ML20234E208

Exam Rept 50-089/OL-87-01 on 870519-20.Exam Results:All Reactor Operator Candidates Passed Oral & Written Exams. Written Exam & Answer Key Encl

ML20234E208
Person / Time
Site:	General Atomics
Issue date:	06/11/1987
From:	Elin J, Meadows T, Morrill P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20234E165	List: ML20234E163 ML20234E208
References
50-089-OL-87-01, 50-89-OL-87-1, NUDOCS 8707070495
Download: ML20234E208 (84)

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{{#Wiki_filter:, i U. S. NUCLEAR REGULATORY COMMISSION REGION V ] Examination Report No. 50-89/0L-87-01 Facility: GA Technologies Inc. - Mark I and Mark F TRIGAs j Docket Nos.: 50-89 and 50-163 Examinations administered at the GA Technologies TRIGA Test Reactor Facilities, La Jolla, California. j l x::cc y n.~d-f ~- j Chief Examiner: /'- s ~' d' '2 ' e-"-#7 l Phillip J. Morrill, Operator Licensing Examiner Date Signed l Examiner: [ W + A M s. /$ w e-u-/' Thomas Meadows, Operator Licensing Examiner Date Signed Approved: h/ C.-h-97 John 0 7tlin, Chief, Op3 rations Section Date Signed Y I Summary: l l Examinations on May 19 and 20, 1987. { 'l Written and oral examinations were administered to two R0 candidates. All candidates passed the oral and written examinations. R0 licenses were l granted. l l l B707070495 870618 l hDR ADOCK 05000089 l PDR w_----____-______-_______-______.

E 4 l k I REPORT DETAILS j 1. Examiners:

• P. Morrill, hRC T. Meadows, NRC (Grader) l l
• Chief Examiner

) 1 2. Persons attending the exit meetino. i P. Morrill, NRC W. Whittemore, GA Technologies j J. Razvi, GA Technologies j 3. Written Examination and Facility Review i i Written examinations were administered as follows: 2 R0 Exams - May 19, 1987. All sections. At the conclusion of the examination, the facility staff reviewed the j 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 Examiner prior to grading the candidate j responses. The examiner's resolution of the licensee's comments are documented in Attachment 1. 4. Operating Examinations: Oral examinations and facility walkthroughs were administered to the two R0 candidates on May 20, 1987. 5. Exit Meetino: On May 21, 1987, the Chief Examiner met with the licensee representatives listed in paragraph 2 above. The Chief Examiner observed that the only generic weakness appeared to be difficulty in identifying how the Mark F console could be completely de-engergized. The Chief Examiner also discussed the grading process for the written examination and the schedule. l

1 l l l ATTACHMENT 1 RESOLUTION OF FACILITY COMMENTS ON GULF TECHNOLOGIES INC. WRITTEN EXAMINATION MAY 19, 1987 ) QUESTION A.04(b) COMMENT: This type of transient behavior is not applicable to a TRIGA reactor. The effects of a large prompt negative temperature coefficient are ignored and there can be confusion regarding rod drop time and SCRAM delay time. j l RESOLUTION: Comment accepted, however, the question and its' assumptions are clear. No c.mge will be made to the key. QUESTION A.07(b) COMMENT: 40 to 50 hou S for equilibrium xenon should be changed to 50 to 60 hours to be consistent with the reference material, fESOLUTION: Comment accepted. Key changed to read "50 to 60 hours". QUESTION A.08(c) COMMENT: The postulates of the question completely ignore the principles of TRIGA l reactor operation. The negative void coe1ficient and large prompt negative temperature coefficient make the sequence of events described impossible. l The reactor will shutdown after an excursion to 1000% power and 100% power can only be re-established from a shutdown condition. Thus normal cooling will prevail and coolant-clad delta 1 will be 20 to 30 C not 500 to 1000 C. RESOLUTION: Although TRIGA performance is different from the postulates of the question, the question clearly states the situation and what is being asked. Therefore the key will not be changed. In the event the candidate answers part (c) with 20 to 30 C and justifies this answer consistent with the comment partial credit will be given.

p 1 6 t QUESTION B.05 General j l COMMENT: I The rotary specimen rack is an "out of core" irradiation facility. RESOLUTION: Comment accepted. No change to the key. 1 l l QUESTION B.05(b) and(c) COMMENTS: The Mechanical Maintenance Manual is not applicable at GA Technologies and is not part of our reference material. No leakage into the GA Technologies Lazy Susans has been observed in thirty years of operation. There are no holes in the bottom of the tubes in the Lazy Susan. We would detect moisture by,looking for wetness on the sample holders as they are removed. Water can also be pumped out by use of a small pipe and tubing. RESOLUTION I Based on examination of the Lazy Susan and. construction drawings 28-010R0100 and 28-310R0100 comment accepted. The key will be appropriately modified. i QUESTION B.06 ) COMMENT: The reference material states that one of the functions of the water treatment system is to reduce radioactivity in the water. Tne key's answer explains how it does this. RESOLUTION: Comment accepted. The key will be changed so that part (2) reads " Reduce radioactivity in the water (by removing radioactive particulate and radioactive ions)". Each of the three numbered answers will be worth 0.66 points. QUESTION B.07 COMMENT: Mercury and copper are handled with special care because they are highly corrosive. Although they are not easily removable this is not the real problem. The key is not consistent with the reference material. RESOLUTION: Comment accepted. The key will be changed to read " Mercury and copper are highly corrosive. (The water treatment system will not remove these effectively.)" \\ J

QUESTION C.01(a) COMMENT: Pu-240 has a minor effect and is not discussed in the reference material. U-238 is the major contributor. 1 RESOLUTION: Comment accepted. The words "and Pu-240" will be placed in parentheses. 1 QUESTION C.01(c) l COMMENT: J The last section of the keys' answer omits the effect of the steel cladding. The reference material describes the Dyson effect (cell effect) in more detail on page 21 of Chapter 6. 1 RESOLUTION: ) I Comment accepted. The words "and the steel cladding" in parentheses will be l inserted after the words " surrounding water". 4 QUESTION C.04 (General) I COMMENTS: The wording of choice (C) should be "Become subcritical due to void formation....". The Mechanical Maintenance Manual is not applicable in the GA Technologies reactors. RESOLUTION: Comment accepted. No changes appear appropriate to the key. QUESTION C.05 PARTS (b) AND (c) COMMENTS: The Mechanical Maintenance Manual is not applicable to the GA Technologies reactors. Pages I-19, 21, and 31 of the GA Technologies reference material should be used. Therefore, the answer to part (b) should read " Convection (natural circulation, reduced density of hotter water)" and the answer to part (c) should read density of hotter water)" and the answer to part (c) should read " Cooling water flows down the outside of the reactor, under the core and up through holes drilled in the lower grid plate." j RESOLUTION: Comment accepted based on GA Technologies reference material. The key will be modified as described above.

f i QUESTION D.02 COMMENTS: The answers to parts-(a) and (b) are not completely accurate in that the pull rod is attached to a fixture which engages the rod down switch and the push 4 rod provides a magnet full up indication (the rod may not be latched). RESOLUTION: l Comments accepted based on Figure I-18 on page I-28 of the GA Technologies reference material. The key will be appropriately changed. ] QUESTION D.03(b) COMMENT: The Mark I does not have an antimony-beryllium source. See page 16 of I Chapter 1 of the reference material. RESOLUTION: Comment accepted. Antimony-beryllium will be deleted from the part (b) answer. QUESTION D.05 COMMENT! The linear power channel of the Mark I does not have any associated SCRAMS and is a fission chamber. This is described in the reference material. RESOLUTION: Comment accepted. Part (a) will be revised to read " Fission chamber" and part (b) to read "None". QUESTION E.01 COMMENT: The fuel temperature SCRAM setpoint for the Mark F is set at 650 C. The reference material states 800 C to be consistent with Technical Specifications. RESOLUTION: The examiner verified tht.t the setpoint is actually 650 C. The comment is accepted. The key will be changed to read "The actual setpoint is 650 C (however 800 F is correct for the reference material)."

