Text

Reviews Written Exam Administered at Faclity on 920824 & Found No Questions Causing Applicants Problems
	ML20115G633
Person / Time
Site:	05000128
Issue date:	08/28/1992
From:	Asher B; TEXAS A&M UNIV., COLLEGE STATION, TX
To:	Collins F; Office of Nuclear Reactor Regulation
Shared Package
ML20115G565	List: ML20115G633;
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	NUDOCS 9210260270
	Download: ML20115G633 (59)
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ENCLOSURE 2 TEX AS E N GIN E ERIN G EXPE Rlhi ENT STATION TEXAS A&M UNIVERSITY COLLEGE STATION, TEXAS 77643-2575

[

August 28,1992 _

I L

NUCLEAR SCIENCE CENTER 409'845-7551 hir. Frank Collins Division of Licensee Performance and Evaluation U.S. Nuclear Regulatory Commission hiail Stop 10-D 22, O.W.F.N.92-406 Washington, D.C. 20555

Dear hir. Collins:

After reviewing the written examination that was administered at this facility on August 24,1992, I have not found any questions which would cause the applicants any problems.

This was a good examination. hiy coinpliments to you and Mr. Hemmings.

Sincerely,

/

~ ..

l Bill F. Asher hianager, Reactor Operations l cc- Dr. W.D. Reece l Bruce Carbsle 9220260270 PDR 92101a ADOCK 05000528 PDR RESEARCH AND DEVELOPMENT FOR MANKIND J

,v

ENCLOSURE~ 3

,g

sC Official Uso Only

4-6 1

MASTERCOPY e

Nuclear Regulatory Commission Oparator-Licensing Examination 1

1 a

4 4

1 This documer.t is retaoved from official Use only category on ~i

date of examination, a

NRC Official Use Only .-

2 MASTERCC?Y

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c+w--w- we v

,k MASTERCO)Y '

U. S. NUCLEAR REGULATORY COMMISSION l

NON-POWER REACTOR LICENSE EXAMINATION '

FACILITY: Texas A&M REACTOR TYPE: 'TRIGA 4

DATE ADMINISTERED: 92/08/24

REGION: 4 i CANDIDATE:

l l LICENSE APPLIED FOR:

INSTRUCTIONS TO CANDIDATE:

j Answers are to be written on the exam page itself, or the answer sheet

! provided. Write answers one side ONLY. Attach any answer sheets to the examination. Points for each question are indicated in parentheses-for i each question. A 70% in each section is required to pass the examination.

Examinations will be picked up three (3) hours after the examination ~ starts.

% OF i CATEGORY % OF CANDIDATE'S CATEGORY

, VALUE TOTAL SCORE VALUE CATEGORY l

f 20.00 33.33 A. REACTOR THEORY, THERMODYNAMICS AND PACILITY OPERATING l CHARACTERISTICS i

! 20.00 33.33 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL

[ CONTROLS 20.00 33.33 C. PLANT:AND RADIATION MONITORING SYSTEMS f

60.00 TOTALS-FINAL GRADE All work done on-this examination is my own. I have neither given nor

, received aid.

~~

( Candidate's Signature L VAST 3 COPY l

. .-~ _

4 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

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

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your owe and you have not received or given assistance in completing the. examination. This must be done after you complete the examination.

3. 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.

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

S. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

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

7. The point ' 'te for each-question is indicated in parentheses after the question, amount of blank space on an examination question page is NOT an inau .on of the depth of answer required.

8. If the intent of a question is unclear, ask questions of the examiner only.

'9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.

10. To pass the examination, you must achieve at least 70% in each category.

11. There is a time limit of (3) hours for completion-of the examination.

12. When you are done and have turned in your examination, leave the examin-ation area as defined .by the examiner.

If you are found in this area while the examination ri still in progress, your license may be denied or revoked.

VASTBCOPY

.i

_A.- 10( THEORY,' THERMO & FAC OP CHARS Paga 3 t

QUESTION: 001 (1.00)

Which ONE of the following statements concerning_ Xenon-135 production'and ,

romoval is-correct?

i a. At full power, equilibrium conditions, about half of.the Xenon is produced _by Iodine decay and the other half is produced as.

a direct fission product.

b. Following a~ reactor trip from equilibrium conditions,-Xenon peaks because -delayed- neutron precursors continue to- decay to' s

Xenon while neutron absorption (burnout) has ceased.

i

c. At low power levels, Xenon decay is the major. removal method and at high power levels, burnout-is:the major removal method.

s

d. Xenon production-and removal increases linearly as power level

-l increases; i.e., the1value of 100% equilibrium: Xenon is twico

that of 50% equilibrium Xenon.

i QUESTION: 002 (1.00) i 4

After operating at 50%-power for several days, reactor power is rapidly

increased to 100%. Reactivity changes over the next two hours immediately following the power increase (assuming NO further. operator action)fwill be

j a. POSITIVE - due to the increased rate of decay of' Xenon to Cesium.

! b. POSITIVE - due to the faster burnup of= Xenon at higher neutron _ flux levels.

{ c. CONSTANT - due to the 6.2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months half life of-Iodine 135.

d. NEGATIVE - due to-the increased production of Xenon at-the, j higher. fission rate.

NASIBCP'

)

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A. RX THEORY, THERMO & FAC OP CHARS' 'Paga 4 4

QUESTION: 003 (1.00)

Which ONE of the following correctly describes.the observed reactor i response for the same small addition of reactivity, one-positive and one-negative?

! a. The response will be faster for the negat:1ve. addition at all

times in core' life.

4

b. The response will be faster for the negative addition at end of core life.

l c. The response will be faster for the positive ada'ition at all times in core life.

d. The response will be the same for both the positive and-negative addition at all times in core life..

i i.

3 QUESTION: 004 (1.00)

Reactor power increases from 40 to 60 watts in 20 seconds. What is the reactor period associated with this power increase?

! a. 8.1 seconds

[

4

b. 4.93 seconds j c. 49.3 seconds

d. 81.1 seconds-i t

i L GIRCOPY .

