Text

Exam Rept 50-224/OL-86-01 on 860902-03.Exam Results: Candidate Passed Written & Oral Exams.Exam & Answer Key Encl
	ML20214V764
Person / Time
Site:	Berkeley Research Reactor
Issue date:	09/10/1986
From:	Elin J, Morrill P, Obrien J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
Shared Package
ML20214V753	List: ML20214V751; ML20214V764;
References
	50-224-OL-86-01, 50-224-OL-86-1, NUDOCS 8610020398
	Download: ML20214V764 (49)
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EXAMINATION REPORT Facility Licensee: Berkeley Test Reactor University of California Department of Nuclear Engineering Berkeley, California 94720 Facility Docket No.: 50-224 Exam Report No. 50-244'/0L-86-01 Facility License No.: R-10 Examinations administered at the Berkeley Test Reactor, Berkeley, California.

Chief Examiner: f -/d -

Jo 'P. O'Brien Date Signed

. 1 Examiner:

-l ~b P. Morrill Date Signed

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Approved by:

N J. O. Elfin, Chief, 'Opegitions Section Date Signed Summary:

Examinations administered on September 2-3, 1986.

Written and oral examinations were administered to one RO candidate. The candidate passed these examinations.

gj O 98 860913 ":

V CK 05000224 PDR j

REPORT DETAILS I

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1. Examiner (s)

*J. P. O'Brien, Chief Examiner i P. Morrill

2. Examination Review Meeting At the conclusion of the written examination, the Examiner met with Tek H. Lim and Mike Denton of the facility staff to review the written examination and answer key. The facility comments on the examination i and answer key and the resolution of the comments are attached to this report.

3. Exit Meeting At the conclusion of the site' visit, the examiners met with the facility staff to discuss the results of the examination. The examiners made the following observations concerning your training program:

a. Areas of generic weaknesses were found in the use of radiation protection procedures; the use of portable radiation instruments; and the electrical distribution and emergency backup power supplies.

! b. Areas in which the examiners believe that the candidate exhibited good training and knowledge were the control board systems and operating procedures.

Further discussed was the need to improve the reference material sent to the examiners for future exams.

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ATTACHMENT 1 d

FACILITY COMMEU'S ON RO EXAM Comment:

C.02 The " worth" of the transient rod as measured on 10/85 was $2.79 (See attachment).

Resolution:

Accepted; key corrected.

Comment:

D.03 In January of 1980, the operation of the shim rod by the servo-controller was discontinued. Members of the reactor staff were officially informed of the change by the Reactor Supervisor in his memo dated March 21, 1980 (See attachment).

Resolution:

Revised key; redistributed points.

4 Comment:

D.05a While in the Pulse Mode, the linear recorder indicates the pulse

[ peak power only. A revised drawing is attached. We apologize for not including this revised drawing in the packet.

Resolution:

Revised key; redistributed points.

Comment:

E.06 Technical Specification #3.4.2 list 5 automatic scrams which must be operable to proceed with operations, plus a transient rod scram on a timer. We do not consider the dropping of the transient rod to be a recorded scram, as the other three rods remain withdrawn in positions that could leave the reactor in a critical condition.

Resolution:

Revised key to add 7th possibility for Hi Volt Scram and to indicate that preset timer is for transient rod only. No point change required.

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- __ - , -, -,_m _. . _ _ ,,_ _ - - , . , _ . - _ _ _ _ _ , _ _ , - - . . _ . . _ . . . . _ _ _ , , _ _ _ . _ . _ _ , _ _ _ , . _ ,

, o Comment:

F.04 Technical Specification #5.7 for the BRR states that the pool level switch shall be activated at approximately two (2) feet above the top of the core. The same specification puts the minimum pool depth above the top of the core to be 14 feet. Therefor, either answer should be acceptable. Note the operating procedure #1.5 also references the 2 feet above core specification.

Resolution:

Revised key to accept as stated cg; "2 feet above the core". No point change required.

Comment:

F.05 BRR internal operating procedure (#1.1.3) restricts the pre-pulse power to between 3.and 100 watts. Technical Specification (Table 1, page.12) restricts the power to a level of less than 1,000 watts.

Resolution:

Noted info in key; no change of key required.

Comment:

F.07 There are three (3) reactor system alarms provided to the police station. They are:

1. High Radiation Alarms

2. Door Alarms

3. Low Pool Water Level Alarm Resolution:

Revised key.

.t

3 Comment:

F.13 Emergency Procedure #4.5, page 67 list the actions that the operator must take:

1. Notify other present of disturbance

2. Scram reactor if operating

3. Secure all experiments

4. Activate door alarn

5. Notify policy

6. Lock and vacate all first floor areas

7. Proceed to Nuclear Engineering Department Office or other designated areas.

Resolution:

Revised key to above.

Comment:

G.11 We think that the phrasing of the question requires inclusion in the answer, the three basic principles of reducing radiation exposure to a source of radiation: time, distance, and shielding.

Resolution:

Included these as 3 additiondl possibilities; even though, they

.are the basic principles on which the original 8 are based.

.' '- a U. S. NUCLEAR REGULATORY COMMISSION REACTOR 0,PERATOR LICENSE EXAMINATION FACILITY: UNIVERSITY OF CALIFORNIA

REACTOR TYPE: TEST

/

/ DATE ADMINISTERED: 86/09/03 EXAMINER: HUENEFELD, J. /JARRELL, D. -

CANDIDATE: M A 9767C. EXA+ff @/I6 INSTRUCTIONS T0-CANDIDATE:

Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. - Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the-examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 14.00 14.58 A. PRINCIPLES OF REACTOR OPERATION 13.00 13.54 B. FEATURES OF FACILITY DESIGN

{ ' '1 0 12.50 C. GENERAL OPERATING

, CHARACTERISTICS 14.50 15.10 D. INSTRUMENTS AND CONTROLS 13.00 13.54 E. SAFETY AND EMERGENCY SYSTEMS

! 15.00 15.63 F. STANDARD AND EMERGENCY OPERATING PROCEDURES

! 14.50 15.10 G. RADIATION CONTROL AND SAFETY l Q V/ 00 Totals I Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature L

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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 dental 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.

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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 on one side of the paper, and write "Last Page" on the last answer sheet.