l QUESTION E.04 1 COMMENT: The reference should be " SOP, TRIGA MK I, Section 8 and Technical Specifications". l i RESOLUTION: i Comment accepted. Reference will be clarified. l QUESTION G.06 COMMENT The reference material is in error and will be revised. Both instruments have a range of 0 to 10 R/Hr. One alarms at 5 R/Hr. and the other alarms at 20 Mr/Hr. The Rack unit with four indicators is in the Radiation Auxiliary Panel of the Mark I reactor room. The remote indicators are in the respective reactor control rooms. i RESOLUTION: The examiner verified that the facility comments were correct. Comments accepted. The key will be appropriately changed. ) 1

'N ntef(if,a y,%.m iczy ES-204-2 i U.S. NUCLEAR REGULATORY COMMISSION-l REACTOR OPERATOR LICENSE EXAMINATION Facility:. G ut.F: Atomic _ Reactor Type: TTilt C /4 Date Administered: rfA Y ICf l98'7 Examiner: ~IEN E Lid Candidate:- INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Write answers on one side only. Staple question. sheet on. top of the answer sheets. Points for each question are indi-cated in parentheses after the question..The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts. Category % of Candidate's % of Value Total Score Cat. Value 16 16 A. Principles of Reactor Operation \\ 15.5 15.5 B. Features of Facility Design 15.5 15.5 C. General Operating Characteristics 15 15 D. Instruments and Controls 12 12 E. Safety and Emergency Systems j 12 12 F. Standard and Emergency Operating -r Procedures ~ 14 14 G. Radiation Control and Safety .] 100 1 Final Grade All work done on this exam is my own. I have neither given nor received aid. . Candidate's Signature i -1 Examiner Standards 6 of 6

i e' GULF ATOMIC RO EXAM i SECTION A KEY A.01 REACTOR PERIOD 1.25 A.02 Keff 1.50 A.03. SOURCE CRITICAL O.50 A.04 POWER CXCURSION 2.50 A.05 DELAYED NEUTRONS 1.75 A.Oh REACTIVITY TRANSIENT 2.50 A.07 XENON TRANSIENT 3.00 I A.08 DNB 3.00 I i 16.00 GRADE'SECTION A ( SECTION B 1 B.01 CORE LAYOUT 2.50 B.02 REFLECTOR '2.50 B.03 FUEL MARK F 2.00 B.04 FUEL MARK 1 1.00 j B.05 LAZY SUSAN 2.00 B.06 WATER TREATMENT 2.00 B.07 MERCURY / COPPER 1.00 i B.08 POOL WATER PARAMETERS 1.00 B.09 WATER TREAT PARAMETER 1.50 15.50 GRADE SECTION B SECTION C C.01 FTC EFFECTS 3.00 i C.02 FTC VALUES 1.00 C 03 FTC DIFFERENCES 1.50 C.04 VOID COEFFICIENT 1.00 1 C.05 CORE COOLING 3.00 C.06 ROD WORTH 2.00 1 C.07 POOL REQUIREMENTS 2.50 C.OB RESPONSE DIFFERENCES 1.50 15.50 GilADE SECTION C ) e w-___.____-.--_---_-___-__--_-----_-__-._----__.

SECTION D D.01 ROD DRIVE COMPONENT 2.50 D.02 ROD DRIVE FUNCTION 2.50 D.03 NEUTRON SOURCE 2.00 1D.04 LOG POWER 1.50 l D.05 LINEAR POWER 1.00 l D.06 DETECTORS 1.50 D.07 FISSION CHAMBER 1.50 D.08 ION CHAMBER 1.50 D.09 GAS DETECTOR CURVE 1.00 15.00 GRADE SECTION D SECTION E E.01 MARK F TRIPS 1.50 E.02 AUTO CONTROL 2.25 E.03 MARK 1 TRIPS 0.75 E.04 HEAT BAL. 2.50 E.05 ROD DROP O.50 E.06 ROD CONTROL 2.00 E.07 PULSE REQ 2.50 12.00 GRADE SECTION E SECTION F F.01 SCRAM INDICATIONS 2.00 F.02 ATWS ACTIONS 2.00 F.03 IN CORE EXP 1.00 F.04 EARTHOUAKE SCRAM 1.50 F.05 ACCESS 2.00 F.06 FUEL LOAD 2.00 F.07 FIRE PROCEDURES 1.50 12.00 GRADE SECTION F i SECTION G G.01 BETA / GAMMA meter 2.25 G.02 Wholebody Limits 1.00 G.03 ALPHA meter 1.50 G.04 Neutron meter 1.25 G.05 Time /Dist/ Shield 1.00 G.06 Area monitor 2.00 G. 07 Area Postings / survey 2.50 G.00 Rad Safety Rules 2.50 14.00 GRADE SECTION G-v"

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i REQUIREMENTS FDR ADMINISTRATION OF WRITTEN EX/MINATIONS T7[ 1. A single room shall be provided for completing the written examina-

Y tion. The location of this room and supporting restroom facilities Y

shall be such as to prevent contact with all other facility anG/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. 0b-g&c;..- taining this room is the responsibility of the licensee. ss. n Min'imum spacing is required to ensure examination integrity as ) E' ' ' 2. determined by the chief examiner. Minimum spacing should be one e l candidate per table, with a 3-ft space between tables. No wall . charts, models, and/or other training materials shall be present in r 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 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate t:as 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 8-3/2 by 'l in. Ifned paper in l 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 calculators, or slide rules into the examination room,, pencils, f' 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

M e-f:.. i NRC RULES AND GUIDELI.NES FOR LICENSE EXAMINATIONS l +- 3, i During the administration of this' examination the following rules ~ apply:l q .l C-1. Cheating on the. examination means an automatic denial of your' application' and could result in more severe penalties. 2. t:4: Restroom trips are to be limited and only one candidate at a time may leave.

4 You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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"#~ 3. Use black ink or dark pencil only to facilitate legible reproductions. j

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I'N - 4. Print'your name in the blank provided on the cover sheet of the 4 Q,4 examination. [, 5. Fill in the date on the cover sheet of the examination (if necessary). I h '6. Use only the paper provided for answers. r 4 F 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. p. i,; 8. Consecutively number each answer sheet, write "End-of Category _ " as appropriate, start each category on a new page, write.only one side of-the paper, and write "Last P,nge" on the last answer sheet. 1 9. Number each answer as to category and' number, for example,1.4, 6.3. 4

10. Skip at least three lines between each answer.

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11. Separate answer sheets from pad and place finished answer sheets faca g,,

down on your desk or table. n.

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

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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.

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

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

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

17. Youmustsignthestatementonthecoversheetthatindicatesthitthe work is your own and you have not received or been given assiktance in completing the examination. This must be done after the examination has been completed.