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4 4

.e ,, ~ 4-m,.--

A. RX THEORY, THERMO & FAC OP CHARS Pcgs 5 QUESTION: 005 (1.00)

Which ONE of the following correctly describes how delayed neutrons affect reactor control?

a. Increase the fast fissions of U-238 contributing to the prompt neutrons in thc chain reaction and results in a shorter reactor period,

b. Increase the neutron generation lifetime which causes the reactor period to be longer.

c. Decrease the leakage which causes the Beff/B ratio to be less than unity resulting in a longer reactor neriod.

d. Decrease the average neatron energy causing a smaller fast

neutron leakage probability resulting in a Beff/B ratio less than 1 and a shorter reactor period.

4 QUESTION: 006 (1.00) ,g[

Which ONE of the followin auses the constant rate of power change 10 minutes after a reactor rip from full power?

a. The decay rate of the LONGEST-lived delayed neutron precursor.

b. The decay rate of the SHORTEST-lived delayed neutron precursor.

1

c. The decay rate of the MOST PROBABLE delayed ncrtron precursor.

d. The mean average decay rate of ALL of the delayed neutron precursors.

ET51 COPY

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I A. RX THEORY, THERMO & FAC'OP_ CHARS' Pago 6*:

~

d QUESTION: 007 (1.00) ,

Which ONE of the following causes-indicated power (count rate) to stabilize several hours after a reactor trip? Assume a' full power-history, all systema / components operating properly, and no removal-of experimento or tuel from the reactor. ,

a. suberitical multiplication of source neutrons, b.- Continuing decay o:. the shortest-lived delayed neutron precursor.

c. Actual power (count rate) dropping below the minimum detectable level of the it.atrumentation.

d. Decaying off of--compensation voltage at low power levels.

, .QUESTION: 008 (1.00)

Complete the statement.

Eight minutes after a reactor trip from. full power, the negati.ve reactor period will be approximately:

a. 70 seconds

b. 75 seconds .

c. 80 seconds

d. 85 seconds NAST3CCPY

'I i

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CATEGORY A CONTINUED ON NEXT P. AGE *****)

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[ A. RX THEORY, THERMO & FAC OP CilARS' PagoI 7

} QUESTION:l009 (1.00) i- Which ONE of the following charactcristics is desirable'in a thermal reactor fuel?

4

a. Low concentration of fissile-atoms l b. Low coefficient _of expansion i

j c. Low mass nilmber I

d. Low absorption cross-section-i I

l QUEST 10H 61 0 (1.00)

By what factor will power have increased after the= reactor has Paso prompt critical for exactly one hundredth of one second (0.01 sec.)?

{

Assume an effective-delayed neutron fraction of .0070,.and neglect any reactivity added by reactivity coefficients.

i

! a. 10

[ b. 100

! c. -1000 l.

! 'd . 10,000 t.

4

~

N E S C:PY f

I I

I (***** CATEGORY A CONTINUED ON-hEXT P?9E *****)

,. ., m ._; ._ _ , - . , , . - - - . - . . . . . . . . - . . . . ,

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

A. RX THEORY, THERMO &1FAC OP CHARS Page- 8~

~. s i

QUESTION: 011 (1.00) :

r" l . Select the statementithat describes why' neutron sources =are used in

teactor cores.

4-

t. -

a. Increase the count rate by an amount equal to the source-l- contribution.

. b. Increase the count rate by.1/M (M = Subcritical. Multiplication Factor),

c. Provide the source neutrons to initiate-the chain reaction

. when first starting-up the' reactor. ,

d. Provide a neutron level high enough to be monitored by: source.

range instrumentation. .

i j

QUESTION: 012 (1.00)

With the reactor operating at 100% rated power, select the answorLthat.

describes the major contributor to heat transfer'from the fuel cladding i surface to the coolant.

a. nucleate' boiling.

b. conduction.

. c.- radiation.

f d. convection.

i l

i.

! MASECOPY i

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_,-....2 .. __ n - . ..-_.._.c.-.--..a...-._,.. ,a.

! A. RX TIIEORY, Tl!ERMO & FAC OP CilARS' Pago 9

~

. QUESTION: 013 (1.00)

Select the statement that describes the difference between a moderator and a reflector. ,

a. A reflector-increases the neutron production factor and a moderator increases the fast fission factor.

I b. A reflector increases.the neutron production factor and a moderator decreases the-fast fission factor.

i

. c. A reflector increases the fast non-leakage factor and a l moderator increases the thermal utilization factor.

l' d. A reflector decreases the fast non-leakage factor'and a moderator increases the thermal utilization factor.

QUESTTON: 014 (1.00)

Select the statement that describes delayed neutrons.

a. Neutrons emitted from the fission of U-238 that have an energy j less than 0.5 MeV.

t ,

b. Neutrons that originate from the. Beta-decay of certain fission

} fragments.

c. Neutrons that are emitted by spontaneous fission of the' fuel after the reactor is shutdown.

d. Neutrons that are reflected back;into the-core by the grhphite reflector,-and subsequently cause-fission.

kASTERCOPY I

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A. RX THEORY, THERMO & FAG =OP. CHARS; Pago.10 QUESTION: 015 (1.00)

Which ONE of the following accurately details the effect that fuel-temperature has.on core operating-characteristics?.

a. Fuel temperature increase will decrease the resonance escape probability,

b. Fuel temperature decrease results in Doppler ~ Broadening of: ,

U-238 and Pu-240 resonance peaks andLthe decrease of resonance-escape probability.'

c. Decrease in fuel temperature will.' increase neutron absorption-by U-238 and Pu-240.-

d. Fuel temperature increase results in Doppler Broadening-of U-238 and Pu-240 resenancefpeaks and the decrease of neutron absorption during moderation.

QUESTION: 016 (1. 00)

A source of delayed neutrons is:

a. delayed [ission.

b. gamma interactions with structural ~ materials,

c. decay of fission products.-

d._ instrumentation dead bands and reaction: times.