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

i 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.

I 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.

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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 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.

1

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 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.

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p EQUATION SHEET f = ma v = s/t C w = ag a = v,t + at 2 Cycle efficiency = "*

E k t)

/ E = mC a = (vf-- v g)/t 2 t KE = mv v ,V + at A = AN A = A,e f f o

< PE = agh to = 6/t A = in 2/tg = 0.693/tg c W = vaP~

tq(eff) = (t g)(tu)

AE = 931Am (t +t) 3 Q

= k PAT I.Ieo -IX j Q = UAAT I.Ie -UX

, Pwr = Wg In I-I 10

-X/ M o

P=P 10 SUR(t) TVL = 1.3/p p.p e th M = 0.693/u o

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

fA

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CR SUR = 26 g j = S/(1 - K,gg )

T = '(t*/p ) + {(f !p)/A CR y (1 - Keff)g = CR 2 (l - Keff)2 p}

7 , g*j g _ g M = 1/(1 - K,ff) = CR /CR g 0

" ~

! eff E M = (1 - K,ff)0 /(1 - K,gg)g-

" ( eff" }! eff " A eff eff 2 SDM = (1 - K,ff)/K,gg p= [1*/TKygg .] + [il/(1 + A,ggT )] ,

1* = 1 x 10- seconds l' = I$V/(3 x 1010) A,g = 0.1 seconds

t = ,.

! Idlg=Id22 WATER PARAMETERS Idg =I022 1 gal. = 8.345 1hm R/hr = (0.5 CE)/d (meters) 1 gal. = 3.78 liters R/hr = 6 CE/d (feet) 1 ft3 = 7.48 gal. MISCELLANEOUS CONVERSIONS .

l Density = 62.4 lbm/ft 10 1 Curie = 3.7 x 10 dps 3

Density = 1 gm/cm 1 kg = 2'.21 lba Heat of vaiorization = 970 Etu/lbm 1 hp = 2.54 x 10 3BTU /hr 0

, Heat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 10 Btu /hr 1 Atm = 14.7 psi = 29.9 in, l'g. 1 Btu = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 C = 5/9 ( F - 32)

A. PRINCIPLES OF REACTOR OPERATION PAGE 2 QUESTICN A.01 (1.50)

DEFINE Shutdown Margin. (1.5)

QUESTION A.02 (3.50) -

Below is a linear plot of neutron response to a continuous insertion of positive reactivity, followed by a pause of several seconds, ,.

foll. owed by a continuous insertion of negative reactivity.- The '

solid line is neutron countrate. The closed dotted line is inverse reactor period with infinity represented by the widely spaced dots.

ANSWER the following questions about the response depicted in this graph.

countrate inverse

7 period /

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,, t + (-)

."2 A 8 3 1 .

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a. IDENTIFY (mark) on the graph the time intervals of reactivity insertion. (1.0)

b. WHICH is larger in magnitudes, the positive or the negative reactivity insertion? JUSTIFY your answer. (1.0)

c. EXPLAIN the shape of the graph of inverse period between "A" and "B". (1.5)

(*****CATEGORYA CONTINUED ON NEXT PAGE *****)

A. PRINCIPLES OF REACTOR OPERATION PAGE 3 QUESTION A.03 (1.50)

ANSWER TRUE or FALSE.

If reactor period is positive and increasing, then the instantaneous

. delayed neutron fraction (i.e., the amount of neutrons in the current generation born delayed divided by the total neutron population) is '

increasing. EXPLAIN. (1.5)

QUESTION A.04 (1.50)

Given that power increases from 20% to 40% on the linear power channel in 10 seconds, CALCULATE the period. (SHOWyourwork.) (1.5) q QUESTION A.05 (2.00)

Curve "A" on the trace below is a logarithmic plot of total neutron power versus time after a reactor trip. Curve "B" is a plot of the neutron power due to delayed neutrons alone 'versus time for the same trip. EXPLAIN why total neutron power (i.e., curve A) does not drop all the way down to the delayed neutron level (i.e., to curve B). (2.0) 1 A - To ut. neurnon l

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(*****CATEGORYA CONTINUED ON NEXT PAGE *****)

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A. PRINCIPLES OF REACTOR OPERATION PAGE 4 QUESTION A.06 (2.00)

a. GIVE a brief definition of " Bath" temperature coefficient. (1.0)

b. IS the Bath temperature coefficient POSITIVE or NEGATIVE at room temperature? (0.5)

c. ANSWER TRUE or FALSE. The prompt transient (i.e., pulsing) behavior of the TRIGA reactor is primarily determined by the Bath temperature coefficient. (0.5)

QUESTION A.07 (2.00)

EXPLAIN the " prompt jump" phenomena of a small (rho ( $1), but rapid, insertion of positive reactivity from a physical stand-point.

(2.0) 3 l

(***** END OF CATEGORY A *****)

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l B. FEATURES OF FACILITY DESIGN PAGE 5 l I

QUESTION B.01 (1.00)

The Nitrogen-16 Diffuser is designed to (1.0)

(a.) remove the oxygen from water above the core and thereby -

reduce the N-16 radiation level at the pool surface.

(b.) increase the transport time for the N-16 from the top of the core to the pool surface.

(c.) break up the gas bubbles of 0-16 and thereby reduce the probability of forming N-16.

(d.) provide a 20 gpm stream of pool water ta' ken from the return flow of the Water Cooling Purification System and angled downward above the top of the core shroud.

QUESTION B.02 (2.00)

Specify which grid ring each of the four (4) control rods are located in. (2.0).

t i

QUESTION B.03 (1.00) i .

a. WHAT is the difference between the follower section of the ;

regulating rod and the follower section of the transient rod? (1.0)

b. WHAT design feature slows the control rods during the last j phase of their travel during a reactor scram? (1.0) l QUESTION B.04 (1.50) i The water treatment system on the reactor serves five (5) functions.

NAME three (3) of them. (1.5) l QUESTION B.05 (1.00)

DEFINE experiment as stated in the Technical Specifications. (1.0)

(*****CATEGORYB CONTINUED ON NEXT PAGE *****)

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B. FEATURES OF FACILITY DESIGN PAGE 6 QUESTION B.06 (2.00)

Identify the following components on the attached grid array,

a. The rabbit terminus .

b. The linear chamber . ,

c. The log chamber .

d. The source .

