IR 05000005/1989002

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Exam Rept 50-005/89-02OL on 890522-23.Exam Results:Both Reactor Operator Candidates Passed Written & Operating Exams
ML20247N089
Person / Time
Site: Pennsylvania State University
Issue date: 07/24/1989
From: Eselgroth P, Denise Wallace
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20247N087 List:
References
50-005-89-02OL, 50-5-89-2OL, NUDOCS 8908020274
Download: ML20247N089 (92)
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' U.S. Nuclear Regulatory Commission Region I OPERATOR LICENSING EXAMINATION REPORT-EXAMINATION REPORT NO.: 89-02(0L)

FACILITY DOCKET NO.: 50-05 FACILITY LICENSE NO.: R-2 LICENSEE Pennsylvania State University FACILITY: Pennsylvania State Breazeale Reactor EXAMINATION DATES: May 22 - 23, 1989 CHIEF EXAMINER: I David Wallace a 7-W '6f Date Operations Engineer / Examiner APPROVED BY: g# N Peter W. Eselgro , Chief Date PWR Section, Op tions Branch Division of Rea tor Safety SUMMARY: Written and operating examinations were administered to two Reactor Operator (RO) candidates. Both candidates passed their examination kh V

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TYPE OF EXAMINATIONS: Reactor Operator (RO) written and operatin i EXAMINATION RESULTS: Both candidates passed the examination ) Chief Examiner: David Wallace It was noted during the oral examination that the candidates were not familiar with event classifications as described in the Emergency Pla Although it is the duty of a Senior Reactor Operator to classify an event, it was agreed that the Reactor Operator should have some knowledge of these classifications. The Reactor Supervisor stated that a minimal amount of training could adequately address the concerns; the examiner agreed. No other concerns were identifie Attachments: Written Examination Examination Answer Key I

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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 1 FACILITY: Pennsylvania State Uni REACTOR TYPE: TRIGA III DATE ADMINISTERED: 59/05/22 INSTRUCTIONS TO CANDIDATE:

Use separate paper for the answer Write answers on one side onl Staple question sheet on top cf the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each categor Examination papers will bo picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE_ TOTAL SCORE VALUE CATEGORY 14.50 14.50 PRINCIPLES OF REACTOR OPERATION 14.50 14.50 FEATURES OF FACILITY DESIGN 14.50 14.50 GENERAL OPERATING CHARACTERISTICS 14.50 14.50 INSTRUMENTS AND CONTROLS 14.00 14.00 SAFETY AND EMERGENCY SYSTEMS 14.50 14.50 STANDARD AND EMERGENCY OPERATING PROCEDURES 13.50 13.50 RADIATION CONTROL AND SAFETY 10 % TOTALS FINAL GRADE All work done on this examination is my ow I have neither given nor received ai Candidate's Signature

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NRC' RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l-During the administration _of this examination the_following rules apply:

1 ' Cheating.on the examination means an automatic' denial _of your application end could_ result in more severe penaltie l2 .Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with.anyone outside the examination room to avoid even the appearance or possibility of. cheating.

' Use black ink or dark pencil only to f acilitate legible reproductions.

E'4, Print your name in the blank provided on the cover sheet of the examinatio . ' Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer , Print your name in the upper right-hand corner of the first page of each section of the answer shee . 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 shee . Number _each answer as to category and number, for example, 1.4, . Skip at least three lines'between each answe . Separate answer sheets from pad and place finished answer sheets face down'on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . 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 require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl '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 examinatio This must be done after the examination has been completed.

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18. When you complete your examination, you shall:

a .- Assemble your examination as follows:

(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part or the answe Turn in your copy of the examination and all pages used to answer the examination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examiner. If after leaving, you are found in this aiea while the examination is still in progress. :rour license may be denied or revoke _ _ - _ - _ - _ - - _ - _ - _ - _ _ - - - _ _ - . - -

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go PNINCIPLES OF REACTOR OPERATION Page 4 QUESTION A.01 (1.00)

At approximately what minimum power level, in kW, does the Negative-Temperature Coefficient become significant for the POBR7 l

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,- . . PRINCIPLES OF REACTOR OPERATIO,N Page 5 QUESTION A.02 (1.00) ,

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-Over a period of time while the reactor is operating in the j automatic mode at 800 kW, the fuel temperature increased from '

400 degrees to 405 degrees Assuming the temperature l coefficient for the reactor is -1.4 x 10**-4 delta k/k/ degrees C, i the regulating rod is worth 0.1% delta h/k/ inch, and none of l the other control rods mov How far would the regulating rod move to compensate for the I temperature change? (0.75) In WHAT direction would the regulating rod move? (0.25)

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c::- -QUESTION' A.03 -(1.50)

-Tha major contributing factor to.the negative temperature coefficient

' is : '.' cell ef f ects . " . EXPLAIN HOW and WHY cell effects contribute t:> the-

, inegative temperature-coefficient.'

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' QUESTION A.04 (1.50)

. State the TWO production mechanisms for Xenon-13 (1.0) How long after a shutdown from extended power operation will Xenon reach its peak? (0.5)

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. PNINCIPLES OF' REACTOR OPERATION Page 8 QUESTION A.05 (1.50)

What is the period that would cause the PSBR power to double in 69 seconds? (show your work)

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4 P INCIPLES OF REACTOR OPERATION Page 9 QUESTION A.06 (1.50)

c. What is the startup neutron source used at the PSBR7 (0.5)

b. Why is a startup neutron source used in the reactor? (1.0)

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g 7 QUESTION ~ A.07' (l'.00)

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~ EXPLAIN WHY, during a reactor startup using pull and wait, as contro?.

rods are withdrawn,-.it takes longer between each control' rod pull for the count rate multiplication ~to level ou ,

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l L-( QUESTION A.08 (1.50) Explain the importance of delayed neutrons in the operation of the-PSBR.

[ Why is Beta-effective larger than Beta for the PSBR7 (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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TQUESTION.: A.09 (1.50)'

Tha~locationof.'thefuelNeing.added, detector' location, and'

.nsutron source' location'are factors:that:should be considered 7duringfa critical: mass-experiment. :The ideal arrangement is Jonotwhere the location of the fuel"beingladded is between the nsutron'. source.an'd the detecto Why'cis:: this the ideal'

Terrangement?

