Text

Exam Rept 50-128/OL-93-02 on 930518.Exam Results:Applicant Passed Both Written Exam & Operating Evaluation
	ML20056C457
Person / Time
Site:	05000128
Issue date:	06/07/1993
From:	Caldwell J, Collins F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20056C456	List: ML20056C455; ML20056C457;
References
	50-128-OL-93-02, 50-128-OL-93-2, NUDOCS 9306240158
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l ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION

~ OPERATOR LICENSING INITIAL EXAMINATION REPORT l l

REPORT NO.: 50-128/0L-93-02 >

FACILITY DOCKET NO : 50-128 FACILITY LICENSE NO : R-83 FACILITY: Texas A&M University EXAMINATION DATES: May 18, 1993 EXAMINER: Fra i faminer SUBMITTED BY:

di nk ollins, C 'ef xaminer

[ 7/M D6te,-

APPROVED BY: fyMf/)

Jame . 'Caldweil, Chief Date Non Power Reactor Section Ope ator Licensing Branch Division of Reactor Controls 'i and Human factors Office of Nuclear Reactor Regulation t

SUMMARY

An operator licensing initial examination was conducted at the Texas Engineering Experiment Station Triga reactor on May 18, 1993. Written and operating evaluations were administered by Mr. Frank Collins to one Reactor Operator (RO) applicant. The applicant passed both the written examination and the operating evaluation.

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9306240158 930608 PDR ADOCK 05000128 .

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rep 0RT DETAILS

1. Examiners:

Frank Collins, . Chief Examiner .

2. Results:

R0 SRO Total .

(Pass / Fail) (Pass / Fail) (pass / Fail) :

NRC' Grading: 1/0 0/0 1/0

3. Written Examination:

The written examination was administered on Tuesday, May 18, 1993. The applicant completed.the examination within the allotted three hour's. A copy-of the examination was concurrently provided to facility management for review and comment. No clarifications were requested by the applicant during the examination.

Facility comments were received within.one week followi_ng the-examination in accordance with the provisions of Examiner Standard ES-201 .ind are included as an attachment to this.' report. Two changes. ,

were requested by the' facility. Question C-10 was deleted in accordance with the facility's recommendation since' incorrect. wording in-the stem of the question resulted 'in three correct answers. Question C-13 was changed to accept either option a) or option b) as a correct response due to' ambiguous component identification in-the stem of the question.

4. 0perating Tests:

The operating evaluation was administered on' Tuesday, May 18, 1993. The ;

examination included a normal reactor startup and pulsing operations. l The applicant passed all sections of the operating evaluation.

5. Exit Meeting:

An exit meeting was conducted on Tuesday, May'18,-1993 between Mr'.

Collins and Mr. Bill Asher, Manager,. Reactor Operatic >ns. The Chief . :

Examiner thanked the facility for support during the examination and reviewed the conduct of the-written and operating evaluations. . Specific examination.results were 'not yet available, pending incorporation or ,

resolution of. formally submitted facility comments on the written. .

examination and grading:of the operating evaluation.

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.i TEXAS ENGINEERING EXPERIMENT STATION- l TEXAS A&M UNIVERSITY --

COLLEGE STATION, TEXAS 77843-3575 1 WW4L _

24 May 1993 NUCLEAR SCIENCE CENTER 409/845-7551.

Mr. Frank Collins' 93-0165 Division of Licensee Performance

.~and Evaluation U.S. Nuclear Regulatory Commission Mail Stop 10-D-22, O.W.F.N.

Washington, D.C. 20555

Dear Mr. Collins:

r After reviewing the Operator Licensing-Examination, which was i administered at the Texas A&M University-Nuclear _ Science l Center.

on 18 May 1993,-I have comments concerning the following questions

Section C. Plant and Radiation Monitoring System a

Question: -010 ,

There are three-(3) correct answers to-this question. The'only-scram that can be bypassed is the Period ~ Scram'(RefLSOP II-d-4). .

Consequently, I recommend that this question be removed from the exam. ;

Question: 013 The termin' ology " Shield Floor" in this question could cause.some confusion. The entry into the cave is through the'" Cave = Door"

.which would cause a reactor scram and an audible alarm. However, '

opening the shield block on-the top.of the cave will cause an; '

audible alarm only (Ref SOP.IV-f, Figures IV-F-l'and IV-F-3).

Consequently, I recommend that this question be removed from the.

exam.

' RESEARCH AND DEVELOPMENT FOR MANKIND '

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Mr. Frank Collins 93-0165 Page 2 Aside from the two aforementioned questions I felt that this was an excellent examination. If you have any questions please contact me at (409) 845-7551.