QUESTION B.07 (2.50)

DRAW a basic schematic of the Transient Rod Drive showing the bottom limit, the air supply hose with the three-way valve, the ball nut, the worm gear, the piston, and the externally threaded cylinder with vent holes. (2.5)

QUESTION B.08 (2.00)

WHAT design features provide for neutron reflection in the radial AND the axial direction in your reactor? (2.0) l l

(***** END OF CATEGORY B *****)

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C. GENERAL OPERATING CHARACTERISTICS PAGE 7

~

QUESTION C.01 (1.00)

Measurements of the " power coefficient" were made for typical Mark III cores,

a. SKETCH a typical power-defect curve for a Mark III core for reactor powers from 0 to 1000 kW. (1.0)

b. HOW does this curve change for a fresh core versus a core that has been pulsed 2000 times to 2000 MW7 WHY does the power defect change with the number of pulses? (2.0)

QUESTION C.02 (2.00)

I LIST the total reactivity worths in dollars for each of the four (4) control rods. (2.0)

QUESTION C.03 (2.50)

LIST the three (3) effects (components) that contribute to the large prompt negative fuel-temperature coefficient of the Triga reactor.

INDICATE which component has the largest effect and which has the smallest. (2.5)

QUESTION C.04 (1.50)

IIATCH the following pulse characteristics with the appropriate relationship to reactivity: (1.5)

a. Pulse height 1. approx. **1/2 Full-with-at-half-max.

b. 11. approx.

c. Total energy liberated 111. approx. **2 iv. approx. **-1 QUESTION C.05 (1.50)

WHY is it important that the reactor be scrammed following a pulse? (1.5)

(*****CATEGORYC CONTINUED ON NEXT PAGE *****)

C. GENERAL OPERATING CHARACTERISTICS PAGE 8 QUESTION C.06 (.50)

ANSWER TRUE or FALSE.

" Cold critical" as defined in Technical Specifications implies xenon free. (0.5) ,

QUESTION C.07 (2.00)

DRAW a simple sistch of a reactor pulse (assume $3.00). On the same time scale, SKETCH what fuel temperature does during the pulse. (2.0)

QUESTION C.08 (1.00)

If a line supplying nitrogen to an experiment in the core were to break, causing bubble formation within the core lattice, WHAT would core reactivity do and WHY? (1.0) i 1

(*****ENDOFCATEGORYC *****)

D. INSTRUMENTS AND CONTROLS PAGE 9 QUESTION- D.01 (1.00)

Briefly EXPLAIN WHY the power level monitor that reads in % power (2 to 100+%) can use an uncompensated ion chamber (UIC) rather than a compensated ion chamber (CIC). (1.0)

QUESTION D.02 (3.00)

SPECIFY the condition (ON or OFF) of the UP, DOWN and CONT lights for the regulation under the following conditions:

a. The reactor was scrammed 100 msec ago and there are no system malfunctions. (0.6)

b. The control rod and rod drive are fully withdrawn and there are no system malfunctions. (0.6)

c. Either control rod insertion or withdrawal is possible and there are no system malfunctions. (0.6)

d. The control rod and rod drive are at their lower limits and the magnet is making contact with the armature and there are no system malfunctions. (0.6)

e. The reactor was scrammed 10 min ago and the control rod stuck and did not move from its fully withdrawn position. (0.6)

QUESTION D.03 (1.00)

WHICH control rods may be positioned utilizing the servo-controller? (1.0)

QUESTION D.04 (3.00)

a. At WHAT relative radial position is the instrumented fuel rod located? WHY? (1.5)

b. WHAT is the technical specification concern requiring the maintenance of a temperature limit? (1.5) l

(*****CATEGORYD CONTINUEDONNEXTPAGE*****)

__ , , , _ _ . _ , . . _.,......_.,._,n.-~,. , , . .---__._ -,.-_ _ . - , _ , . __ __._ - _ _ , . _ _ - . _ .

. D. INSTRUMENTS AND CONTROLS PAGE 10 s

s*

QUESTION D.05 (1.50)

a. While in the pulse mode, WHAT indications are available on the linear recorder? .

(1.0)

~

b. While in the pulse mode, WHAT indications are available on the Log Recorder? (0.5)

QUESTION D.06 (2.00) d HOW is gamma radiation compensated for in a compensated ion chamber? (2.0)

QUESTION D.07 (3.00)

SKETCH a block diagram of the reactor power nuclear instrumentation system for steady state operation. INCLUDE all neutron count rate detection systems, amplifiers and indicators. (3.0) c l

, (*****ENDOFCATECORYD *****)

E. SAFETY AND EMERGENCY SYSTEMS PAGE 11 QUESTION E.01 (1.50)

IDENTIFY three (3) electrical loads that are supplied by the emergency power supply. (1.5)

QUESTION E.02 (2.00)

LIST the four (4) different types of radiation monitors which when alarming will initiate a radiation alarm to the campus police. (2.0)

QUESTION E.03 (1.00)

STATE the Technical Specification alarm set point for fuel temperature and COMPARE it with the actual safety, limit. (1.0) ,

QUESTION E.04 (2.00)

EXPLAIN the purpose of the interlock which limits initial power prior to a pulse to a value lower than 1000 w? (2.0)

QUESTION E.05 (2.00)

A one-line diagram of the ventilation system for the Neutronics Laboratory, NEl-1 is shown in the attached figure. IDENTIFY the CWS filters, glove box, fume hood, butterfly valves, charcoal scrubber, and all supply and exhaust fans. (2.0)

QUESTION E.06 (3.00)

The Technical Specifications state six (6) automatic SCRAMS that must be operable in order to proceed with critical operations.