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A- PItINCIPLES OF REACTOR OPERATION Page 13

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QUESTION A.10 (2.50)

List FIVE reactivity effects that can affect reactivity within the rcacto i (***** END OF CATEGORY A *****)

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' .; F5ATURES OF FACILITY DESIGN Page 14 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

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. e FIATURES OF FACILITY DESIGN Page 15 QUESTION B.01 (2.50) Ilow is the reactor bay area maintained at a negative pressure with respect to the atmosphere and the remainder of the building during normal operation? (0.5) How does the ventilation system respond to a building evacuation alarm? (1.0) List the components, in order of flowpath, encountered in the emergency exhaust syste (1.0)

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QUESTION B.02 (1.50) What is the purpose of the aluminium safety plate? (1.0) Where, in relation to the reactor core, is the safety plate located? (0.5)

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iQUESTION' B.03' (1.50,)L

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'What is(the purposo of'the 10-minute time' delay relay in'the-

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i FEATURES OFFFACILITY DESIGN :Page 18

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+:2 (QUESTIONL IB,04 (2.00)-

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~ List lFOUR functions that the reactor pool performs during reactor

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  • . . FIATURES OF FACILITY DESIGN Page 19

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! . QUESTION B.05 (1.50)

Sttte the TWO purposes of the triangular spacer blocks on the upper cnd of the fuel elements.

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FACILITY DESIGN Peco 21 l

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QUESTION.- fB.07 (3.00)

.: [Idrutify THREE ways for adding ~ water to the reactor pool, Consider

? both normal'and abnormal' conditions. Include'the water source, flowpath,: and.any,special hookups in your answer, t

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I .. QUESTION- B 0 .'(1.50)

jWah,IWhatL:in.thepurpose.of'the'N-16:diffusersystem? (0.5)

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C. * GEN RAL OPERATING CHARACTERISTICS Page 23 s .

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JC'.NGEN5RALL'OPERATINGTCHARACTERISTICS Page 24

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.. . i. QUESTION-, 1C.01 (2.50) ra

Stdtoiwhether each ofzthe following;have'a. POSITIVE or NEGATIVE

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ir;tetivity worth with~ respect'to wate ?db.'D20 tank'at/southc' ore' positio ~

a lb..LRCA tubelat the'B-9 core-position, c..-Rabbit:II/ bare at the E-11 core positio td; Graffite reflector at the-core periphery i L1 51 cc' air' void(0.66% void) at the C.T. core.. position'.

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x L 'iGEN$RAL OPERATING CHARACTERISTICS Page 25 s.

QUESTIO C.02 (2.50)

La. "One reactivity.effect ofiaLmassive leak of D20 from the D20 tank

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circulated throughlthe core is an-increase in the'k/ infinity of

' core due:to the lower neutron absorbtion crossection of D2 :Briefly describe the other reactivity effect of the massive D20 Lt'ank leak AND include the'overa11'effect on core excess reactivit (1.5)

-b. 'With the reactor operating in standby and the D20. tank positioned against-the reactor, what would.be the effect on

.the countrate if.the boral plate'on the top of the tank was removed?. Include-in your answer the reason for the change 11n countrat (1.0)

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< ; ,. o (QUESTION. 'C;03: (1.00)

Whtn;.the mode switch is,in' AUTOMATIC, whatils the approximate

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period: control' setting that power changes are usually made? -

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LQUESTION- C.04' (1.50)

- In the lower'suberitical. range.of a reactor-start-up, the reactor 1

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l::: operator observes an increase in neutron; population on the' log L-Lcountirate recorder,' but notices there is not a corresponding baindication;on::the" period mete Assumin'g.NO equipment malfunction, E

y Lwhat . is .the reason f or this : observation?

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..Ci'G ENEitAL' OPERATING CHARACTERISTICS Page 28' ;

QUESTION" C.05 -(1'.50)L Why'will.the' percent' power meter increase.by 1 to 2% from its initial'

- randing-during.the hour or<two of operati n after reaching 1 MW from n Xenon-free core condition reactor start-up?

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1-QUESTION- C;06 (1-.50)

. t Thn: removal of an experiment and'a. change in:the Xenon concentration ov:ar time hasJincreased the. source. range ~ indication to 196 CP ' CALCULATE. inLdelta-K/K, the1 reactivity contribution from Xenon for iths following reactor' conditions: (Show all' work and assumptions)-

Jc . Initial" startup' channel -indication :is ~ 100 CPS

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iSafety. rod is fullyLwithdrawn

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Current reactivity present in the core is minus 4% delta-K/ '

The experiment-has-a reactivity worth of minus $1.43

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- OPERATING CHARACTERISTICS Page 30 QUESTION C.07 (2.00)

With the reactor critical at 30 watts, the reactor operator withdraws tha regulating rod a small amoun Immediately after rod withdrawal o doubling time'(DT) of 24 seconds is recorde a.- A suming the effective decay constant (lambda) is 0.1 see-1, calculate how much reactivity was added to the core by the reactor operator? Show all wor Aosuming NO operator action and no additional rod motion, HOW and WHY would subsequent DTs change?

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.C. ' GENERAL ~ OPERATING-CHARACTERISTICS- Page 31

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-QUESTION 1 C.08l .(2,00.)..

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-How (INCREASE, DECREASE, NO EFFECT) will the actual shutdown margin of,tho reactor be:affected by the following events or conditions?

LCongider'each separatel .de " Reactor power is increased from 10% to 100% powe ; A used fuel assembly is replaced by a new fuel assembl 'c;;.. .

During a reactor startup,'a' neutron source of twice the strength'

(identical substance) is.use "d. . gTwo hours after a scram that.was preceeded by 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />'of-100%

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D. * INSTRUMENTS AND CONTROLS Page 33

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QUESTION D. 01 (1.00)

When the radiation monitor Jocated on the Rabbit I panel in the reactor bay alarms, what TWO actions automatically occur to minimize gas leakage to the building?

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<4 D.*~ INSTR 0MENTS AND CONTROLS Page 34

. QUESTION D.02 (1.50) What components provide for the shim or safety control rod position indication?

(0.5) What does the CONT light on the consolo indicate when lit? (0.5) What causes the DOWN light on the console to illuminate? (0,5)  ;

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QUESTION D.03 (2.00)

l.Lict the FOUR neutron detecting channels and STATE the type of dat:ctor associated with each channel.