Sincerely,

$f Bill F. Asher Manager Reactor Operations l:

BFA/ym xc: W. D. Reece, Director, NSC B.S. Carlisle, Director, NSC i

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UNITED STATES NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING EXAMINATION MASTER COPY l

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TEXAS ENGINEERING EXPERIMENT STATION TEXAS A&M UNIVERSITY TRIGA REACTOR 05/18/93

. ;i NRC'0FFICIAL USE ONLY NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING EXAMINATION THIS DOCUMENT IS REMOVED FROM OFFICIAL USE ONLY CATEGORY'ON DATE OF EXAMINATION NRC 0FFICIAL USE ONLY

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Texas A&M REACTOR TYPE: TRIGA DATE ADMINISTERED: 93/05/18 fifl.q..=.r.]f=:r j ut .

El o!%s v Ed t %#\ji ! REGION: 4 CANDIDATE:

LICENSE APPLIED FOR:

INSTRUCTIONS TO CANDIDATE:

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 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 CATEGORY % OF CANDIDATE'S. CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 hs 3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS

\ 3- B. NORMAL AND EMERGENCY OPERATING 4.\$@20.00 PROCEDURES AND RADIOLOGICAL

\T CONTROLS IQ 32.2

-20.00 -M WJ3 C. PLANT AND RADIATION MONITORING j SYSTEMS !

5~'/ -

-&O.00 TOTALF

% l FINAL GRADE I 1

All work done on this examination is my own. I have neither.given nor- l received aid. ,p 4 g pf p y 0ba ! r l Candidate's Signature

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

'During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic 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 own 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. ,

5. 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).

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-7. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication 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 tbts area while the examination is still in progress, your license may be denied or revoked.

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A..RX' THEORY, THERMO & FAC OP. CHARS Page 3 QUESTION: 001 _(1. 00)

-Which one of the below describes why neutron sources are used in reactor' cores?

a. Increase the count rate by an amount equal to the source ;

contribution.

b. Increase the count rate by 1/M (M = Suberitical 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. ,

C QUESTION: 002 (1.00) !

Which one of the below characterizes heat transfer from the' fuel.

cladding surface to the coolant with the reactor operating'at 100% rated.

. power?

a. Nucleate boiling.

b. Conduction. ['

c. Radiation.

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d. Convection. ,

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A. 'RXLTHEORY, THERMO & FAC OP CHARS Page 4-

-QUESTION: 003 (1.00)

Which ONE of the below is the hottest part of the_ fuel element during steady state operation and immediately following a pulse?

Steady State Pulse

a. Center Outside edge

b. Outside edge Center

c. Center Center

d. Outside edge Outside edge QUESTION: 004 (1.00)

Which one of the below describes the difference between a reflector and a moderator?

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

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

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

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

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' - A. RX THEORY,L THERMO &_FAC OP' CHARS Page 5

. QUESTION: 005 (1.00)

-Which one of the below describes the inherent safety feature provided by the moderator. temperature coefficient of reactivity?

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

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

c. Its positive value causes reactivity to increase as moderator temperature increases.

d. Its-positive value causes reactivity to decrease as moderator temperature increases.

QUESTION: 006 (1.00)

Which one of the following algebraic terms represents the effective multiplication factor (Keff)?

of neutrons produced from all fission

a. --------------------------------------- I

of neutrons in the previous generation

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of neutrons produced from fast fission l

b. -------------------------------------------

of neutrons produced from thermal fission l l

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of neutrons absorbed in the fuel

c. ------------------------------------------

of neutrons absorbed by fission products

of neutrons in the present generation d.----------------------------------------

of neutrons in the previous generation

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A. RX THEORY, THERMO & FAC OP CHARS Page 6 QUESTION: 007 (1.00)

Complete the following statement' assuming identical pulse reactivity

-insertions.are performed on FLIP and Standard TRIGA cores.

The core would see the highest peak power, the core would see the widest pulse width, and the core would see the highest fuel temperature.

a. Standard, Standard, FLIP.

b. FLIP, FLIP, Standard.

c. FLIP, Standard, FLIP

d. Standard, FLIP, Standard.

QUESTION: 008 (1.00)

Delayed neutrons comprise approximately what percent of all neutrons produced in the reactor?

a. 0.75%

b. 1.5% '

c. 5.0%

d. 10%

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A. IO( . THEORY, THERMO &'FAC OP CHARS Page 7 QUESTION: 009 (1.00)

Which one of the followJng accurately details the effect that fuel ;

temperature has on core operating characteristics?

a. Increase in fuel temperature will decrease the resonance escape- ,

probability.

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

c. Fuel temperature decrease results in Doppler Broadening of U-238 and Pu-240 resonance peaks and the decrease of resonance escape probability.

d. Fuel temperature increase results in Doppler Broadening of U-238 ,

and Pu-240 resonance peaks and the decrease of neutron absorption during moderation.

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QUESTION: 010 (1.00)

Which one of the below describes the change to the delayed neutron fraction, B(beta), over core life?

a. Pu-239 concentration increases causing B to increase.

b. Temperature coefficient of reactivity increases causing B to increase.

c. Pu-239 concentration increases causing B to decrease.

d. Temperature coefficient of reactivity increases causing B to decrease.

