ML20213G982

Exam Rept 50-089/OL-86-02 on 861021 & 22.Exam Results:One Senior Reactor Operator Candidate Administered & Passed Oral & Written Exams & License Granted.Written Exam & Answer Key Encl

ML20213G982
Person / Time
Site:	General Atomics
Issue date:	10/30/1986
From:	Elin J, Morrill P, Pate R, Royack M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20213G981	List: ML20213G979 ML20213G982
References
50-089-OL-86-02, 50-89-OL-86-2, NUDOCS 8611180443
Download: ML20213G982 (54)

Text

.

U. S. NUCLEAR REGULATORY COMMISSION REGION V Examination Report No. 50-89/0L-86-02 ,

Facility: GA Technologies Inc. - Mark I and Mark F TRIGAs Docket Nos: 50-89 and 50-163 t

Examinations administered at the GA Technologies TRIGA Test Reactor Facilities, La Jolla, California.

Chief Examiner: (0/g/f6 Philip Morfill,OperatorLicensingExaminer Da'te Si'gned Examiner: s #!3e f(C-Date Signed

~

p ael J Royac peratorhensing Examiner Approved: .

M4 /d-Jo [G J ( O. Elih, Chief, Operations Section Date Signed k/ YW lO $

Da'te $igned Robert J. Pate, ghief, Reactor Safety Branch Summary:

Examinations on October 21 and 22, 1986.

Written and oral examinations were administered to one SRO candidate. The candidate passed the oral and. written examinations. One SRO license was granted.

8611180443 861103 PDR V

ADOCK 05000089 PDR

-o REPORT DETAILS

1. Examiners:

P. J. Morrill, NRC M. J. Royack, NRC (Observer)

2. Persons attending the exit meeting:

P. J. Morrill..NRC M. J. Royack, NRC J. Shoptaugh, GA Tech.

3. Written Examination and Facility Review Written examinations were administered as follows:

1 SRO Exam - October 21, 1986: 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 and resolved with the examiners.

Based on these discussions, appropriate revisions were made to the master examination key by the examiner prior to grading the candidate responses.

4. Operating Examinations: >

An oral examination and facility walkthrough was administered to the SRO candidate.

5. Exit Meeting:

On October 22, 1986, the examiners met with the licensee representative listed in paragraph 3, above. The examiners advised the licensee representative that no generic weakness was observed. The examiners also discussed the grading process for the written examination and the schedule.

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i U.S. NUCLEAR REGULATORY CDMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: GA TECHNOLOGIES INC.

Reactor Type: TRIGA MK I & MK F Date Administered: OCTOBER 21, 1986 Examiner: P. MORRILL Candidate:

INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Writer enswers 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 and a final grade of at least 70%. Examination papers will be picked up six (6) hours after the examination starts.

Category  % of Applicant's  % of Value Total Score Cat. Value Category 20 20 H. Reactor Theory 20 20 I. Radioactive Materials s

Handling Disposal and Hazards 20 20 J. Specific Operating Characteristics 20 20 K. Fuel Handling and Core Parameters 20 20 L. Administrative Procedures, Conditions and Limitations 100 100 Totals Final Grade  %

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

i Candidate's Signature

ES-201-2 ATTACHMENT 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS

1. A single room shall be provided for completing the written examina-tion. The location of this room and supporting restroom farilities shall be such 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. Ob-taining this room is the responsibility of the licensee.

2. Minimum spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one candidate per table, with a 3-ft space between tables. 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 candi-dates are to have lunch, coffee, or other refreshments. These arrangements shall 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 provide formal written comments with supporting documentation on

. the examination and answer key to the chief examiner or to the regional office section chief.

5. The licensee shall provide pads of 8-1/2 by 11 in. lined paper in unopened packages for each candidate's use in completing the exam-ination. 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 rules into the examination room, and no other equipment or reference material shall be allowed.

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

Examiner Standards 11 of 18

. ES-201-2 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

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

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

3. Use black ink or dark pencil only to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the examination.

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

6. Use only the paper provided for answers.

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

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

9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

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

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given. Therefore, AN5WER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

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

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

been completed. '

Examiner Standards 12 of 18

ES-201-2

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.

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

d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

i i

l Examiner Standards 13 of 18

EQUATION SHEET f = ma v = s/t w = mg 2 Cycle efficiency = N 11 k t) s = v,t + at E = mC' a = (vI - y )/t KE = my 2 v g=v A = AN A=Aeg -At g+ at PE = mgh m = 0/t A = In 2/tg = 0.693/tg W = vaP AE = 931Am tq(eff) = (t i )(t5)

(t +t) b Q=$ CAT p I.Ie -IX

= UIAT I.Ie -px Pwr = U f I' I=I 10"*

o P=P 10 SUR(t) TVL = 1.3/p P=P oe tN HVL = 0.693/u SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,ff) p SUR = 26

/Aeff )

g CR,= S/(1 - K,fgx)

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T = '(1*/p ) + {(f 'p)/Aef p]

T = 1*/ (p - h M " IIII ~ Keff) = CR /CR g 0

"( ~ P)! eff D

M = (1 - K ff)0 (I ~ eff)1 P " ( eff~l)/Keff " OKeff/Keff SDM = (1 - K,gg)/K,gg p= [1*/TK,'gf ] + [8/(1 + A,gfT )] 1* = 1 x 10~ seconds f ,

-1 P = I$V/(3 x 10 0) A,gg = 0.1 seconds I = No Idly =Id22 i WATER PARAMETERS Id g =Id 2 I gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters)

I gal. = 3.78 liters R/hr = 6 CE/d (feet) 3 I ft = 7.48 gal. MISCELLANEOUS CONVERSIONS .