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IQUESTION D.04 (2.00)

i c', - A signal from the count rate channel amplifier goes to the low count rate histable. What is the purpose of the low count rate bistable? Include in your answer the setpoint associated with this bistabl (1.0)

What power level, in watts, corresponds to the upper limit of count rate channel indication? (0,5) At what power level will the count rate channel detector withdraw from the core? (0.5)

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'What are THREE of the four input signals to the Power Regulation

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D.' ' INSTRUMENTS AND CONTROLS Page 38

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.. QUESTION 'D.06' (2.50) What are the TWO different types of pool tempere.ture detectors

.used to determi',e pool temperature? (1.0) i

. State the TWO reasons for the reactor pool temperature limi (1.5)

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QUESTION D.07 {1.00)

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What TWO conditions must be met to enable the TRANSIENT RCD FIRE button? Assume the PSBR is operating at.750 watts steady stat .

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-JQUESTION D.08 (1. 50 )-

n.- -'OneL-of the<two auxiliary circuits'of the power regulation

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' system:is-lthe Slave; control circuit, briefly" explain HOW it

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-' performs its function /purpos Include any applicab]e

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,1cetpoint (1.0)

l What is the other auxiliary circuit of the power regulati'on system?'

-(O.5)

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! QUESTION ~ D.09 (1.50)

How cre the nuclear instrumentation channels affected by selecting c tho-. pulse" mode of operation? Be specifi !

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E.* SA $TY AND' EMERGENCY SYSTEMS Page 43 QUESTION: E.01 (2.50)

.Lict.FIVE.of.the seven measuring ~ channels required by AP-5, Technical Specifications, to be operable for reactor operation in the manual or cutomatic mod I

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" QUESTION., r:. 02 (3.00):

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[.lListTSIX.!different types of facility ~ devices that are sulaplied by Ljth2 uninterruptible' power supplyL(UPS) in'the event of a loss of

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QUESTION E.03 (3.00)

S;;1 cot FOUR of the five Safety Interlocks for PSBR operation and state tha function for each, according to Technical Specification a-(***** CATEGORY E CONTINUED ON NEXT PAGE *****)

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QtTESTION  : E.04 /(1.50)=

16., What-is thelfuelLelement' temperature ~cafety limit?

(0,5)

' [.bi, EWhich' reactor safety' system channels assure.that.the reactor is, automatically shutdown before the safety limit on fuel-g; temperature is' exceeded? (1.0). .

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SAhETYANDEMERGENCYSYSTEMS Page 47 l

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QUESTION E.05 (3.00) List TWO of the different radiation monitors, which when reaching their alarm setpoint will automatically result in an evacuation clarm actuatio (1.0)

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l With the intrusion alarm system in its normal lineup and NO operator actions or IAS key actuation, list FOUR different alarm conditions that will automatically result in the meter on the telephone line to Police services to indicate an alarm conditio (2.0)

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$QUESTIONJ

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E.06 (1100)'

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e LHow1'can(operasion of.the emergency exhaust system be verified

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l 0 'STNDARDANDEMERGENCYOPERATINGPROCEDURES Page 49

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QUESTION tF.01 -(1.00).

tAcco'rding.to! SOP-1, ." Reactor Operating Procedure," which detecting chnnnel must-be used by'the. operator to assure the l'MW license

/ limit is'not exceeded?.

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.. r QUESTION. !F.02: (3.00):

!i'According to Emergency Procedure EP-1, " Evacuation,":what-are SIX-

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ofitha~seven actions required.by the reactor operator-in' respons '

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Ll.i;tofen evacuation .' alar /'

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MUESTIONM-F.03 '(2150)

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,.f. List'FIVE of the.. actions required by SOP-1, " Reactor Operating ~

"'1Procsdure"p to secure the' reactor, other than-removing enough fdal;} f rom .thef cor '

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QUESTION: F.04 (2.00)t 4:

i iTh31following~ concern'AP-1, " Personnel" Requirements For Reacto Operation"' procedure, e.,

Whenever the' reactor.is NOT secure :1.:What is'the minimum number of-personnel required to be present atLthe' facility?

2. Who'is required to:be~at the contrcl console?

' b ; :- Whenever power. level changes are mad ~1.. How many- personne~1 must be' present at the control console?

- What license requirements must be satisfied in b.1., above? l I E4 J

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? .l QUESTION F.05; (2.00)

Tha."following' concern AOP-3," Loss.of Cobalt-60 Pool Water" procedure.

Li : State THREE indications that.would alert an. operator that the

-

Cobalt-60. pool level is below normal?.(Consider level dropping:a I a low: rate as opposed-to an extensive loss of. pool level.)- (1.5)

'b, What is_the. prime ~ concern of'a low Cobalt-60. pool water level?.

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Fi* STANDARD AND EMERGENCY OPERATING PROCEDURES -Page 55

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1 QUESTIONi F.06- (1.50)-

c According to'the Technical Specifications, WHAT is the maximum c11owable reactor pool water conductivity.while the reacter i operating? (0,5)

!b. - What;are-TWO. reasons / basis for this limit? ~

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. QUESTION. : F,07- J(1.00)

'LTRUEor[ FALSE,Lconcerning.AP-7, " Console Indicator Lights. Abnormal-

,l conditions" procedur em.-Activating the. BEAM PORT PLUG REMOVED push-button indicator-K . light on the. reactor console is considered a:" tag'out" that

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the pluss are' remove < b '. The licensed reactor operator must-activate the PERSON ON ROOF push-button when issuing the control room key that unlocks the barrier on1.the access ladder to the reactor bay roo t

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SQUESTION.' F.08- ~-(0. 50 ) -

.L'ist 'ONE indication that the Hot' Cell sprinkler system has been

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Q ESTION- L F. 09 -- . ( 1; 00 )'

LTRUETorzFALSE7"'Concerning EP-2, " Fire or Explosion" procedur La.iFor'a. minor fire that involves non radioactive. material, an

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. attempt may.be'made to extinguish it before sounding the:

building. fire ~ alarm system'.

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.N.} department. Sounding'the building fire. alarm system will summon the fire

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1; l4 QUESTION' . G . 01 - (3.00)

En.1;What are the most restrictive 10 CFR 20. quarterly limits for

- whole body,. skin, and extremities?