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A.' RX THEORY) THERMO & FAC OP CHARS Page 8 .i QUESTION: 011 (1.00) -

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A subcritical reactor is being started up. The operator withdraws the shim safety rods (in gang] to the critical position in four (4) equal steps. Which one of the below accurately characterizes reactor-

-behavior? *

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

b. Reactor power will increase by the same amount for each withdrawal 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.

s QUESTION: 012 (1.00) '

Which of the following factors has the LEAST effect on rod worth?

a. Number and location of adjacent rods.

b. Temperature of the moderator. I

c. Temperature of the fuel.

d. Core age.

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' " A .' ' RX THEORY, THERMO & FAC OP, CHARS- Page 9-QUESTION: 013 (1.00). ,

'A reactor with an: initial population of 24000 neutrons is operating with Keff = 1.01. Considering only the increase in' neutron population, how many neutrons will-be prompt when the neutron population changes from the current generation to the next?

a. 25

b. 238

c. 2500

d. 24240 -

QUESTION: 014 (1.00)

Tci ensure stored fuel and sources remain subcritical, Technical

' Specifications place limits on the:

a. effective multiplication factor,

b. infinite multiplication factor,

c. effective decay factor.

d. mean migration factor.

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A.- RX' THEORY,'THERMO & FAC OP CHARS Page 10

. QUESTION: 015. (1.00) 101 initial count rate of 100 is doubled five times during startup.

Assuming initial Keff = 0.950, which one of the belowlis the new Keff? -

a. 0.957 *

b. 0.979

c. 0.988 '

d. 0.998 QUESTION: 016 (1.00) ;

-While operating with the reactor critical at-l' Watt,-rod motion causes power to increase on a 30 second period. Which one of the below is reactor power level 2 minutes later,

a. 5 Watts

b. 14 Watts

c. 27 Watts

d. 54 Watts QUESTION: 017 (1.00)

Which ONE of the following characteristics is desirable in a thermal

reactor fuel?

a. Low concentration of fissile atoms 1

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b. Low coefficient of expansion

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-c. Low mass number 1

d. Low absorption cross-section i

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A. RX THEORY, THERMO & FAC OP CHARS Page 11'

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QUESTION: 018 :(1.00) )

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

a. The response will be faster for the negative addition at all -

times in core life. ,

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

c. The response will be faster for the positive addition 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.

QUESTION: 019 (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 -

b. 4.93 seconds

c. 49.3 seconds

d. 81.1 seconds l

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' ' -~A.[ RX THEORY,- THERMO & FAC OP CHARS - Page 12 ,

E QUESTION: 020 (1.00)

After operating at 50% power for several days, reactor power is rapidly increased to 100%. Assuming no further operator action, which one of the'below describes'the reactivity change over the next two hours immediately following the power increase?

a. NEGATIVE - Due :tcr the increased rate of decay of Xenon to Cesium.

b. NEGATIVE - due to the increased-production of Xenon at the-higher fission rate.

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c. POSITIVE - due to the faster burnup of Xenon at higher neutron flux levels,

d. 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.

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EB. NORMAL /EMERG PROCEDURES & RAD' CON Page 13 QUESTION: 001 (1.00)

While conducting an external survey on a shipping container that has

'just arrived at-the.NSC, the duty health physicist (HP) ' discovers ,

surface contamination measuring 9.0 E05 DPM-per 100 cm2.-

Which one of i

'the'below is the immediate notification required of the_ surveying HP?

a. No notification is required.

b. Only the Director of the Nuclear Science Center..-

c. Only the University Radiological Safety Officer.

d. Both the University Radiological Safety Officer AND the Director' of the Nuclear Science Center.

QUESTION: 002 (1.00)

A radiation survey of a given area has determined that occupancy of this; area for 5 consecutive days will result in a dose rate _of 250 millirem.

Assuming the radiation levels remain constant over time, which oneHof the below is the proper posting for this~ area? ,

a. Unrestricted Area

b. Radiation Area

c. High Radiation Area

d. Exclusion Zone.

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'B . NORMAL /EMERG PROCEDURES & RAD CON- Page 14-QUESTION: 003 (1.00)

Which one of the below is the individual who has the initial '

responsibility'for assuming the Emergency Director position in the event.

of:an NSC Emergency?

a. The Reactor Operator. I

b. Manager of Reactor Operations,

c. The most senior member of NSC Management on site,

d. The on duty Senior Reactor Operator.

-QUESTION: 004 (1.00)

Which one of the below is the reason the lab receivers in the pneumatic '

system are kept closed'except-when loading or unloading a sample?

a.. Prolonged opening will introduce air into theLsystem and' result in high levels of radioactive'AR-41.

b. Prolonged opening will cause pool leakage into the transport hoses due to the pressure differential.

c. They remain closed for neutron shielding purposes during reactor core operation,

d. They remain closed to prevent any CO2 leakage.past the isolation valve from entering the labs.