Examiner Standards 4

1 l 18.- When you complete your examination, you shall: a. Assemble your examination as follows: .s (1) Exam questions on top. ~ (2) Exam aids - figures, tables, etc. i

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(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 ...c,.. the examination questions. cjb. c. Turn in all scrap paper and the balance of the paper that you did gf:3F not use for answering the questions. e:s. 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 progr,ess, your license may be denied or revoked. 4 l 1 Examiner Standards A

EQUATION SHEET f = ma v = s/t l 2 Cycle efficiency = N 1ork ti v = eg s=v: + at E = mC a = (vI - y )/t 2 KE = hmv A = A,e-At f = v, + at A = AN v PE = mgh to = 0/t A = In 2/tg = 0.693/tg W = vaP q(cff) = (t, )(t ) AE = 9314m t t (g 4g) Q = $C AT -IX P I.Ie Q = UAAT o I.Ie-VX 4 l Per = W In -X/M I II lo SUR(t) O P=P 10 TyL = 1,3/p e /T t P=P HVL ='0.693/u i o SUR = 26.06/T f T = 1.44 DT SCR = S/!1 - K,ff) /Aeff ) p SUR = 26 CR, = S/(1 - K,ff ) T = '(1*/o ) + [(s ' p)/A,g ] 0 ~leff)2. 1 en 1 " 2 o T = 1*/ (p - D M " 1/Cl - Eeff) = CR /CR y 0 ~E eff M = (1 - K,g)0fIl - Eeff)1 D" -1) eff " OEeff eff eff IE SDM = (1 - K,ff)/K,ff [1*/TK,ff ] + [E/(1 + A,g )] g* = 1 x 10 seconds p= T P = I4V/(3 x 1010) A,ff = 0.1 seconds I = No a I Idgy=Id22 I WATER PARAMETERS Id =10 y 22 ,1 gal. = 8.345 lbm 2 R/hr = (0.5 CE)/d (meters) I gal. = 3.78 liters 3 R/hr = 6 CE/d (feet) 1 ft = 7.48 gal. i MISCELLANEOUS CONVERSIONS Density = 62.4 lbm/ft3 1 Curic = 3.7 x 1010dps k Density = 1 gm/cm i kg = 2.21 lbm Heat of vaporization = 970 Itu/lbm I hp = 2.54 x 103 BIU/hr Heat of fusicn = 144 Btu /11;m 1 Hw = 3.41 x 100 Btu /hr 1 Atm = 14. 7 psi = 29.9 it.. Ig. I Btu = 778 f t-lbf I ft. H O = 0,4335 lbf/in 2 1 inch = 2.54 cm P = 9/5 C + 32 "C = 5/9 ( F - 32) ) o

1 1 1 1 l J A.01 (1.25) 1 1 A reactor is at a very low power level and increasing i n power with a Reactor Period of 25 seconds. How much time would be required'for the power level to i ncrease by a factor of 1000 (3 decades) 7 ANSWER d i T = 25 sec. t/T t/25 P/Po = 1000 = e = e (0.75)' In 1000 = t/25 t = 25 In 1000 t =~172 seconds (2.87 min.) (0.5)- or SUR u 26.06/25 = 1.04 dpm .( 0. 7 5 ) time for 3 decades = 3/1.04 = 2.88 min. (0.5) REFERENCE Chapter VI, pages 9 - 15 Equation sheet ] 1 1 i I I 1 4 _____m____ J

e' A.02 (1.5) A reactor is subcritical with a Keff of 0.95. Due to the addition ) of. a reactor e>tperi ment, the indicated count rate han increased from 10 cps to 20 cps. What is the new Keff of the reactor ? ANSWER new Keff: CR1/CR2 n (1 - Keff 2) / (1 - Keff 1) (0.75) 10 / 20 = (1 - Keff 2) / (1 - 0.95) (0.5) ( 0. :5 ) >( (0.05) (1 - Keff 2) = Keff 2= 1 - (0. 5) (0. 05) 0.975 (0.25) = REFERENCE Chapter VI, pages 9 - 15 Equation sheet 2

1 I A.03 (0,5) SELECT THE BEST ANSWER A reactor is SOURCE CRITICAL. . Wi th no. reactivi ty changes it will; a. Maintain the.SAME power level over a long period of time. b. Slowly INCREASE in power l evel due to the ' moderatior, of prompt neutrons. i c. Slowly DECREASE in power level due to the decay of delayed -1 neutron precursors. 'l d. Slow 1v INCREASE in power. level due to the addition of source neutrons. 1 ANSWER (A) J REFERENCE i .J CHAPTER'VI page 17 I 1 i lq ) I i l I a ___________m.____.________ _______i____.-_.m____i_________ .__l,_.

D A.04 (2.5) The MARK 1 reactor is operatlng at 250 kw (full power) and the reactor power l evel trip is incorrectly set for 125% full power. A reacitivity excursion creates an approximate stable reactor period of '200 milliseconds. The reactor trips with a rod drop ~ (scram delay) time of 0.5 seconds. (assume no temperature or-void effects; and that power peaks and turns after a complete rod drop) a. At what power level will the reactor trip (0,5) with this incorrect trip setpoint ? b. What peak power will be' reached ? (2.0) i 1 ANSWER a. 250 kw x 1.25 = 312.5 kw (0.5) 6. T = 200 x 10(-3) sec = 0.2 sec P(final) = P(initial) x e(t/T) (0.5) ) P ( f i.n al ) 312.5 kw x e(.5/.2)- (1.0) = P(final) 312.5 kw x e (2.5) { = 312.5 kw x 12.19 = P (f i nal ) 3807 kw (0.5) = REFERENCES EQUATION SHEET TECHNICAL SPECIFICATION MARK 1 CHAPTER 2 pages 2-44 4 i e l

.\\ l A.05 (1.75) Following a scram there is an initial prompt drop in power level f ollowed by a power decrease and a negative period, a. What is the magnitude (value) of this negative (0.75) j period ? b. Why.is it always the same ? (1.0) i ANSWER' a. ~80 seconds, b.. Power cannot decrease faster than mean life time of. longest lived precursor. (Thi s i s 1. 44 ' x 55 sec.1/2 life of Br) REFERENCE Chapter VI page 14 l 1 l 1 l ) i l l i i l 5 ,~ h

A.06 (2.5) Refer to FIGURE A-1 which shows as. instantaneous,

positive, reactivity insertion into an already critical reactor (at t 0),

= followed by a removal of this positive reactivity af ter a stable reactor period is reached (at time t = 1), thus making the reactor just critical again. Assuming no source neutrons: (a) Show the resulting REACTOR PERIOD as a. (1.0) function of ti me for these reactivity changes. (b) Show the resulting REACTOR. POWER RESPONSE as (1.0) a function of time for these reacti vi ty i changes. (c) What accounts for the shape of the reactor' (0.5) power response or reactor period response during the time IMMEDIATELY AFTER t = 0 7 ANSWER (a) AND (b) ATTACHED l (c) " Prompt Jump" or "Trainsent Period" due to the increase in prompt neutron production with the increased reacitvity. REFERENCE Chapter VI, page 14 i t I 4 1 l 1 J l l I 6 t

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o l A.07 (3.0) Figure A-2 is a sketch of Reactor Power vs Time in hours. At t = 0 hours a reactor startup from Xenon free conditions to 100 % power occurs. q 70 hours a reactor trip occurs followed by a reactor I At t = startup to 100 % power at t = 80 hours. (a) Sketch the Xenon reactivity response in the (1.0) core from.this power transient. I (b) At what time will Xenon first reach (0.5) i approximately eculibrium concentrations for 100 % power ? (c) At what time will the maximum concentration (0.5) of Xenon occur ? (d) At what time will the maximum rate of rod (0,5)- motion be required in order to overcome the j Xenon transient ? ) (Assume reactivity from rods and Xenon only.) (e) Will this rod motion be IN or GUT 7 (0.5) ANSWER (A) ATTACHED (b) 50 to 60 hours i (c) 75 to 80 hours (d) 80 to 85 hours (e) IN REFERENCE I Chapter VI page 27 i ) 1 1 1 7 k 1 4