NASTRCDPY

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

_._y A. . RX THEORY, THERMO & FAC OP CHARS' P299 11 l

QUESTION: 017 (1.00)

A subcritical reactor is being started up. Tne operator withdraws the chim safety rods (in-gang) t.o the critical position in.4. equal steps.- ;

select the statement which MOST accurately characterizes reactor behavior. . j

a. Each withdrawal of the safety rods will add the same amount of reactivity,

b. Roactor power will increase by the same amount for each wic'irawal-if equal reactivity is added for each. withdrawal. ..

c. The time it takes for period to stabilize following each withdrawal increases as criticality is approached.

d. Decreasing the time intervals between withdrawals will result in a lower critical rod height. 1 QUESTION: 018 (1.00)

Which ONE of the fol3owing statements describes count rate characteristics after a control rod withdrawal with the reactor subcritical? (Assume the reactor remains subcr.itical.)

a. Count rate will-rapidly increase (prompt jump) then. gradually increase and stabilize at a-new value higher than the original ,

starting value,

b. Count rate will rapidly increase -(prompt jump). then gradually decrease and stabilize at.the original starting value.

c. Count rate will rapidly increase (prompt jump) then gradually decrease and stabilize at a.new value lower than the original starting value,

d. Count rate will not change until the reactor is critical.

MSTBCOPY

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l - A. RX THEORY,_THERMO & FAC OP CHARS' _Paga 12 I

i' (1.00)

QUESTION: 019 Select the. answer that explains why Erbium is loaded in FLIP fuel.

a. Enhance fuel hydriding, physical strengthening the fuel

.l matrix.

b. Add negative reactivity, allowing excess' fuel loading in the 4 core.

i

c. Permit _ reduced clad thickness in FLIP fuel as compared to-l~

standard fuel._

d. Reduce the value of the prompt negative-temperature coefficient of reactivity.

\

i 4

QUESTION: 020 '1.00) 1 Select the answer that describes the. inherent safety feature provided by

~

the temperature coefficient of reactivity.

i a. Its negative value causes reactivity to increase as moderator temperature increases.

l b. Its-negative value causes reactivity to decrease as moderator l temperature increases.

c. Its positive value causes reactivity to_ increase as_mcderator temperature increases.

[ d. Its positive value causes reactivity to' decrease'as moderator

, temperature increases.

p I

WSTERTY i

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

! B. -NORMAL /EMERG-PROCEDURES & RAD CON Paga 13 QUESTION: 001 (1.00)

) Select the-correct sequence of rod withdrawal during a reactor start-up

for pulse operation.

a. Transient rod to mid position,. shim safety rods (in-gang) to upper limit, regulating rodLto-criticality..

l

b. Regulating ' rod tx) upper limit, transient' rod to mid position,

shim safety rods (in gang) to criticality.

c. Transient rod'to upper limit, regulating rod to mid position,-

shim safety rods (in gang) to' criticality.

! d. Transient rod full in, regulating. rod mid position,fshim l- safety rods-(in gang) to criticality.

l t

f- QUESTION: 002 (1.00) i Which ONE of the following is correct concerning-the worth of the-regulating rod in the calculation of' Shutdown Margin (SDM) when-the regulating rod is NOT scramable.

l

a. The worth of the regulating rod is combined with the highest worth. control rod.

!~

b. The worth of-the regulating rod can be.used only if l- calculating.for cold-condition without Xenon.

!' c. The worth of the regulating; rod is alreadylconsideredLin the i . assumptions made for calculating SDM.

i l d. Only one-half of the regulating rod worth may-be used when; i determining shutdown reactivity.

i o

! MASERCOPY I

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B.- NORMAL /EMERG PROCELC ' , & RAD CdN . Paga 14 QUESTION: 003 (1.00)

Select the person authorized to release rec _ tags in accordance with S0P1 VI-D, Red Tag Procedures.

a.- AnysNSC staff member.

1

! b. Any membs~r of NSC management, providing-the SRO is notified.

c. Any licensed senior reactor operator, providing the SRO is=

1 notified, f

{ d. Onlf the SRO.

J l

I

- QUESTION: 004 (1.00) i 4

A reactor scram occurs due to high fuel element temperature. . Select the

- required followup action. ,

a. Perform an evaluation to determine if a. fuel element temperature safety limit-was exceeded.

3 b. Inspect tbe reactor fuel elements for damage in'accordance

with Tech Spec 4.2.4.

c. A. channel check of the fuel element temperature channel shall' be completed.

b l d.- The temperature measuring channels'must'be calibrated.

L 1-kASERCOPY i

(***** CATEGORYL B CONTINUED ON NEXT PAGE *****)

J

,- e- += r- , e- , ,.e- , - ,,r4- ,we'=rw-r--e.,t=>s- - - p.- x

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

1 B. -NORMAL /EMERG PROCEDURES & RAD CO'N Paga_15-

, _ QUESTION: 005 (1.00)

Select the statement that describes when the Period Scram Bypass Circuit- #

may be bypassed, and who is authorized to activate,the. bypass switch.-

a. During pulsing operations, _by the. Director, NSC

b. Any time, shutdown or during critical! operations, by the SRO

c. During reactor start-up, by the reactor operator i d. During steady-state critical operations,.by the Director, NSC t

e f

QUESTION: 006 (1.00)

. Which of-the below is correct concerning the use of extremity dosimetry

{

4 monitors such as TLD ring badges?

3

a. They are used only by personnel in thelhigh risk category when i

high extremity exposures are possible.

b. They are used only by personnel in.the low risk category when high extremity exposures are possible.

c. They are used by personnel in the high1and low risk category when high extremity exposures are possible.

4

d. They-are used'only by personnel in the high risk category.when i high extremity exposures are possible AND.their exposure-is NOT monitored daily.

7 i

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EERCOPY

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4.

. B. NORMAL /EMERG PROCEDURES & RAD CdN Pago 16 i

~

i

-QUESTION: 007 '(1.00)

, Which ONE of the following statements concerning the control of access to-

_ a High Radiation Area is allowable, in accordance with 10CFR20?

a. High Radiation-Area signs must be posted only when an individual has made an entry into the area, and the access

point will remain _ unlocked at all times.-

b. High Radiation Area signs must be posted at all times,_and the

. access-point must be maintained locked at all times'except during periods of access.

c. High Radiation Area signs must be posted only when an j -- individual has made an entry into the area, and the access-- -

. point must be maintained locked at all times.

i ,

d. High Rattation-Area signs must be posted at all times,_and no further controls are required for the access point..

e QUESTION: 008 (1.00)

[ If the dose from a-Gamma point source is 12 Rem /hr at a distance of 8 4 foot,-Nhat would be the approximate dose received:from 'ie same source at a distance of 12 feet?