3 10 Density = 62.4 lbm/ft 1 Curie = 3.7 x 10 dps Density = 1 gm/cm ,

1 kg = 2.21 lbm 3

Heat of varorization = 970 Etu/lbm I hp = 2.54 x 10 BTU /hr 6

Heat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 10 Btu /hr

, 1 Atm = 14.7 psi = 29.9 in. I'g. I Btu = 778 ft-lbf I ft. H O2

= 0.4335 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 C = 5/9 ( F - 32)

4 a

e i CATEGOPY H REACTOR THEDRY

, H-1 Question: (2.0) .

Regardi.g the neutron cour ce ( L ) f or the Ibr i F a n d M c., r- L. I lh}~'

reactors (a) Why is an instelled neutroti source r eeded to conduct a reactor startup '? (1.0)

(b) What type of neutron source is used f or the Mar k: I and the mark F TRIGA reactor (n) ? ( 1. Oi i

(hswers:

(a) The neutron source provides a sufficient number of neutennc t

-

l qive accurate instru~ient readings a.nd therby permit .cntr oll ed startups. (1.O) l i (1.0)

(b) Amer i c i um--b er y l l i um source

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Reference:

Instruction Manual for the Torrey Pines TRIGA Reactors, Chapter 1, j

j Page 14 i

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i H-2 Ouest ion: (2.O) -

l The terms FROMPT NEUTRDM n n ri FAST NCUTRON sound similiar a s. do the  !

term = DELAYED NEUTRON ar;d SLOW NEUTRON, yet are quirte different in  !

meaning. Explain'the differences, G .'.')

{l Ans.Jers: '

The PROMPT and DELAYED terms refer tc the time after the fission event that the neetorn' wcs relaeased. The FAST and SLOW refer to tne  ;

energy l evel (velocity or temperature) of the neutron. (2.0)

Reference:

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H-3 Ouention: (2.0)

The TRIGA r eactors utilize both REFLECTOR 5 end MODERATORS.

(a) What is the difference between a relector and a moderato- (;? . 0)

(b) What re-flector oateri al (s) are used in the Mark F TRIGA ir, the radial direction ? (0,5)

(c) What reflector material (s) are used in the Mark I TRIGA in the r adi al direction ? ( 0. 5 'i Answers:

(a) A moderator slows down or thermalizes fast neutrons. A reflector reflects neutrons back into the reactor core. (1.0)

(b) Water (0.5)

(c) Graphite (0.5)

Reference:

Instruction Manual for the Torrey Pines TRIGA Reactors, Che.pter 1,

-page 16 and Chapter VI, pages 6 - 7. Pages 5 - 11.

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H -- 4 Quest i on: (3.O) i d

A res.ctor. containing a neutron E cur t te is initially shutdow1 wi i n e count rate of 20 CPS on the count-rate channel. K(eff) has been ci e r -

mined to be'O. E (a) What k(eff)' in necessary to t recrease tne count rcte t '_., 'a '

l CPS (steady state) with the same source neutront. fl.e4 (b) How much reac t1 vi t y change (i n ,

c) would thic a requirt 5 i ( 1. '> >

i i (c) If enough reactivity was added to make the reactor just l

< critical at 200 CP5 and thte source installed, why will the count rato slowly increase ? (1.0)

Answers:

i (a) CR1(1 - Reff1) = CR2(1 - Ke4f2)

'. 2O(1 - O.95) = 80(1 - Kcf f 2) i s Kefi2 = 0.9875 '1.0)

(b) reactivity = (Keff - 1)/Keff j O.0125/O.9875 = 0.0127 1

O.05/O.95 = 0.0526 '

O.0526 - O.0127 = 0.03Y9 b c- 0.0073 so $ = p/b = 0.0399/O.0073 4 = 5.47 (1.0)

( (c) The increase in count rate is due to the increase in neutron t population caused by tne neutrons added by the source (and tne l multiplication of these neutrons). '(1.0) l r b

Reference:

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Instruction Manual for the Torrey Pines TRIGA Reactors, Chapte' %I, pages 9 - 17.

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F H-5 Questi on (3.O) 4 The TRIGA reactorc have been designed with a large prompt negative fuel temperature coefficient. List the three principle effects used j' to schieve t his and brie'] y e" plain hcw each of these decreasec reac-  !

. 1tivity when fuel te;mperature increases.

i I Annwers:

(a) Cel 1 and InSomcgenei t i es; incrc4aned fuel (c i r coni um hydri de'i teracerature increase the ef f ective neutron temper ature which all me.-

more leakage out of the fuel elemente z.nd conceauently increased parasitic capture in the cladding and water. (1.0)

(b) Doppler Effect; Incteased fuel temperature broadens the cc.pture i resonances in the U-238 present in the core thereby decreasing'the resonance escape probabil3ty. (1.0)

, (c) Core Leakage; Similiar to the cell effect. When the core heats i up, leakage of neutrons into the reflector is increased and more captures occur outside the fuel. (1.0) 1

Reference:

l Instruction Manual for the Torrey Pines TRIGA Reactors, Chapter VI, pages 2O_- 21.