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A.08 (3.0) Refer to Figure A-3 Assume you have a heat flux at full power (100.%) of 100,000 BTU's / (hour) (sq. f t. ). (a) What is the temperature difference between (0.5) the cladding and the coolant bulk temperature for normal operation at 100 % power ? l (b) If' reactor power could be raised to 1000% (0.5) long enough for' temperatures to stabilize; I what would be.the temperature difference i between the cladding and the coolant bulk temperature ? (c) If reactor power could be increased to 1000%, (0.5) temperatures stabilized, and THEN reduced to 100%

power, what would be the temperature difference between the. cladding and the coolant bulk temperature 9 (d)

Describe the heat transfer process which (0.75) occurs between the coolant and the

clad, during NUCLEATE EDILING ?

(e) Describe the heat transfer process which (0.75) occurs between the coolant and the clad, during FILM BOILING ? ANSWER j i (a) 15 TO 20 DEGREES ( ( (b) GREATER THAN 1000 DEGREES (c) 500 TO 1000 DEGREES (Partial credit will be given fcr stating that the negative void coefficient and large prompt negative temperature coefficient make the sequence of events described impossible. The reactor would shutdown after reaching 1000% power and could only get back to 100% f rom shutdcwn. Thus the delat T would be 20 to 30 C.) l (d) In NUCLEATE BOILING vapor bubbles f orm at. the heated surface and mix with the bulk of the coolant transferring heat I away f rom the clad. (e) In FILM. BOILING the entire surface of the clad is covered by vapor, thus the main heat transf er mechanism is radiation. REFEPENCE l Chapter VI, pages 2829 8

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h B.01 (2.5) Refer to Figure B.1 attached, a cutaway drawing of the Mark I reactor core assembly. Match each component listed below with it's core location as defined by the letter.on the drawing. (0.5 each) (a) Transient rod (b) Control Rod (c) Specimen Rack (d) Icn Chamber (e) Neutron Reflector ANSWER (a) C l (b) B (c) D l (d) A (e) E l REFERENCE GULF Chapter 1 page 1-9 l l I 1 __________________-__-__.a

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e B.02 (2.5) A reflector is provided in the design of the TRIGA reactor to reduce the amount of fuel in the core. (a) What material is used as a radial neutron (0.75) reflector in the MARK 1 reactor? l (b) What is used as a radial neutron reflector (0.75) in the MARK F reactor? (c) How does a neutron reflector increase the (1.0) neutron population in the core? ANSWER (a) graphite (canned in aluminium) i (b) water j (c) By thermalizing fast neutron leakage from-the core (0.5) at the core boundry thereby increasing the thermal neutron population near the' core boundry (0.5) (By scattering leakage neutrons back into the core.) REFERENCE Chapter 1, page 1-16 Chapter 6 page 7 I 2

1 1 B.03 (2.0) l 4 Figure B.2 is a drawing of a typical fuel-moderater (High-Hydride) element as used in the MARK F reactor. (a) What is the composition of the component (0.5) labeled "A" ? (b) What is the f unction of the component labeled (0.5) "A" ? (c) What is the composition of the component ( 0. 5 ) - labeled "B" ? (d) What is the material used for cladding 7 (0.5) i 1 ANSWER (a) Graphite (b) neutron reflector (c) Zirconium hydride and (8.5 wt %) Uranium 1 (d) Stainless steel (304 SS) REFERENCE Chapter 1 page 1-11 i i

i TOP END-FIXTURE G i TRIFLUTE . !? 7 ^ 1 / j i f ll ll im \\% Si em ik 8 at N CLADING THICXNESS l 0.02 E 15IN. 28.37 IN. l.43171 - l 1 ~ 1.47 IN. + . y

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g if f!!:' l I j ggfi 3.47 IN. l 7 3..-r N BOTTOM END-FIXTUR$ l l 'e 1 l Fig. 31 Typical TRIGA l l

B.04 (1.0) The TRIGA MARK 1 reactor uses a LOW-HYDRIDE fuel element assembly. (a) What material is used for cladding in this (0.5) assembly ? (b) According to the License, can the HIGH-(0.5) HYDRIDE fuel element assemblites be used in 1 the MARK 17 l ANSWER ) 1 (a) Aluminum l i (b) yes REFERENCE Chapter 1 page 1 - 12 l j I i l I l 1 i 1 i 4 i

i B.05 (2.0) The Rotary Specimen Rack is one of the in-core design features of a TRIGA reactor that allows it to be used as an irradiation facility. (a) Of what material is the rotary specimen rack (0.5) made ? (b) How is accumulated condensation absorbed in (1,0) the rotary specimen rack ? (c) How is water leakage detected in the rotary (0.5) specimen rack ? ANSWER (a) Aluminum (b) Four of the specimen tubes are perforated and can be filled with a water absorbing material or water can be pumped out by means of a small pipe and tubing. (c) Moisture or leakage is detected by looking f cr wetness on the sample holders as they are removed. REFERENCE Lazy Susan construction d awings 29-310RO100 and 28-010RO100 4 4 / 5

~ i B.6 (2.0) What are three functions of the water treatment syst2m ? l i ANSWER (1) (provide low conductivity) to minimize corrosion (0.66) (2) Reduce radioactivity in the water (by removing radioactive particulate and radioactive ions) (0.66) (3) Maintain optical transparency of the water pool (0.66) REFERENCE CHAPTER 1 PAGE 1 -32 l i i i 4 6 A

B.07 (1.0) Why should special care be taken when usino Mercury or-Copper compounds near-the reactor pool ? 1 ANSWER I Mercury and copper are highly corrosive. (The water treatment system will not remove these ef f ectively. ) REFERENCE i i Chapter 1 page 1-32 1 l l l l l I

B.08 (1.0) l What two water parameters are monitored in-the MARK 1 reactor pit or pool ? I ANSWER (0.5 each) (1). Temperature (2) Conducti vity l l REFERENCE Chapter 1 Figure 1.21 3 i ) i I G w

B.09 (1.5) What_ three water parameters are monitored in the TRAGA MARK 1 water treatment system ? ANSWER (0.5 each) (1) Temperature (2) Radiation (3) Flow REFERENCE Chapter i Figure 1.21 9

i C.01 (3.0) l The TRIGA reactor has been designed with a large prompt negative fuel coefficient (FTC). Three principle ef f ects provide this 1 negative FTC;

Doppler, core leakage,-

and Cell and. Inhomogeneities.- l (a) How does DOPPLER produce a negative fuel (0.75) temperature coefficient ? (b) How does CORE LEAKAGE produce a negative (1.0) fuel temperature coefficient ? (c) How does CELL & INHOMOGENEITIES produce a (1.25) negative fuel temperature coefficient ? ANSWER (a) With increasing fuel temperatures the resonance absorption bands of U-238 (and Pu-240) broaden which increases the probability of a non-fission capture of a fast neutren (by U-238 or Pu-240). (0.5) (b) With increasing fuel and Zirconium Hydride temperature the thermal neutron population is hardened (increased energy) (0.5) thereby increasing the average distance a thermal neutron diffuses. The increased thermal neutron track length allows-an increase in the core leakage (0.5). (c) With increasing fuel and Zirconium Hydride temperature'the thermal neutron population is hardened (increased energy) (0,5) thereby decreasing the probability of absorption and fission in U-235 (0.5). Due to the non-homogeneous core construction, this increases the probability of thermalization and absorption in the surrounding water (and the steel cladding) (0.25). REFERENCE Chapter 6 page 20 and 21 l l I J 1 1

C.02 (1.0) I Of the three contributors to the (negative fuel temperature coefficient (FTC); CELL and INHOMOGENEITIES,

DOPPLER, and CORE

LEAKAGE, which is the dominant or principle effect ?