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- permit-this radiation exposure?-

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QUESTION G.02

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What are THREE of the four areaa that must be conjunction with a beam port experimental s operated in facilityradiati E

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r 0 QUESTION: ' G.0 (1.50)-

.Whnt are THREE of the-four areas that'must be <antrolled as potential.

L srzdiction or high radiation areas when the. reactor is operated in

',;.. conjunction-with a beam port experimental fac111ty,.according to SP-1

"Rezetor Operation using a Beam Port Experimental Facility" procedure? : r; ,

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'! QUESTION- ' G . 0 3 '. .(3.00)

lThi following concern the inverse square law,-which is usually icpplied'to the calculation of dose rates as a function'of distance

- f rom.'a point <- sourc ; For distances that are relatively close to the. source; l'. Would the calculated dose rate be higher or lower than

,

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the actual' dose rate? (0.5)

2. Explain why'.the' inverse square relationship may sive incorrect result (1.0)

/I

' Forfdistances that are especially far from'the source;

"1. Would the calculated dose rate be higher or lower'than the actual dose rate? (0.5)

2. Explain why the inverse square relationship may give incorrect result (1.0)

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. RAk5IATIONCONTROLANDSAFETY Page 63 QUESTION G.04 (1.60) List TWO sources of Tritium at the PSBR, (1.0)

E How is the release of Tritium reduced at the PSBR facility?(0.5)

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[ QUESTION G.05 .(2.00)

& ' List the TWO potential sources'of. major. gaseous radioactive

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.. release from the: reactor' poo :- ;What:immediate actionLis' required.in the event of.a gaseous Lrelease indicated by air particulate ~ radiation monitor-

-alarms, according to EP-5, " Gaseous Release" procedure?

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,1 QUESTION G.06 (2.50);

c.- .Name the.TWO.'different types of. completely portable ionization chambers (surveyLmeters)-normally available to the reactor

. operator in'.the reactor bay.- INCLUDE the overall instrument

. range AND type of radiation that can'be measure (2.0)

. WHAT portable. instrument is used to detect and measure.the dose rate from neutrons?- (0,5)

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= ,= + g,g 2 Cycle efficiency = - CI '

E = aC *'

a = (vg - v,) / t KE = my vg A = AN A = A,e' E

.= v + at PE = agh w = e/c 1 = In 2/tq = 0.693/tg ,

W = v&P" (t,,)(ev )

AE = 9314m *

t (eff)

.V(g+t) b k = k paT ,

y . g ,4x

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k"UAAT'

I = I ,WX

~Pwr = W'g m" ~

- I == oI 10 *

-

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P=P o e /T HVL 6 0.693/u

'SUR = 26.06/ ~

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

f1 * m)

SUR = 26 CR g x = S/(1 - K,ggg)

eff}1 * b (l

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T = f*/ (o - T)

, M " I/(1 - K,gg) = CR g/CRg i = (I - 9)/ A*ffp M = (1 - K,gg)0/Cl ~ raff)1 8 " ( aff~U eff " #effIEeff SDM = (1 - Keff)/Keff

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p= [1*/TKygg .} + DI/(1 + A,ggT )] 1* = 1 x 10 seconds

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P = I$v/(3 x 1010) 1,ggA= 0.1 seconds I = No

.

Idgg=Id22 UATER PARAMETERS Id =I02 g

1 gal. = 8.345 lba 2 R/hr = (0.5 CE)/d g,,,,,,)

1 gal. = 3.78 liters R/hr = 6 CE/d (feet) -

. 1 fc3 = 7.48 ga MYSCEtt.ANEOUS CONVERSIONS .

Density = 62.4 lbm/ft 1 Curia = 3.7 x 10 dps O Density = 1 gm/cm 1 kg = 2.21 lba Heat of vaporization = 970 Ecu/lba 1 hp = 2.54 x 103 BTU /hr Heat of furica = 144 Beu/lba 0 1 Hw = 3.41 x 10 Etu/hr 1 Ata = 14,7 psi = 29.9 in. I' Btu = 778 ft-lbf 1 ft. H 2O = 0.4333 lbf/in 1' inch = 2.54 cm F = 9/5 C + 32

_ _ _ _ _ _ _ _ _ _ _ C = 980 a'i? o vsm

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,iANSWE VA.01- (1.00)^ $W $0SMW, .:> e23  ?.;

'(At;approximately)'1.k ; [1.0)

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1NEFERENC <PSBR Training. Manual. Chapter 2,!Section C, p. 2-3 '

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A .' 0 2 ' (1.00)

d-li.4fx 10**-4" delta k/k/degr?e C) x (5 degrees C) =

,

.-7.jx:'10**-4 delta k/k [0. 25) .

'4

-

--Nx'10 I delta.k/N

.___ ---------------

[0.25). :- 0.7 inches [0.25)

e0.001fdelta~k/k/ inch 3bl The. control rod ~ moves.'out' . [0.25)

,

l REFERENCE PSBR1 Training Manual, Chapter 2, Section C, pp 2-26 and 2-34; SAR,..p.IX-2 VANSWER 'A.03'~ (l'.50)

Hydrogen-atoms' bound in the 2rH lattice act like harmonic oscillators

! ' [0. 5) . - As the temperature'of the hydride increases, more neutrons L -sain. energy from an excited state of an oscillating hydrogen atom l': -in.the. lattice [0.5]. Fission cross-sections are lower for neutrons Lwhich have higher energy, the probility for fission' decreases [0.5).

REFERENCE'

.PSBR: Training Manual,-Chaptec 2, Section C, p. 2-34.

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)A2 PRINCIPLE 3'OF REACTOR OPERATION' ;Page 67-

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IANSWER A.04 (1.50)~ Xenon-135.is the decay product of.I-135, (which,is a-fission

' product-:via.Te-135):[+0.5].--Xenon-135 is also produced as a- .

' direct result:of.the fission. process [+0.5].

. . Maximum xenon poisoning occurs about 10 to-l2 hours after a

shutdown...[0.5].

.