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1 H-6 Question (2.0)

Based on the Fuchs-Nordheim n:odel , state how thc following pera-meters vary as a functicr of prompt excess reestivity inserted into a TRIGA reactor . (di rectly, inversely, not at all, as the sque e, or e::al ai n other) i (a) Peak Fower (O.51 (b) Energy Release (0.5)

(c) Reflector Temperature (0. 5 )

(d) Initial Reactor Period (0.b)

Answers:

(a) Varies as the square (0.57 (b) Varies linearly (0.5)

(c) Nat at all (0.5)

(d) Varies inversly (0.51 1

Reference:

Instruction Manual for the Torrey Pines TRIGA Reactors, Chapter VI, Pages 32 - 43.

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H-7 Question (2.O)

J Refer t o Fi gur e H-1 wr.i c h choe ar- i n ct en t ane'aur positive ree t: vi ,-

i n c.er t i on into an already critical reacto- core at time T = 0. A+ te a etebl e period ic reached on i r.s t a n tan ecus r rrm oval of this ". 0 ". I t i v :=-

reattivitv occurs at time T= 1. Mecpcna to the fol1twing quention3-assumi no source neutrons are not L i a. n i f i c an t (a) Sketch thee reactor power level as a function of t i rr e cn F i c;u e-H-1 for these reactivity changes. (i' !

(b) Sketch the resulting reactar period at a function of tire on Figure H-1 for these reactivity char. gen. si.0) i Annwers:

(a .L E' ) see attached drawing (1.0 each)

Reference:

Instruction Manual fer the Torrey Fines TR]EA Reactors, Chat.ter VI, paces 12 - 17.

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H-8 Questior, ( 1. O)

Estimate the shutdown mergin of a fully Icade- Mark I core uring the tallowing data, Rod Worths in $

Tr an si er.t 2.35 SM ety 2.05 Shim 1.87 Fegulating 1.79 Normal E:< cess reactivi ty 3. 0S Answer:

2.85 + 2.05 + 1.87 + 1.79 = 8.56 G.56 - 3.05 = 5.51 (1.0)

Reference:

Written Proceduren for Mark I 1 RIG 4, IV and V i

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H-9 Question ( 1. 0 l-l Pat h t he Mar t: F cnd the Marl: I ere culted Oom lou powe- Icvele

. ( l e s :, than 1 F.W) . State onc reason wh / celsing from high pcwer not allowed for ei thc- r eac t or ?

tin s wter :

This is duc ta t he fact that the 4 ut 1 temperatur e ucul d already b c-i high (270 - 400 C) and the pulse woul d add another ueveral hund-cd

, degreen to the fur) t emper ature. (Depa

• ure f rom nuclee.te boilirm (DNB) could be e:'cceded caucinq cladding burr-aut. Also it is

ponnitil e to e::ceed the phane change temperature for e mari: I f uy1 element.)

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j Refurence:

Instruct i on Manuel for the Torrey N nos TlilGA Reacters. Chapter bI, l page 30.

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f H- 10 Quer.ti on (2.0) i Significant ti ene dept >ndent reactivity effe:ts occur in reactert an a result of the isotopen xenen-135 and samarium-149..

(a) What are the tuo ways ::enen It remeved frem the reactor while it

• is operating 7 (1 0)

(b) How long after shutdown will it take to reach peak :enon (maximun negative reactivity) ? (0.5)

(c) While the reactor is operating how is samarium removed from the reactor ? (0.5)

Answers: i I

(a) By radioactive decay and buenout (1.0)

(b) 7 to 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (0.5)

(c) burnout (0.5)

Reference:

Instruction Planual for the Torrey Pines TRIEA Reactorn, Chapter VI, pages 23 - 28.

END OF SECTION H GO ON TO SECTION I t

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C AT EF_'R Y I PADIGACTIVE MATERl(i.5 HANDLING. DIEPO3A'_ AND HAZAhD3 I-1 Dues t i en (2.0)

When di ccut.si no rediati on exposure, one ofter, hcars the terar RAD and REM.

' ( 1. 0 :'

(a) What it the d2fference between these terms

( b 's How rr.any RE.Ms are associated with an exposure of 1 RAL c4 thermal neutrons Explain why are they different. (1.O' Answers:

(a) A RAD is a measure of absorbed dare in terms of energy ce;3 ce : t ed per CC. while REN is a measure of the biological darage caused cy the absorbed done. (1.O)

(b) 1 RAD of thermal neutron is about 10 REM. When absorbed, a thermal neutron does not cause much total ionization, but the ionization it doen cause is very intense locally, fhus, biological damage is very high in a small area. ( 1. 0 ~

Reference:

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l l I-2 Quest 2cr. (3.0) l I

j In occercance with 10 CFR 20 " Standards for protection Aqairst j Radiation" l

j (a) What three li mi t s, must be met to comply with Radi ati on Dosc i Sta.ndards for individuals in restricted areas per calandar qua-ter

l (1.0 4

! (b) What are the quarterly standards for r,i n or s (under 18) 5' l (1.U) 4 i

! (c) What are the weekly standards for members of the public ?

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Answers:

t j (a) Whol e body 1.25. ski n 7. 5, handsNeet 18. 75 Rea:/Ot r . (1. O!

