Health Physics personnel are recorded in the H.P. Service i Records, however daily and weekly calibration checks are conducted by the operators on watch and recorded in the Operations Log. "C" is the correct answer. The reference material does not discuss these daily and weekly checks. ] i Resolution: The examiner verified the facility personnels' statements. The key will be changed to indicate "C" is the correct I answer. l

I ATTACHMENT 1 - CONTINUED-i - Question: L-16 o ' Facility Comment: There is no maximum reactivity limit for experiments in the Mark F anymore. Amendment 33.to the Technical Specifications sets limits of $3.00 per experiment, but no overa;l limit. This amendment was accidentally omitted from the copy of the Technical Specifications sent to the examiner. In any case, the answer in the key is still correct since both the Mark I and the Mark F were included in the question.

Response

No change was made to;the key. l

ORIGI Al19L ' kli YH Pi*rc I L I T'Y 1 l co 2EEcT70^)S i -i U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: cA Technologies Reactor Type: TRIGA MK1 and MKF Date Administered: Aucust 4. 1987 Examiner: p-

3. Mntr m Candidate:

INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Write answers on one side only. Staple- [. ques. tion sheet on top of the answer sheets. Points for each question 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 if: Value Total Score Cat. Value H. Reactor Theory

j I.

Radioactive Materials Handling Disposal and Hazards i J. Specific Ope' rating - j Characteristics K. Fuel Handling and Core Parameters L. Administrative Procedures, Conditions and Limitations Totals Final Grade All work done on this exam is my own. I have neither given nor recieved aid. Candidate's Signature i 1 4

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z REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS

[ l ' 1. A single room shall be provided for completing the written examination. The location of this room and supporting restroom facilities shall be silch as to prevent contact with all other facility and/or contractor personnel during the duration of 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. the licensee. Obtaining this room is the responsibility of 2. Minimum spacing is required to ensure examination integrity as determined by the chG # examiner. with a 3-ft space between tables. Minimum spacing should be one candidate per tabl No wall charts, models, and/or other training materials shall be present in the examination room. 3. Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshments. These arrangements chall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor. 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to pro-vide formal written comments with supporting documentation on the examina-tion and answer key to the chief examiner or to the regional office section chief. 5. The facility licensee shall provide pads of 8-1/2 by 11 in lined paper in unopened packages for each candidate's use in completing the examination. The examiner shall distribute these pads to the candidates. All reference material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens, pencils, calculators, or slide rilles into the examination coord, shall be allowed. and no other equipment or reference material 6. Only black ink or dark pencils should be used for writing answers to questions. ~. 8 4 . q:; 3 i.+ d_

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: ~ 1. Cheating on the examination means an automatic denial of your applicatioit and could result in more severe penalties. 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. i 3. Use black ink or dark pencil only to facilitate legible reproductions. 4. Print your name in the blank provided on the cover sheet of the examinatica. l S. Fill in the date on the cover sheet of the examination (if necessary). 6. Use only the. paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of each section of the enswer sheet. 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write o g one side of the paper, and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for example,1.4, 6.3. 10. Skip at least three lines between each answer. 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table. 12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the deptn of answer required;-

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the cuestion or not. 15. Partial credit may be given. Therefore, ANSWER ALL PARIS OF THE QUESTICN AND DO NOT LEAVE ANY ANSWER BLANK. 16. If parts of the examination are not clear as to intent, ask questions of the examiner only. l 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.

( - i l

18. When you complete your examination, you shall:

a. Assemble your examination as follows': (1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are a part of the answer. b. Turn in your copy of the' examination and all pages used to answer the examination questions. Turn in all scrap paper and the balance of the paper that you did c. not use for answering the questions. d. Leave the examination area, as defined by the examiner. If after' leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. ~.

EQUATION SHEET I l l f = ma v = s/t 2 Cycle efficiency = N W k t) v = mg s=vt+ at E=mC a = (vf - v )/t ~* KE = hmv v A = AN A=Ae f = v, + a g PE = mgh e = e/t A = in 2/tg = 0.693/tg W = vaP aE = 931am

• h(* ) " (t )(t )

i s (t +t) b Q = mC ar 1,f,-Ix p 9 Q = UAAT -px 7,7 f [n Pwr = V I=I 10 *! M ~ SUR(t)' P=P 10 TVL = 1.3/p e /T HVL = 0.693/p t P=P SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K gg) /Aeff ) p WR = 26 CR = S/(1 - Keffx) g CR (1 - Keff)1 = CR (1 ~~Keff)2 T = '(1*/p )+ {(6 a )/x fg ] 1 2 f p p T = F/ (p - D M = 1/(1 - K gg) = CR /CR i 3 0 ~ P)! P eff M = (1 - K ff)0 (1 ~ eff)1 ~l)/Kdf = AK,ff/K eff eff SDM = (1 - K,ff)/K,ff [1*/TK,'ff ] + [H/(1 + A,gfd t*=1x10becods p= P = I4V/(3 x 1010) A,ff = 0.1 seconds ~ I = No Id ~Id y1 22 WATER PARAME'iERS Id =1d y 2 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters) I gal. = 3.78 liters R/hr = 6 CE/d (feet) 3 1 ft = 7.48 gal. MISCELLANEOUS CONVERSIONS 3 10 Density = 62.4 *,5m/ft 1 Curie = 3.7 x 10 dps Density = 1 gm/cm I kg = 2.21 lbm 3 Heat of vaporization = 970 Etu/lbm I hp = 2.54 x 10 BTU /hr 6 IIcat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 10 Btu /hr 1 Atm = 14.7 psi = 29.9 in. Ig. . Ctu = 778 ft-lbf 1 ft. H O = 0.4333 lbf/in 1 inch = 2.54 cm 2 F = 9/5 C + 32 "C = 5/9 ( F - 32)

V Lg CATEGGRY H REACTOR THEORY ll H-1 (2.0) Refer to Figure H-1 which shows an instantaneous negstive . reactivity insertion into an already critical reactor core -at ' tame 'T = 0. After a stable period is reached an instantaneous removal of this negative reactivity occurs at time T = 1.-Respond to the following ~ questions, assuming source neutrons are not significant. (a) Sketch the reactor power level as a function of (1.0) time on Figure H-1 for these reactivity changes. (b) Sketch'the resulting reactor period as a function (1.0) of time on Figure H-1 for these reactivity changes. H-1 Answers (a & B) nc? attached drawino (1.~0 each)

Reference:

Chapter VI, pagen 12-l'ii 1 1 i

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l l .s t-l 1 H-2 - ( l'. O) 1 MULTIPLE' CHOICE --SELECT THE BEST' ANSWER-l ~ The reactorcis shutdown with a count rate of 10 CPS cn the count-rate channel. K(eff) has been determined to be 0.95. What K(eff) is' necessary to increase the count rate to 80 CPS with the,*same source neutrons ? a. 0.990 b. 0.994 c. 0.988 d. 0.983 H-? answer- .b. E.CR 1 ( 1 - Neff1) = GR2(1 - 1.eff2) (1.0) i 10(1 - O.95) 80(1 - Kef f.?. ) = .Kuif2 .0,99373 Ref farence: Chiepter VI, page 16

l< A, h-.- . v i l ] 'H-3 ( 1. 0 F MULTIPLE CHOICE.-. SELECT THE'BEST ANSWER . I I t' delta K changes f rom 0.0 to 0.9 the reactivity changes by: ?. c l a. + 0.10 i l ~-b. ..+ 0. 1'4 c. - O.10 Ld. - O'.14. -H-3 ' An twer.. QUESTION DELETED Referencee Ch apt er : VI., page 9 4 I l

r.: s r-H-4 '< 0; 5)' MULTIPLE; CHOICE -- SELECT THE BEST ANSWER Source neutrons 'for the Mark F reactor come f. rom. an inste.11ed source which uses.: t ~ a.. Americium - cesium .. b.. Plutonium - antimony c. Plutonium - polimium l .j ..d. Americium - beryllium H-4 ~ Answern d. (0.5) k i

Reference:

Chanter I,. pace 14 and Chapter VI, page 16 l 4 .~

[ H-5 (0. 5 ): I MULTIPLE'CHDICE - SELECT THE EEST ANSWER t-l,. i i An' installed neutron source is needed to conduct .a reactor .startup'in order"to: . a'. provide overlap between' neutron detector channels b. allow calibration of compensated ion chambers at low power n. c.- permit contrc11ed startups using; accurate indicatien d. ' reduce uncertainty in the period meter after a long shutdown H-S Answer :- c. ' ( 0. '3 ) Referencer-gbapter VI, page 16 i I i