LIST these six (6) automatic SCRAMS and their set points. (3.0) l I

(*****CATEGORYE CONTINUED ON NEXT PAGE *****)

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PErlTil0VSE ROOF LEVEL o n o n E-14 E-6 E-21

) ROOF LEVEL

////>((///// / / .'// / /// ////// ///// / / / / / // / / / ,' // //

7. SECOND FLOOR LEVEL -

77 //////////// ////>

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U BEAM PORT

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TilROUGil- I L PORT % /

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EXPOSURE ROOM N 4* " REACTOR -

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LABORATORY \\

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Fig. 2.ls Exhaust and supply system for the neutronics laboratory fpp sto 672. E,os' I

E. SAFETY AND EMERGENCY SYSTEMS PAGE 12 e

j QUESTION E.07 (1.50)

According to Technical Specifications WHAT three (3) conditions must be met for the reactor to be considred secured? (1.5) 4 f

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(*****ENDOFCATEGORYE *****)

I

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 13 t

QUESTION F.01 (.50)

For reactor operations, above WHAT power level must the diffuser pump be turned on? (0.5)

QUESTION F.02 (1.00)

During a reactor startup or power increase, WHAT is the minimum allowable period and WHY? (1.0)

QUESTION F.03 (3.50)

a. HOW would you know (as a reactor operator) if an electric power failure had occurred? (0.5)

b. NAME six (6) actions required following such an occurrence. (3.0)

QUESTION F.04 (.50)

WHERE and at WHAT depth is the pool level alarm switch located? (0.5)

QUESTION F.05 (.50)

WHAT is.the allowable pre-pulse power range? (0.5) l QUESTION F.06 (.50)

WHEN should a shut-down check sheet be completed and noted in the log book? (0.5) i QUESTION F 07 (1.00) g 3 i

Auk WHAT two (2) reaetor system alarms are provided to the UC police i dispatch desk?- .(1.0) -

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(***** CATEGORY F CONTINUED ON NEXT PAGE *****)

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_ ._ _ ___. _ )

F F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 14 QUESTION F.08 (1.50)

WHAT are three (3) of the four (4) effects that must be estimated (calculated) prior to any modification of reactor geom 2try? (1.5)

QUESTION F.09 (.50)

HOW large must the fission startup count rate be before a startup may proceed? (0.5)

QUESTION F.10 (1.00)

HOW and WHEN are area radiation monitors tested for proper response to ionizing radiation.. (1.0)

QUESTION F.11 (1.00)

BRIEFLY DESCRIBE the method used to calibrate the linear power channel. (1.0) j QUESTION F.12 (2.00)

BRIEFLY LIST the classes of experiments conducted at UC Berkeley, how they are differ.entiated and the extent of approval for each. (2.0)

QUESTION F.13 (1.50)

You are operating the reactor at 100% power 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months into a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months experiment, when the secretary runs into the control room and tells i you that a " mob of students" carrying anti-nuclear banners are

! approaching Etcheverry Hall. STATE three actions that you are directed to take. (1.5) l

(***** END OF CATEGORY F **)

G. RADIATION CONTROL AND SAFETY PAGE 15 QUESTION G.01 (1.00)

WHAT is the objective of the Routine Swipe Program and WHY is the information of interest? (1.0) ,

QUESTION G.02 (1.00)

You are operating the reactor at full power when the Health Physicist informs you that the continuous air particulate monitor is not

)

functioning properly. WHAT are two (2) acceptable alternatives? (1.0)

QUESTION G.03 (1.00)

If two (2) centimeters of 'ead placed at a certain location in a narrow beam of gamma rays would reduce the gamma radiation level from 100 mR/hr.to 50 mR/hr, WHAT thickness of lead placed in the initial beam would reduce the gamma radiation level from

a. 400 mR/hr to 50 mR/hr? (0.5)

b. 50 mR/hr to 25 mR/hr?

(0.5)

QUESTION G.04 (2.50)

A small fixed cobalt source emits a radition level of 1 Rem /hr at a distance of 15 ft. If an operator requires one (1) minute to operate a valve located 5 ft from this source, HOW MANY times can he operate the valve before he receives a dose in excess of the 10 CFR 20 quarterly whole body exposure limit assuming he starts with no exposure? SHOW all work and assumptions. (2.5) l l

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(*****CATEGORYG CONTINUEDONNEXTPAGE*****)

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G. RADIATION CONTROL AND SAFETY PAGE 16 QUESTION G.05 (1.50)

GIVE an example of the following:

a. Penetrating tonizing radiation (0.5)

.b. Non-tonizing radiation (0.5)

c. Non-penetrating tonizing radiation (0.5)

QUESTION G.06 (.50)

WAT is the maximum unrestricted area dose that may be received in a one year period? (0.5)

QUESTION G.07 (1.50)

Relative to radiation incidents where a radioactive spill occurs; 1.e., contamination is present, WAT characterizes a Minor Incident?

GIVE three (3) characteristics. (1.5)

QUESTION G.08 (1.00)

HOW can you tell if your pocket ion chamber dostmeter is within its allowable calibration? (1.0)

QUESTION G.09 (1.00)

WAT does the acronym ALARA stano for? (1.0)

QUESTION G.10 (1.00)

WAT is the maximum dose (mrem) that visitors to the reactor facility who are under 18 may receive? (1.0) l

(***** CATEGORY G CONTINUED ON NEXT PAGE *****)

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G. RADIATION CONTROL AND SAFETY PAGE 17 QUESTION G.11 (2.50) .

NAME five (5) ways in which dose rates are maintained ALARA at the reactor. (2.5)

(

l

(*****ENDOFCATEGORYG *****)

(************* END OF EXAMINATION ***************)

l A. PRINCIPLES OF REACTOR OPERATION PAGE 18 I L

ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER A.01 (1.50)

Shutdown Margin shall mean the minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems, starting from any permissible ~

operating conditions and that the reactor will remain subcritical without further operator action. [+1.5]

REFERENCE

1. Berkeley: Technical Specifications, p. 2.

ANSWER A.02 (3.50)

a. ~

6, .tt,a e v. ,s e: <-

A s u tt.,t t.]

. s.. ~

z., . :.

$ N stie s A M ia:ty T IllE

b. The reactor is initially on an infinite period. After the reactivity manipulations power is increasing on a positive period. This implies that the negative insertion is of less magnitude than the positive insertion. [+1.0]

c. This is the response immediately after the negative insertion l of reactivity has been terminated. ~ During this time the delayed neutrons are coming to a new equilibrium resulting in a stable l positive period. [+1.5]

REFERENCE

1. Berkeley: Syllabus and TRIGA Training Manual, "GA Technologies,"

p. 6-12.

l

.---c -- -- - , - ~ - - ,--,--,------,...--,.-.--,,---,-,--,.,n, . - , -.- -,n.----. - - , - , -- ,,--

A. PRINCIPLES OF REACTOR OPERATION PAGE 19 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER A.03 (1.50)

~

False. [+0.5] The instantaneous delayed neutron fraction would be decreasing because of the non-equilibrium between prompt and delayed .

neutrons indicated by the changing period. [+1.0]

REFERENCE

1. Berkeley: Syllabus and TRIGA Training Manual, "GA Technologies,"

p. 6-13.