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B. NORMAL /EMERG PROCEDURES & RAD CON Page 15 3

-i QUESTION: 005 (1.00)

Which'one of the below describes the BASIS for maintaining bulk pool water chemistry? *

a. Reduce the corrosion of the pool liner.

b. Maintain water pH in the range 8.5 and 10.5.

c. Maintain water clarity to facilitate completion of Tech. Spec.

required surveillances.

d. Extend the longevity _and integrity of the' fuel cladding.

QUESTION: 006 (1.00)

For accident analysis, Limiting Safety System Settings establish peak core temperatures for the fuel. Select the phenomenon that would result in clad failure if peak core temperatures are exceeded,

a. Phase change in the type 304 stainless steel reducing yield strength,

b. Production of Zirconium hydride which-induces swelling.

c. Hydrogen over pressurization from the disassociation of zirconium hydride.

d. Metallic creep in the type 304 stainless steel.

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B.' NORMAL /EMERG PROCEDURES & RAD CON Page 16 QUESTION: 007 (1.00)

Which one of the below is required to ensure the contents of a liquid waste tank is less than MPC prior to discharge?

a. The tank is stirred for 10 minutes then a sample of the tank is analyzed for MPC.

b. An amount of domestic water equal to the amount of liquid waste in the tank is added prior to discharge.

c. A sample is taken from the bottom of the tank and top of the liquid, both of which must be less than MPC.

d. The creek bed is flushed with domestic water for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after.a tank is drained.

QUESTION: 008 (1.00)

A reactor scram occurs due to high fuel element temperature during PULSING OPERATIONS. Which one of the below is the required followup action?

a. The reactor fuel elements shall be inspected for damage in accordance with Tech Spec 4.2.4.

b. The shutdown margin shall be re-calculated in accordance with Tech Spec 4.2.3.

c. An evaluation shall be conducted to determine whether a fuel element temperature safety limit was_ exceeded.

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

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._B.'

NORMAL /EMERG PROCEDURES & RAD CON page 17

-QUESTION: 009 (1.00) ;

Which one of the below is authorized to release red tags in accordance with SOP VI-D, Red Tag Procedures? '

a. Any NSC staff member,

b. Any member of NSC management.

c. Either the senior reactor operator or reactor operator. ,

d. The senior reactor operator.

QUESTION: 010 (1.00)

Which coe of the below is the correct sequence of rod withdrawal during a normal reactor start-up?

a. Shim safety rods (in gang) to upper limit, transient rod to mid position, regulating rod to criticality.

b. Regulating rod to upper limit, transient rod to_40-60%, 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 to upper limit, shim safety rods (in gang) to 40-60%, regulating-rod to criticality.

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n QUESTION: 011 (1.00)

An accident occurs within the facility resulting in the SRO being .

contaminated, seriously injured and requiring immediate medical attention. Which one of the following describes the responsibilities of the operating staff?

a. The Health Physicist (HP) will be the emergency director, the~

Reactor Operator (RO) will shut down the reactor and accompany. ,

the ambulance to the hospital. !

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b. The RO will shutdown the reactor and assume emergency director, and the HP will accompany the ambulance to the hospital.

c. One member of NSC Management will be the emergency director and' the HP will accompany the ambulance to the hospital.

d. The HP will be the emergency director and one member of NSC <

management will notify the University Radiological Safety Officer and accompany the ambulance to the hospital. l QUESTION: 012 (1.00) ;

Channel #2 of the facility air monitor alarms following pulsing operations. Which one of the following statements describes the actions to.be taken by the Reactor Operator?

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a. Notify the Senior Reactor Operator (SRO), record the. channel every 15 minutes until the alarm clears.

b. Record the alarm in the operations log and verify alarm clear

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before further pulsing operations.

c. Notify the'SRO and the Health Physicist, restrict reactor operations to less than 400 watts until the source of the alarm can be determined.

d. Notify the SRO, shutdown the reactor, and evacuate the facility. l

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B.- NORMAL /EMERG PROCEDURES & RAD CON Page 19

-QUESTION: 013 (1.00)

An area has been roped off five feet from an experiment' producing 2500

-mrem /hr at 18 inches. Which one of the below is the correct boundary- !

posting for this area?

a. RADIATION' AREA i

b. HIGH RADIATION AREA

c. EXCLUSION AREA

d. RADIOACTIVE MATERIALS QUESTION: 014 (1.00)

Work must be performed in a radiation field of 400 mrem /hr gamma-and 2.0

. Rem /hr fast neutron. The worker is 24 years'old and has a lifetime exposure through last quarter of 28 Rem on his NRC Form 4. What is~the .i MAXIMUM time this worker may be permitted to work in this area per the limits of 10CFR20? (Assume that the man has no exposure in the present