[i l

o o_______. 1

,i 'H-6 '(2.O) .The Mark will be operating at full power for sevetal: days. (A) How long willit take xenon to reach equilibrum'P . (0. 5) (b)- What'condit-ions cause equilibrum xenon? ,,"( O. 5 ) (in terms of xenon sources and losses) _. c ). How long will it tak'e f or xenon to peak f ollowing ( a shutdown? (maximum negative reactivity) (G.5, 1 (d) What causes xenon to peak following a shutdown?. (0. 5). 3,. H-6 ~ Anuwers I -(a) 50-70 hourn (0.5) 4 i (b) Xenon is decayina cin c being burned out at the name i rate it in being produced. (0.5) l (c) 5 to 7'hourri (0,5) (d) Xenon i <., c t i l l b ai n ti produced from decaying J a d i n a ( 131 ) while it is no l on g e r" being removed by bu: nou*, or the hal#-1if e at 1-131 in

2. e n s ::han the half-1if e of X e - 1 3 1.,

(0.5) Ref erenca: Chapter VI, pegac 5-27 1 4 2 k l l i 3 i p =p l

a Lp p. L H-7 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER The negative. reactivity due to the fission product' poison samarium: a. has an equilibrum value independent of power -level "~and decreases slowly after shutdown. 'b.- has an equilibrum value independent of power 'l eve l and' increases slowly after shutdown, c. has an equilibrum value which increases with power level and decrease slowly after shutdown. d.- has an equilibrum value which increases with power level and increases slowly after shutdown, i M ~'/ in u wser N b. (0. 5) Re f ern nr:et Chapter VI, page '? 7 1

H-9 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER Refer to-Figure H-2 which graphs heat flux as a. f unction of delta T between the fuel cladding and the coolant temperature. The, type of heat transfer at point "X" on Figure H-2 is best described by: a. Convection 6. Film boiling c. Nucleate boiling d, Conduction H-B Answer c. (0,5) Referente:. Chapter V: pagoa.d7-52 si i l d i 1

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'H-9. (1.0)- MULTIPLE CHOICE - SELECT THE BEST ANSWER Refer to' Figure H-2 which graphs heat. flux as a function of delt& T between the fuel cladding and the coolant temperature,- a reactor has been started.up frem zero power and is new producing 50,000 Btu /Hr-SqFt. If the heat flux could be increased to 100,000 - Btu /Hr-SqFt, the delta:T would change from: a. 20tto 30 F b. 20 to 120 F c. 150 TD1 1000 f d. 700 TO 1000 F i M-9 fan 5WLtr a. (i.0)

Reference:

Citapter-VI, p ages 27--32 l L_.

r a N-10 0,0) During high power operation or large positive reacti vi ty i nr.erti ons, what are the two principle' characteristics of TRIGA reactors which prevent departure from nucleate boiling and subsequent burn-out of the fuel? -H-10 Answer The l ar ge negative temp!rature coefficient (0.5) and the l ar g:3 nieg at i ve void coefficient (0,5) will decrease power beform DNB and burnout cccur.

Reference:

Chapter VI, page 32 4., [ i l

H-11 (1.0) MU'LTIPLE' CHOICE - SELECT THE BEST ANSWER l q The symbol b (beta) and b(eff)- (beta effective) both denote the-total fracton of delayed neutrons. The difference between these two is: [ j a. b(eff) is smaller than b since delayed neutrons are born with lower energy levels than prompt neutrons. b. b(eff) is larger than b since delayed neutrons are born with lower energy levels than prompt neutrons. c. b(eff) is smaller than b since delayed neutrons are born with higher energy levels than prcmpt neutrons. d. b(eff) is larger than b since delayed neutrons are born with higher energy levels than prompt neutrons. 1 H-11 Answer l b. C(eff) denotes the

1. f*vct:ve del ayed neutron (1.0) fracton and in lara'tr tnan o aince the agerage delayed neutron enerny in.1ower t h s.n the prompt neutrono.3

Reference:

Chaptor VI, p a;t es 9-il L i 1 i 1 I 1 4 l l i 4 1 4 I ) l l

I H-12f(1.O). 'What is the difference'between. fast neutrons and prompt neutrons?- i 1 H-12:Annwer -1 Fast neutrons-are-neutrcna with a h?gh cenergy 2evyt t n d, -thuc . travel a.t high velocity (0.5) while pec>act.neutrens are etnitted immediatly at er during the fiosion precesc (O 5), j a

Reference:

Chapter VI, pagen 6--11 i o,. I

1 1 1 .i H-13' (3.0) 4 The TRIGA reactors. have-_been designed. with :a large prompt ] negative fuel temperature coefficient (NTC). (a) Why'is the " cell effect" contribution to the NTC .much more significant for " FLIP" fuel? [(1.0) (Dyson effect) ~

(b)

Why'does the " FLIP" fuel NTC increase i apidly as a j function of fuel temperature? (1.0) i (c).What are'two' advantages of the NTC increasing rapidly with fuel temperature? (1.0) H-13 Annwers l (a).The cell effect i s much more tu.ani f i cant to 'l i the NTC in FLIP fuel due to the short neutron ] range in the fuel, or due tc the.i arne abso:-ber crasaw ection in the tuel (due to erbium poison i and Et t r a U-2??.i), (The j n r.r p4ftrM! p<9 r p si t i c ;;;ipture in the stainless steal _tadding far neutrons thermalined in the coolant :t n the ajo-contriDuter t o 3. $ +, Cldd'lGW Gnr i chPi fuCl.' ( 1. O) (b) An increasing n urrt er at thernal ~urrann nr e pushed into the erbien rcucnance p: A N) as.the f uOl' tc'fi.per at ur"O r i n:Pt. (1,0) (C) A IT,i '. imum react 1VItV l d 5 'O i% JIC u r r G C in FUiching normal op er ai.i n g o"'p e r ett ur r e, but i.n y Gizeable increana.in care temper =:ture wili i n c e _. e e thU NTC to act as ' chutdown cv nan i ";n. (1.0) i e erence: Ch.ap ter \\,;I. p-, a :. .2.T, Ze in 1 ~' I I .i 0

'H ( 1. O ) - Why will doubling the time a target nuclide is irradiated not double the resultant activity' ? o e H-14 Answer The-rcidi oact i ve decay of tne radio-n_:clidu wh.i l e the target is being i rred i wL re d will elecreane the 2c ti vi t y. 1

Reference:

CAF 1A i

1 ) ._H (0.5) MULTIPLE CHOICE - SELECT THE'BEST ANSWER How will peak power vary as a. function of prompt excess reactivity. inserted into the Mark I' TRIGA reacter? a.- -Inversely b. No change c. Directly d. As the square H-15 Answer d. (0,5) Reference Chapter V1, p a g ra 34 l Il l ________________-___________a

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, c.

H-16 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER How will. fuel can pressure vary as a function of prompt excess reactivity inserted into the Mark I TRIGA reactor? ,j" a. . Inversely 6. No change c.. Directly. d. 'As the square H-16 Ansswer t. (0.5)

Reference:

Chey]t er V1, page do and 67 i l 4 I i l l ) 16 1 i

t l 1 .H-17 (0.5) . MULTIPLE CHOICE - SELECT THE_BEST' ANSWER - The difference between reflectors and moderators is that: ~ ~ a. Reflectors slow down neutrons while moderators decrease core leakage. b. Reflectors. shield aginst neutrons while moderators decrease core leakage. c. , Reflectors shield aginst neutrons while moderatcrs decrease plutonium production. d. Reflectors decrease ' core leakage while moderators thermalize neutrons. H-17 Annwer d. (0. 5 )

Reference:

Chapter VI, paaes 6-3 17 A--.._______._

n.m. w e..x. m a a = -- .c

=-

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%d':,:N[MM' 'l -d^ 'l' "ULTI' P EEC H' OI' C' E' "* - : S E' LE' 'CT' ? THE i BEST ANSWER M L N W, &, mMw.d~W m m{.y-...M' .a... F. Y.The;::TRIGA Markf ICimioperatirig ? at 5fwatts; - s How much reactivity-isi J required ! f orc,a : 20 # second : posi ti vel peri od? QWx, .M, fu T " ~ i. o M U.a. + ~ ' Mr.] " _.. 3 g y; :

• 3 9 s %.4,]f. y 1 r

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b e, ' +38' : c ent s e.<

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• U t

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g_ 3.. H-19 (1.5) While the TRIGA reacters are operating the fuel is hatter than A the surrounding coolant. (a) During steady state full power operation, where is the hottest location in a given fuel element? (0.5) (b) Immediatly after a pulse (before heat transfer becomes significant) where is the hattest location 'in a given fuel element? (O.5) e (c) Immediatly after a pulse (before heat transfer becomes significant) where is the greatest delta T? (across fuel, across fuel / clad gap, across clacding, or between cladding and the bulk ccclant) (0.5) 4 H-19 Answers (a) Al on ti the ce.nterrlane of tho fut' element sO.5) e, ta ) At the edge of the fi'ol aide tht' c l a dtii n c: N.5) (c) Gcrnas the fuel /c3md nap '..S'<