~

i

{ a. 0.75 R/hr.

b. 5 R/hr.

1-

c. 12 R/hr.

d. 48 R/hr.

r NASlIRCOPY

(***** CATEGORY B CONTINUED ON'NEXT PAGE *****)

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

B.- NORMAL /EMERG PROCEDURES & RAD CO'N Paga 17=

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, s

+

3 1

QUESTION: 009 (1.00)

A transient during pulse operations of a TRIGA-FLIP core:-resulted in a.

temperature condition._ An_autom ic reactor scram failed to-

'high occu nd a manual scram-was successfu . Later investigation the highest. fuel element temperature was 2000 degrees-F with no 4 revea fuel damage. In accordance-with Tech. Specs., which ONE of~the below is-1 correct' based on the stated conditions?-

l a. This is a reportable occurrence based onJfailure of a reactor

safety system component.

b. Reactor operation may-not. resume until authorized by the'NRC. ,

5 c. A report must.be made to the: Reactor Safety Board'within~one j week.

t l d. Reactor-operation may not resume until authorized by the_-

r Chairman, Reactor Safety Board.

?

i e

i i

I QUESTION: 010 (1.00) 1 - - - - -

! In accordance with1the NSC Emergency Plan, who has the respcnsibility for j termination of an emergency?- Assume no emergency plan positions are-4 manned by backup personnel.

i-.

I a. Emergency Director i

l b. Emergency Coordinator j- c. Reactor Operator.

l d. The senior onsite member of NSC_ management- <

l' j

r Mar1reraR.it COPY a

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B. NORMAL /EMERG PROCEDURES & RAD CdN Page 18 QUESTION: 011 (1.00) ,

Which ONE of the below require' IMMEDIATE notification of the HRC in j accordance With NSC SOP VII-A3, Health Physics Administration?

1 i a. Whole body exposure of any individual of 5 rems.

I

{ b. Release of radioactive material whose 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months average' exceeds i 500-times the limits of 10CFR20, Appendix B, Table II.

l l c. A Loss of ono day or more of operation of any facilities j affected.

i d. Property damage in excess of $200,000.

i l

]

QUESTION: 012 (1.00)

] Which ONC of the below is the correctly-stated testriction which is placed i upon the reactor for steady state operatien to prevent exceeding the fuel temperature safuty limit due to power poet:ing?

a. In a mixed core configuration, the FLIP. region.is to be j located;in a contiguous central region with a minimum of 30 ;

FLIP elements.

I

b. The reactor shall not be taken critical with a core lattice i position vacant except for positions along the core periphery, i

! c. Water holes are not allowed in the inner fuel regions.

l j d. Instrumented elements utilized as the LSSS shall'be adjacent j to the central bundle without exception.

?-

f I

MASkRCOPY i

i t.

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B. NORMAL /EMVtG PROCEDURES & RAD CO'N Pago 19 QUESTION: 013 (1.00)

Which one of the below may be used to store irradiated fuel?

a. Only the Fuel Element Storage Room.

b. The Fuel Element Storage Room and Pool Floor Storage Rack.

c. Pool Wall Storage Racks and Pool Floor Storage Rack.

d. Only the Pool Floor Storage Rack.

QUESTION: 014 (1.00)

Which ONE of the below is the reason for keeping the lab receivers in the pnnumatic system closed except when loading or unloading a sample?

a. Prolonged opening will cause pool Icakage 'sto the transport hoses due to the pressure diffet9ntial.

b. They remain closed for neutron chielding purposes d. ring reactor co:e operation.

c. They remain closed to prevant any CO2 leakage past the isolation valve from entering the labs.

d. Prolonged opening will introduce air into the system and result in high levels of radioactive AR-41.

MASRRCCPY

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l 3 B. NORMAL /EMERG PROCEDURES & RAD CO'N Pags 20 i

)

} QUESTION: 015 (1.00)

In performing a power calibration, a difference between indicated and -

measured power is 104. Which ONE of the below is correct based on this information?

l a. Position the detector tor the channel that indicates an l " adjustment to be made" to indicate actual power.

1

b. This calculation is suspect and may_ indicate thermocouple

grounding or improper ice bath preparation.

c. Adjustments to power instrumentation cannot be performed under !

f any circumstances if the difference is greater than 5%.

I

d. This calculation is suspect and indicates a "shadcWing i

effect".

I 1

l QUESTION: 016 (1.00)

The following statement pertains to one of the control rod calibration methods as defined in NSC SOP II-K, Control Rod Calibration.

"The accuracy of this method is affected by detector / control rod

geometry. Poor geometry may yield appreciable error such that thin method will be generally useful only in obtaining approximations for control rod worth".

Which one of the below 3s the tothod described in the preceding paragraph?

j a. Rod Drop Method

'- b. Positive Period Method

> c. Positive Period-Differential Worth Method-

d. Differential Worth Method J

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B. NORMAL /EMERG PROCEDURES & RAD CdH Page 21 QUESTION: 017 (1.00)

The reactivity worth of a particular experiment is determined to be $1.50.

Which ONE of the below is correct concerning this experiment?

a. The experiment cannot be allowed in the core due to an excessive reactivity value.

b. Th+c cyperin?nt can be placed in the core as a non-secured exportment,

c. The experiment is allowed in the core providing analysis indicates the worth is such that removal will not exceed the safety limit.

d. The experiment in allowed in the core but must be secured.

QUESTION: 018 (1.00)

Which ONE of the below lists the emergency classes for the NSCR from LEAST severe to MOST severe?

L. Alert, Operational Event, Reportable Occurrence,

b. Operational Event, Reportable Occurrence, Alert l' c. Operational Event, Notification of Unusual Event, Alert l d. Notitication of Unusual Event, Operational Event, Alert i

4 l MASTBCOPY l.

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i

B. NORMAL /EMERG PROCEDURES & RAD Ccp Pcg3 22 QUESTION: 019 (1.00)

Which ONE of the below radiation monitor alarms procedurally directs vorification the reactor is shutdown as one of the first actions?

a. Channel 2, Fission Product Particulates AND Channel 3, Stack Gas.

b. Channel 1, Stack Particulates AND Channel C, Duilding Gas.

c. Channel 2, Fission Product Particulates.

d. Channel 3, Stack Gas.