ANSWER CELL & INHOMOGENEITIES REFERENCE Chapter 6 page 21 2 o

C.03 (1.5) Why does the High-Hydride fuel element as used in the. MARK F reactor have a substantially larger.value for.the CELL Effect than the Low-Hydride fuel element'as used in the MARK 1 reactor ? ANSWER l The stainless steel clad adds a' poison region between the fuel j element and the cooling water which increases non-fission absorption of neutrons thermalized in the water. REFERENCE Chapter 6 page 21 1 l i 3 ] ^

C.04 (1.0) SELECT THE BEST ANSWER If, while operating the reactor at 100 %

power, a

nitrogen supply line to an in-core experiment ruptured causing a large nitrogen bubble to f orm in the core region (75% core volume), the core's reactivity would; (a) remain unchanged as nitrogen does not act as a significant neutron absorber or producer. (b) become prompt critical as the nitrogen would displace the core's moderator without effecting prompt neutron production. (c) become subtritical as the nitrogen would provide a large negative void coef ficient. (d) become source critical due to the large production of N-ia gammas. ANSWER (C) REFERENCE G.A. TRIGA MARK 1 Reactor Mechinical Maintenance and Operating Manual. { Chapter 6 page 23 4 4 4

C.05 (3.0) The MARK 1 reactor pool (or pit) provides water for cooling' the fuel elements. (a) What is the path of cooling water flow. from (1.0) the area of the fuel elements to the area above the upper grid plate ? (b) What is the motive force for this cooling (1.0) water flow ? (c) What is the cooling water flow path from the (1.0) pool into the fuel element area ? ANSWER ) (a) Cooling water passes through the gap between the triangular spacer block at the top of each fuel element and the circular hole in the upper grid plate. (b) Convection (natural circulation, reduced density of hatter-water) (c) Cooling water flows down the outside of the reactor, uncer the core, and up through holes drilled in the lower grid plate. REFERENCE GA Tech. Manual I-19, 21, and 31 i l l I 5 6 L_-________.________-________________________

C.06 (2.0) What are the approximate reactivity worth of the f ollowing; (a) a standard control roc ? (1.0) (b) a transient rod ? (1.0) l ANSWER (a) $2.00 I (b) $3,00 l REFERENCE j Chapter i page 23 6 4

C.07 (2.5) j The design of the MARK 1 and MARK F reactors incorporates a water pool or pit. (a) What is the minimum pool level specified in (0.5) the Technical Specifications for the MARK 1 reactor ? (b) What is the minimum pool level specified in (0,5) the Technical Specifications for the MARK-F ) reactor ? I (c) What are two reasons for these minimum (1.0) j -levels ? (d) At what bulk pool temperature must the MARK (0.5) 1 or MARK F reactors be shutdown in accordance with the Technical Speci f i cati ons? ANSWER i (a) 14 feet above the top of the grid plate. (b) 16 feet above the top of the grid plate. (c) (1) shielding from core. (0,5) (2) allow pool skimmer to operate. (0.5) (d) 65 degrees C REFERENCE MARK 1 TECHNICAL SPECIFICATIONS page 4 MARK F TECHNICAL SPECIFICATIONS page 3 I G.A. TRIGA Mark 1 Reactor Mechanical Maintenance and Operating Manual, pages 26a 24 81. ] \\ l ) 7 ]

i I C.08 (1.5) While operating the MARK F reactor at low power levels and low fuel temperatures, you note that the reactor response is f aster (less " sluggish") than the MARK 1 would be at the same low temperatures. (a) What acounts_for this response difference 7 (1,0) (b) What is the " rule of thumb" for reacti vi ty (0.5) insertion with increasing power for the MARK 1 reactor? I ANSWER (a) The MARK F reactor has a small prompt negative temperature-coefficient at low temperatures, therefore the power feedback is small and reactor response is fast. ( The MARK 1 reactor has a larger p:ompt negative temperature coef fi ci ent which is nearly constant at all operating temperatures.) (b) one cent per kilowatt REFERENCE TRIGA TPAINING PROGRAM OUESTIONS k i ) i 8

D.01.(2.5) Figure D-1 is a drawing of a control-rod drive mechanism. Match each component listed below with it's location on the control rod drive mechanism as defined by letter on the-attached drawing. (0.5 each) (a) Push rod (b) Pull rod (c) armature (d) potentiometer (e) motor ANSWER (a) D (b) A ') (c) G (d) C (e) B REFERENCE CHAPTER 1 page 25 1

e ~ MAGNET WIRE CONOUlT MAGNET DOWN A0JUSTMENT SCREW - MOTOR BI AS A0JUSTMENT MAGNET OR AW TUBg CENTER SWITCH 1 MOUNTING PLATE ROD 00WN LIMIT SWITCH [ M AGNET WIRE CONOUlT i ) PULL-ROD ' S PR!NG f MAGNET UP LIMIT SWITCH ADJUSTMENT SCREW. ~>

• { d'

[( A D' ) 'v BLOCK l BARREL = l i s ., 7. 4 i e /t ] t 4 4 h h CONNECTING ROD J V Fig. D-{ -Rod drive mechanism, showing components and adjustment locations O e

D.02 (2.5) i REFER to figure D-1, a drawing of a control rod drive mechinism. (a) What is the function or purpose of the pull rod ? (0.5) (b) What is the function or purpose of the push rod ? (0.5) (c) What is the purpose of the potentiometer ? (0.5) (d) What action occurs in this mechanism to allow (1.0) a rod to drop on a reactor trip or scram ? l ANSWER (a) Provides a rod bottom indication (pull rod attached to a l fixture which engages the rod down switch). { (b) Provides a magnet full up indication (rod attached to the full up switch). (c) Provides rod position indication when electromagnet engages iron armature. (d) Electromagnet de-energises and releases iron armature allowing rod to drop. REFERENCE CHAPTER 1 page 23 -31 and Figure I-18 I i l l 2 e

1 1

i D.03 (2.0) l 1

Neutron Sources are provided in the design of both the MARK 1 and The MARK F reactors. (a) 'Why is a neutron source important for reactor (1.0) operation after a long shut down period ? ) (b) What types of sources are provided in the MARK 1 (0. 5) - reactor ? (c) What types of sources are provided in the MARK F (0.5) reactor ?- ANSWER (a) To ensure that nuclear power can be accurately monitored during a reactor startup from low initial count rates. (b) MARK 1 Americium-Berylium (c) MARK F Americium-Berylium l i REFERENCE Chapter 1, page 15 and 16 l 3 e

1 l D.04 (1.5) l Reactor power is ronitored by neutron detectors installed near the core in the MARK 1 reactor. i l (a) What type of detector is used for the WIDE (0.5) d RANGE LOG CHANNEL ? (b) What is the range of the WIDE RANGE LOG (0.5) CHANNEL in term of percent reactor power ? (c) What reactor trips are provided by the WIDE (0.5) I RANGE LOG CHANNEL ? ANEWER (a) Fission counter (b) 10-8% to 100% i (c) none REFERENCE Chapter 2, page 2-37 j l 1 i 4