Reference:

Chapter VI, pages IO - 51 103 H 1 END OF EECTION H SO ON TO SECTION I 3

e ..?.

b-CATAGORY I RADIOACTIVE MATERIALS HANDLING, DISPOSAL, AND HAZARDS I-1' (1.0)

MULTIPLE CHOICE - SELECT _THE BEST. ANSWER How long can you remain in an area with a gamma dose-rate of 2.5 R/hr without. exceeding the 10 CFR 20 quarterly whole body limit?' a. 15 min b. 30 min-c. 45 min d. 60 min 1 Answer b,, (QUARTERLY LlillT r 1.25 H Time w C'(1.,25 H) / (2,5 R/nr) J C 60 min / hr 1 l T i me "- 30 min.) Reforencc: Cha;3ter V page 29 ) l O 1 C_E______1_________.________.._.___ _____._m

I-2 (1.0) MULTIPLE CHDICE - SELECT THE BEST ANSWER A point source of GAMMA radiation measures 32 R/hr at a distance of.2 feet. 9 ^ Which of the f ollowing is the best estimate of the radiation dose rate from the GAMMA source at a distance of 16 feet ? a. 500 R /hr b. 2 R/hr c. 500 mR/hr d. 1000 mR/hr I-2 Answer C. ( DOEE RATE iriversely proparta anal to distance nquared ) 500 Mr n-IR ) ( 32 r/HR) (2/16)E2 3 2 +i-1/ M = >=

Reference:

RTD Time, Di atance, Shelding c a1 cul ati on b

I \\ l I-3 (2.0) ANSWER THE FOLLOWING MULTIPLE CHOICE OUESTIONS : J A survey of radiation and contamination levels has been made by ] Radiation Protection personnel. The map (Figure I-1) on the i following page has the results of this survey. Portions of 10 CFR 20 Appendix B, Concentrations in Air and Water Above Natural Background (Figure I-2), are also provided. j -Based only on thia survey and the requirements of 10 CFR 20 answer the following MULTIPLE CHOICE questions. I-3(a) What posting is required in the LABORATORY ? (0,5) (a) CAUTION AIRBORNE RADIOACTIVITY AREA. (b) CAUTION HIGH RADIATION AREA (c) CAUTION RADIATION AREA (d) NO RADIATION POSTING REQUIRED I-3(b) What posting is required in the MARK F (0.5) REACTOR ROOM ? (a) CAUTION AIRBORNE RADIOACTIVITY AREA (b) CAUTION HIGH RADIATION AREA (c) CAUTION RADIATION AREA (d) NO RADIATION POSTING REQUIRED I-3(c) What posting is required in the EHOP ? (0,5) (a) CAUTION AIRBORNE RADIOACTIVITY AREA (b) CAUTION HIGH RADIATION AREA (c) CAUTION RADIATION AREA (d) NO RADIATION POSTING REQUIRED I-3 (d ) What posting is required in the STORADE ( 0. 5.) BUILDING ? (a) CAUTION AIRBORNE RADIOACTIVITY AREA (b) CAUTION HIGH RADIATION AREA (c) CAUTION RADIATICN AREA (d) NO RADIATION POETING REQUIRED I-7 An swn.r r (6) U 85) ,-s 'd) ' 6. ' c.: r e n m : 10 I, -) 8

h. EC SM I f N O F d4 E O M F E R O e/ E C t I KM-X). 4wG F A0 cR0 F 2 O M. + SO R T ADO' R R E E s JS l l C C >x I I e /g %, F F T 4 R F F N O O O O O R D C ,J 7 7 F { l Mf E L /f I O K r S R N O ,V MN w~ g E E { R g M E H K C D g O ~ W A R T N I DA R A 2 R" T OY W T N T O IREM S %asA. e 1 T EME e C KTTT B g \\3 o A MAAS M g [ oo E WEY f R RS ta u e oc T / L mn { o ES s UE P y G Rxa e, H r O FL 7Y N 4 gg I M C p A TO NO T 7 a vo o UR P n c, A i E I g 7' f O E Fns A e n C C i ER L [ A MA H C L ') Y E R TP[ L O O T E o \\ / F S A C K N R E o N M O O R o R C O B o FT I ( A (/' L C KA [ ME ~ R /r I \\ / M ./ 'l -[ Y .r s R A mR O 'T T RNM A A e R sWs hEEMT O gTS B PAY A a ES L e/e 5 s R g z # T e r. q A [ j

J Y k(CEO I~ D l 1 l-Nuclear Regulatory Commission l Port 20, App,8 APPENDfX B-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGRO 1' (See footnotes at and of Appends 81 e dancope ' 7able i Tabie 11 Elememt (atomic number) Col.1-A, M 2-M 2- - ca,,,,,4j, (pCumn y*', (po/mq g4' . lusene (53) i 125 S 5 x10 4 x10-' 8 x 10-H 2x 10-' i 2 x 10-8 8 x10-8 8 x 10-' 2x10-8 l 126 S 8 x10-' Sx10** 9 x 10* H 3 x 10-' l 3x 10-* 3 x10-8 1 x 10-8 9 x 10-8 ,4 i129 6 2 x10*' 1 x 10*

• 2 x 10-u 8x10-8 l

7x 10-8 8 x10-8 2 x 10-' 2 x10-8 l131 S 9 x 10-' 8 x 10-* 1 x 10-" 3x10*' I 3 x 10** 2 x10-8 1 x 10-' 8 x 10-' 1132 8 2x t0-' 2x10*8 3 x 10-' 8 x10-* I 9 x 10-' 6 x 10*

• 3 x 10-'

' 2x10-8 4133 8 3 x t0-' 2 r 10-* 4 x 10* " 1 x 10-e 1 2 x 10 1 x10-e 7x 10-8 4 x10-e i 134 S 6 x 10-' 4 x 10-8 8 x 10-* 2 x 10** I 3 x 10-* 2x10-8 1 x 10 8 x 10-* i135 .8 1 x 10-' 7 x 10-* 1 x 10-' 4xto-e 1 4 x 10-' e'x 10*

• 1 x 10-8 7 x10-s

...,s u..m... indium 97) ir 100 8. 1 x10-8 8 x10-e 4 x 10-' 2 x 10-' i 4 x 10-' S W 10-s g x io-e 2 x t0-* k192 8 1 x 10-' 1 x 10-' 4 x 10** 4 x10-8 4 3 x 10-8 1 x 10-* D x 10-" 4 x 10"* 1r 194 S 2 x 10*' 1x10 8 8 x10-8 3 x 10-' 1 2 x 10* ' 0 x 10-8 5 x 10-' 3x10-8 Iron F6) - Fe 65 5 0 x 10 2 x 10* ' 3 x10-8 8 x 10** l 1 x 10 7x 10-' 3x10-' 2x t0-8 Fe 69 . 8 1 x t0*' 2 x 10*

• 5 x 10-'

8 x 10-* I 8 x 10 2 x 10*

• 2 x 10-'

6 x10-8 Krypton (38) Kr r,5m Sub 8 x 10-* 1 x 10-' Kr85 Sub 1 x 10** 3 x 10-' Kt 87 Sub 1 x 10-* 2 x 10-8 Kr 88. Sub 1 x 10-8 2 x t0** Lanthanum (57).- La 140 i 1 x10-8 7 x 10-e 4 xio-o 2x10-s S 2 x 10-' 7 x 10-8 5 x 10-* 2 x 10-' Leed (82)- Pb 203 S 3 x 10-* 1 x 10-8 0 x10-8 4 x 10-* i ' 2 x 10-* 1x10** 8 x 10-e 4 xio-e Pb 210 S 1x10'" 4 x 10-8 4 x 10-" 1 x 10-' i 2x 10-" 5 x 10-8 8 x 10-** 2 x 10*

• Pb 212 6

2 x 10** 8 x 10-8 8 x 10* " 2x 10*

• I 2 x 10**

6 x 10-8 7 x 10- 8' 2 x10-8 Luleeum p1) LutT7 S 6 x 10*

• 3 x 10-'

2 x 10-' 1 x 10-* i 6 x 10-' 3 x t0** 2x 10-e 1 x t0** Man 0anese (25) Mn62 S 2 x 10-' 1 x 10-' 7 x 10-' 3 x 10-* i 1 x 10-' 8 x 10** 5 x 10-' 3 x 10-' i } Mn$4 8 4 x 10-' 4 x 10-8 1 x 10-' 1 x 10-* i I 4 x 10-* 3 x 10-8 1 x 10-' 1 x 10-* Mn 66.,,. S 8 x 10-' 4 x 10-e 3 x 10-e 1 x 10** I 6 x 10-' 3 x 10-8 2 x 10** 1 x 10-* Mercury (80) Hg 197m I 8 x 10-' 6x10 8 3 x 10-' 2x10" S 7 x 10*' 8 x10* e 3 x 10** 2 x 10-* Hg 197 S l x 10-8 9 x 10** 4 x 10-' 3 x 10** I 3 x 10*