ANSWER A.04 (1.50)

P(1) = P(o) e**t/T 2 = e**t/T T = t/In2 = 10/0.693 = 14.4 seconds

[+1.5]

REFERENCE

1. Berkeley: Syllabus and TRIGA Training Manual, "GA Technologies,"

Section 6.

ANSWER A.05 (2.00)

The magnitude of the prompt drop is dependent upon the amount of negative reactivity that is inserted. The countiate above and beyond that due to delayed neutrons alone is caused by subcritical multiplication of the delayed neutrons. If an infinite amount of negative reactivity was inserted, then Curve A would fall immediately to Curve B upon Rx trip. [+2.0]

REFERENCE

1. Berkeley: Syllabus and TRIGA Training Manual, "GA Technologies,"

Section 6.

l l

A. PRINCIPLES OF REACTOR OPERATION PAGE 20 i -

ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER A.06 (2.00)

a. The change in reactivity associated with a change in pool temperature. [+1.0]

b. Positive. [+0.5]

c. False. [+0.5]

REFERENCE

1. Berkeley: GA Training Manual, p. 6-28.

ANSWER A.07 (2.00)

Following a rapid reactivity insertion, the fission rate increases generating additional prompt neutrons, and causing the reaction rate to begin to diverge on prompt neutrons alone. Since the system is actually subcritical on prompt neutrons, it must wait for the delayed neutron groups to contribute their necessary fraction causing the power increase to continue at a much more gradual rate. [+2.0]

, REFERENCE

1. Lamarsh, J.R. " Introduction to Nuclear Reactor Theory,"

p. 427.

1 I

B. FEATURES OF FACILITY DESIGN PAGE 21 4

ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER B.01 (1.00)

(b.) [+1.0]

REFERENCE

1. Berkeley: Safety Analysis Report for the University of California Berkeley Research Reactor,'p. 3-31.

ANSWER B.02 (2.00)

1. Regulating Rod - C ring

2. Shim Rod - D ring

3. Safety Rod - D ring

4. Transient Rod - C ring

[+0.5] each REFERENCE

1. Berkeley: SAR, [p. 3-12 and Figure 3-12.

ANSWER B.03 (1.00)

a. The regulating rod has a fuel follower whereas the transient rod has a hollow follower section. [+1.0]

b. A dashpot on the control shaft. [+1.0]

REFERENCE I 1. Berkeley: SAR, Figure 3.6.

~

2. Generic: Syllabus and TRIGA Training Manual, GA Technologies,

pp. 1-22.

i i

i

B. FEATURES OF FACILITY DESIGN PAGE 22 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD,J.

ANSWER B.04 (1.50)

1. Maintain low conductivity of the water to minimize corrosion of reactor components, particularly fuel.

2. Reduces radioactivity in the water by removing nearly all particulate and soluble impurities.

3. Maintains optical clarity of the water.

4. Provides a means of dissipating the heat generated in 'the reactor.

5. Circulate water to fission product monitor.

Any three (3) [+0.5] each, +1.5 maximum.

REFERENCE

1. Berkeley: Safety Analysis Report for the University of California Berkeley Research Reactor, p. 3-30.

ANSWER B.05 (1.00)

Any apparatus, device, or material which is not a normal part of the core or experimental facilities, but which is inserted in these facilities or is in line with a beam of radiation originating from the reactor core; or any operation designed to measure reactor parameters or characteristics. [+1.0]

REFERENCE

1. Berkeley: Technical Specifications, p. 2.

i ANSWER B.06 (2.00)

a. 5

b. 2

c. 10

d. 8

[+0.5] each I

f

8. FEATURES OF FACILITY DESIGN PAGE 23 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

REFERENCE

1. Berkeley: SAR, Figure 3.12.

ANSWER B.07 (2.50)

See the attached figure.

REFERENCE

1. Berkeley: SAR, Figure 3.9.

ANSWER B.08 (2.00)

The end sections of the fuel rods are made of graphite, this provides axial reflection. [+1.0] Radial reflection is provided by a graphite jacket enclosed in aluminum surrounding the core. [+1.0]

REFERENCE

1. Berkeley: SAR, Figure 3.5.

mn y

S110CK ABSORBER l

' VENT ll0LES =i m /

{

. ,43 .

. EXTERNALLY . .

. . TilREADED CYLINDER

=

PISTO,N SUPPORT

. O I I r

T' , , , , ,

y , ,

". L._ _ l I II

!__J BEARINGS

/

f WJ M~ VIORM BAR NUT WORM GEAR

* # ~

I_ = Il0VSillG n o- .

PISTON ROD - -* VENT

SUPPLY AIR SUPPLY 1103E

SOLEN 01D VALVE s,

=

ONNECTION TO BOTTOM LIMIT -

CONTROL ROD .

> . (MI-37)

Y

Fig. 3 9 Schematic drawing of transient-rod drive s ,

{ (dr] sun (c T 07 .

l

C. GENERAL OPERATING CHARACTERISTICS PAGE 24

~

ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER C.01 ,(1.00) '

a. See Figure attached. [+1.0] -

b. The power coefficient increases in magnitude, i.e. the power -

defect increases for any power level, as the number of pulses increases [+0.5]. The changes are due to the themal cycling of the fuel [+0.5] which results in a decreased thermal conductivity of the gap [+0.5]. This results in a higher fuel temperature for a given power level [+0.5] and due to the negative temperature coefficient, a larger decrease in reactivity for a given power level [+0.5].

+2.0 maximum REFERENCE

1. Berkeley: Safety Analysis Report for the University of California Berkeley Research Reactor, pp. 5-5, 5-6, and Figure 5.2.