. REFERENCE

)PSBR Training Manual, Chapter 2, Section 0, pp..2-28, 2-29, 2-3 . ANSWER' ' A.05 (1.'50)

~t/T 69/T

.P:Po*e ', . substituting values 2=e [0,5)

OR . Doubling time-(DT)'= 693*T- [0.5]

. Solving'for T (period), T = 69/.693 99.6 seconds [1.0]

REFERENCE'

PSBR Training Manual, p 2-2 ANSWER A.06 (1.5b)

a. Mb-S: 'enimvur km ,111u O [0.5] -

'b; :The source is used to elevate the neutron count in the reactor 6 fcva.e O 8*eck hy/NO*

=during shutdown to a level that is high enough to be readily seen by the nuclear instrumentation [1.0].

L REFERENCE I

PSBR' Training. Manual,' pp 2-21 & 2-22b; SAR III-2 l 1 . .

. .

ANSWER A'07-

. (1.00)

.As Keff approaches unity, it takes many more neutron generations

'bofore the new higher equilibrium neutron density is reached [1.0].

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

_=-___=_____-_ _ _ _ _ _ _ _ __ ___-_ - __- ____ _ ____ __ ____ _ - - - -__ _ - _ - __ __ _ __ _ _

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-5

, 'A . FRINCIPLES-OF-REACTOR OPERATION Page 68 l

REFERENCE'

.PSBRLTraining Manual,-Chapter 2. Section'B, p 2-22; Chapter 8, p 8- ANSWER A.08 (1.50) (Delayed' neutrons increase the neutron generation lifetime), which causes the' reactor period to be longer, allowing more time for control of the reactor [0.75). Beta-effective takes into account that delayed neutrons are given off at lower. energies [0.75) (and don't leak out of the system as readily as prompt neutrons, . increasing Keff)

. REFERENCE PSBR Training Manual, Chapter 2, p 2-17 to 2-1 l ANSWER A.09 (1.50)

'It' offers the greatest amount of multiplying medium for source neutrons to travel prior to detection [0.5), making the detector most sensitive to increases in count rate as fuel is added [1.0).

REFERENCE PSBR Training Manual, Chapter 2, Section A, .

ANSWER A.10 (2.50) control rod movement fuel burn-up (depletion) fission product inventory (poisoning) moderator. temperature changes experimental worths fuel temperature (cell effects)

,, Ope /& e,w u D20 %4 Any five, [0.57 eac : REFERENCE

.

I-PSBR. Training Manual, Chapter 2, p 2-14, 2-2 (***** END OF CATEGORY A *****)

- _ _ _ - __ -___- - - ____ --- _-___ -___ . - _ .

_ _ _ _ _ _ _ - _ _

.

,

[ , ',[

iS; FEATURES OF' FACILITY DESIGN Pega 69

' ANSWER B.01 (2.50)

c6 The roof exhaust fans discharge air to the atmosphere (at the roof level), providing enough suction on the building to maintain less than atmospheric pressure in the reactor bay area [0.5]. The. normal system is secured automatically (fans stop and

~ dampers /lcuvers shut) [0.5] and the emergency exhaust system

' automatically starts [0.5) The air passes through roughing filters (prefilters) [0.2),

absolute filters [0.2), and charcoal filters [0.2), then the

. exhaust fan [0.2] (discharges to above the roof level). [0.2 for correct order).

REFERENCE PSBR SAR, p V-1 to V-5; Training Manual, Chapter 3, pp.3-24 to 3-2 ANSWER B.02 (1.50) To prevent the control rods from dropping out of the core should their mechanical connections fail. [1.0) 'The safety plate is suspended (12.75 in.) below the bottom grid plate. [0.5]

REFERENCE PSBR Training Manual, Chapter 3, p 3-1'and 3- ANSWER B.03 (1.50)

The purpose is to prevent softening of the polyethylene capsules [0.75).

.Tha time delay relay prohibits transfer system use (for 10 minutes)

-ofter the system is turned on, this allows the recirculation blower to. cool the core terminus [0.75).

-REFERENCE PSBR SAR, p. VI-12; Training Manual, Chapter 3, Section D, p. 3-3 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

. - _ _ . . _ _ _ -_---

, -m- ---,..

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~

d B, . FEATURES OF FACILITY' DESIGN

'

Paco 70 6 -

_

-

l IANSWE B.04 ~( ~ 2. 00 )'

1~- . radiation
shielding moderation

. reflection ~

" '

4 '. ' heat absorptio . corrosion control.

[ :Any-four.[0.5] eac .

.

REFERENCE'

~

,

PSBR Training Manual Chapter.3,..Section B, pp 3-12 and 3-1 .

,

LANSWER .B.05 (1.50)

J Provide a means'for' cooling water to flow up.through the core iand out the top grid plate. [0.75].

- To position'the. fuel element in the 3,op grid plate [0.75).

.

REFERENC Aho &ccew . red-sdy # d fk+ w ( M W Y w Q PSBR SAR, p III-2 '1 ANSWER B 06 - ( 1. 00 )-

g Central thimble contains water (to prevent streaming) [0.5]

' 2. :A cutaway section in the central thimble (allows samples to be

. removed-below.the pool surface) [0.5]

-REFERENCE-

'

PSBR'SAR p~VI-6 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

..

. _:_ _- _ _ .

. - - - - ..

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

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t .>

.

OB '.- . FEATURES OF FACILIIY DESIG Page 71 L

ANSWE B.07: (3.00)

-

,

(Anycthree,~1.0 each) The' waste' evaporator. distillate [0,5],(which is stored in the 6000

. gallon processed: water tank), can be pumped'into the recirculation

' loop..for normal water make-up. [0.5] .The University: water system.[0.5) can be added.to-the pool through

.theldemineralizer. [0.5]

2 The' University water system [0.5] can be added at a high flhw rate to the pool drain lines after connecting a fire hose. [0.5] ~

Emergency water from the secondary side of the heat exchanger-

-[0.5] can be directly diverted to the pool through a fire hose. [0.5)

1 REFERENCE-PSBR Training Manual, pages 3-12 and 3-19 ANSWER B.08 (1.50) ~

To. increase the transport time for N-16 to reach the pool surface (OR minimizing the radiation level in reactor bay area by allowing more decay-time of N-16). [0.5]

' A submersible pump [0.33] discharges through a nozzle arrangement

[0.33] (approx. 3 feet) above the reactor core [0.33]

REFERENCE'

PSBR Training Manual,. Chapter 3, p 3-1 .

!