• 1 x 10-8 9 x 10-*

8 x 10-* Hg 203 8 7 x 10-' 6 x 10-* 2 x 10 2 x 10-8 I l x 10-' 3 x 10*

• 4 x 10-*

1 x t0-* Mo8ytxsonum (42) Mo 09. S T x 10 ' 8 x 10-8 3 x 10-' 2 x t0-* 1 2 x 10-' 1 x 10-8 7x 10-' 4 x 10-* Neooynum (80) .. Nd144 S 8 x 10-" 2 x 10-8 3 x 10-a 7 x 10-* I 3 x 10-" 2 x 10-8 1 x tO-H 8 x 10-s Nd 147 6 4 x 10-' 2 x 10*

• 1 x 10*
• 8 x 10-'

I 2 x 10-' 2 x 10-a 8 x 10-* 8 x 10-8 Nd 149 S 2x 10 ' 8 x 10-8 6 x 10-' 3 x 10-* I l x 10-* 8x10-' 5 x 10** 3 x 10" Neptumum (93) Np 237 - S 4 x 10-" 9 x 10-8 1 x 10 3 x 10-8 i tuto

• 0x10 8 4x10 "

3 x 10-* Np 239 8 8 x 10 ' 4 k t0-* 3 x 10-8 1 x to-* 1 7 x 10 *

• 4 x 10-*

2 x 10-* 1 x 10" NKhel (28) Ni 69. .S 6 x 10-' 8 x 10 2x 10 ' 2 x 10-* 277 v l i

I-4 (2.0) In Accordance with the RADIOLOGICAL EAFETY RL'LES established.for guidance of work with radioactive materials; (a) What must be done prior to removal of material ( 0. 5 ). from a Contamination Centrol Zone? o (b) Above what source strength shculd material (OM) not be manipulated witn tne fingers ? (c) At what general area radiation leval must (0.5) j. personnel monitoring devices be worn ? (d) What special equipment is required for transferring (0. 9 low level radioactive liquid between containers? I-4 "emuers (a) '.1CCk iOr s"GC!1 OGCh i Vf.' T l'.n t #1 m i.'1 8 7 1 0 3 (h) O.6 uCi (c) 2 oRem/br

d) a ncnbreal

:abl e ca tcts pan Re'f r'!# G n C O$ ; O l a ;.] l. L.'P V.

p ?.g (? n '? b /

I-5. (1.5) political awareness group has arrived forca visit and A-local' tour'of the Gulf Atomic ~TRIGA facility..This group consists of 12 people; six adult males 1(>21 Years old),.four adult-females (>21 years'old) cne of which is in her second trimester of pregnancy, one 14 year old adolesent male, and one 8 year old female. f As the SRO =on shift at the operating

facility, and with no authority other than the NORMAL-ACESS' RULES, (a)

How many of these people may you allow to. enter (0.5) the reactor facility without violating normal access requirements? (b). What is the mimimun number of dosimeters required' (0.5) for access for thirty minutes by the six adult males, (assuming access approved)? (c) If three of the adult males are to be granted (0.5) access for a period of several

hours, how many dosimeters will be required?

I-5 Ansters (a) nine (b) tou (c) ' bre

Reference:

Chapim III, pages 12/13

..I-6 (0.5) MULTIPLE' CHOICE - SELECT.THE BEST ANSWER Which of.the following types cf' radiation will be expected Et the beam, ports of a shutdown reactor? (a) fast neutrons (b) slow neutrons (c) alpha (d) gamma

1-6 Answer D '.

Reference:

i:haptor ')., page S l a 1 ) l

1 I-7 (0.5) r4 MULTIPLE CHOICE - SELECT THE BEST-ANSWER Which of the following-types of radiation will NOT be expected at the beam ports of a reacter at full power ?

(a) fast neutrons (b) sicw neutrons (c) alpha

- (d) gamma ' I--7 Answer C

Reference:

Chapter V, page 8 l ) l 1 l I l h i J

l I I-8 (1.0) The production of radioactive gasses is a potential hazard in the operation of.a TRIGA reactor. (a) What radioactive gas is produced by (0.5) irradiation of the reactor coolant ? / (b) What radioactive gas is produced by (0.5) irradiation of air ? I-8 Answers (a) Nitrogen 16 (b) Arlon 41 Referencer Chapter V, page 3/7 f 9 ?f l

I-9 (2.0) Figure I--3 shows a JUNO model 9 portable radiation meter. . (a) What three types of radiation can this meter detect? (1.5) (b) What type of detector does this meter have? [D.5) I-9. Answers (a) (0.0 each) gamma beta alpha-(not caliorated) (b) ionization chamber (0,5)

Reference:

Chapter V, pacje 8 r e 0 4

Fm Dr Eu ) Re s k e ] i L R n S O e R i W) I r LO iW x R lI. r C q F W h o QS C R r C M O l R R )- ( 4 ~r E/ MP R L R O 7 L 0 h Tn I R TR o/ i A E E n R s E MD V M a. Z BN M R no ( E U I ho L( TH lR G t l e ma dir r h H {h/ CTAR lv o SI t xx R 'C-O T r C e ~ E s LE S F (o 0 r W o O s / B L AT G B AT B

s .?- i I-10 (1.O) Figure I-4 shows an Eberline PAC iSA Alpha Counter. Why must care be taken not to set the detector down en areas that { may puncture the probe face? { q l I-10 Answer { The sneter will respond to 12aht 1f i unc t ur ed., 4 (It uses a l i ght 'aeitui ti vo photc multinlier tube.> l l

Reference:

Chapter V, Page 14 I 4 I t

___,___,.__,____m_ 1 i 1 I PROBE C ONue CTOM Pt.asTic C,uertD ain G"d>Aken l V__ 4 4 . \\ g~ j PRoTec" trod Cft IDS ~ m:n j

../

N f p - '~ l r-1 4 u e g. 3m m suce MI 4 l ort i ev U [ p l- & q,O c:Sc g. cueen PORTABLE CottntR SCW 7 TYPE %iY 2 v I e

' I-11 (2.5) Figure I-5 shows a NP-2 portable radiation detector. (a) What is the purpose of the " outer moderator (0.5) (item 5 an Figure I-5) ? i (b) Of what is the " outer moderator" made (i tem 5 cn (0.5) Figure I-5)? + (c) Why does the attenuator (items 1,2,b. 3 of Figure' (1.0) I-5) have holes ?' (d) What type of detector does this instrument have ? (0.5) I-1) Arunwer s (a) t h or nitt l i r m +,a r& n et.t t r oi,-> (b) pOlYOthylena (c) flo19n in t h r a L t' en t ta

• a,-

. C., r a 4 ven - he r >ul neutrons (fran ? %> xrt e r vi e'r o r ) :o . intd the i n.. ! f' W O C i rse a t D r M1 fc' al. n UtF tGri illH *i6Gil i T &Cl s i in the inne ..-d w P o r "n ,v a if s. n e u -: + t re] ci i penpurtional 10 iin9 < ; o -* "iwu> (1.O) i i 0, t I.,, h. ... + ,,h',.'.I' '. % af rar F nCia" ( 5'. l :[) il ( 5, '?, - ~; t - e i

r. GdE ~ h A t [ n-J.0 = O/ N~ l O o J. l u~ % 6fte+ } %(Coax K5 C#P) [ CRP 5 ' HRWDLE -e b a u meier ' / yy m, - - v O \\

• o y

O 0,0 h 0 g'o CAP o g* oe o o Go

• o,o ol o

c I o ,0 l 0 b 's*l ,. / n \\ 8-Attenuator, rur /* oo ' 5" / 0 twit noo tt 0 [ /4 Inner mode or

5. Outer ademor' c

3 l 00 /

6. Plus, moderator O

(. V-l j l / i cae Portable neutron detector (S'n00Py) with exploded view of probe a-___-__-_-___-______

I. (2. 0)' Continuous-. monitors are employed at the TRIGA Reactors-Facility 1to' detect airborne and water borne radioactive material. (a) What-type of detector.is used.for continuous (0,5) monitors-? (b) What is the. alarm setpoint of the " Criticality (0.5) Alarm" (RM-12) ? (c) What is,the alarm setpoint of the " water activity (0.5) i alarm" (RM-14) (d) What is the alarm setpoint of the " air filter (0.5) activity alarm" (RM-14) I-12 Answers (a) GM tubes -(b) 15 mR/nr, (c) 45 mR/hr (d) 3 mR/hr R ef'erenc e : Chapter V., Pageu 10 ':.6 l 1 i 1 l i 1 i i i i i l 1 _a