ANSWER C.02 (2.00)

1. safety rod 2.5$

e la ng rod fh MMy M P i

4. transient rod '

I' N I [+0.5]each

! REFERENCE

1. Berkeley: Safety Analysis Report for the University of California Berkeley Research Reactor, p. 3-13.

I I

I s

t

F ANSWER C.01 a I 3 'i ll I ll l l l Il f ll

{l I I I '

'l 'i l I

iI l I

! !l ll ! I l l l

l! ll 4.00 1 I !

l ! I il ll l!!

I ! i

[ t l -

! I I 91 l I

l N l l !

l .

I I

l l I .

.;/ll$l l lL l i i

ll l :

/ ' l l' }

I l

! , lli -

,i i l lk l l l j'" Y '

4 , -

IL q i

i j i .!lij n

[ } .

.1 l l ,

~

p I , j.

1l1

>- f ,1 l - l

{ l-l- .. I i l I i l i l l l ll1 l l l

l !

l l 2.00 l I I

' f

d. : -

lIl I l '

l l 1 l

l

, ' l l lh'fgf E ' I l l i I l l Il ll l l l l l' .l .I !.. . ,

I

. l l i f ; l l I ! l ,

l l j it I

l . l i I

l' : l tX I l l !

ll, .l ! I i !! l !! ll [

1. 00 . ' -

i h,! I I i j j .

I

.j J, l I '

! ; l fl , ll l 'i f l !

I l l ?

I l

.1(i

. I l'

l l l lll l I 'l l l l l I! il i l

j I il! '

I I .lhlld! ;;l

.i i .!

j'F j l ' i ll , II ; T' i I li' ,

' I!'

! ! l lI l l I l j !

iJ l ..llm_,!; ! i!I 0 . .. l l i ilti il 0 200 400 600 800 1000 1200 1400 . 1600 iteactor Power, kilowatts Reactivity loss verous reactor' power-prototype reactor U gure c.01. (ANSWER)

C. GENERAL OPERATING CHARACTERISTICS PAGE 25 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER C.03 (2.50)

1. cell and inhomogenities

2. Doppler

3. core leakage The cell and inhomogenities effect is the largest.

The core leakage effect is the smallest.

[+0.5] each REFERENCE

1. GA: TRIGA Training Manual, GA Technologies Inc., Chapter 6, para. 6.2.3.

ANSWER C.04 (1.50)

a. 111

b. iv

c. 11

[+0.5] each REFERENCE

1. Berkeley: SAR, pp. 5-7 through 5-9.

l 2. Generic: Instruction Manual for the TORREY PINES TRIGA REACTORS, Consideration of Pulsing Characteristics, p. 6-31.

ANSWER C.05 (1.50)

Because the fuel elements will rapidly cool off, potentially inserting several dollars worth of poisitive reactivity. This could result in an uncontrolled power excursion. [+1.5]

REFERENCE

1. Berkeley: Operation Manual, p.5.

2. Generic: Triga Training Manual, GA Technologies, Figure 6.18.

C. GENERAL OPERATING CHARACTERISTICS PAGE 26 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER C.06 (.50)

True. [+0.5] (The technical specification definition states equilibrium samarium, however, there would be no way to achieve .

equilibrium samarium at low power ((40 deg F) without being xenon free.) ,

REFERENCE

1. Berkeley: Technical Specifications, p.1.

ANSWER C.07 (2.00)

N 0E e,*on v e r % - -

h tA %petstore.

/ -

I

/

11nt Note: Sketch must show temperature continuing to rise to a factor of approximately 2 times that at the time of the peak.

REFERENCE

1. Syllabus and TRIGA Training Manual, GA Technologies, p. 6-31.

ANSWER C.08 (1.00)

Decrease. [+0.5] The core has a negative void reactivity coefficient.

I

[+0.5]

REFERENCE

1. Syllabus and TRIGA Training Manual, GA Technologies, p. 6-22.

4

-%., -----_.mm--.-. - ,--, - _ _ _

D. INSTRUMENTS AND CONTROLS PAGE 27 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER D.01 (1.00)

The intensity of the neutron at the signal range of this instrument (2 to 100+%) ovemhelms the included si nal from the gamma flux making compensation unnecessary. [+1.0 REFERENCE

1. Berkeley: Safety Analysis Report for the University of California Berkeley Research Reactor, pp. 3-8, 3-20.

ANSWER D.02 (3.00)

UP DOWN CONT

a. OFF OFF OFF '+0. 6'

b. ON OFF ON '+0. 6'

c. OFF OFF ON '+0. 6'

d. OFF ON ON '+0.6'

e. ON OFF- ON l+0.6l

(+0.2 for each element of an answer)

REFERENCE

1. Syllabus & TRIGA Training Manual, GA Technologies Inc., REACTOR INSTRUMENTATION AND CONTROL CIRCUITRY, pp. 2-9 through 2-14.

ANSWER D.03 (1.00) pp7 ,

The regulating and the ro . [+1.0]

REFERENCE

1. Berkeley: Technical Specifications, p. 3.

D. INSTRUMENTS $D CONTROLS PAGE 28

~

ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD,'J.

ANSWER D.04 (3.00)

a. Ring C. [+0.5] The instrumented fuel rod is located in the inner regions of the core where neutron flux, and therefore fission rate, are the highest. [+1.0] -

b. To ensure that fuel rod internal pressure is, within limits to prevent a loss of fuel element cladding integrity. [+1.5]

REFERENCE

1. Berkeley: SAR, Figure 3.12.

ANSWER D.05 (1.50)

a. ulse peak power Integrated pulse power ) Aewon-e wf curtoc sb euob,

b. Fuel temperature

[+0.5] each REFERENCE 1.- Berkeley: SAR, Figure 3.11.

ANSWER D.06 (2.00)

Neutron count rate is sensed in the outer can by interaction with boron paint. Gamma radiation is sensed in both the outer can and inner can. The lack of boron paint in the inner can causes only gamma interactions to take place. A compensating voltage is applied i

to the inner can to exactly balance the gamma current being sensed in the outer can. [+2.0]

REFERENCE I

1. TRIGA Manual, p. 2-39 and 2-40.

ANSWER D.07 (3.00)

See attached figure. (Grade +0.2 for each correct component shown on attached figure, up to +3.0.)

i l

FISSICM PRE-COUNTER AMPt.!FIER L

- AMPL!FIER -

- ~ ~ ~"'I COUNT RATE -

g -4 SOURCE INTERLOCX l COUNTER l

L.- Q WITHORAW k _. I.1D0,,R AJ,,,,,A,y,4OjN)gl,$,JgA!.,,,, _ __ _ _ _ .