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

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~4-

<

? GENERAL' OPERATING CHARACTERISTICS Page 72 I

h

. ANSWER l

.

C.01- (2.50)-

a. ' positive- [0.' 5]

, b 's . negative '[0.5] .

! negative [0. 5]-

- positive. [0.5]

- positive [0.5]

./ REFERENCE PSBR Training Manual, Chapter 5,.pp 5-2 and 5- ANSWER C.02 (2.50)

a.. The larger age and diffusion length of D20 causes an increase ~

in1the-neutron leakage (major effect) [1.0]. The core excess reactivity is decreased [0,5].

ib. 'The countrate.-(linear. reading) would increase [0.5], (the greater neutron reflection property of the D20 will increase the flux _seen by the CIC's.(and/or the Gamma chamber would still see approx. true-power level in relation to the CIC's))

since the.boral plate acts as a neutron absorber [0.5].

REFERENCE

PSBR-Training Manual,. Chapter 3, pp 3-37,3-39; Chapter 5, p 5- LANSWER C.03 (1.00).

.Usually set at approximately 15 second period [1.5]

REFERENCE PSBR Training Manual, Chapter 4, Section C, p 4-2 ANSWER- C.04 (1.50)

The period meter gets its signal from the log N channel [0.75].

Ths. flux level during the suberitical range of startup is not high enough to' register an indication on the log N channel [0.75].

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

I

_ - _ _ _ _ _ _ - . _ - _ _ _ _ _ - . . - _ _ _ _ _ _ _ _ - _ - _ _ - - - - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - _ - _ _ _ _ - - _ _

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i GENERAL OPERATING CHARACTERISTICS Page 73

' REFERENCE

. PSBR Training Manual, Chapter 5, p 5-1.

i ANSWER' C '. 0 5 (1.50)

-The indicated power increase is due to an increase in the number of-gammas [0,5], which_is due to an increase in fission products (decay

. gammas) [1.0], (as the core fission product inventory approaches an equilibrium condition)

REFERENCE PSBR Training Manual, Chapter 5, p 5- ANSWER C.06- (1.50)

rhol = K1-1/K1 = -0.04. delta-K/K kl = 1/((1-(-0.04)) = 0.9615 [0.25]

100(1-0.9615) = 196(1-K2), K2 = 0.9804 [0.25]

rho 2 = (0.9804-1)/0.9804 = -0.02 delta-K/K [0.25] i rho exp = ((0.7% delta-K/K)/$1.0) X $1.43 = 1% delta-K/K [0.25]

Delta rho = rho 2 - rhol = -0.02 - (-0.04) = 0.02 delta-K/K [0.25].

0.01 delta-K/K is the experiment, thus the remaining 0.01 delta-K/K is from Xenon [0.25].

' REFERENCE PSBR_ Chapter 2, p 14; Chapter 8, pp 4, (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _.________.m___..__,..__ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ d

,_ _

.

.-..' *

'C . -GENERAL OPERATING CHARACTERISTICS Page 74 ANSWER C.07 (2.00)

.o. P = Pi e**t/T, t DT = 0.693 T [0.25]

T = 34.6 sec [0.25]

T = (B-rho)/ lambda rho [0.25]

rho : B/(lambda T + 1)': 0.159% delta-K/K OR = 22 cents [0.25)

.b. DTs will increase [0.25] because of the addition of negative reactivity as temperature (power) increases (0.75].

REFERENCE lPSBR Chapter 2, pp 21,23,3 ANSWER C.08 (2.00)

c. NO EFFECT b. DECREASE c. NO EFFECT d. INCREASE [0.5, each)

i REFERENCE PSBR TECH SPEC, p 6; Training Manual, Chapter 2, pp 2-26 to 2-3 i I

l l

(***** END OF CATEGORY C *****)

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.

'D -INSTRUMENTS AND CONTROLS Page 75 h m

ANSWER .D. 01- (1.00).

! Prevents: blower. operation'[0.5).

Opens a; valve-to bypass the pressure. relief manometer so that

,:anyLpressure.in'the system is relieved [0.5].

. REFERENCE

PSBR SAR p VI-1 JANSWER D.02 (1.50)

c , A (bidirectional) pulse generator (with digital' output) [0.25)

'

feeds'a signal to a recorder / counter located in the reactor console'.-[0.25)

' .That'the magnet'and the control rod have made contact. [0.5)

i c .- Operation-of a microswitch actuated when the control rod is in the down position. [0.5)

,; REFERENCE

'PSBR Training Manual,,pp 4-25 to 4-2 ANSWER D.03 (2.00)-

-

Channel Detector

----------------------- count rate _(startup) fission chamber linear power compensated ion chamber percent power gamma ion chamber

' log.N.(power) and period compensated ion chamber (

[0.5 each] ,

' REFERENCE PSBR Training-Manual, Chapter 4, p 4-15; SAR, pp VII-1 to VII- ,

(***** CATEGORY D CONTINUED ON NEXT PAGE *****) _ . _

,

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Di ~ INSTRUMENTS AND CONTROLS

-

Page 76'

&

'

.

LANSWER . D.04' (2.00)

c.- Prevents rod withdrawal [0.75), if the count rate is less than 2' counts per'second [0.25).

' M4 Approximately 100 watts [0.5).

. At approximately 800 watts-[0,5).

. REFERENC ~

PSBR Training Manual, Chapter 4, pp 4-19 and 4-2 . ANSWE D.05- (1.50)

1.iLinear Power Channel 2. Log N Channel 4 or Femf /M* !

, Regulating Rod. Tachometer feedback signal 4. Power Demand Signal (Any three 0.5 each).

REFERENCE PSBR Training-Manual.. Chapter 4, pp 4-22 through 4-2 ANSWER D.06 (2.50) Resistance bulbs [0.5), and bulb-capillary tube end bellows-(spring-temperature indicating needle) arrangement [0.5).

- . Decrease evaporation losses [0.5).

2. Prevent damage to the demineralized (anion) resins [1.0). ,

" REFERENCE-PSBR Training Manual, Chapter 4, p 4-21; SAR, p IV- .

ANSWER D.07 (1.00)

1. The pulse mode is selected. [0.5)

2.-The range switch positioned in the 1 MW (PULSE) position. [0.53 (***** CATEGORY D CONTINUED ON NEXT PAGE *****)

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y

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yf uD; INSTRUMENTS AND~ CONTROLS Page 77 1

l REFERENCE:

I dPSBR'SAR, p*VII- l

ANSWER

.