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(b) 1/10 of the above limits (1.0) i i

j (c) 100 Mrem in seven consecutive days (1,0) i i

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Reference:

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! 10 CFR 20, 20.104, 20.101, 20.105

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In accordc.nce with 10 CFR 20 "5iancaron 1or pratettion Ag ai nr; t i

Radiation" I-

! (a) Wr,t c h ereas must be mart:ad " CAUTION, RfLIATICN AREA" ? (1.0)

(b) Which area-2 must bc marked "CHU f l God , HIGH R43I ATI 2N AF EA" ?  :

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(a) Areas accessable to personnel in which e major portion of tre body could receive radiation exceeding 5 Mrem in one hour or 100 j Mrem in five tonnecutive dayn. (1.O) i i

) (b) Areas accessable to personnel in which a major portion of the

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body coul d receivt radiation ex c eedi rig 100 Mr en i n one h cur . F i (1.0) j t

References, 10 CFH 20, 20,20?

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I-4 Ouestion (2.0)

Refer to Figure 1-1 which Shows c. typical icnication curve, p l at t. i nt the number of ion pairs collected per icnizing event versus voltcge appli ed to the nas fillt>d choTibe , Nac e cach of the indicatte r en ce (a) Reg i or' II 50 ;'

(b) hegion I11 (C . '

(c) Pegi on V K b)

(d) Region VI '0.L)

Aqswers:

(0.5 each)

(a) Ionization or saturation dubrcq1on (b) Proportional

! (c) Geiger - Mueller i

! (d) Continuous discharge l

Re e crence:

TRIGA Training Material s - Supplirnentary Meterial , Detector Fundamentals pages 4 - 5.

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i , i 0 V, V, V, V, V, Curve 1: Radiation event of lower specific loniza' tion.

Curve 2: Radiation event of higher specific ionization.

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I-S Ovention (3.0) l t

The Radiction Aren Monitarc (RA!1c ) arc used to sctisf y the rcartte Technical Sp eci f i cati onc which require a sy 1/2 = 1.7 inches (f ull credit for correct application of expoential attenuation) (1.0)

Reference:

Example Test 3, Duestions 11 and 12

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I-7 (2.0)

Which decay mode 1isted below ie clocent to thet of the 1isted

$ isotopes ? Enote: select 1,2,3, or 4 for (a) and 1,2,3, or 4 for

! (b)3 j (a) Ar gon-41 (1.0) l-(1) T(1/2) = 3.81 hr/ beta- decay /no gamma l (2) T(1/2) = 1.03 hr/ beta- decay /1-2 Mev gamma 1

(3) T(1/2) = 7. 35 Set / beta + dec ay/ 6--9 Mev gamma i

(4) T(1/2) = 21.7 Min / beta + decay /no gamma i (b) Nitrogen-16 (1.0) j (1) T(1/2) = 1.83 Hr/ alpha decay /no gemme 1

l (2) T(1/2) = 35.7 Sec/ beta- decay /1-2 Mev gamma i

i (3) T(1/2) = 7.35 Sec/ beta- decay /6-8 Mev gamma i

1 (4) T(1/2) = 21.7 Min / beta + decay /no gamma 1

i I

I

!- I-7 Answers (a) 2 (1.0) l (b) 3 (1.0) i Feference:

i l

Instruction Manual 4or Terry Pines TRIGA Reactors, Chapter 'J , page i 9 and 10. Chart of the Nuclidea i

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

f s

I-8 Question (1.5)

List the three (3) basic f actors which af f ect en i ndi vi dual ' E dra l in a radiati on area, i

Ant:wt rs :

(0.5 each) ,

(a) Ti nre.

(b) Distance. / ,

?

(c) Ehielding.

Reference:

CAF, Dasic Rad i a t i can Protection E

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1-9 Cuestico (1.5)

Pr ovi tir> the falJowinci informat10n about a)pha, beta, and gamna radiation:

(a) Arrarige in order of descending re'ative i onizing capabili tien, highest ionizing potential first. (1.0)

(b) For the same curie content, which of the three pones, the greatest hazard when taken internally? (0.5)

Answers:

(a) alpha, bete, gamma (1.0)

(b) alpha (0.5)

Reference:

Radiation Protection by Shapiro, pg 10 -- 41 END O' SECTION I GO ON TU EECTION J

i [

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t CATEDDRY J S'EC Iiric GPERATIN3 CH4R-%Citi"l15 i!CS -

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J -i Que st :. cn (? Ct

+

Rraardinn "puine" TR1E4 opPrat1Do:  ;

l  !

j. (a) List the Ind;. cations which are available to monitc- tt e 11 art I l j iuel t er.per atur e (2.O)

(b) What.is the ma:-:i mum rcac"ivi ty i nc e -ti or: ellowed durina a atise of the Mark 1 '> ( 1. t.O i (c) How is ptir.e peal. power sensed and where in peak power

! dicalaved f or .t he MarI: 1 ? () b) 4 l

Anwere: t (a) The 100 power recorder and the ( .! ) feel temper atur e trat er (c ) f (1 0)  ;

disp 1ay fuel temperatur e. i (b) $ '.00 .

(c) An ion chambec feuds an NVT circuit tnr ough t h re lincar pounc- r a mp l i f i. er through the n-v circuit. The lincar rcccrder dispicy.i the l ti rj ne l .