I-13 (3.0) Figure-I-6 shows a TLD badge. (a) Where should the TLD badge be worn ? (0.5) - (b)L Of.what is.the TLD chips made ? ( O'. 5 ) -(c) .What allows the difference in response between TLD (1.0) ' - 100 and TLD '700 to be a measure - of' Thermal Neutron' dose 7 (d) What it, the purpose of the cadmium (Cd) filter 7 (1.0) ( lead or copper not used at TRIGA ) 7-13 Answerr, (a) left breast pocl::et (b) lithium floride 1 (c) Ono chip has a higher percuntr-ae c*- L: --b Whi l e the other has -a higher parcentage af L I--7 L J. -6 h.t c a higher thermal neutron ':r os s section than Li-7, thus the difference in-r e ad i nct s is due to thermal neutrons. (d) El i;ni n ateu thermal nututrons ( .hN ter a cut n et ttr cn f donc measurement. Raference. Chaptet V, Pa g e ',- 3--?5 i 2 i 1 \\ l 1 i END OF SECTION I GO ON TO SECTION L

'l 1 f ' P tq 00.C~ T ~ O' FRONT VIEW (Actual Size) CcPPER. T 6 I / L...J a e L.....-.-..-l h j 1 J l i ^J s 4w.eJ(-no-as TLD EF.us.c LR6.EL) SIDE VIEW (Explo'ded) Pb h & BEL u Cu TLO4tx3 w% TL 0-M ' M LC icd -// / J 7 ' !0 N j -\\ / ~ cu // d Cross sectional views of Personnel Dosimeter Badges

-f4, CATAGORY J SPECIFIC OPERATING CHARACTERISTICS 3 J-1 (2.0) Thel TRIGA Mark I reactor is operating at 100 Kw steady st.$te in t the servo, mode. Unknown to the

operator, the high ' voltage conductor to'the fission chamber breaks.

Otherwise, the high i voltags: supply continues to operate normally. { What initial indications would'ycu expect the cperator to observe for each of the following devices? (0.5 each) i (a) % power channel #1 (b) linear recorder (c) log recorder l (d) regulating rod position 4 1 U*1 An%WOrG (u) "'. power i>cxli n s to ircrease .(0 5) (b) linerar ocarder f a i. t :; l a ;r.c r e (0. 5)- (c) the ~.i n g r<.ords- 'alla to sen Kh S ) (d) tha recpd atin.7 rad mo vea cu t--. (0.9) j .[ [ !.h[ f). ( I[b g ) [, ( f I' *, h\\ (( g

,J-2' (2.O) The MK I reactor:is critical at 500 W in the " automatic" mode of operation. The transient rod is fully up. Consider each of the f ollowing situations one at a time. Bryefly -state-how. the control reds, ~1inear recorder. i ndi cati on,'. and j actual reactor power will respond during the resulting transient. (a) The shim rod UP switch is depressed briefly (1.0) (b) The AIR push button under the manual SCRAM bar is depressed .(1.O) J-2 Anr4Wer 3 (a) t.he sh:i m r aci move, nut, reactor a n ci lin ar r ot, cn3r u power i n C r G G.9H99 and the t egul atinel rad,~ oves in (1.0) 3 (b) the tr anni c.nt rod f alls _ a nto t he c cru, rmL:or and u nc ar recorner p. or.creese, tneremtwg ~c MU V e!5 D!At (1.O) NefOrenCn: C h O pit Q r II, p aq H44 17-16 i ) l i l 4

J-3 '3.0) The TRIGA control rods are controlled by illuminated push button switches in the center of the control pannel. For each of. the following indications state the location of the control rod (UP,. DN or between UP & DN), the location of its

drive, and * (if appropriate) any abnormal condition.

You may assume all light bulbs are good and the reactor. operate switch is ON. (0.75 each) (a) UP light - off DOWN light - off CONT light - on ON light - on (b) UP light - on DOWN light - off CONT light - on ON light -'cn 1 (c) UP light - off i DOWN light - en CONT light - on DN. light - Off (b) UP light'- on DOWN light - off CONT light - off ON light - on a (3 .3 !"t n fl? W :VU (a) red .nd dei ve antw en tc p and >attom QN 5 UP) (0./5) (b1 rcd - ~d drtve cwo<;tely wt t h d r aun ( 0, ^/ f_i ! (c) FOd .pu V h- .: n h a t. t ( , 4) i:.tp1 pen CP n,n t DN, .J i. \\ 2 L:0 t i,H )

• t!

" r! ! J N,, *hi$ tJ:,c ur N SQ t'- .A ilh C ar t {.. i n ' 'R-%-! ( 0, "7 5 ) (d) rad is at tattam cciv ,,, t ru.' aut rosit.ior ( n, 75 ) .a R af :::r wit e : C o 1 t :.. r

one, 10 l

) m__-__-mm_____------------------

L- 'g _.4 ' 41,o) MULTIPLE CHOICE - SELECT THE EEJT ANSWER L The Mark .I and. the Mark F each have varicus irradiation L facilities available.

Answer, the following multsple choice questions.

/ .J-4(a) Which irradiation. facility is used at both the Mark I and the Mark F? (0.5) a. intore, hollow element -1 b. lazy susan, 40 places 1"_dia. c. pneumatic transfer system d. dry irradiation facility J-4(b) . Which irradiation facility is used only at the Mark F7 (0.5) a. irccre. hollow element b. lazy susan, 40 places 1" dia. c. pneumatic transfer system d. dry irradiation facility J-a Answere i t) n, Cr d, '\\ (b) DELETED Rc+eren m r.. m p t ra - ,uano w

L-J -( 0. 5 ) MULTIPLE CHOICE - SELECT THE EEST ANSWER - Th e - "J-TUEES" are Joften used for irradiation of electronic components because: a. Water or condensation is trapped-at the low part of.the tube and will not damage the components.. ' b. the large bend of the pipe prevents radiation f rom streaming up the tube during irradiations. 'c. the shape of'the tube minimizes distortions in the. fast . neutron flux.around the test area. d. any release of radioactive gasses will tend to stav in the tube and not be quickly released. J-5 an rsw ar b. I [NP ' Pr('ilc D: ChaptDr I "QP l 'i 3 t

l i I,. l t 1 ' l, =J-6 (0. 5) ~ MULTIPLE CHDICE - SELECT THE BEST ANSWER i The best irradiation facility to use for fast reutrons would ber a. the Lazy Susan. b. the void tank. c. the removable exposure can. d. the-cadmium lined dry tube. i l J~h OrtGwer l d, R nt p r E.n Cci; ' lIJ rl Al p I. C l-' 1, page. / -- 4 0 i l l 1 l ) i m -__-___b.___._-_-________m.m._

J-7 (1 0) Refer to the attachea' Figure J-1 which depicts a diagram of the Torrey, Pines pneumatic transfer (RABBIT) system. On Figure J-1 draw in the positions of the f our solenoid-operhted valves (1, 2, 3, and 4) for getting a " RABBIT" into the core. 3-7 nnewers See Esttaci'ed drawing. Pt*ferentOg

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1 KEY i. W " RABBIT" f yyy RECEIVER - an, 3 L _I L JL -~' Ii o.g 2 0 23 '3 0F 4 0.25 u U j as / \\ v e v. ? 4 NOTE: Ex4MPlg SGLouJ FILTER'I 'N N REACTOR CORE + v,v 4 RABBIT TRAVEL CLOSED _ ct'EM V BLOWER 1 AIR TRAVEL l ( Anou]s oewcaAL) I i I Fig. 7 %/ Torrey Pines pneumatic transfer system schematic i 1 I 4 6 .__________m.___ m

J-9 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER During normal cperation the TRIGA reactor cores are cooled mostly by; a. forced convection. a b. forced conduction. i .1 c. natural convection. d. natural conduction J-9 Answer c.

Reference:

Chapter I, r e a g;> 6 A f 1

J-9 (1.5) An. independent water treatment system is provided f or each TRIGA reactor. What are the three most important functions et the whter treatment' systems? J-9 Answers Maintetin law electrical c onctutt a vi" " ( t.l', '.'D r ecluce rarJ10acti vi ty (0.5), and maintainantical transparency ( O. f:5 ) of the-water,

Reference:

Chapter 1, paq)e 32 4 l l t 7

J-10 (0.5)- t1ULTiPLE: CHDICE - SELECT THE BEST ANSWER The monitor box in the tiark F water treatmer,t system contains a probe to measure: l a. Ph-b. conductivity 'c. radioactivity .d.- temperature J-10 Answer .c. (0.5) '4ta f er en c e: Chapter I, parle 36 t I f1 1: 1

'.i ' ~ J-11 (0.5) MULTIPLE' CHOICE - SELECT THE.EEST ANSWER In -the: event the Mark F evaporative cooler fails due to a stuck. -closed float: a. cooling will still be supplied by the cooler fans in high speed. b ~. consideration should be given to cross connecting the Mark'I coolina system, c.- losses of water may be made up .from the 8000 gallon underground storage tank. d. the reactor pit level will : decrease due to evaporative losses not being replaced. J-il Annwer b. (O.M)

Reference:

Chapter'Is page 'T and Operating Procedures, : 1 11 F paga -VI-8 12

l l :- J-12.(1.0) A control rod calibration of theLMark F regulating rod is being conducted using the " bump period" method. ' Initially the reactor is critical at'20 watts and the regulating rod in " bumped" out. o (a) Why should the operator. Wait 90 seconds before -taking data? (0.5) (b) Why must power be kept below about 1 Kw during 'the calibration? (0.5) q J-12 Answers (a) To nilow the trarttients d u n-to red wi t hd r av;l (0.5) to decay. (b) To prevent. negative reactivity additions fenm 00.5) NTC.