D.08 (1.50)

c. The slave control senses the position of the regulating rod and .]'

initiates operation of the shim rod [0.5] when the regulating rod reaches 75% of.its travel when withdrawing or 25% of its travel when. inserting [0.5]. (Permitting. larger changes.in reactivity  ;

'

.than'could be obtained'with a single control rod.)

"b. The. Square Wave control circuit. [0.5]

>

REFERENCE PSBR Training Manual,. Chapter 4, pp 4-22,4-24; SAR, p VII- ' ANSWER D.09 (1.50)

'

The startup channel, log hower and period chanrel, and linear CIC

.are deactivated [0.2 each, 0.6 total). .The output of the of the G.I.C. (from the % power-channel) is fed through an amp 1fier-memory ,

circuit [0.2] and the linear amplifier of the linear' power channel I

[0.2], displayed on the blue pen of the chart recorder [0.3] after a i time delay [0.2].

REFERENC .

l PSBR:SAR, p'VII- ,

)

l l 8 l

l

'

(***** END OF CATEGORY D *****)

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.s*.C ~

Ji iSAFET 1AND EMERGENCY SYSTEMS- . Peso 78-

, +

a

-i

' JANSWER- E.01.' (2.50), d

!

- , fuel element > temperatur . linear. power ' percent power :- /l

, log. power

. S '. pulse'. peak-power . . count rate

, , 7.' ' reactor: period .[Five' required,' O.5'each)

REFERENCE PSBR'.'AP.5,. Technical. Specifications, p 1 ANSWERJ -E;02 L( 3. 00 ') :

.[Any.!six,.0;5:each],

'

'

l '. control' room-' annunciator-(visicon)' pane . -reactor. bridge east'-(or west) radiation monitor . reactor bay' east (or west) air monitors (except pumps).

.4: cobalt-60Lbay .(or beamhole'. lab.) area-monito . : 'several. evacuation. alarms (bay, beamho'le lab, cobalt bay) . intrusion alarm ~ system

. 7 '. control rod position digital; indicator REFERENCE PSBR: Training. Manual, Chapter 3, p 3-24; SAR, p V- .

J

'

!

, i l

,

l l

(***** CATEGORY E CONTINUED ON NEXT PAGE *****) {

i a=  ;:_----__-.--__-_---_------___---_-- - - _ - _ - - - _ - - - - - - - - _ - . _ - - - - _ - - - - - - - - _ _ - - - - - _ _ _ _ . - _ - - - - - _ _ - - _ _ - - _

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4EU ~ SAFETY'AND' EMERGENCY-~ SYSTEMS Page 79 r -

E.03-

'

LANSWER .(3.00)

[Four" required, 0.75 each]

. .

S S6urce ' level- - Preve nt rod' withdrawal with less than two counts -

- per second"on.theLstartup channe b Log power -- Prevent pulsing from-levels above i k ..

'

Transient' Rod ' Prevent applications'of air unless cylinder-is fully inserte !-- Shim,' Safety, and regulating rod - Prevent movement of any

rod except-transient ro . Simultaneous'R$d Withdrawal'- Prevents simultaneous withdrawal

-

l(Manual).of-two rods.'

REFERENCE

,

PSBR ' TS , .p 17 ; AP- 5, - p 1 ANSWER E 04 (1.50)

a. . The fuel.: element temperature shall not exceed 1150 degrees C

. (under any operating conditions) [0.5).

. The fuel temperature [0.5] and (two) high power level [C.5].

REFERENCE lPSBR Technical Specifications, pp 7 and 1 s .. .

y '

- : ,

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

{ v );; l

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E; SMETY AND EMERGENCY' SYSTEMS Page 80

,

i

ANSWE E.05 .(3.00)

E ,; Reactor bridge east (or west)

-2. Reactor AIR east (or west)

3. Cobalt-60 bay-

.4. Reactor beam hole lab'  :[Two required, 0.'5 each)

i b .' 1. Reactor bridge-east-(or west)~

2.. Reactor AIR east (or west).

3.' Cobalt-60-bay

'4. Reactor. beam hole lab-

'5. Cobalt-60-pool' level low

'6.-Fuel storage ~ room (APB) [Four required, 0.5'each]

.

/47 // O A u d :

REFERENCE jf A,,/ gu /

PSBR SOP-4, Radiation.. Evacuation and-alarm checkn 8 # N N '~7 O "#

..,-

fANSWER E,06- (1.00)

The control panel' located in the Cobalt-60. entrance lobby can

.bo viewed from outside the reactor building' perimeter fence [0.75)

itheired' air flow light and/or d/p gauges would indicate system .

.

operation [0.25).

fREFERENCE

.

  1. PSBR. Training Manual,-Chapter 3, p 3-26; SOP-4, p 1 .

( (***** END OF CATEGORY E *****)

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Jf F; STANDARD AND EMEB9ENCY' OPERATING PBOCEDURES Pags 81

,' ,

ANSWER , -F.01- (1.00)

iThb__ linear channel [1.0)

' YREFERENCE 7PSBRLSOP-1'. " Reactor! Operating Procedure," p LANSWER..- F.02 '(3.00)

> Remove the HAGNET POWEREswitch key (to ensure that the reactor is shut'down). Check the reactor-console readout modules and the annunciator

.for alarm ;' . Check-that a11' reactor bay doors are close

.

,

u

! Evacuate via the marked evacuation route-sign . Check WestLstairwell panel for alarr ]

. .

1 Rapidly move to the emergency support center (ESC). Be: alert for persons that do not-evacuat [Any Six, 0,5 each)

,-

REFERENCE'

-

d

~PSBR'EF-li " Evacuation, . p .

- y '

. ;

Il l

.q i

!

!

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

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- +.

ij g ,~'

cf TANDARD~AND EMERGENCY OPERATING PROCEDURES Page 82 i:

,

JANSWER: F.03- '(2.50)

At least three control rods inserted to the-' lower' limi . .The MAGNET POWER key switch locked in OFF position. (The-key removad and under control of a licensed operator)

os

'3s :The N-16' pump turned off (if it is operating)

4 .- ,The POWER ON button-is depressed (green light goes out).