Reforence: ,

l Instruction Manual for the lorry Pinen TRIGe4 Rr.' o c t or n , Chapter II.  !

pages 10, 19 - 32. Techn i c(t1 Specificatiers 7.3 I i

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j 0 -2 L!t e t t l or (3.0) lhe Mark I rcmctor ie : r. tne "autenatic' r t se of c;p er at i on at 1 .'

watts Cc' sider ca:h of tne follcaine siteatitne one at a timc.

S t a t e- what linea- roccrder i nd: r at : a' the operator will set al 0  ::

+he centrol reds vili respond.

(a) Tr e regul atinn rod " d o.vr " twitch 1r aeprrwrrd. (1.

(b> The shim rec: "dovn" switch is depressed. (1.0/

(h) The r angr' Lwitch iE swi tched t t, a higher scal e, li c"; i r o T: 100 to 250 w) (1.0)

Answers:

(e) No chenge in indicated power. The regulating red ulli not move.

( 1. 0 )

(b) The power will ini tall y d2 crease anci then returr to 100 wettc.

The t=crvo artplitier wi)1 move thr- regulating rod out to con per ! ete for the thim rod moving in. ( 1. 0 )

(c) lhe linear recorder trace decreater from fell rcale to lerc t h e r.

half scale and the servo-amplifier withdraws the regulating rod.

( 1. 0 )

Reference:

Instructinr1 Manuel for the Torry Pi ries TRIGA Reactors, Cherter 'I.

pages 10 -19.

J-5 Duestion (2.0)

Annwer True er Falce for the f oll owing statements- (0 5 each)

(a) For the Mari: I reactor the maximum av.='latie r:xcess reactivity (cold with e:4. peri ment e , it any, in place rhell be $ $.00 dur ne transisnt operations. .

(b) For the Mark F r eactor during trantient oper at i ont . the un i r - .

reactivity worth of any trancient ccntrol red shell b e -i 'i . 5 0 .

(c) All fuel element" t4 h al l be Etored such that Ueff i ti lern than 0.9 under all conditions of moderaticn.

(d) 1he number and parition of operable contrcl reds, at least ene of which shall be a standard control rod, and their r es:3ect i ve worthe shall be cuch oc to t, hut down the reector by at least 25 cents at all times (10 cents for the fiark F with direct conve-sto, en rier i men t n ) , even.with the most reactive rod stuck cut.

Answerst (0.5 ench)

(a) False (b) True (c) Fa1co (d) Fal t e

Reference:

l Technical Specificatione, t1arl; I; 5.1.2, 6.1, end 7.2: end har L F; l 6.1.2. 7.1, Y.1.2, and 9.2.3.

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'J-4 C3.0)

The control red drive svetem uter thre illuminated puchbuttorc for the shim, safety, and regulatino rods.

During a training start-up, e tr ai ntee inadvertently presten the  !

" CONT /ON" switch of the shim roc af t er the rod has been fully (

withdradwn. What subsenuent i n di c at i or:s (l i ght color & on/off) do [

you expect to see for the "DOWN", "UP", and " CONT /ON" pushbuttcas  ;

and what does each of these indi cations vignif y.  ;

Answers ,

DOWN White, off, r od and rod drive not at lower limit (1.0) i UP Red, off, as soon as rod starts driving down (1.0)

CONT /ON Bl ue L yel l ow, "on" light on b " CONT" licht off, ( 1. 0) .,

magnet energized but rod not attached j

Reference:

Instruction Manual for the Torry Pines TRIGA Rcettors, Chopter II, [

pages.12 - 15. [

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J-5 Questi on (2.O)

State the purpoce of the core diffuror tyntems for the Mari: I nrd the Marl: F and explain how the systems wat-E (briefly) for each r e a c t c,r .

Answer:

The purpose ic to reduce radiation 1 evel s at the pcol surface (1.0,.

Port ci the Mari I pool cooling flow discharges harirontally abas c the core thrtugh a fi c.w f

defl ector b u:: . In t h te Ma-k F a separ e t e pur.:3 and diffuser cause a hcrizontal flow of water above the core. Both of there arrangements ellow for 14-16 to decay prior to reacning tm surface (1.0).

Reference:

Instruttion hanual for the Torry Pine; TRIGA Reactoru, Chapter 1, page 30 and Cnopter V, page 9.

1 i

l 5

1

J-6 Ouesti on (4.O)

For the control board devices listed below, complete the tabl e by indicating the associated SCRAM (s) and i nterl oci: (s) with concr21 s y =. t err s . Include set poi nt s if appr opri at e.

- (O.8 eat 1)

(a) Mark I start-up(count rate) channel (b) Mark IWide range log power channel (c) Mart I % power chennel (d) Mark F linear power channel (e) Mark F fuel temperature channel.

Answert:

(0.8 cach)

(a) Start-up (count rate) channel. Sour ce :nterlock preventu red withdrawl below 2x10-8 %.

(b) Wide range 1og power channel. Froviden interlock which prevents pulsing above 1 KW. Provides interlock te keep period longer t h a n '5 seconds when in automatic mode of control.

(c) Percent power channel. Provides a 110 % SCRAM (275 FW)

(d) Mark F linear power channel. Providen a 110 % ECRAM (1659 KW)

(e) Mark F fuel temperature channel. Provides en 800 C fuel temperature SCRAM.

Reference:

Inc truct i on Manuel for the Terry Pinn TRIGA heactorn, Ch ap t er II, pages 16, 18, 20, and 44

4 .