Reference:

Mar le. F Operating Frecedureti I X -- 1 i:. n d 2 i i 2

I. j l l. l J-13 --(1. 5) 'l I i A control. rod calibration of the Mark I shim rod is being conducted using the " rod-drop" tnethod. Initially the reactor is critical.at i KW.and the shim rod is full cut. The following data l is recorded: a TIME AFTER' ROD DROP REACTCR POWER (LINEAR RECORDER) 1 5 seconds 180 watts 10 seconds 135 watts 'i 15 seconds 100 watts Using this data and the attached figure J-2, what is the worth of. the shim rod 7 J-13 Answer P1/PO :' O.180, 22/PO = 0.135, P3/PO - 0,100 (0.75) From graph p/b 2 = $2 (0.75) = Refernnte: Mari: 1 Operating Pr ot eciur ec IX-:' ~ 1

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l J-14 (0.5) MULTIPLE CHOICE - EELECT THE BEST ANSWER A reactor power calibration (cc.lorimetric) is being concucted ic v-the. Mark I. . hich of the following errors will cause calcul'ated-W power to be lower thari actual? a. 'The calorimetric is conducted at 150 Kw reactor power rather than 200 Kw required by procedure. b.- The pool depth is six inches below the ":ero" mark (15 inches below the top of the tank). c. The forced cooling water system is not fully isolateo and is left running. d. The digital-thermometer used with the installed thermistor probe has a constant -5 degrees error. I J-14 Answer-c.

Reference:

Mark I Operatioq ? c o t:,a d u e n, VIII-1 ) i l I i 1 I l l l 1 l l l J

I' J-15'(0.5) MULTIFLE CHOICE ~- SELECT THE BEST ANEWER i 4 reactor power calibration (calorimetric) is being conducted for l the. Mark I. Which of the following errors will cause calculated power.to be higher ~than actual? a. The calorimetric is conducted at 150.Kw reacter power rather than 200 Kw required by procedura. b. The pool. depth is six inches below the "n ero'" mark ~ (15-inches below the top of the tank). c.: The f orced cooling water, system is not fully isolated and is left running. d. The digital thermometer used with the installed thermistor probe has a constant -5 degrees error. J - 15 +n swer b ^ p M' Orffl C D ; f i ' r 1 O p C;?r d.t i n g E'F C'? O d u r G Ei n

1. i i 'l ~ 1

i J-161 (3.0) f [ For. the ' instrument channels listed below, comolete the table by listing the type :cf' detector used and the automatic reactor protection features (SCRAMS and interlocks) associated with that indicator. Include setpoints if appropriate. DEVICE DETECTOR TYPE AUTOMATIC FEATURES Mark F-linear (0.5) (0.5) power Ch. K-1 Mark F fuel Temp. (0.5) (0.5) meter-T-2 i Mark.I % power (0.5) (0.5) -[ . channel No. 1 7 - 16 An<=. wor n Ofi'dXC~ DETECT:R iYPC i : Ti F 9-'r r I c p c, i:.ibec 9 Mark F linea.- Cf" HC%fd it 16tio O! p Dlv "f r-Ch. 'r ~1 C.: " ! 10,', , t: Wor ' Mark F fuel Temp. TC Screw 9.t 650 C meter i-' Metrk i '/ n c wrer i!!f, E:C F /' M

.t t i20' r: h a n n n i No.

.I RPf er tencu ? Ch /9 p t (?r if p h q P Fp 1Q, '21, ! 11,' 14 t ,3 INIE'h'. k* 9 erch it cal f 11,: !, i. c2'1:v +

l 1 a J-17'(0,5) MULTIPLE. CHOICE SELECT THE BEST ANSWER Loss of the gamma compensating signal to a compensated ion .chanber will: a. cause a sudden increase in indicated power at low power. b. cause a sudden decrease in indicated power at low power. cause a sudden increase in indicated power at high power. c. d.. cause a sudden decrease in indicated power at high power. J-17 Answer a.

Reference:

Chapter II, page 40 l i l l END OF SECTION J GO CN TO SECTION K I 3-l

l CATAGORY K FUEL HANDLING AND CORE PARAMETERS K-1 (2.O) o: Fuel temperature is the basic limit for steady state operation of the Mark F reactor cere. (a) Why does increasing fuel temperature increase the stress in the-fuel cladding? (1.0) (b) What is the operational fuel temperature limit f for steady state FLIP fuel operation? (1.0) K-1 Answers (a) Outganning of hydrogen fron the Iuel i ru:r ea ses internal pressure. (1.0) (b) 650 C to 700 C (1.0)

Reference:

C,h a p t e r V I., page t51 rin rJ 62

} -I l K-2 (0.5) k ( MULTIPLE CHOICE - SELECT THE BEST ANSWER Which of - the following is a reasen for adding stainless steel dummy; elements to.the. Mark F reactor core? -c j a. To change the radial flux distribution in the ccre. l b.' To compensate f or excess erbium in the Mark F cc: e. c. To decrease the excess reactivity of the Mark F core. d. To compensate for experiments that add negative reactivity. 1 K-;2 An9Wer -1 C. fd?-f e r e n c O " Chapter V1, pag 2 'C 4 i i 1 f I .i 0 a m.__m._

5 P K-3 (2.0) A study of the responses of ctandard and FLIP fueled cores during pulse operations has been conducted using a high speed oscillograph. (power level as a function of time) (a) . With the same reactivity insertion, why will a pulse in a FLIP fueled core be about on-half the width of the pulse in a standard care? (1.0) fL (b'> What causes the pulses of the FLIP fueled core to be asymmetrical? (1.0) K-3 4nnwerv. b (a) The FLIP fuel han, mttch snor t" , ompt ocutrc-lifetime than the standard %ci. (19 su 19 as../ (1.0) IN GL

f. ?

.oFO (15 0 ~t s'!.' O. t. i Y E' J.t.?".'P r -(tt.:I P C C Of f i c i (7.n t Which is tcacer -.tw o eM p e r >-" a n t. (1.O) ROierenct-f: hap t er 'v' I, p at gle _ .a ri d 2 :) a

K-4 (1.0) MULTIPLE CHOICE - SELECT THE BEST ANSWER Adding fuel elements, relative to the water filled fuel location in an otherwise completely loaded core will add varrying amtfunt s of positive reactivity. K-4(a) For the Mark I reactor, addition of a fuel element to a water filled position will cause the greatest reactivity addition in ther a. B ring. b. C ring. c. D ring. d. E ring. K-4(b) For the Mark F reactor, addition of a fuel element to a water filled position will cause the greatest reactivity addition in the: a. B ring. b. O ring. c. D ring. d. E ring. K -4 c.r a wy fI-d (,,t ) (;r. 1 r ,T l 4 (l; ) 1 >m (t. Rei~ ent1 J'., c.; l

'l o-K-5 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER Pulses are NOT started from icw power: levels: a.- to avoid a phace change in the. Mark'I (standard) fuel. b. to prevent DNB of the cladding. I c.- to prevent bulk boiling of the water coolant. d. to prevent burnout of the fuel elements. i K-5 'AMGWer c. I N9f GFleric o: Ch ap t z t- '!I, ;]agje '??? 'l ) l l I 1 1

7 K-6 (1.0) MULTIPLE CHOICE - SELECT THE BEST ANSWER K-6(a) At low power the Mark I and Mark F reacter negatWe void coefficients are approximately: a. 1*10-4 Mk I and 2*10-3 Mk F l b. 2*10-3 Mk I and 1*10-4 Mk F c. 2*10-5 Mk I and 1*10-4 Mk F d. 1*10-4 Mk I and 2*10-5 Mk F K-6(b) At low power the Mark I and the Mark F reacter prompt negative temperature coefficients are I approximately: j a. 1*10-4 Mk I and 2*10-3 Mk F b. 2*10-3 Mk I and 1+10-4 Mk F c. 2*10-5 Mk I and 1*10-4 Mk F d. 1*10-4 Mk I anc 2*10-5 Mk F K% on amer s K-6(a) b. ( 0, 5 ) e s1 L d Referonc rhapter VI, acu - ral , <. r u i3" r, -c. 1 I h l