] D.05 (1.0) j In the steady-state mode the linear power channel provides power indication.from below source level to full power. This is accomplished with a ninteen (19) position range switch. (ai-What type of detector is used in the LINEAR (0.5) POWER CHANNEL for the MARK 1 reactor ? (b) What reactor scram or trip functions are (0.5) provided by the LINEAR POWER CHANNEL for the MARK 1 reactor? ANSWER (a) Fission chamber i (b) None i REFERENCE i Chapter 2, page 2-16 L 2-17 1 i l I I i I 5 4

l D.06 (1.5) The MARK F reactor also utilizes neutron detectors near the core for monitoring reactor power. l (a) Which reactor power channel in the MARK F (0.5) reactor. uses both the pulse rate technique 1 and the Campbell technique in providing a I ) power l evel indication ? i (b) What types of detectors are used in the MARK (1.0) F LINEAR POWER CHANNELS, K1,K2,and K3 ? ANSWER (a) Wide Range Log Channel (b) K1 - compensated ion chamber (0.5) K2 8< K3 - uncompensated ion chambern_ (0.5) REFERENCE Chapter 2 page 37 6

l l I ' :l D.07 (1.5) 1 The FISSION CHAMBER is a type of neutron detector at Gulf Atomic. (a) Sketch or describe the detector construction (0.5) or geometry. (b) What materials are used to allow det ecti on of (0,5) neutrons 7 (c) What region of the output pulse vs' detector (0,5) voltage curve does the FISSION CHAMBER use 7 ANSWER (a) Concentric can (cathode) and central probe (anode) (b) U-235 (c) proportional REFERENCE s 'al f Atomi c detector fundamentals l o' 7 l 1 l i

D.OB (1.5) The Compensated Ion Chamber is another type,of detector used at Gulf Atomic. -l (a) Sketch or describe the detector construction or geometry. (0.5) (b) What materials are used to allow detection of (0.5) neutrons ? (c) What does the COMPENSATED ION CHAMBER compensate _0.5) ( for 7 ANSWER (a) Two dif f erentia11y connected detecting volumes only one of which is coated with a neutron sensitive material. (b) baron (c) gamma radiation REFERENCE Gulf Atomic Detector Fundamentals 8

1 D.09 (1.0) Name the five basic operating regions.of a gas filled radiation ] detector as shown on the attached sketch. '(Region VI is continuous discharge of the filling gas) r ~ ~ VI V f XV log by current .I[ III II Counter Voltage ANSWER (0.2 each) (I) Recombination region (II) Saturation or ion chamber region (III) Proportional region (IV) Limited proportional region (V) G-M region REFERENCE Detector f undamental s ( l 9

E.01 (1.5) For the f ollowing reactor scram channels, indicate the scram setpoint. (a) MARK F reactor Keithley uua meter (0.75) (b) Mark F reactor - Fuel Element Temperature (0.75) ANSWER (a) 1650 kW (b) The actual setpoint is 650 C (800 degrees C is correct per the reference material.) REFERENCE Table 2.2 page 2-44 i ) l I I l I s 1

E.02 (2.25) In the TRIGA reactor in steady state operation a servo amplifier can operate as an automatic reactor control system. (a) What is the maximum rate of change of (0.75) reactor power in terns of period that this control system can provide ? (b) What are the three signal inputs to this (1.5) automatic reactor control system ? ANSWER (a) > or = 5 seconds (b) (0.5 each) (1) power demand from the demand potentiometer on the control panel. (2) reactor power from the linear power channel (3) reactor period from the period circuit of the log power channel i REFERENCE CHAPTER 2 page 2-20 1 = i i

E.03 (0.75) What is the Fuel Element Temperature trip setting in the MARK 1 reactor ? ANSWER 500 degrees centigrade REFERENCE Table 2.2 page 2-44 ) i 3 i v

i l E.04 (2.5) The neutron detection channels used for power measurment i are required to be operable by the MARK 1 Technical Specification. I -Periodic calibration runs are conducted to meet this requirement. (a) What is the calibration period required by (-0.75) Technical Specifications on these power j measuring channels ? (b) What two (2) parameters must be recorded to (1.0) calculate the power level during the s calibration run ? (c) How are the nuclear channels adjusted to (0.75) read within 5% of calculated power ? ANSWER (a) quarterly (b) (0.5 each) (1) time (2) pool temperature (c) (loosen the clamp and) adjust the vertical position of the detector REFERENCE SOP, TRIGA MK 1, Sec. O and Technical Specifications i 4 4 6

E.05 (O.5) What in the ma>:i mum reactor scram delay time required by the Technical Specifications ? ANSWER l 2 seconds I REFERRED l T.S. l 0 l ) I i 5 a

E.06 (2.0) For the following backlighted pushbutton control rod drive switch conditions indicate the what normal or abnormal condition exists; (a) UP LIGHT - OFF (1.0) DOWN LIGHT - ON CONT /ON LIGHT - ON l (b) UP LIGHT - OFF (1.0) l DOWN LIGHT - ON l CONT /ON LIGHT OFF l l ANSWER (a) NORMAL, rod at lower limit and magnet making contact (b) Abnormal, Rod and Drive completly down REFERENCE Chapter 2 page 14 i l I I i I i l \\ l 1 6

I E.07-(2.5) Regarding the pulsing operation o+ the TRIGA MARK 1; (a) What is the maximum reactivity insertion i n (0.5) dollars'for a pulse ? (b) What power level should the Keithley wide (1.0) range pointer be set to prior to a pulsing event ? (c) What action must be taken if the transiant (1.0) rod f ail s to drop back into the core following a pulse 7 ANSWER (a) $3.00 (b) 1000 MW (c) Manually scram the reactor REFERENCE Chapter 5 and 6 pages 5-1 and 6-7 l 9 1 'I i 7 'l (

F.01 (2.0) The Mark.I-reactor is operating at 200 KW when a SCRAM occurs. Based on the Alarm and SCRAM Procedures there' are five event s/i ndi cati ons which can be observed at the operator's c on sol e. j What are these five events / indications ? ANSWER (0.4 each) 1 1. Contact lights out, (rod up lights out) 2. Rod indicators drive down 3. Power decreases on all channels 4. Fuel temperature decreases l 5. (after the rod drive mechanisms have driven full down) the down lights come on. { t REFERENCE Operating Procedures for the Mark I TRIGA, page VI-1 1 I i l o l 1

F.02 (2.0) Following a SCRAM the Mark F control rods did not drop into the You are attempting to shut down the reactor using the Alarm core. and SCRAM Procedures. Securing the console power is one of the first four steps. e. What are the three other immediate steps to try to shut the reactor down 7 (1.5) ) i b. Why is console power restored in the fifth step of the procedure ? (0.5) l ANSWER J l a. (0.5 each) l ) Try the manual SCRAM bar Turn off the magnet power key Unpl.ug the control rod drive power at the bridge b. This will allow power channels to be monitored. (0.5) REFERENCE Operating Procedures for the Mark F TRIGA., page VI-G I ) 2

F.03 (1.0) Based on the TRIGA facility Radiological Safety requirements related to Radio-i sotopes and In-core Experiments, what type of container must be used in the rotary specimen rack when irradiating fissionable material ? ANSWER Aluminum container (1.0) REFERENCE Radiological Safety, Chapter V, page V-5 l 1 l i 3