J-7 Cuention (1.5) _

i i-f tow would the fol1owing mi5takec or cituations affett the calculated power for a reactor pcwcr calibration (calorimetric) 7 (calcuiated power too high, too low, or no effect)

(a) Forced wrter cooling System not CCFpletely turned off (0.5) j (b) Tne digital th er'momet er han a constant error of 4 5C (0.5)

(c) Pool' depth Icwer than normal (C.5) a i Answers:

{ (0.5 each)

(a) Calculated power too 1ow (b) No effett t

(c) Calculated power too high i

l

Reference:

Mark F TRIGA written Procedures, VIII Power Calibratient i 4

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J-8 Question (1.5) - . .

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l Ansisr the following quentier.e true or f al se. , ' (0.5 ea$h) 5 v. J4 .

. The con,tinuous air tr.onitor high ale m. car,$intt of an amten , light '

'-(a) , ,.

1 and a bell. ~

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I (b) The klaxon '(evacuation alarm)' tan-he eauecd by on tw 5 R / D' al a': n ,

a 20 mr/hr alarm, or the criticality alarm setpoint e:<ceede.t. -

j 7

(t) The water radiation detector's for the h$rl; 1 and the Mar!. F reactors are located in water bo::es in each, reactors' water 'S 4 [

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treatment system.

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Answers:

(0. 5 eath ? ' - - . ,~

Y, b I (a) False -

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i (b) False ...

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j (c) Trw ,, ,,,

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Instruction Manualaf'or the Torry Pinen TRIGA Reat'to du, Chapter V,

! pagen 18 - 23., Mart,F Written Operatino Procedurai,, VI r 4., ,

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END OF SECTION J .

l GO ON TO GECTION M ,-

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CATEGOR'( K FUEL HANDLIN'E AND CO'RE PARAF ETER3 N-1 Que: tion (2.0) ,

Reactor ope-ations include fuel movement and work on t ne contr c :

rods. The Mark F and Mark I written procedurea require that certain personnel be present during fuel mo ve. me a t or work on the cor. tral rods.

(a) Which personnel (by title or position) must be present when fuel is being moved in the Mark F ? (1.0)

(b) Which personnel (by title or position) Mutst be present when control rod drives are being rep ai red in the Mark I or Mark F (no reactivity changes'are being made) ? (1.0)

Answer s:

(a) A senior reactor operater (to directly supervise), and a cactor operator (or a person desionated by the PIC) at the console shall bc present. (1.0)

~

(b) A senior reactor operator and one additional per son shall be present. (1.0)

Reference:

Written Procedures f or the TRIGA Mark I and Marl: F. I-2, X-1, and X1-1.

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K-2 Ovection (4.0)

< >, Techni cal ' Speci f icati ont 4.3 (Mark I) and 5.5 (Merk F) require at annual intpectied of fuel el ement s.

('[

(a) What three tects or inspectionn ere perfnrmed for uninntrumr-ntre fue! elements ? (1.5) l (b) What test or inspection is perf or med for instrumented fuel elements ? (1.0)

(c) What are the three criterie used to define " damaged" fuel per the Technical Specificaticrs ? (assume alumin'am clad) (1.5)

Antwerc:

(a) Visual for damage, overall length, and transverse bending.

, (1.5)

(b) Visual for damege. (1.0)

? t ,,

(c) Transverse bending greater thnq 1/16 inch, el ongati on gr eat er than 0.5 inch, or if a clad def oct (l eak ) e::i st s . (1.5)

\

Reference:

--)

j_ TRIGA Technical Specificatio,c 4.3 and 5.5.

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- .. . _ _ , = - _ .

. _ . - - . . _ , . . - . . .. . - - _ . - . =_

! K-3 Question (1.0)

A carnol e is to be irradate:1 with a high atio of thermal to 4ert neutronn. Which of the following irr adi ation f acilities should bc "

used. (Eclect one of the followino)

(a) The pneumatic transf er systern (Ma -k: I) <

i (b) The dry tube at the center of the ro-e (Mert I)

(c) The lazy-susen device (Mari: I)

\ l^

(d) The graphite t her rnal column (Mark F)

. Ancwer:

i

/,1. 0)

(d) i

Reference:

l Instruction Manual for Torrey Pines TRIGA Reactors, Chapter I, Mechanical Design and Components, pa;;es 36 - 43.

4 1

i 1

-- *-%-, -r.- ,7 _ . , , , _ _ . _ , , . _ _ _ _ _ _ _ _

?

K-4 Duertinr (3.O)

The Icoding required fer cri ti cali t y ie deter: .i r.ed by obser vi r:g t '.o multiplication of source neutrent s 's fuel is added to the carc. l Unnu t he data belcw antwer the 'ollow:nq quections. ,

i NUMBER Or ELEMENT 3 CCUNT RATE MU'_T1PLICAT TCiJ 40 4000 2.O ,

50 GOOO 4.0 (a) How many elements will be required for criticali ty ? :1.0)

(b) With the reactor subtriticel ar.d at a count rate cf 20000 CPM, how would count rate be af f ected (i ncr eace, decrease, or stay the same) if the neutron source were reccved. Brief ly expl air. your answer. ('. 0)

Answers:

(a) 9 to 12 additional elenente (1.0) 7 (b) It would dect.2ase becauce the neutron population is caused b,  ;

subcritical mul ti pl i cati on . Without the neutron source therc is nothing to multiply (count rate will decrease with a -80 Scc period). (2.O)

References  :

Instruction Manual for Torrey Pines TRIGA Reactors, Reactor Physics ,

and Kenitics. Chapter VI CAF .