5.-: Pens lifted from the recorder char ' No work done on' core fuel, structure, rods, or rod' drive . :Nosexperiments moved or serviced in or near the. reactor cor [Any five, 0.5.each].

~ REFERENCE -

.PSBR SOP-1, p 11 ANSWER ~F.04 (2.00)- . RO-orjSRO [0.5 each]

t ., 2

~

iL One of the two persons must be a licensed SRO [0.5 each]

1 REFERENCF

.PSBR'AP-1, p i ANSWER- F.05 (2.00) .. Ped-light on the Co-60 bay alarm pane . Audible alarm on the Co-60 bay alarm panel, i 3. POOL LEVEL LOW annunciator in control roo j 4. Meter!on' telephone line to police station indicates alarm conditio [Three required, 0.5 each]

sb.-The' prime: concern would be to maintain water shielding [0.5]

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

I

.

.

s _ .

au f[{ ;

YF; ; STANDARD AND EMERGENCY OPERATING PROCEDURES Page 83 s

.A REFERENCE'

WPSBR AOP-3,.pp 1;and- .'

'

3.; ANSWER ~ . 'F . 0 6 '( l'. 50 ) ~

cC5 micrombos/cm- [ 0 , 5 ] '.

b. 1".ETo prevent activatedicomtaminants from becoming a radiologica hazard. . [0. 5)-

,. 2. To~ minimize / preclude corrosion of the fuel .claddi* g:and other

'

primary components. [0. 5].

, REFERENCE-PSBR Technical Specifications, p.21.

g. ; ANSWERT Fi0 (1.00)

.o."

-

True-

b. ! False (duty senior operator) [0.5 each)

REFERENCE-PSBR AP-7,.pp 1 and 2.

,' [ ANSWER" lF.08- (0.50)

An. alarm.* cell on the hot cell loading dock -OR- An alarm signal to Police-Service. [0.5)

~

i REFERENCE- ~!

"

--PSBR EP-2, p ANSUER F.09 (1 00)

a.LTrue b. False [0,5'each)

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

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,.

. STANDARD AND EMERGENCY OPERATING PROCEDURES pcg3 84 i

i REFERENCE PSBR'EP-2, p i l

I

.

i

!

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l l

l

)

{

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

!

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. . . .

Gi 1 RADIATION CONTROL'AND' SAFETY Page 85 LANSWER G . 0 .(3.00)

1 .25 R - whole body 17.5-R - skin

.18.75 R - extremities [0.5 each)

in . Quarterly dose less than 3 rems Lifetime dose less than 5(N-18)

Accumulated occupational exposure is. documented on NRC Form 4

.[0.5 each)

REFERENCE 10.CFR 20.101, p 20- LANSWER' G.02 -(1.50)

1. Beam Hole Laboratory . (EHL).

2.. Parking. area behind the BH .LRoof of the BH . Reactor bay above the BH [Three required. 0.5 each]

. REFERENCE PSBRtSP-1, p ' ANSWER -G.03 (3.00)

L . The calculated dose rate would be LOWER than the actual dose rate when close to the source. [0.5]

2.-Because the source vill show characteristics of a plane source r#Jher than a point source [1.03 v ,1 '. The calculated dose rate would te HIGHER than actual dose rate when far from the source. [0.5)

-2. Because the inverse square law does not include a factor for attenuation by air. [1.0)

i i

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

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.

f 'G . NADIATION'CONTROLANDSAFETY Page~85 ANSWER ( 'G.01 .('3.,00)

Ec. 11.25 R=- whole body-7.5 R.- skin 18.75.R - extremities [0.5 each]

.

.b; ' Quarter 3y dose less than 3 rems-

,

. Lifetime dose less than 5(N-18)

' Accumulated occupational exposure is documented on NRC Form 4

[0.5 each]-

REFERENCE 10 CFR 20.101, p 20- .

ANSWER G 02 (1.50)

1. Beam Hole Laboratory (BHL).

-

2,.1 Parking area behind the BH . Roof of the BH . Reactor bay above the BH [Three required, 0.5 each)

REFERENCE

,

PSBR SP-1, p ANSWER G.03 . ( 3. 00 )-

f . The calculated dose rate would be LOWER than the actual dose rate when close'to the source. [0.5)

2. Because the source uill show cht.rseteristics of a plane

. source rather than a point source [1.03 . The calculated dose rate would be HIGHER than actual-dose rate when far from the source. [0.5]

2.'Because the inverse square law does not include a factor for attenuation by air. [1.0)

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

= - - _ ___ - _ . _ _ . _ _ _ _ _ _ _

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.

- ~ , ~ - -

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-.

. RADIATION CONTROL AND SAFETY Page 86 REFERENCE l PSBR Training Manual, Chapter 7, pp 7-28 through 't-? !

ANSWER G.04 (1.50) [Two Jequired, 0.5 each)

1. Neutron' activation of the naturally occurring Deuterium in

.the pool wate . Leakage of tritium contaminated water from the thermal colum . Leakage of fission product tritium from the reactor fuel, b. By returning the dehumidifier condensate from the bay air conditioning system to the reactor pool. [0.5)

CR . . By /?f a N h ;*7 (ho fm h of 5.v.b~ k 4 Ao /

REFERENCE PSBR Environmental Impact Appraisal, pp 3 and ANSWER G.05 (2.00) . The rupture of one or more fuel elements. [0.5)

2. Leakage or rupture of an irradiated sample or experimental apparatus. [0.5) All personnel must evacuate. [1.0)

REFERENCE PSBR EP-5, "Geseous Release," pp 1 and ANSWER G.06 (2.50) Chamber Name Range Type

----------- ------------------ V$ctoreen (440) 0-300 mR/hr beta. gamma (x-ray)

[0.4) [0.3] [0.15 each) Eberline (RO-2) 0-5 R/hr beta, gamma,(x-ray)

[0.4] [0.3] [0.15 each) Eberline PRS-1Q/NRD -OR- ESPD-NRD [0.5)

A6 vwM "6w/ J. # " ,iw- dm, aJ Scc 44 / Nn7 4o A fy

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

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'REFERENCEi _J-m 'j

PSBR Training Manual, Chapter 4, p 4-10; Environmental. Impact Appraisal',

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i (***** END OF CATEGORY G *****)  ;

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

_

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