(ORIVE j .,

(

\ LOG N .

1 COMPENSATED ION LOG R RECORDER CHAMBER AMPLIFIER PERIOO CIRC'JIT f -

l . . .

COMPENSATED ION * .

CMAMBER AM FIER -

p i v -

{ LINEAR PWR

[

y ,{ RECORDER .

i * '

I SCRAM

! Td ROOS j ION POWER-LEVEL I

gp -> -

I CHAM 8ER MONITOR *

gpg,gg I

I

~~~

L__f _

1 POWER - DEMANO P FIER l } - - - - - - - - - _. ._{,, A j, L_ _ _ _ !

i Fig 3.10 Block diagram of reacto~r inst: 2nentatien for steady-state operation

QA) S u) E~9 h . 64. . --

I i

1 ,

E. SAFETY AND EMERGENCY SYSTEMS PAGE 29 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER E.01 (1.50)

1. Reactor console

2. Air monitoring equipment ,

3. Radiation monitors

4. Scrubber fan (glove box fan)

5. Lights in reactor room Any three (3) [+0.5] each, +1.5 maximum REFERENCE

1. Berkeley: Safety Analysis Report for the University of California Berkeley Research Reactor, P. 2-8.

ANSWER E.02 (2.00)

1. Any of nine (9) area radiation monitors

2. Stackgas radiation monitor

3. Air-particulate monitor

4. Water-radiation monitor

[+0.5each]

REFERENCE

1. Berkeley: EMERGENCY PROCEDURES, 4.8.2, p. 72.

l ANSWER E.03 (1.00)

Alarm, 930 deg Safety limit, 1830Fdeg (500 deg(C)

F 1000degC)

[+0.5] each REFERENCE

1. Berkeley: Technical Specifications, p. 6.

i i

pef 1THOUSE_ ROOF LEVEL E-14 E6 E-21

_ J J ROOF LEVEL

///f f//// / //.'////// ////// ///////////////,' // //

k-- SECOND FLOOR LEVEL u n n//,///n / n i,-

-%.6N% .

O Nd

~# ' BEAM PORT T THROUGH- I PORT % /

y) l / EXPOSURE ROOM GWS THERMAL

_. FILTERS COLUMff , REACTOR -

/ NEUTRONICS '

\

'\

l LABORATORY \

NE l-l

~

ll=

'SARCOAL g _'

C

" , l .,,-SCRUBBER _

(I.)

GLOVE (2) CWS FILTERS

/. ci Lo4~ box (, 2 ]

2 , C. t a S F st T M $ ( .Y 3, C k cc4c.1estuBoets ( 2) tl, ctoS Fn- M s ( L)

f. F'1*E' *06 (

L)

G*

"?N!f,(j{@)'f,)(L)

7. 1dh v pe] (, 2.) .

3

Al&h ext / Hos E-/V c-s (. </) ,, .

. EMERGENty'F.xt pgs e- hD+(, z) '

If

E. SAFETY AND EMERGENCY SYSTEMS PAGE 30 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER E.04 (2.00)

If this pulse were fired with the reactor already at a high steady-state power, heat would already be present in the fuel. Upon pulsing ,

another large amount of heat (typical full pulse results in 400 to 410 deg C) would be added to the already heated elements. There is the the distinct possibility of exceeding DNB and causing cladding burnout.

The pulse interlock prevents this from occurring.

REFERENCE

1. Syllabus and T.RIGA Training Manual, p. 6-29.

ANSWER E.05 (2.00)

See attached figure. (Each answer +0.5; +2.0 maximum)

REFERENCE

1. Berkeley: SAR, Figure 2.4.

ANSWER E.06 (3.00) '

g7

\

Set Point f)(

1. Linear power level -110%

2. Safety power level -110% of selected scale

3. Log power, period ( 3 seconds

4. Linear and safety detector Loss of power power supply

5. Preset timer SCRAM secondsak a pulse TVU TcDT%pp)LN

6. Earthquake detector Detection of horizontal acceleration

[+0.5] each group REFERENCE

1. Berkeley: Technical Specifications, Table 1, p. 12.

I I

L

E. SAFETY AND EMERGENCY SYSTEMS PAGE 31 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER E.07 (1.50)

The reactor is secured when all the following conditions are satisfied: ,

a. The reactor is shut down. [+0.5]

b. The console key swtich is in the "off" position and the key is removed from the console and stored in a locked cabinet. +0.5]

c. No work is in progress involving in-core fuel handling or refueling operations, maintenance of the reactor or its control mechanisms. [+0.5]

REFERENCE

1. Berkeley: Technical Specifications, p. 1.

l l

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 32 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER F.01 (.50)

Powers greater than 100 kW. [+0.5]

REFERENCE -

1. Berkeley: Operations Manual - BRR - June 1986, p. 3.

ANSWER F.02 (1.00)

Twelve (12) seconds [+0.5]. This minimum is specified because more rapid rates (shorter period) would require very fast operator responses with a high possibility of a loss of positive operator control [+0.5].

REFERENCE

1. Berkeley Operations Manual - 3RR - June 1986, p. 3.

l l

i

r e

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 33

~

ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER F.03 (3.50)

a. A reactor scram with back up indication (check with campus -

patrol-digital clock or computer loss). [+0.5]

b. Any six (6) of the following list:

1. Check batteries of emergency light in reactor room.

2. Reset emergency light in the reactor office.

3. Check with UCPD and reset all UCPD emergency alarms.

4. Ensure proper operation of stackgas computer in the reactor office.

5. Check and reset all radiation monitors and alams.

6. Note power failure on all radiation monitor recorders (stackgas analog and digital recorders and air particulate recorder).

7. Check building air pressure.

8. Redo daily startup check list if continued reactor operation is required.

9. Note power failure in logbook,

[+0.uj each, +3.0 maximum REFERENCE

1. Berkeley: Operations Manual - BRR - June 1986, p. 8.

ANSWER F.04 (.50)

'l- fdtT A00VG' ToPJf Cat 7 At the northwest corner of the pool approximately 1 Meet below-the normal _ water _ surface-level of-the-pooh [+0.5]

REFERENCE

1. Berkeley Operation Manual--BRR--June '86, p. 11.

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 34 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER F.05 (.50) ,