L l,

I l

V-L Duention-(2.0)

Regardinc the structure of t h t' 1RI"iA reacter core:

(a) Wha.t precluder the possibility of 4.. control rod dropping out cI the core 9 il.e)

( ti ) How is the 6.:eight of the cor e (fuel elements) transmittet to the bottom of the pool in t he Nar k I ? '.1. O >

1 l . Answers:

i *

! (a) In the Mark F thimbles are installed on the grid plate. . 0) i In the Mark I the rod is larger than the grid plate holed.

t

< (b) The bottom grid plate suppcrts the core. The grid plate is welded to the reflector container support which rests on the pool b ot t ora . (1.0)

J I

j

Reference:

l Instruction Manual for "forrey Pines TRIGA Reactors, Chapter 1,

! Mechanical Design and Components, paqcc le & 20.

. . . . . _ . . = - - _ . .. =- . .- - - - . _ . . . . . . . . ~ - - . - - - - . . . . - _ . . . - . . - . . _ _ _ . .

r 1

l K-6 Question (1.0) j j The void coefficient of reactivity ior the Nar; F TRIGA in: '. s al ec t i one of the following)

! l l (a) About -1 :' 10-5 delte K/k/ 1 % '

i j (b) About -1 .

10-4 delta K/K/ 1 %

i (c)

~

About +1 :< 10-D delta K/K/ 1 */. i r

(d) About +1 :: 10-4 delta K/K/ 17.

1-i Answer:

(b) (1.0) r

Reference:

Instruction Manual for To rey Pinen TRIGA Reactors, Chapter VI, 4 Reactor Physics and Kenitics, page B-2 l

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-..-.,,.,,-,---_,,a. . - . , , - , - _ - -nn..,,.--,. , - - , , . - - . - - .

y__.._. __ _ _ _ _ _ _ _ . - _ . ___ _____._ _. . _ _ _ _ _ . _ _ _ _ _ . - . . __ . _ _ _ -_ _ _ _ . _ _

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K--7 Quest i on (1.0)

What is the purpose of the graphite sluqc at each end of the eur eler,ents ?

I l

An svaer : .

The graphi te it a r elector ( v:hi c h leve3n f l u:: and increaser reactivityi. (1.0) 4 j

Reference:

Instruction Manual for Torrey Pinen TRIGA Reactors, Chapter I, j Mechanic 91 Design and Components, page 11; Che,pter VI, Reactor Physics and Kenitics, page 7 i

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K-8 Question (3.0)

The Meri: F TRIGA usen stainless eteel clad " FLIP" fuel which contains crbium.

(a) What are two effects of (or purpate of) adding erbium to tnc FLIP fuel ? (P.O' (b) Is the Fuch-Nordhei m model valid for FLIP fuel 7 (1.0)

Answers:

(a) Adding erbium (burnable poicon) allows more urani um and a longcr

.burnino core. (1.0) The addition of erbium causes the negative temperature coefficient to increase with tempe-ature, thus acting as additional shutdown margin. (1.0)

(b) No. (1.0)

Reference:

' Instruction Manual for Torrey Pi nec TRIGA React ors. Chapter V;,

Reactor Physics and Kenitics, page 55 and 60.

f I

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r L. --9 Pu e r, t i e n (2.O)

Regardir g sample containers and experiments i rr adi ated in the .o e:

(c) Wnct is the advantage of using plestic sample containers ?

(1.0)

(b) When must aluminum sampl e contai nces be used 9 (1.0)

Answers:

I (a) The plastic container is not eccily activi ated by neutront.

(1.0)

(b) Aluminum containers must be used when fissionable materials are i rradi at ed. (1.0)

Reference:

Instruction Manual for Torrey Pinen TRIGA Reattors, Chapter V, Radiological Safety, pace 6.

,. . .. _ _ _ . . . _ . . _ . . _ _ ._- ___- . _ _ - - _ _ - . _ _ - _ _ . _ ____._m . . . _ . _ _ .

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K-10 Duwestion (1.0) ,

Regarding Mart' F core rear.tivity limitations ~ contained in the

, Technical-Specifications for all experinento (except low power F reactivit y worth experiments):

(a) What is the manimum total inccre reactivity of an individual experiment

(0.5)

! (b) What in the minimum cold xenen frce shut-down margin'with a1y

single centrol rod fully wi thdr awre ? (0.5) i i

Answers:

(a) $ 3.00 (0.5)

(b) $ 4.00 (0.5) 4 l

Reference:

Mark F Technical Epecification 10.2 i

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I l END OF SECTION K GO ON TO SECTION L i

_.---,m. - , , _ . _ _ . . . __ - - - - - -

l 3

i CATEECRY L ADMINI5TRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS l J

6 L-1 Question (3.0)

There are three classes of experiments perforced with the 1crry-  !