QUESTJON: 020 (1.00)

An area has been roped off five feet from an experiment producing 2500 mrem /5r at 18 inches. Which ONE of the below is the correct boundary posting for this situation?

a. RADIATION AREA.

b. HIGH RADIATION AREA.

c. EXCLUSION AREA.

d. RADIOACTIVE MATERIALS MGOPY

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

C. PIANT AND RAD MONITORING SYSTEMS Pugs 23 1

?

QUESTION: 001 (1.00)

. Which ONE of the below correctly completes the following statement concerning the Facility Air Monitorina System?

l .

l The Facility Air Monitoring System used at the Nuclear Science

, Center consists of several diacrete channels each of which perform ;

l a seperate function. Tnese channel consist of Sodium Iodide ;

(T1) scintillators for radiations and j 3 scintillators for particulate radiations,

a. 2, gamma, gaseous, beta b.

2, beta, particulate, gamma

c. 3, gamma, gaseous, beta i i d. 3, beta, particulate, gamma u

1 l QUESTION: 002 (1.00)

Which ONE of the below correctly completes the statement?

r Fuel designated as FLIP is almost identical to the standard TRIGA fuel excepts

a. it has a calculated lifetime of 13 Mw-years.. <

b. the hydrogen to zirconium ratio was increased.

c. natural erbium was added as a burnable poison.

d. the enrichment was decreased.

MLSIBCOPY i i

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

i i

l-

. , _ _ . . , . . . - , . , - . _ . .- . . . _ _ . _..-.....-#...__ _ _ , , ._..,-,_,.r . _,m. _ _ _ , _ . _ .

l l l ,

I c. PLANT AL ,<AD MONITORING SYSTEMd Page 24 .

i ;

) .

1 i

ot'3STION: 003 (1.00) i Which control rod (s) have scram capability? l l

a. Only shim-safety rods.

b. The transient control rod and the regulating rod.

E c. Shim-safety rods and the transient rod.

1 j d. Shim-safety rods, transient rod, and regulating rod. l i

i '

j i

1 j QUESTION: 004 (1.00)

{ Pool _ makeup is provided by raw water, which enters the purification .

system

a. at.the suction of the demineralizer recirculation pump.

l b. between the demineralizer recirculation pump and the activated i charcoal filter.

. c. -between the mixed bed demineralizer and the cotton-wound- '

l cartridge filter.

I.

d. between the voixed bed demineralizer and the activated charcoal f11ter.

l 4

i' r

L 1-ggiaCTY :

l l

l-j: (#****

6 CATEGORY C' CONTINUED ON NEXT_PAGE *****)

em e- -cm--.---y-,ym,,,+-,$,,.,9# ye % y. m,-,-9 , y,,,,-g.w-,~w.,y ,y.,-+-,,,yy., -

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yswrr t ,w-r a w -i mpe e - w- * -ece,we- e, wg

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

i I

i C. PLANT AND RAD MONITORING SYSTEM $ Pago 25 1

(

{

i i

l QUESTION: 005 (1.00)

! The emergency exhauat air filter system, installed between the exhaust fan !

and the exhaust stack, consists of:

l i

a. ONE activated carbon filter bank, and TWO particulate filter l banks.

{

! b. ONE activated carbon filter bank, and ONE particulate filter .

l bank. -

I- c. TWO activated carbon filter banks, and ONE particulate filter bank.

TWO activated carbon filter _ banks, and TWO particulate' filter j_ d.

4 banks.

QUESTION: 006 (1.00) l The confinement ventilation system divides the occupied spaces into zones l

. of varying presrure for control of the spread of contamination. Which ONE combination listed below describes these zones in order of LEAST to GREATEST NEGATIVE PRESSURE?

, a. Lower research level.- upper research level'- control room '

b. Lower research level . electronics _ shop - upper research level

c. Upper research level - lower research level - control room

d. Control room - Upper research level - lower research level f

1 ,

1

(***** CATEGORY _ _C CONTINUED ON NEXT PAGE *****)

. _ _ . _ . . .._-._,a_.. . _ . . . _ . . . . - . - , , _ . _ . _ - . ,_,_ .._....2_...., ..s,_.._ , _ . _ - _ . - -.._ .a .a..

C. PLANT AND RAD MONITORING SYSTEM $ Pago 26 QUESTION: 007 (1.00)

Which ONE of the below describes thu functicn of the reactor safety plate assembly?

t

a. Retains a control rod follower should it become detached from

! its mounting.

i

b. Provide additional support to the reactor grid plate for the use of highly enriched FLIP fuel elements.

, c. Is located above the reactor grid plate.

d. Allows passage of the fueled section of the control rods.

QUESTION: 008 (1.00)

The transient rod drive is equipped with limit swicches which actuate to provide indication of:

a. air cylinder upper limit, air cylinder lower limit, and piston upper limit.

b. piston upper limit, piston lower limit, and air cylinder lower limit.

c. piston upper limit, piston lower limit, and air cylinder upper limit.

i

d. air tylinder upper limit, air cylinder lower limit, and piston 3 lower limit.

QSIBC)PY

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

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- , . . . , - , . - - - - - - . - , - , . , y -

i j C. PLANT AND RAD MONITORING SYSTEM $ Pago 27 !

,i 1_

i i

j QUESTION: 009 (1.00) I Which ONE of the below is correct concerning movement of the transient control rod?

a. An interlock prevents electromechanical withdrawal when l reactor power is greTter than 400 watts.

I b. The piston must be in the full _up position before air can be

applied for steady state operation. '

j

c. An interlock prevents application of air to the piston when l all shim-cafety rods are withdrawn using the gang switch.

d. The transient control rod will move only if all shim-safety rods are stationary. 4 1

4 QUESTION: 010 (1.00)

Which ONE of the-below describes the-indications available in the reactor l control room for monitoring the pool water cooling system?

l a. Loss of primary flow alarm, primary; flow rate indicator, pool-water pH meter.

b. Loss of secondary flow alarm, primary flow-rate indicator, pool water temperature recorder.

c. Loss of primary flow alarm,- secondary flow rate indicator, pool water temperature recorder. ~

d. Loss of secondary flow alarm, secondary flow rate indicator, ~

pool water: conductivity meter.

L l

UASlIRCOPY .