K-7 (2.5) Technical Specifications require that fuel element inspections must be accomplished at least once a year. (a) Based on the Technical Specifications, whe.t are the l three criteria for " damaged" stainless' steel clad fuel? (1.5) l (b) Which two inspections are not required for the l-instrumented fuel elements? (1.0) K-7 An%ers (a) L.e n s thian 1/16 inch bend or sagitta (0.5) i Less than 0.1 inch longer than.i t a ' original length (0.5) No elad def ects '( 0.,5 ) (b) length e n t, bend examinations are not required ( '. 0 ) Ref er r-n c e : Technical Specifications, MK I pelg e 5, MK P page 5 and -l 3a l i } I i l -_-__A

5 . K-8 .(1.0) When-it= is suspected that fuel damage has

occured, when do Technical Specifications allow reactor operation'to be continued?

o o bbW@f ' Operati on may continue for the~ ~i u r P r~ r~ f 1 cating a c:uspected ~ ^ damaged fuel element. ~

Reference:

Technical Specification 3 Pa?les -S and 5a-$b L-__.__-_,,___

K-9 (2.0) l The TRIGA cores contain both moderators and reflectors. (a) What (two items) provide neutron reflection for the Mark I reactor? ( 1". 0 ) (b) What (two items) provide for neutron moderation in the Mark I reactor? (1,0) K-9 Ansween-(a) Graphite at the end of the fuel el en:ent s and graphite in the annulus ar oun ct the coro. (1.0) (b) Zirconium hydrida (f uel mixture) and water coolant. ( 1, 0 )

Reference:

Chapter I, page 16, Chapter (' I p ag mi 6-0 a.qd 22, j

K-10 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER l According to the Technical Specifications, all fuel elements or fuel devices must be stored in a safe geometry with: a. Keff less than 0.9 for all conditions of moderation. b. Keff less than O.O for all canditions of moderation c. Subcritical by at least $4 for all conditions of moderation. d. Subtritical by at least $3 for all conditions of moderation. I-.-10 Answer b. Reef e* er);e: Gac;1r t <1 E r.> Eic i f i e i t L. i o n '> > > <. a _, '5 ^ n t.1 7 4

j: ' 1: j .K (3. 5)

l

[ ~ 'The-Mark I.and.the Mark F' written procedures require certain- ~l I .-personnel to be present during' core modifications. -(a) What personnel must be present during removal of a' control rod for-maintenance? (1.0) .(b) What personnel must be present while. adding an additional fuel element to the core? (1.0)

(c)

What personnel must be present while installing ) an experiment with $2 of reactivity? (1.5) 1 1 K-11 Answere (a) A nenior operator e,uct directly'cupervinci tne work ( 0. 5) and the conocle instrumentation must be monitored by a lit.cnced operator. (0.5) (b) A senier operatcr mast directly supervise the WorP (0.5) and the caneale instrumentation murit be monitored by licensed . J operatar. -(0. D) .] (c) The. m: p er i mer i t. can he innta.tled by a reactor operator (or persor Josignated bs the p?IC) (0,5), the ccnnale muut be observed by a 1.icenstd operstor (0,5) 0.n d the-prccoEG must be g -mupervised'by a santor reactor operator.(O<5) .) Ref eron::: : hapter IV pacio 2-3 and Oper ating Proceduren X,, XI, and XII l 4 4 m i l

i K-12 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER Control rods are prevented from dropping out the bottom of-the Cores! a. the Mark I and the Mark F rods are larger than the grid pl ate. hol es. b. the Mark I and the Mark F have thimbles installed on the . grid plates. c. the Mark I has thimbles installed on the grid plate,- while the Mark F control rods are larger than the grid plate holes. d. -the Mark F has thimbles installed on the grid plata, while the Mark I control rods are larger than the gric plate holes. K-12 Arvi,ver d ( O. ' 'i ) l Ref er en c e.: r:i;a p t e r Is pap s 2-,' s a 6 i s '. '

j: K-13 (1.0) MULTIPLE CHOICE - SELECT THE BEST ANSWER-o ' K-13 ( a ) - Criticality at' low power is indicated by: a. reactor power increasing linearly with the source

removed, b.

reactor power decreasing linearly with the source removed. c. reactor power increasing linearly with the source installed. d. ' reactor power ~ decreasing linearly with the source installed. K-13(b) A slightly suoercritical' reactor is indicated by: l' a. reactor power increasing linearly below the point of adding sensible heat. 'b. reactor power increasing linearly above the point of adding sensible heat. c. logarithmic increase in reactor power below the point of adding heat. d. logarithmic increase in reactor power above the point of adding heat. K-13 Answera c. ( 0. S ) 1 c. (0,5) Ref m ent.g: ry o n ct ar, .m - d i i )

F - K-14 (2.O) l-Fuel-is. picked up.using a fuel handling tool. (a)- What is the purpose of the lanyard.at the top of the' f uel handling tool?- .(1.0) (b )' What will happen if-the-lanyard is pulled while a fuelnelement is being picked.up? (1.0) f K-14 Ani:swers ( et ) The lanyard i s usecJ to release un element ur .to compress the spring inside the tool. ( l',, 0 ) ' (b) The. ei ertnernt will dr op or.wi l l. i tp.t be ;n c h eu .t p. (1.0)

Reference:

Chapter I, p e t;.ca s 4 4 - 4 7 i 4 i j IND GF EECTION K GO ON TO SECTION L i _i__m___u-.___w.o_ u_

l l.L CATAGORY L q l' . ADMINISTRATIVE PROCEDURES, CONDITIONS, 5 l AND LIMITATIONS l 1 L-1 (3.0) I i The three classes of experiments that can be perforned with the TRIGA reactors are classified as " Routine", Modified Routine", i l and "Speci al ". (a) What is the difference between " Routine" and " Modified Routine" experiments? (1.0) (b) Who can authorize " Modified Routine" experiments? (0.5) (c) 'Who are three of the four persons or groups who must review '"Special Experiments"? (1.5) L- ;l (:,n swer s (a) Routine a periments involve operations'which havr-been prevlaunly extenr.ively euamined. Modi 4ied Routino experiments have not previoaul y been per #ormed but Are aimiliar to prev'.ounty performed experiments and do r;.t t have si gn1 +i ct~ntly greater t,nn ar d c. t1.O) (b) Madi f i eri Rautinc experiments ara authorized by the Phy%icitet in Charge (PTC) (0,5) ( c.) (0.5 for any 3 of the follchina) PIC Heal th Physi c t; - Critical:.tv _ a f eguar de Comm'.ttee L i C a n 'f,i t t e.l 4tn d NdC.!. C @ r C OmD l l ::.n C D

Reference:

Anmtniutr:1h m Feauir: ment iIi pam i 2-4 i 1 6

1 i 'L-2 .(2.0) An experimenter-wishes to use the crane to reposi ti on his experiment. i (a) Who-must give permission f or this individual to manipulate the crane? ([.0) (b) Whose authorization must be cotained by the experimenter:to allow him to control the crane? (1.0) L-2 Answers ( a') The SRO (on duty) or above ( 1. 0). l (b) The Phyaicist in Charge (1,0) Reference Operating Proceduren, ,W I I I - i i i 4 c k s I s i \\

-1 b. 4 I l 1 1 L-3 (3.0) J 1 . The TRIGA facility Cri ti cali ty Safeguards Committee (CSC) J

reviews, evaluates, and. approves various aspects of reactor l

operations. (a) What are three minimum requirements for the ' 1 composition of the CSC? (1.5) (b) What are four of the six responsibilities of the CSC (or designated subcommittee)? (1.0) i .i (c) What constitutes a quorm of the CSC?- (0.5) I L-3 Answers (a) The I'5C murt concist of not

1. es s than four persons

- ( 0., 5 ),, who must not be airectly involved in TRIGA operationu (0.5), and collectively possens expertine in Ell arrns of reacto aperstiang and cafety(0.5). (b) (O.23 OGCh f L.T any four of the fc1)orfing) Reviaw anri approval of enporiments Review and approval af rhangen to the 'acility, Technical Specification ,.: Prncedurco DEntDrm3nALion af Nheathr-i?. rcposed c h a n t,e, tOGt. Dr f "o p OF i FT.?n t W0uld C Q r,'a t i t Li C An .An r O V i W W e d 03fOty

u h.st., o n of a ct:ange to the Tecnnical Spec;fications Rev;.ow of the ap'arat i on and operational recoram Reviow 3 a b n o r ra al per f orm ance a-;

t lui p::w o t or oprarationo j RG V i ':0 8.+1 Q

.b n OP P a l C '~ u r ?.t 0; L; J 'l

• :: C ' ;r F O ti C O ' A

"!C 11 ",idCnt3 i t'*j)[ r * ;d]l n !t!)(l a"" I iW; ^R P (c) o r,.o r >.t < n m i e ~ . jar of tN fr,renb ' v t:i, (0.5) R f-N U r t in c.,. : J'ir! Os i f l i. J 3 '.. r i : !