. quarter.)

a. 20 minutes

b. 50 minutes

c. 75 minutes

d. 125 minutes i

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l B. NORMAL /EMERG PROCEDURES & RAD CON Page 20 l

. QUESTION: 015 (1.00)

The detectors in the area radiation monitoring system are calibrated: )

a. semi-annually using a Cs-137 source.

b. annually using a Cs-137 source.

c. semi-annually _using comparison readings obtained from portable instruments.

d. annually using comparison readings obtained from portable i instruments.

i QUESTION: 016 (1.00)

In accordance with the NSC Emergency Plan, who has the responsibility-for termination of an emergency? Assume no emergency plan. positions are l manned by backup personnel. i

a. Emergency Director

b. Emergency Coordinator

c. Reactor Operator

d. The senior onsite member of NSC_ management.

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

Which one of the below lists the emergency classes for.the NSCR from '

LEAST severe to MOST severo?

a. Alert, Operational Event, Reportable Occurrence,

b. Operational Event, Reportable Occurrence, Alert

c. Operational Event, Notification of Unusual Event,. Alert

d. Notification of Unusual Event, Operational Event, Alert l

QUESTION: 018 (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. The experiment can be placed in the core as a-non-secured '

experiment.

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 is allowed in the core but must be secured.

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"B.' NORMAL /EMERG PROCEDURES'& RAD CON Page 22 I 1

QUESTION: 019 (1.00)

Which ONE of the following is correct concerning.the worth.of.the regulating rod in the calculation of Shutdown Margin (SDM)?

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 calculating '

for cold condition without Xenon. ,

c. The worth of the regulating rod is already considered in the assumptions made for calculating SDM.

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

QUESTION: 020 (1.00)

In accordance with 10CFR55, which one of the below is the corrective action (s) required to restore an " inactive" license to " active" status?

a. Perform a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of shift functions under.

observation. i

b. Perform a minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under observation.

c. Perform a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of shift functions under t observation and complete a requalification exam. f

d. Perform a minimum of seven 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts under observation in !

one quarter.

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(**w** END OF CATEGORY B *****) '

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i LC. ' PLANT AND RAD MONITORING SYSTEMS Page 23 1 QUESTION: 001 (1.00) ,

i The fuel temperature signal for the fuel temperature scram is determined by:

a. an instrumented fuel rod that has three thermocouples imbedded in the fuel. Core construction only allows the instrumented rod to be placed adjacent to the central bundle. '

b. an instrumented fuel rod that has three thermocouples imbedded in the fuel. The three thermocouples are averaged to determine fuel temperature,

c. an instrumented fuel rod that has three thermocouples imbedded in the fuel. One the three thermocouples can be selected by disconnects at the reactor bridge.

d. three instrumented fuel rods that each have a single thermocouple inserted in the instrumented rod. The' rod to be used for monitoring fuel temperature can be selected by disconnects at the reactor bridge.

~ QUESTION: 002 (1.00)

Identify what is achieved by use of the Core Diffuser System during operation.

a. Better distribution of heat throughout the pool.

b. Better heat transfer across all fuel elements in the core.

c. Reduced dose rate at the pool surface from N16 and Ar41. >

d. Flow through the core assures water chemistry in the core.

l I

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

j

.C. PLANT AND RAD MONITORING SYSTEMS Page 24J ;

i QUESTION: 003 (1.00)

Which of the following locations ~ is normally the MOST negative pressure?

a. Control Room

b. Electronics Shop '

c. Materials Handling Area

d. Beam Port Area QUESTION: 004 (1.00) i An experimenter is attempting to open beam port doors on a beam port other than #4 while the reactor is in operation. Identify.the response

when the beam port doors are opened, a.

An alarm horn in the lower research area is activated to warn the experimenter that the reactor is in operation. ,

b. An annunciator occurs on the console in the control room- i indicating beam port doors are being opened. ,

c. The cameras in the lower research area are automatically scanned '

so the operator would observe the beam port doors being opened.'

d. Opening of the beam port doors during operation will result in a l scram.

QUESTION: 005 (1.00)

Which of the following prevents inadvertent irradiation of an experimenter placing components in the Irradiation cell?

a. Moving the reactor within eight. feet of cell window the causes a '

scram. This scram can be overridden. '

b. Opening the irradiation cell door any. time the reactor is within 8 feetiof the cell. Window causes a scram.

c. Opening the irradiation. cell door at any time causes'a scram. !

d. Moving the reactor within eight feet of the cell window will.

~

prevent energizing the motor for the cell door.

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

. . _ , _ _ ____ _. ._, ,__ ._ ~

i

. .. I C. PLANT AND RAD MONITORING SYSTEMS Page'25 QUESTION: 006 (1.00)

.The reactor is operating at 300 KW in " Servo" mode. The operator Lincreases the 6esired power on the linear power. recorder to 400 KW. The regulating rod contir.uously. withdraws beyond 400 KW due to a.

miscalibration of the channel. !