Pines TRIGA reactor s. List and describe the three' classes of experiments, including how each is approved before it is performed. i Answer:

(a) Routine experiments are those which are performed under conditions that have been previously examined and are authcrized by the Technical. Specification. The Physicist-in-Charge or his designated alternate can approve these experiments. (1.0)

(

(b) Modified routine exper2ments are those which have not been i' previously performed, but are similiar in nature to' experiments which have been performed, where the associated hazzards are not.

significantly different or greater, and the Technical Sp eci f i catt or,s -

are met. The Physicint-in-Charge may operove these experinents. ( 1. '_ ;

(c) Special experiments are any experiments which are not one of the above. They must be approved by the Physicist-in-Charge, Hecith

- Physics, the Criticality Safeguards Committee, and Licensing Administration. (1.0)

Reference:

l '

Instr ucti on flanual for Torrey Pines TRIGA Reactors, Chapter III.

Administrative Procedures, pages 2- 5.

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L-2 Ouestion (4.0)

The Technical Speci f i cati one require that a C'iticality Safegterte Committee (CSC) be established to revi er: 1RIGA operations.

(a) What is the minimum sice and composition of the CSC ? (1,0)

(b) How are members at the CSC selected ? (1.0)

(c) What ar e f our of the si:' items required to be cover ed in the CEC charter ? (2.07 Answers:

(a) The CSC shall be not less than four persons who are not directly involved with TRIGA reactor operations. The commi ttee shall collectively posess expertise in all creas of reactor cpe ati o s and reactor safety. ' 1. C )

(b) The CSC members e-e selected by the Vica Fresident, Power Reactor Programs. (1.0)

(c) (0.5 each fo- any four of the f ollowing) meeting frecuency voting rules quorums i . methods of submicslon and c ontent of reports use of subcommittees l review, approval, cnd disseminati on of ninutet i

l

Reference:

Instruction Manual for Torrey Pines TRIEA Peacters, Chtpter Ill, Administrative Procedures, page 7, and Techbnical Specificationu 9.2 (Marl I) and 8.2 (Ma-k F)

O 1

= 1 L-3 Ducoticn f. 4 . 0 )

~ne ti~ a n 'St tul DDWN" and "FECTRE D ' a,e v .e ~y r2a11:ar, but :-

ouito different in the I R 100. ce.hqic+1 fic E c ; + i t.c t : o n s .

(ai Wi c n in a ^!RIGO cc c t c,: 'iHi l f r4 NN '

(: , ,

(b) W> C_ th'ce conc' tic,' rest be cet fcr a Tr:1 ~.: A r eact cr to t-i.EttR .D (_. ')

(i n '. Wf ~ !! !

( 4- ) Wher- t'ie r eac t c r i ts subcriticel by at leart one dollar of reacti vit /. (1.0)

(b) (1.0 eath)

'he reactor ic Enutdown.

C'0wer to the contrcl rod megnett and actuating solenoidt h c t.  ;

been switched off and the Iey removed.

No work is in progress i nvol vi nqi in cor e fuel hanciang or refuelinc cperations, reactt- cr reactor contral mcintenance, or insertion or withdrawl of experiments -f r om the ttr e.

Reference:

Techni c al Epecifications 1.1 4nd 1.2

i L-4 Question (2.0)

Sor e Rentter Oper at ionc Logt:toF entrict ar e in red and other r nr <.

underlined in red.

( is ) . What tntries are c.ede in red 9 (..Oi (b) What entries are underlined in red ? (1.07 Aricuer E:

(a) Any entri en pt-rtai nir g to fuel changer,-are in red, ti.0,

- (b) Any core changes other than fuel changes are underlined in rod.

(1,0)

Ref errence:

Written Procedures for the Mar k I and (1ar k F- onge 1 -/t , Par ag. aph 7 I

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L-5 Question (2.0)

WP,at are the ~r R I rs A facility procedaral etelfin; requirerr. ente r*cr b o t ', reactors are operating; 9 Answer:

One licensed reactor operator at each reactor and cr e t er icr r e nc t t. r operator readily available on call. (2.0)

Rcference: /

I Written Procedures for the Mark I and the Mark F, Procedural and Adninistrative Limitations, page 1 I

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L-6 Lt ect 2 nn 12.0-F t,r c;r cu p = ci s: c 1 '. o r t c f- v:>r a cun eges (16 - 2 0) visiting the -~ d G A

+ cility, w h ., t do?: meters crc c quirca to be i ssu ced "? ( 2. '. )

wwnn< :

One dori r:ete- fu- each p er t.an under the age of 18. ene et least cne doelmeter for every five vi si tors in a l arge group. (2.0)

Reference:

Instruction Manua) for the Torrey Pinec TRIGA Reactors, Chapter III.

Administrat.ive Procedures 5, pages 12 - 13.

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'o e.

t L-7 Question (3.0)

Ycu are in charge while the PIL 1.s hect:ng fo oian dignitariec--

off-site. While both reacters arc operating an e"periment ruptures.

The air monitors al arm as do the cont: nuout; area monitors. Eurvcv instruments indicate a4 to 8 R/hr fie!d ir the facility. Whci. c >-

your immediate actions and directions to the r eactor operaturt:

Answer:

Direct the operators to SCRAM the reactors, ehttdown the ventilation systems, scund the evacuation alarm (if it hasn't sounded), and proceed to Guerd Station ttT to make emergency notifications (Main Security Office, PIC, APIC, etc.) (3 0)

Reference:

Written Procedures, Emergency Procedures for the Laboratory, Pagt VII-4 i

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i END GP SECTION L END GF EXAMINATION

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