9 F.04 (1.5) I ou are conducting the weekly surveillance of -the earthquake 1 Y SCRAM circuit in accordance with the TRIGA facility Operating Procedures. You have just displaced the movable contact block and observe that the the upper contact point drops slightly, a. What indication do you expect to see at the control console ? (0,5) 1 b. How do you reset the switch contact point ?- ( 1. 0) - ANSWER a. All console lights go out (all power is removed) (0.5) b. Depress the lever at the side of the switch box (0.5) and align the contact points manually. (0.5) ( 1. 0) - REFERENCE TRIGA Operating Procedures page IV-9 4

F.05 (2.0) Based on the Operating Procedures for Access to the TRIGA Reactor Facility entry of visitors is controlled by the on duty SRO/RD, a. For a group of 15 visitors, how many dosimeters must be i tzsued ? (0.5) b. To what three groups of individuals must film badges or TLD dosimeters be issued ? (1.5) ANSWER a. Three (at lease one for every five visitors) '(0.5) b. (0.5 each) Every person'under 18 years of age Every individual who will be handling nuclear or radioactive material Every individual who will be working in the facility or be in the facility more than one hour. REFERENCE Operating Procedures, page III-12 4 1 i 1 5 ^

i i ) I F.06 (2.0) The TRIGA Mark F procedure for fuel loading is being followed. The daily checklist has just been completed. An RO and an SRO are present. a. What are the functions of the RO and SRO during fuel loading 7 (1.0) b. How many elements at a time may be moved into or out of the core 7 (0.33) c. What are two of the three places that fuel moves must be logged 7 (0.67) ANSWER a. The RO monitors the console instruments and the SRO directly supervises the core changes. (1.0) b. one (0.33) c. (0.33 each for any two of the f oll owi ng) (0.67) Logbook (in red ink) j on the fuel cards on the core display board REFERENCF TRIGA Mark F Operating Procedure XI 4 i 6

F.07 (1.5) A large scale fire has occured in the TRIGA Facility workshop. The Mark F reactor is currently operating and the Mark. 1 is shu.down to add two new fuel elements. The Emergency Procedure for Fire Inside the Reactor Building is being implemented. a. Other than fighting the fire, what three immediate actions should be taken ? (1.0) b. What should be done with a fuel element not yet loaded into the Mark I ? (0.5) ANSWER a. (0.33 each) Shutdown the Mark F l Secure ventilation Shut off all non-essential electrical breakers b. Remove it to the storage locker or (if the locker is inaccessible remove the element from the building and keep it under survei l l anc e. ( 0. 5) - REFERENCE Operating Procedures TRIGA Mark F, page VII-4 7

G.01 (2.25) You are conducting a survey of a contaminated area with a JUNO (Model 9) survey meter (shown in Figure. G-1). You note the following readings while holding the instrument close to the contaminated area; With the "G TAB" in the up position, and the "SELECTO9 FWITCH " in the "X 10 R/hr" position, the meter reads "1.5". With the "G TAB" in the down position, and the " SELECTOR SWITCH" in the "X 10 R/hr" position, the meter reads "1.3". j (a) What is the GAMMA dose rate as measured above ? (0.5) (b) What is the Beta dose rate as measured above ? (0.5) -(c) What position should the " SELECTOR SWITCH" be (0.25) j in when warming up the instrument ? i, J (d) How is the instrument periodically re:erced ? (0.5) (e) What is the function or purpose of the (0.5) " RED RESET BUTTON" ? ANSWER (a) gamma = window closed reading (0.25) gamma = 13 R/hr (G TAB down) (0.25) (b) beta = window open - window closed (-0.25) beta = 15 R/hr - 13 R/hr = 2 R/hr (0.25) (c) " SET" (0.25) (d) Return " SELECTOR SWITCH" to " SET" (0.25) and adjust "ZERO CONTROL" (0.25). (e) Depressing the RED RESET BUTTON checks the zero setting without turning the selector switch (0.5). I REFERENCE CHAPTER v page 14 f i

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l ) G.02 (1.0) How long can you remain in an area with a gamma dose rate of 3.5 R/hr without exceeding the 10 CFR 20 quarterly whole body limit? i ANSWER I OUARTERLY LIMIT = 1.25 R (0.5) Time = E (1.25 R) / (3.5 R/hr) J E 60 min / hr ] (0.25) J Time = 21.4 min. (0.25) REFERENCE j CHAPTER V page 28 1 1 i l i l l 2 b

I I G.03 (1.5) Figure G-2 shows an "EBERLINE PAC iSA" portable radiation detector. (a) What type of radiation does this instrument (0.5) measure ? (b) What type of detector does this instrument (0.5) utilize ? (c) How _many " counts per second" should register (0.5) on the meter if the probe is held over the "U SOURCE" ? ANSWER (a) Alpha j (b) Scintillation detector (c) 300 to 500 cps 1 REFERENCE l CHAPTER V page 16 ) ) 1 j i 3 + 4

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I 1 I G.04 (1.25) i Figure G-3 shows a NP-2 (SNOOPY) portable radiation monitor. j (a) What type of radiation does this instrument (0.5) ) measure ? q l (b) What type of detector does the NP-2 utilize ? (0.5) j (c) What would the instrument read ( in MREM /hr) (0.25) in a 100 R/hr Gamma field ? ANSWER (a) Neutron (fast and thermal) l (b) BF3 prcportienal detector l l (c) zero (insensitive to gamma up to 500 R/hr) ) REFERENCE l CHAPTER V pages 16-18 i l i i .l I I J 4 6 6 O

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• HRuDLE 9

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l ~ G.05 (1.0) l SELECT THE BEST ANSWER j A point' source of GAMMA radiation measures 8 R/hr at a distance j of. .2 feet. Which of the following is the best estimate of the radiation dose rate from the GAMMA source at a distance of 8 feet.? (a) 500 R /hr (b) 2 R/hr l l (c) 500 mR/hr (d) 200 mR/hr ANSWER (C) DOSE RATE inversely proportional to distance squared distance increased by 4 l DOSE RATE decreased by 16 REFERENCE STD Ti me, Distance, Shelding calculation l . ] i l l i 5 4

'l l l G.06 (2.0) Figure G-4 shows the Radiation Area Monitor (RAM) instruments. 4 l (a) What type of radiation do these instruments (0.5) j detect ? 4 (b) What is the High Alarm (RED) setpoint for the (0.25) 5 R/hr RAMS ? (c) What is the High Alarm (RED) setpoint for the (0.25) 20mR/hr RAMS ? (d) Where is the Rack Unit with the four (0.25) indicators installed ? (e) 'Where are the Remote Indicators installed ? (0.25) i i (f) In accordance with the Technical Specifications, when must the RAMS be in operation 7 (0.5) l ANSWER (a) Gamma (b) 5 R/hr j l (c) 20 mR/hr (d) Radiation Auxiliary Panel, Mark I reactor room l l (e) respective reactor control rocms (f) During reactor operations ( exceot for short periods of repair while pertable gamma instruments with alarms are in operation near the reactor.) l REFERENCE CAF Technical Specifications 6.2 6

k ~ C-' F 3 RAMS g ,M, ' \\ + - seeino 70,sasa gems ( (seunJ4r) --a R * *LS e=amak &LBt/ll$ -a,. 4, [o7 ai* ** s j4. -s gg Q. --e F t