IDENTIFY the expected response of the regulating control rod. !

a. The regulating rod control will automatically transfer to manual ;

control. '

b. The regulating rod automatically withdraws until a scram occurs.

c. The regulating rod automatically withdraws to full travel.

d. The regulating rod stops with further movement prevented in both automatic or manual control.

QUESTION: 007 (1.00) '

Which of the following controls the amount of reactivity that is inserted by the transient rod during pulse operations? ,

a. The timer setting that vents.the pneumatic piston.

b. The pressure of the air applied to the pneumatic piston.

c. The position of the cylinder. ,

d. The initial power level of the reactor prior to firing the pulse, n

I f

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

e =

C.. PLANT AND RAD MONITORING SYSTEMS Page 26 QUESTION: 008 (1.00)

A shutdown of the air handler units has occurred causing a facility isolation.

IDENTIFY the air monitoring system that initiated this response.

a. Stack Fission Product monitor

b. Building Particulate Activity

c. Building Gas Activity

d. Stack Particulate Activity QUESTION: 009 (1.00)

How is confinement achieved in the part of the containment structure that is 55 feet of above grade?

a. The building is constantly pressurized via a blower.

b. Only one outside door may.be open at any time.

c. Outside doors have inner doors which maintain confinement. ,

d. Outside doors have seals-installed. .!

QUESTION: 010 (1.00)

LWhich of the following scram signals cannot be bypassed? p

a. Hi power level scram g

/$d

-b. Bridge lock scrams c.

~

Fuel element temperature scram

('; - .{7

d. Period scram

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

i C. PLANT AND' RAD MONITORING SYSTEMS Page 27 j i

QUESTION: 011 '(1.00)

Which.one'of the.following identifies the fuel element design parameter

.that11s different between FLIP fuel and standard TRIGA fuel?

a. Fuel-moderator material

b. Uranium content of.the fuel (percent)

c. U-235 enrichment

d. Cladding material >

-QUESTION: 012 (1.00)

.A leak has developed in the heat exchanger during operation with both

~

the primary and secondary pumps in operation. IDENTIFY the response'to this condition.

a. Level in the reactor pool will increase and automatic level control will makeup water to the secondary. ,

b. Level in the reactor pool will be maintained by. automatic makeup and level in the cooling tower will increase,

c. Level in the reactor pool will increase and water will have to be made up to the secondary to makeup for losses to the primary.

d. Level in the reactor pool will decrease and the level in'the cooling tower basin will increase.

1 i

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

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

t

. a' .

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.C. PLANT'AND RAD MONITORING SYSTEMS Page 28 ;

QUESTION: 013 (1.00) l The reactor is located in the stall and positioned against the radiography reflector while operating at the maximum power allowed per 3

SOP IV-F, Neutron Radiography Beam Port #4. An NSC technician assigned to reposition an experiment opens the shield floor to_ enter the' cave.

-Which one of the below. describes the indication (s) the operator would see in the control room?

a. A reactor scram will occur and an audible alarm will sound,

b. An audible alarm will sound indicating the door is open.

c. The beamport No. 4 area radiation monitor would alarm.

No indication would be seen in the control room.

1 d.

QUESTION: 014 (1. 0 0 ) .

IRRADIATED fuel elements are stored in which one of the following locations?

t

a. Fuel storage room in approved shipping containers.

b. Fuel storage room in cadmium lined Aluminum' tubes.

c. Storage racks on the floor.of the pool.

d. Radioisotope storage pits on the floor of the pool.

- QUESTION: 015 (1.00) y Select the. type of detector the Linear Power channel utilizes. '

a. Fission chamber

b. Geiger-Muller

c. Compensated ion chamber 1

d. Uncompensated ion chamber '

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

._ .u

1 10.- PLANT-AND RAD MONITORING SYSTEMS Page 29 QUESTION: 016 (1.00) ,

In the event of a building ventilation isolation, the emergency _ exhaust system can be operated in a manual mode from:

a. the Emergency Operating Panel in the central mechanical chase,

b. the Air Handling Control Panel ~in the reception room.

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

d. the Supervisor's Console in the control room.

QUESTION: 017 (1.00)

What protection is provided to maintain core coverage in the event of a loss of beam tube integrity?

a. Beam tube doors are sealed and the volume of the beam tube is '

not sufficient to uncover the core.

b. Four fire hose stations, two of which are always connected, are available to fill the-pool.

c. Diffuser spray will continue to cool the core in the event of core uncovery. ;

d. Two raw water emergency fill lines exist as an emergency supply to the pool.

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

C. PLANT AND RAD MONITORING SYSTEMS Page 30 QUESTION: 018 (1.00) ,

Wh'ich of the following describes the flow path in the skimmer system.

a. From.the skimmers through a strainer to the skimmer pump.- The pump discharges through a micron filter bank to the pool,

b. From the skimmers through a strainer to the skimmer pump. The pump discharges through a micron filter to the purification system.

c. From the skimmers through a micron filter to the suction of the recirculation pump.

d. From the skimmers through a micro filter to-the suction of the purification pump.