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

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

C. PLANT'AND RAD MONITORING SYSTEMS Pago 28 a

i i

1 j QUESTION: 011 (1.00) i Which ONE of the following reactor safety circuits is required to be j operational in BOTH the steady state and prise modes?

4 j a. Log power low power interlock.

b. High power level detector low vol', age scram. '

c. High power level scram.

d. Fuel element temperature scram.

i

1 i

i

! QUESTION: 012 (1.00) i What protection is provided for the-reactor pool should a loss of beam l port integrity occur?

i

a. The-106,000 gallons of water contained in the pool and-stall.

j b.. The pool recirculation. pump shuts.off and pool-capacity is so

large that any leak can be corrected before the core uncovers.

c. None is required as the NSC. Safety Analysis Report does not

} identify this as a plausible consideration.

d. Two raw water emergency fill lines, i .

1 I

+

MASTBC0?Y 1

k k

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

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-- n C. PLANT AND RAD MONITORING SYSTEMS Paga 29 QUESTION: 013 (1.00)

In the event of a building vnntilation isolation, the emergency exhaust system can be operated in a manual modo from the:

a. Emergency Operating Panel in the central mechanical chase.

b. Radiation Release Monitoring Panel in the Health Physicist's Office.

c. Air Handling Control Panel in the reception room.

d. Supervisor's Console in the control room.

QUESTION: 014 (1.00)

Which ONE of the following statements describes system response if pool lovel drops to less than 90%?

a. Two float switches actuate, one switch shuts down the pool water recirculation pump and another switch energizes an alarm in the Univerwity Communications Room,

b. Two floct switches actuate, either one of whica shuts down the pool water recirculation pump and energizes an alarm in thn University Communications-Room.

c. A single float switch shuts down the-pool water l recirculation pump and energizes an-alarm in the University Communico,tions Room.

d. A single float switch actuates to energize;an. alarm in-the University Communications Room, while the pool water, recirculation the reactor, pump continues to operate to_ provide cooling for s

1

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

<- 1

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

.- - . .-- - . . - - - .. .=.- - . - . .. .

l i.

I i C. PLANT AND RAD MONITORING SYSTEMS Pago 30 i

)1 i

QUESTION: 015 (1.00) l 1

During a scram, mechar. cal shock to the shim safety rods is minimized by:

a. a hydraulic dashpot in the core safety plate.

b. mechanical springs at the top of the control rod barrel, i c. a mechanical-hydraulic dashpot in the control rod drive motor i

assembly.

d. the armature piston entering the bottom of the control rod j barrel.

J l

d

QUESTION: Olb (1.00)

! All cf the below are options provided by the Radioactive Liquid Waste Disposal System EXCEPT:

j a. evaporation and solidification of liquid waste.

I b. draining liquid waste to the creek, i

c. . storing 15c'id waste for radioactive decay.

d. diluting liquid waste to comply with 10CRF20-limits.

J f

MASERC:PY i

~

i

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

4

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._ ____ _ _.____ _ _ . . _ _ _ . - _ . _ . _ . _ _ . _ _ . _ _ _ _ _ ~ . . _ . _ _ _ _ _ . ._ __-_.

1 1 :

g C. PLANT AND RAD MONITORING SYSTEMS Pago 31 i

l QUESTIO'J: 017 (1.00)

i i

Which ONE of the following Facility Air Monitoring Systems initiates a z shutdown of the air handling system AND shut air dampers on receipt of an- -

alarm?

a. Building gaseous.

b. Building particulate.

i i c. Stack gaseous. -

j d. Fission product monitor.

i i

i

! QUESTION: 018 (1.00) i j The purpose of the Core Diffuser System is to:

i

a. maintain the pool surface clean, and free of debris.

I j b. improve core heat tr6nsfer by circulating water above the core.

c. maintain pool water purity and pH.

l d. reduce dose-rates at the pool surface.

l

\

l QUESTION: 019 ;(1.00) r

Which ONE of the following is used to detect fission product gases?

h a. A scintillation crystal and gamma' spectrometer. l l -

l- b. -A low sensitivity GM-detector using' filter _ paper.

i. .

c. A scintillation crystal using filter papers

d. A high sensitivity GM detector using ch'arcoal filters.

MER:0?Y

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

I

- _ . _ . - . _ , _ ___ _._ _ _ _ __ -_ .-._ , _. _ _ __ ._ .. ~. . _ _ _. _ .. _ ,__,_-_ - _ .

i C. PLANT AND RAD MONITORING SYSTEM $ Page 32 l

l i

i !

j. QUESTION: 320 (1.00) i j Techn4 cal Specifications 2.1 and the SAR set a limiting safety system l setting for TRIGA fuels. Select the phenomenon that would result from ,

j exceeding peak core temperature, 1

a. Phase change in the type 304 stainless steal, that reduces j yield strength, resulting in clad failure.

b. Zirconium hydride swelling, rasulting in clad failure.

1 :

c. Hydrogen over pressurization from the disassociation of l zirconium hydride, resulting in clad failure.

j d. Metallic creep -in the type 304 stainless steel, resulting in !

clad failure.

i i

i I.'

i i

l i

Y i

I 3

t i '

l L

WSTERCCPY 7

t

(***** END OF. CATEGORY- C *****)

(**********

END-OF EXAMINATION-**********) .

i

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A. RX THEORY, THERMO & FAC OP CHARS Page 33 O

ANSWER: 001 (1.00)

, ETEC9Y

REFERENCE:

Basic Nuc. Engineering (Fostor & Wright) - 3rd Ed., pp. 304-307.

ANSWER: 002 (1.00) b

REFERENCE:

Basic Nuc. Engineering (Foster & Wright) - 3rd Ed., pp. 304-307.

ANSWER: 003 (1.00) 1 f

i

/

REFERENCE:

Glasstone and Sesonske, 5.40 - 5.48, pages 244-247.

(***** CATEGORY A CONTIt'UED ON NEXT PAGE * * * * * )

i A. RX THEORY, TliERMO & FAC OP CHAR $ Pcg3 34 o

1 ,

j ANSWER: 004 (1.00) l I

I

, c.

4 (T = t / Ln(n /n) = 20 sec / Ln(60/40) = 49.3 seconds.)