== c e T _2 t au.. sc _-=r E w., b fe.T"" REMOTE R N TE I p.#@d INDIC ATOR DETECTOR er h (ONE for Exh Tredic.Ahr) 7 o l a 1 N.Y7//r u.s meo armar.anass INDICATO8 w (MARK I m4RK F no.lL-sR/hr-2emeAr en/A,. vanu 3 -f l IT - I' - C I d [ W d i \\ t C _.i di, iC_ i~- D C 99@ @@d ece /WA Und wirH Ru& INoicAToAs (E SE R4.8hE) Radiation Area Monitors (RAMS) for Mark I and Mark F reactors 1'qdRE h ~2 rl F

G.07 (2.5) A survey of radiation and contamination levels has.been-made by Radiation Protection personnel. The map (Figure G-5) on the following page has the results of this survey. Portions of 10 CFR 20 Appendix B, Concentration.s in Air and Water Above Natural Background (Figure G-6), are also provided. Based only on this survey and the requirements of 10 CFR 20; (a) What posting is required in the LABORATORY'? .0.5)- ( (b) What posting is required in the MARK F (0.5) l REACTOR ROOM 7 (c) What posting is required in the SHOP 7 (0.5)' (d) What posting is required in the STORAGE (0,5) BUILDING ? (e) Which areas must be locked or access (0,5) otherwise control l ed in accordance with 10 CFR-20 ? ANSWER (a) CAUTION AIRBORNE RADIOACTIVITY AREA (b) CAUTION HIGH RADIATION AREA (c) CAUTION RADIATION AREA (d) CAUTION RADIATION AREA (e) MARK F REACTOR ROOM REFERENCE 10 CFR 20 7 _. _. _.. _ _ _ _ ~ _. _.

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m OQ&W ]~ 9 Nuclear Regulatory Commission Port 20, App B APPENDIX B---CONCENTRAT40NS IN AIR AND WATER ASOVE NATURAL B ($se footnotee at end of Appenes 51 lootope 8 Table l Table il Element (atome number) Col. 2-Ca 1-Air cat. 2-e,,,,_,4, (pO/m0 -g, ,'n (pG/m0 g,[,g loene (53) 0125 S 6 x10-' 4 x10-8 8 x10*H 2 x to-' I 2x10*' 6x10-s 6 x 10-' 2x10-*' i126 8' 8x10-' 8x10" 9x10*" 3 x10-' 3 x10*' 3 x10-* 1x10" 9 x10-8 1129 S 2 x10** 1x10-e gx10-u 6 x 10-8 I 7 x 10-' 8x10-8 2x10** 2 x 10-* 1 131 8 0 x10** 6 x 10-e 4 x 10-" 3 x10 ' I 3x10" 2x10** 1 x 10-* 6 x10-* 1132 5 2 x 10-' 2x10-8 3 x10" 8 x10-s i e x 10" 6 x 10** 3 x 10*

• 2x10" l133 8

3 x10** i 2 x 10*' ' 2x10-* 4 x 10-" 1 x 10-* 1x 10-e yxio-e 4 x 10* * $ 134 5 8 x 10*' 4 x 10-' 6 x 10-' 2x10" 4 3 x 10-8 2 x10-8 1x10-i 6 x 10-' 4135 8 1x104 Y x 10-* 1 x 10-' 4 x 10-* - 1 4 x 10" 2 x 10*

• 1x 10" 7x 10" kleum (771 er 100 8

1x10" 8 x 10-8 4 x 10-' 2 x 10 ** I 4 x 10-' 8x10 8 1 x 10-' 2 x 10-* k 192 8 1 x 10-' 1x10-8 4 x 10** 4 x 10-' i O x 10-' 1x10-8 9 x10-" 4 x 10-* 1r 194 S 2 x 10*' 1x 10-8 8xto" 3 x10-8 I 2 x 10-' 9 x 10-* 6 x 10-8 3 x 10-8 kon (26) Fe 65 8 9x10" 2 x ' 0-8 3 x 10" e x10-8 8 1x 10-8 7x10-e 3 x10-8 2x 10-8 Fe 69 8 1 x 10-' 2 x 10-* 6 x 10-' 6 x t0-s t 5 x 10-8 2x10-8 2 x 10-' 8 x 104 Krypton (36) -- Mt85m Sub 8 x 10*

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Pb 210 - 6 1 x 10-" 4 x104 4 x 10-ta 1 x 10-' l 2 x 10-" Exit?* 8 x10-u gxip9 ) Pb 212 S 2 x 10-* 6 x10" 8 x10-* 2 x 10" ~ Lutenum (71) l 2x10" E x10-8 Tx t0 " 2x to-* Lu 177 8 6 x 10-' 3 x104 2x10" 1 x t o-* Manganese (25) I 5 x 10-' 3 x10-e 2 x 10-' 1 x 10-* Mn 62 5 2 x 10-' 1 x 10-8 7x10" 3 x to" i 1 x 10*' D x 10-* 6 x 10-* 3 x 10-8 Mn 64 6 4 x10-8 4 x 10-* 1 x 10-' 1x178 I 4 x 10-* 3 x 10-' 1x10 ' 1 x 10-* Mn 66 - S 8 x 10-' 4 x 10-8 3x10" 1 x to-* Mercury (80) 8 6 x 10-' 3x10-8 2x 10-' 1 x 10-' l Hg 197m S 7 x 10" 0 x10-8 3 x 104 2x10" l 8 x 10-' 8 x 10** 3 x10" 2x10-* Hg 197 S 1 x 10** 0x10 8 4 x10-* 3 x 10-* I 3 x 10-* 1 x10-9 x 10-a 6 x 10-* Hg 203 S 7 x 10-' 8 x10" 2 x10" 2 x10-8 l 1 x 10-' 3 x 10-s 4xto e 1 x 10-

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7x 10-' 8x10 a 3 x 104 2 x 10" ~ Neodymium (60) Nd 144 8 x 10'" 2 x 10" 3 x 10"' 7x t0" l 2 x 10-' 1 x 10-a yx io-e 4 x 10** s 3x10-" 2x 10-8 1x10* u O x 10-' Nd 147 5 4 x 10" 2x10" 1 x 10" 6 x 104 8 2 x 10-' 2 x10-8 8 x 10** 6 x 10** Nd 149 S 2 x 10-* 8 x10-8 8 x 104 3x10" 4 1 x 10 8 x 10-8 6 x 10" 3 x 10" Neplumum ~(03) Np 237 S 4 x 10'" 9 x 10-* 1 x 10-" 3 x 10-8 9 1 x 10-" 9 x 10** 4xt0-" 3 x 10 Np 239-S B W 10" 4 x 10-8 3 x 10's 4 x 10** I f x 10" 4x10 8 2x 10-8 1 x 10-* Nchel(28) Ni 69. S 6 x10" 8 x 104 2x104 2 x10" 1 a 6

s G.08 (2.5) In Accordance with the RADIOLOGICAL SAFETY RULES established for guidance of work wi th radioacti ve materials; (a) What four markings must be on Radioactive (1.0) materials or Radiation Sources when unattended ? (b) Above what source strength should material (0.5) not be manipulated with the fingers ? (c) At what general area radiation level must (0.5) personnel monitoring devices be worn 7 (d) Under what two conditions should

smoking, (0.5)

eating, and drinking be stopped when working with radioactive materials ?

ANSWER (a) (0.25 each) (1) magenta radiation symbol (2) words " CAUTION RADIOACTIVE MATERIAL" (3) identification of substance (4) magnitude of r adi oacti vi ty (b) 0.5 uCi (c) 2 mrem /hr I (d) (0.25 each) (i) unsealed radioactive materials are in use or stored (2) potential for surface contamination j REFERENCE CHAPTER V pages 26 & 27 i l i 8 .}}