QUESTION: 019 (1.00)

A leak has developed on the suction of the water purification pump. ;

l IDEhTIFY the resulting level decrease in the pool. !

a. Level decreases to 90% automatically tripping the purification :

pump. l

b. Level decreases to 15 feet below the top of the pool and stops,

c. Level decreases completely. emptying the pool unless the manual. :;

isolation on the' suction-line for purification is. shut.

d. Level decreases completely emptying the pool unless a cover is. l placed on the suction of the pipe in the pool.

i

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

C. PLANT AND RAD MONITORING-SYSTEMS .Page 31 QUESTION: 020 (1.00)

Which ONE of the below describes the function of the reactor safety plate assembly?

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

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

c. Supports the reactor grid plate.

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

1 I

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

(********** **********)

~

END OF EXAMINATION I

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A. MRX THEORY, THERMO & FAC OP CHARS Page- 1 A N-S W E-R SHEET I Multiple Choice -(Circle or X your. choice)

If you change your answer, write your selection in the blank. '

MULTIPLE CHOICE 001 a- b c d 002 a b c d 003 -a. b c d 004 a b c d 005 a b c d

.006 a b c d 007 a b c d ,

008 a b- c d 009 a b c d .

.010 a b c d 011 a b c d 012 a b c d 013 a b c d 014 a b c d ,

015 a' b c d '

'016 .a b' c d T017 a b -c d 018: a b c d 019 a b c d-020- 'a .b c- .d-(*****:END OF CATEGORY A *****)

P

.,a r <

a

i-

. o (B. NORMAL /EMERG' PROCEDURES & RAD CON Page 2 A N.S W E R S H E.E T Multiple choice (Circle or X your choice)

If'you change your answer, write your selection in the blank.

MULTIPLE CHOICE

'001 a b c d

, 002 a b c d 003 a b c d 004 a b c d

'005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d 010 a b c d 011 a b c d 012 a b c d 013 a b c d 014 a b c d

015- a' b c d s 016 a- b -c d 017:; a- b c' d

-018' a b c d

'G19 a b c- d-

'020 a b c d

(***** END OF CATEGORY.- B'*****)

C. PLANT AND IULD MONITORING SYSTEMS Page 3 ANSWER SHEET Multiple Choice (circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CHOICE 001 a b c d 002 a b c d 003 a b c d 004 a b- c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d 010 a b c d 011- a b c d 012 a b c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 017 a b c d 018 a b c d l 019' a' b c d 020 a b c d

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

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

EQUATION SHEET Net Work (out)

Q = m cp AT Cycle Efficiency -

Energy (in)

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

Q - UA AT CR, (1-Keff), - CR2(1-Keff),

26.06 (A,,,p) (1-Keff)o (B - p) (1-Keff),

SUR - 26.06/r M - 1/(1-Keff) - CR /CR o 3

P-P o 10""" SDM - (1-Keff)/Keff P = Po e"'" Pwr - W, m B(1-p)

P= P, f,- 1 x 10~5 seconds B-p 7 - ((*/p) + [(6-p)/A,,,p] 7 = f*/(p-if) p - (Keff-1)/Keff A,,, - 0.1 seconds

p - AKeff/Keff 0.693 :

I1/2 ' "

B - 0.0077 A 2

DR33 D - DR22 0 DR - DR,e'"

1 Curie - 3.7x10'8 dps 1 kg - 2.21 lbm I hp - 2.54x10 3BTU /hr 1 Mw - 3.41x10' BTU /hr l 1 BTU - 778 ft-lbf *F = 9/5'C + 32

-l

'C - 5/9 (*F - 32) 1

\

. . A. RX THEORY, THERMO L'FAC OP CHARS Page'32 ANSWER: 001 (1.00) d

REFERENCE:

. Basic Reactor Theory; TAMU NSC SAR section III.C.3, p. 53 ANSWER: 002 (1.00) d

REFERENCE:

Basic Thermodynamic Theory; TAMU NSC SAR section III.D, p. 53-l 1

i ANSWER: 003 (1.00) '

i

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REFERENCE:

NSC SAR Section'XI, pages 136-137.

l

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

~

'A.' RX THEORY,-THERMO & FAC OP CHARS -Page-33 ANSWER: 004 (1.00) c

REFERENCE:

Nuclear Reactor Theory, p. 113-114; Larnarsh '

t ANSWER: 005 ( l'. 0 0 ) :

b .

i

REFERENCE:

~ Nuclear Reactor Theory p. 449; Lamarsh ANSWER: 006 (1.00) d

REFERENCE:

Nuclear Reactor Theory p. 109; Lamarsh I

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

A. RX THEORY, THERMO & FAC OP CHARS -Page 34 ANSWER: 007 (1.00)

C ,

REFERENCE:

NSC SAR Section III, page 53 and Figure 3-32.