1 0 l l

1

'tEFERENCE:

s Intro. to Nuc. Engnring. (LaMarsh) -

2nd Ed., p. 284.

t t-AriSWER: 005 (1.00) i b i

i t

REFERENCF b

Basic Nuc. Engineering (Foster & Wright) -

3rd Ed., pp. 289-293.

l l

i j ANSWER: 006 (1.00) i i-5 f

d l

i

(***** CATEGORY- A CONTINUED CN NEXT PAGE *****)

s.

I

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~

A. RX TifEORY, THERMO & FAC OP CHAKS Pago 35 .

E

REFERENCE:

i l Basic Nuc. Engineering (Foster & Wright) - 3rd Ed., pp. 289-293.

d l ANSWER: 007 (1.00) j a.

i

REFERENCE:

4 i

Intro. to Nuc. Engnring. (LaMarch) - 2nd Ed., pp. 102-103, 288-290.

1, 4 ANSWEh! 008 (1.00) 1 4

, C 1

REFERENCE:

I Intro. to Nuc. Engnring. (LaMarsh) - 2nd Ed., .. 289.

e t ANSWER: 009 (1.00) b i

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

4

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A. RX THEORY, THERMO & FAC OP CHAR $ Pago 36

REFERENCE:

Glasstone & Sesons):e 8.65 ANSWER: 010 (1.00) 1 c (T = 1*/ Rho. T ' 10E-OS/.0070. T = .00143.

P/Po = eEt/T. P/Po = eFO.01/.00143. P/Po = eE6.99. P/Po = 1,089.)

't i

l

REFERENCE:

1 4

Intro. to Nuc. Engnring. (LaMarsh) - 2nd Ed., pp. 278 286.

L j ANSWER: 011 (1.00),

, d l

REFERENCE:

l Basic Reactor Theory; TAMU NSC SAR section III.C.3, p. 53 l

l' l

l ANSWER: 012 (1.00) i I

d-(***** CATEGORY _ A CONTINUED ON NEXT PAGE *****)

l

-.. -. .. .. .=. . . . .. .. .- .. .. . .-

A. RX TdEORY, THERMO & FAC OP CHAR $ Pago 37 1

a

REFERENCE:

Basic Thermodynamic Theory; TAMU NSC SAR section III.D, p. 53 J

i i

i ANSWER: 013 (1. 00) i C

REFERENCE:

4

Nuclear Reactor Theory, p. 113-114; Lamarsh i

i i

ANSWER: 014 (1. 00) 1 i b 4

REFERENCE:

4 Nuclear Reactor Theory p. 98; Lamarsh 4

a ANSWER: 015 (1.00) [

a 4

(*****

CATEGORY A CCNTINUED ON NEXT PAGE *****)

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l l A. RX TilEORY, TilERMO & FAC OP Cl{AR$ Pcgs 38 I

REFERENCE:

Nuclear Reactor Engineering, p.260; Glasstone & Sesonske ANSWER: 016 (1.00) e

REFERENCE:

Lamarsh, 3.7 ANSWER: 017 (1.00) e

REFERENCE:

Basic Reactor Theory i

ANSWER: 018 (1.00)

' a

-(***** CATEGORY A CONTINUED ON NEXT PA JE * * * * * )

A. RX THEORY, THERMO & FAC OP CHARS Pago 39 REFERENCEt Lamarsh 7.1 ANSWER: 019 (1.00) h

REFERENCE:

TAMU NSC SAR pp. 14, 18, 50 ANSWER: 020 (1.00) b

REFERENCE:

Nuclear Reactor Theory p. 449; Lamarsh

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

i

B. NORMAL /EMERG PROCEDURES t RAD CCN Pago 40 ANSWER: 001 (1.00) d

REFERENCE:

TAMU NSC SOP II-C pgs. I and 3 ANSWER: 002 (1.00) a

REFERENCE:

NSC Tech specs 3.1.3, page 13.

< s ANSWER: 003 (1.00) d

REFERENCE:

TAMU NSC SOP VI-D p.2 l

(***** CATEGORY B CONTINUED ON NEXT-PAGE *****)

i

B. NORMAL /D4 ERG PROCEDURES & RAD CON Paga 41 ANSWER: 004 (1.00) a

REFERENCE:

TAMU NSC Tech Spec 4.3.2, page 35 ANSWER: 005 (1.00) b

REFERENCE:

TAMU NSC SOP II-D p.3' l

l l

ANSWER: 006 (1.00)

C

REFERENCE:

~

NSC SOP VII-Ei, page 2.

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

B. NORMAL /EMERG PROCEDURES & RAD CON Pogo 42 ANSWER: 007 (1.00) b

REFERENCE:

10CFR20. 2 03 (c)

ANSWER: 008 (1.00) b Dose rate inversely proportional to the ratio of the distance.s squared.

(8/12) squared = .4444

.444 X 12 Rem /hr = 5.333

REFERENCE:

Glasstone/Sesonske, Nuclear Reactor Engineering, Section 9.40, Page 524.

ANSWER:' 009 (1.00) i a

l l

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

B. NORMAL /EMERG PROCEDURES & RAD CON Pago 43

REFERENCE:

NSC Tech Spec Sections 1.29, 2.1, and 6.5, paqas 5, 8, 53.

ANSWER: 010 (1.00) a

REFERENCE:

NSC Emergency Plan, SOP IX-C, page 3.

l JNSWER: 011 (1.00) d

REFERENCE:

NSC SOP VII-A3, page 1.

t ANSWER: 012 (1.00) b

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

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

B. NORMAL /EMERG PROCEDURES & RAD CON Pcgs 44

REFERENCE:

NSC SOP II-D, page 1.

ANSWER: 013 (1.00)

C l

REFERENCE:

NSC SOP II-H, page 7.

ANSWER: 014 (1.00) d

REFERENCE:

TAMU NSC SOP IV-C p.1 i

4

, ANSWER: 015 (1.00) b

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

B. NORMAL /EMERG PROCEDURES & RAD CON Pago 45

REFERENCE:

NSC SOP II-J, page 1-3.

ANSWER: 016 (1.00) a

REFERENCE:

NSC SOP II-K, pags 1-2.

ANSWER: 017 (1.00)

I d.