1. J ' r qr.e r i t ; } i 9

1, '-.s g g. ,: ( ' y.n i I

i 1 L-4 (2.0) The Emergency Response and Recovery Director (ERRD) for the TRIGA Reactor Facility has responsibilities during normal operations and during emergencies. (a) Who is the ERRD for the TRIGA Facility? (d.5) (b) What is the task of the ERRD during normal operation? (0.5) (c) What is the task of the ERRD during emergencies? (1.0) L-4 Answorn (a) Th C1 ERhD 15 the l l !. Lir i } e r,; O l ; ' t Dd {titernate ( 0, 5 ) (b) Duri ng normal op o o.tinn thrr ERRO eval. u ca t em t hn emerg: ncy pract,duran (to anm er > tha.t they Gr e O f f C.".i t i V e "' t.t rf) 1 1 i n F,177 Li t Od ). ( U. '3 ) l v (C) 1)Llr i n Cl D T:'.'.F Cl an C 11 :E thP ![ fdd ) ' VD3 LNt L D9 thA scope ?,n c n a t'..t. e L +' h r? c:c ' s. an t nd deciden What itC+ ion 5 :< r t ' J.O p "" o p )' '.. t r. (j.O) Reference-Ad:vi n i st.r :.t i'm Reilt.t i r 'ame n t c III, page 10 i i l 1 l i J

(., L-5 (2.5) While both TRIGA reactors are operating an uncontrolled fire breaks out in the office spaces nearest the fenced in storage yard. The smoke makes it impossible to stay in the building. j (a) What three immediate actions should the operators of the reactor (s) take? (1.5) 3 - (b) Aside from the fire department who should.be (1.0) ') notified? i i L-5 Answers I (a) ShutdoWo the reactorn (0.U), secure the ventilation (0.5), and turn off all non-escential electrical power (0,5). j (b) The PIC cr his desic1nated alternate (0.5) e.n d the Emergency Respcnce Team member on duty X2000 ( 0,, 5 ), References Adminict.rative Requirements III, page 17 and Opera.tinq l Procedures VIl-1 l ,,__m_______-

1 1 i L-6 - (0. 5), J MULTIPLE CHOICE - SELECT THE BEST ANSWER High enriched fuel (>20%) elements can be stored in: o a. storage wells in the floor of the reacter building as long as the radiation is less than 2.5 mr/hr.at the closure. b. in the Mark F canal storage if the. fuel has never been used in a reactor. c. in the Mark I fuel storage racks if the fuel has been used l with radiation levels of 100 mr/hr at 2 feet (unshielded). l d. in a locked steel storage locker in the TRIGA facility as long as seven or fewer elements are stored in a single layer and the fuel has not been used. L-6 Answer l b.

Reference:

Administrative Requirements III, pages 14, 19 and 20 1 I

L-7. (0.5). f1ULTIPLE CHOICE - SELECT T'HE BEST AN5WER TRIGA' reactor fuel is said to be "self protecting" ifs a. the unshielced radiation from the fuel at three feet,is greater than 100 R/Hr. b. the unshielded radiation from the fuel at one foot is greater than 100 R/hr. c. the shielded radiation form the fuel at three feet is greater than 100 R/hr. d. the. shielded radiation from the fuel at. cne foot is greater than 100 R/hr. L-7 Answer a. Re+erento Admi ni ntrati ve Req.ti renen te Ill, p me 14 i l l I l 1 l. 1 l i u -o

l l-L-8 (0.5) l I' MULTIPLE CHOICE - SELECT THE BEST ANSWER l l l' Where would you properly record ree.ctor power calibration data 1 taken during your watch on the TRIGA Mark F? 1 e a. Reacter Maintenance. Logbook b. H. P. Service Records c. Operating log d. None of the above i.. - 8 Answer c. (0.5)

Reference:

Operating Pr otedur ca, ).Vil--I l l .i

l L-9 ' (O. 5) - _ MULTIPLE' CHOICE - SELECT THE BEST AN5WER

Where.

would you properly reccrd

=ntinuous air monitor calibration-data taken during your watch on the TRIGA Mark F7

' Reactor Maintenance Logbcok a. b. H.'Pe Service-Records c. Operating icg d. None of the above L-9 Answer c, t O, ~; ) s e r:.r e n e... : ci n ty n octira r

t [ L-10 (0. 5)- NULTIPLE CHOICE - SELECT THE BEST ANSWER An' entry-must be made.in the Reactor Operaticns Logbook concerning a dummy element change in the ccre.- This entry shpuid - properly be made during your watch on the TRIGA Mark I by: a, an entry in red ink. b. a black ink entry underlined in' red. c. a black ink entry. ' d, a green ink entry. L-10 Answer b. (0,5)

Reference:

Operating Pvoteduren, 1 - /1 I i m _____1____z________________________.__.

. L-11 (0.5) MULTIPLE. CHOICE - SELECT'THE BEST ANSWER An entry must be made in the Reactor Operations Logbook concerning, a fuel' element change in the core. This entry sh,ould properly be made during your waten on the TRIGA Mark I by: a. an entry in red ink. b. a black ink entry underlined in red. c. a black ink entry.

d..

a gr een ink entry. L-11 Answer a. (0.5) Ref t:: rence: Operating Pr ecedur en, I-4 .l I J l i -___m____m.___.__

L-12 (0.5) ) 7 i t1ULTIPLE.CHOTCE - SELECT'THE BEST ANSWER An entry must be made in' the. Reactor Operations Logbook concerning control rod maintenance. This entry should properly be 1 -made.during your' watch on the TRIGA Mark.I by: 1 .a. an-ertry in red ink. .g 6.

a. black ink entry underli.ned in red.

{ I c. a black' ink entry. l d. a green ink entry. j L-12 Ans.wer d. (0,5)

Reference:

Oprerating Proteaureni 1-9 J '. a

.) ) 1 l L-13 (2.5). -1 1 An unplanned shutdown of the TRIGA Mark F has occured. ) (a) Who is responsible for obtaining acproval for returning to power f rom the ERO f ollowing an ) unplanned shutdown? ( O". 5 ) (b) Who is responsible f or informing TRIGA Facility management of any abnormal occurrences? (0.5) (c) Prior to granting permission to restart, what j two requirements are imposed en the SRO on duty? (1.0) '( d ) If the shutdown was caused by an unexplained SCRAM (no apparent cause), who must be notified? (0.5) 'L-13 nnswers (61) Th t? RO on t:lu t y (3.5) l (b) The EPO nn duty ( 0,, 5 ) (c) The 9F(O munt be oil-tu tta ( 0,, S ) and must leave revi ewed all the circumn unces et ttle uor)1 anned unutdown (0,5). (d) The Er3 ti c-n11ty Sat e(7uardt Commi. t tcers (0,5)

Reference:

raministrative Requirements IV, page 4 and Operat2.ng Pr oc edur e-1 --4 1.

L-14 (0. 5 )- MULTIPLE CHOICE - SELECT'THE BEST ANSWER Based-on the Technical Specifications, the maximum excess reactivity during transient.cperation of the Mark I TRIGA is:. a. $ 3. 25. b. $ 4.00 c. $ 5.50 d. $-7.50 L -14 Anwer a ( 0. D ) - References Mark i Technical c.p aci f i c at i on s p apr- '7

r. L-15 (0.5) MULTIPLE CHOICE - SELECT THE'BEST ANSWER Based on the Technical Specifications and no tr a.nsi ent red installed, the maximum e>: cess reactivity during steady state j operation of the Mark F TRIGA is: a. $'3.25 b. $ 4.00 l c. 2 5.50 d.

1. 7.50 L-15 nrstver f"I,

( O. 5) A Kt.'rence: !' e r l. Te 'aical t. fit ati nris :3ngo '? l i I

r . l.- 16 (0.5) MULTIPLE CHOICE - SELECT THE DEST ANSWER Based on the Technical Specifications and opc-retion above 100 Kw, the maximum ' reactivity f or all installed experiments in the. Mark I or the Mark F TRIGA is: 1.. a. $ 3.25 6. $ 4.00 l c. Z 5.50 d. $'7.50 L-15 anmer l E' b. t' O. 5 ). I l . Reference Mark F-Techna caI Gaeci1 ication; m rl,9 11, Har '.: - I page 8'. I 1 i i i l END OF EECTION L j END CF EXAMINATION I 1 1 I I ic i I 1 )}}