Between 3 and 100 w. [+0.5] O S** 4' ' # # ' '~

REFERENCE /NTC/L t.ocX frR <jgo) *

1. Berkeley: Operation Manual--BRR--June '86, p. 5.

ANSWER F.06 (.50)

At the end of each operating day (not required for each scram). [+0.5]

REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, p. 7.

ANSWER F.07 (1.00)

Iow pool water level AF M 40& A 1.

2. , bum-water-temperature-Mgh- @ Dood /)vMui

RAb Amaned

[+0.5]each REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, pp. 11 and 12.

ANSWER F.08 (1.50)

1. shutdown reactivity

2. core excess reactivity

3. rod worth

4. reactivity insertion rate Any three (3) [+0.5] each, +1.5 maximum.

REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, p. 14.

l

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 35 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER F.09 (.50) greater than 2 cpm [+0.5]

REFERENCE -

1. Berkeley Operations Manual--BRR--June '86, p. 2.

ANSWER F.10 (1.00)

The area radiation monitors are source checked at 3 radiation levels

[+0.5] during an annual response check [+0.5].

REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, p. 42.

ANSWER F.11 (1.00)

A rate of temperature rise (calorimetric) on the reactor pool is performed at 1 MW with the pool secondary cooling turned off. [+1.0]

REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, p. 47.

I

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 36 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD,J.

ANSWER F.12 (2.00)

These are four classes of experiments as follows:

Class Experiment Extent Approval -

A low hazard, very small changes Reactor Supervisor, in reactivity, no fissionable HP review materials B medium hazard, 3x class A Reactor Supervisor, l reactivity change, limited HP review, written fissionable material, no specifications required ionizing beams allowed C major changes in core and Reactor Supervisor, shielding configuration-- hazards committee, HP no Tech. Spec. changes review, specs and procedures required D experiments requiring a Reactor Supervisor, Tech. Spec. change to hazards committee, perform DRL-NRC

[+0.5] for each part.

REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, pp. 52-55.

ANSWER F.13 (1.50)

Z i 1. scram the reactor a#.iecure on-going experiments M notify campus police 4 4ctW4v oon 4wt g evacuate and lock the first floor reactor complex

[+0.5]each REFERENCE

1. Berkeley: Operations Manual--BRR--June '86, p. 62.

i r

l

G. RADIATION CONTROL AND SAFETY PAGE 37 ANSWERS -- UN'IVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER G.01 (1.00)

The objective is to determine surface contamination levels within the BRR complex. [+0.5]

The information is used to control unknown contamination and to demonstrate regulatory control. [+0.5]

REFERENCE

1. Berkeley: BRR Radiation Protection Manual-Section RP-34-4.

ANSWER G.02 (1.00)

1. Scram the reactor [+0.5] -

2. Immediately establish beta-gamma instrument surveillance [+0.5]

REFERENCE

1. Berkeley: BRR Technical Specifications, p. 13.

ANSWER G.03 (1.00)

a. 6 cm '+0. 5'

b. 2 cm .'+ 0.5.'

REFERENCE

1. Generic: Radiation Shielding, B.T. Price et al.,1957, pp. 36

, and 37.

I

G. RADIATION CONTROL AND SAFETY PAGE 38 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER G.04 (2.50)

Assumpticos are as follows:

1. the quarterly whole body dose is 1.25 rem .

2. It can be considered a point source

3. onlygammaradiationisconsidered-(thisassumptioncanbe implicit)

4. the operator has no dose this quarter The dose rate at 5 ft will be:

1 rem /hr x 1 hr/60 min x (D(1)**2/(D(2)**2 or 1000 mR/hr x 1 hr/60 min x 15**2/5**2 = 150 mR/ min since it requires one minute to manipulate the valve, the maximum number of operations to reach the quarterly limit is:

1250 mR/150 mR = 8.3 1

or 9 operations will cause him to exceed his quarterly limit. [+2.5]

REFERENCE

1. Berkeley: Radiological Health Handbook, p. 32.

ANSWER G.05 (1.50)

a. gamma, beta r neutron [+0.5] (any one)

b. light +0.5 l c. alpha .;+0.5.;

I REFERENCE

1. Enge, " Nuclear Reaction and Radiation", p. 22.

l 3

G. RADIATION CONTROL AND SAFETY PAGE 39 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER G.06 (.50) 500 mrem [+0.5] '

REFERENCE

1. BRR: Radiation Protection Manual, p. 3-2. '

1 ANSWER G.07 (1.50)

1. contamination of equipment or small section of lab

2. no health hazards

3. no abnormal conditions beyond reactor lab

[+0.5] each REFERENCE

1. Berkeley: Emergency Procedures, p. 69.

. ANSWER G.08 (1.00) l It will have a calibration sticker on it dated within the last six (6) months. [+1.0]

REFERENCE

1. BRR: Radiation Protection Manual, PRP-34-7.

l l

ANSWER G.09 (1.00)

As Low As Reasonably Achievable. [+1.0]

REFERENCE 1.

l i

l

..,.v G. RADIATION CONTROL AND SAFETY PAGE 40 ANSWERS -- UNIVERSITY OF CALIFORNIA -86/09/03-HUENEFELD, J.

ANSWER G 10 (1.00) 500 arem/yr [+1.0]

REFERENCE

1. BRR: Radiation Protection Manual, Section 11, p. 1-2.

ANSWER G.11 (2.50)

1. protective clothing kett

2. work surface coverings

3. radiation detection equipment

4. caution / warning signs

5. mouth pipetting prohibited W ', } W 7 g g ; $#D O _

6.

7.

no eating / smoking in isotope area good housekeeping fh// M , A

8. experimenter training Any five (5) [+0.5] each, +2.5 maximum.

REFERENCE

1. BRR: Radiation F3tection Manual, Section 11, p.1-2,3.

I

ML20214V764

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