REFERENCE:

NSC Tech Specs 3.6.1, page 23, l

ANSWER: 018 (1.00)

{

i c l'

t l (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

l

B. NORMAL /EMERG PilOCEDURES & RAD CON Page 46

REFERENCE:

NSC SGP IX-A, page 4.

o ANSWER: 019 (1.00) n.c .

) 6

{ A 3 .r.2, .NCE:

SOP VII-A, pays 7. -

D

/

4 ANSWER: 020 (1.00) [

l b

REFERENCE-10CPt20 IoDo = IfDf2 This calculation results in 225 mrem /hr at five feet meeting the requirements of the high radiation area posting.

f

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

C. . PLANT A!!D RAD MONITORING SYSTEMS ,

Pago 47 4

P ANSWER: 001 (1.00) a 4

REFERENCE:

i NSC SOP VII-B4, page 5.

ANSWER: 002 (1.00) e

REFERENCE:

NSC SAR Section III, page 11.

l

ANSWER: 003 (1.00) i i C l

REFERENCE:

NSC SAR Section III, page 22.

I l

i

(***** CATEGOR'l C CONTINUED ON NEYT PAGE *****)

A

C. PLANT AND RAD MONITORING SYSTEMS Pcgo 48 i

ANSWER: 00% (1.00) 4

,t i

D

REFERENCE:

4 TAMU NSCR SAR, Fig. 4-7.

i e

l ANSWER: 005 (1.00) i

a

[ -

REFERENCE:

TAMU NSCR SAR, p. 79.

I l

ANSWER: 006 (1.00) l

d.

i i-

REFERENCE:

i i SAR V.B.1, page 79.

l I

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

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e< - , .w sv-

C. PLANT AND RAD MONITORING SYSTEM $ Paga 49 ANSWER: 007 (1.00) a

REFERENCE:

TAMU NSCR SAR, p. 14.

ANSWER: 008 (1.00) d

REFERENCE:

TAMU NSCR SAR, p . 9 9 .' -

ANSWER? 009 (1.00) d.

l-

REFERENCE:

l NSC SAR lage 99.

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

C. PLANT AND RAD MONITORING SYSTEMS Pago 50 ANSWER: 010 (1.00) b

REFERENCE:

NSC SAR, P. 65 ANSWER: 011 (1.00) d B

REFERENCE:

NSC Tech Specs 3.2.2, Table 1.

~ANSWFR: 012 (1.00) d-(***** CATEGOnY C CONTINUED ON NEXT PAGE *****)

I i

C. PLANT AND RAD MONITORING SYSTEMS Pago 51

f.

REFERENCE:

J NSC SAR t. age 112.

i ANSWER: 013 (1.00) c.

i

^

REFERENCE:

i SAR V.B.3, VIII-A; Modification Authorization M-14 4

1 l ANSWER: 014 (1.00) i C.

i

REFERENCE:

3 SAR, VIII.G.1 l

ANSWER: 015 (1.00) d.

l 1

4

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

I

C. PLANT AliD RAD MONITORING , SYSTEMS Pagn 52

REFERENCE:

SAR III.B.7 ANSWER: 016 (1.00) a.

i a

REFERENCE:

SAR IX.B.2 a

i-j ANSWEP: 017 (1.00)

d. ,

REFERENCE:

SAR IX.F, page 119.

4 1

- ANSWER: 018 (1.00) d.

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

C. PLANT AND RAD MONITORING SYSTEMS _Paga 53

REFERENCE:

SAR IV.b.2.d, page 68.

ANSWER: 019 (1.00) b

REFERENCE:

NSC SAR IX.F, Page 119.

ANSWER: 020 (1.00) l C ,

REFERENCE:

l TAMU NSC SAR p. 128, TAMU Tech Spec 2.1 p.8

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

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

l 1

A. RX THEORY, THERM 0 & FAC OP-LHARS Page 1-ANSWER KEY 001 b 002 b l

. 003 c d

j. 004 c 4

005 b 4

006 a 007- a I

008 c r

009 b i

010 c 011 d i

012 d 013 c f 014 b 015 a j 016 c a

017- c 018. a ..

^

019 b 020 b

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

+

4 4

W t

E

}

,, , rem.. ,,rc-,e c-+ ,-++ v *wc.<,. - + , , , = +

1

,a B.

i NORMAL /EMERG PROCEDURES & RAD CON Page 2 i

4 ANSWER KEY 001 d l

002 a 4

3 003 d

. 004 a 005 b 1

006 c f

l 007 b 4

008 b 4

. 009 a j 010 a 4

011 d 012 b 013 c 4

014 d i

! 015 b 016 a i

017 d

, 018 c 019 c 020 b i

(***** END OF-CATEGORY R *****)

I i

i i

, , - - - - m--* . =$y w. ,+w- .y

e y g+- -y--

N C. PLANT AND RAD MONITORING SYSTEMS Page 3 ANSWER KEY 001 a 002 c 003 c 004 b 005 a i 006 d

, 007 a 008 d 3

009 d 4

010 b T

011 d

012 d 013 c 4

4 014 c 015 d i

4 016 a 017 d 018 d 019 b 020 c

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

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

+

, - . 4

~

l EQUATION SHEET Net Work (out)

Q = m c, AT Cycle Efficiency -

Energy (in)

Q = m ah SCR = S/(1-Keff)

Q = UA AT CR (1-Keff)3 3

CR2 (1-Keff)2 26.06 (A,,p) (1-Keff)o SUR = M= -

(B - p) (1-Keff)3 SUR = 26.co/r M = 1/(1-Keff) = CR /CRo 3 P = Po 10"" SDM = (1-Keff)/Keff e.

P = Po e* Pwr - W, m B(1-0)

P= P, l' = 1 x 10 seconds B-p -

r - (f'/p) + [(8-p)/A ,p) r=t'/(p-8) p = (Keff-1)/Keff A,.i = 0.1 seconds

p = oKeff/Keff 0,693 I112

B = 0.0077 A 2

DR3D3 = DR2a D' DR = DRo e

1 Curie - 3.7x10' dps 1 kg - 2.21 lbm I hp - 2.54x10 8BTU /hr 1 Mw = 3.41x10 BTV/hr 8

1 BT!' = 778 ft-lbf 'F = 9/5*C + 32

?

C = 5/9 (*F - 32) w_ , . . .. .. .

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

ML20115G633

Text

Dear hir. Collins:

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