ANSWER: 008 (1.00) a '

REFERENCE:

Nuclear Reactor Theory, p.101; Lamarsh '

ANSWER: 009 (1.00) a

REFERENCE:

~ Nuclear Reactor Engineering, p.260; Glasstone & Sesonske ANSWER: 010 (1.00) c

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

.A. RX'THEdRY, THERMO & FAC OP CHARS. Page 35

REFERENCE:

Glasstone & Sesonske 2.164-2.172

' ANSWER: 011 (1.00) c

REFERENCE:

Glasstone & Sesonske 4.1-4.45 ANSWER: 012 (1.00) c

REFERENCE:

Nuclear Reactor Engineering, p. 284; Glasstone & Sesonske ANSWER: 013- (1.00) f

b. '

t

(***** CATEGORY A CONTINUED ON'NEXT PAGE.*****). ,

~

Q --- -----------_-u--- - - - - - - _ - - , - - - - -'

A. RX THEORY, THERMO & FAC OP CHARS Page 36

REFERENCE:

a 24000 neuts in current gen. X 1.01 = 24240 neuts in next gen.

24240 neuts in next gen. -

24000 neuts ir. current gen. = 240 neuts added 240 neuts added - 0.7% delayed neutron fraction = 238 prompt neuts added ANSWER: 014 (1.00) a.

REFERENCE:

Technical Specifications, 5.5 l

ANSWER: 015 (1.00)

d. J

REFERENCE:

Given - five doublings increases counts by-a factor of 32.

CR1(1-Keff) = CR2(1-Keff)

~

I 100(1-0.950)=3200(1-Keff)

Keff = -3195/-3200 = 0.998

)

i ANSWER: 016 (1.00) l

d. )

I

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

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A. RX. THEORY, THERMO & FAC OP CHARS Page 37

REFERENCE:

P= Poet /T

=Poe120 sec/30 sec

=54.6Po ANSWER: 017 (1.00) b

REFERENCE:

Glasstone & Sesonske 8.65 ANSWER: 018 (1.00) c.

REFERENCE:

Basic Nuc. Engineering (Foster & Wright) - 3rd'Ed., pp. 292-295.

ANSWER: . 019 (1.00)

C.

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

l

)

4

A. RX THEORY, TilERMO & FAC OP CilARS Page 38

REFERENCE:

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

1 0 s

Intro. to Nuc. Engnring. (LaMarsh) - 2nd Ed., p. 284.

ANSWER: 020 (1.00) c.

REFERENCE:

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

l t

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

7 I .-

![ B.. NORMAL /EMERG' PROCEDURES & RAD CON Page 39 p ,

ANSWER: 001 (1.00) d.

REFERENCE:

TAMU NSC SOP VII-C5 p.6 ANSWER: 002 (1.00) b.

REFERENCE:

10CFR20.202

' ANSWER: 003 (1.00) d.

REFERENCE:

TAMU NSC SOP IX-A p.1 I

9 I

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

i

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,B. NORMAL /EMERG PROCEDURES & RAD CON Page 40

-ANSWER: 004 _(1.00) a.

REFERENCE:

TAMU NSC SOP IV-C p.1

. ANSWER: 005 (1.00) d.

REFERENCE:

TAMU NSC Tech' Spec 3.8, p. 29 ANSWER: 006- (1.00)

C.

REFERENCE:

TAF.U NSC SAR p. 128, TAMU Tech Spec 2.1 p.8' ANSWER: 007- (1.00) ,

a.

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

, r; .

'B._-NORMAL /EMERG PROCEDURES'& RAD CON Page 41'

REFERENCE:

SAR page 68

' ANSWER: 008 (1.00)

c. '

REFERENCE:

TAMU NSC Tech Spec 4.3.2, page 35 ,

ANSWER: 009 (1.00) d.

REFERENCE:

TAMU NSC SOP VI-D p.2

-ANSWER: 010 (1.00) c.

I

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

.B.- NOIU4AL/EMERG' PROCEDURES &, RAD CON Page~42 ;

REFERENCE:

TAMU NSC SOP II-C p.3

. ANSWER: 011 (1.00) i c.

REFERENCE:

SOP IX-D, page 2

' ANSWER: 012 (1.00) d.

REFERENCE:

SOP IX-E, page 3.

ANSWER: 013 (1.00) b.

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

B.--NORMAL /EMERGfPROCEDURES & RAD CON Page'43 d,

.)

REFERENCE:

ToDo2 = IfDf2 2500.(1.5)2 = If (5)2 2500 (2.25)/25 = 225 mr/hr 22fi mrem /hr. at 'five f t. makes this a high rad area 10 CFR 20.202 ANSWER: 014 (1.00) b.

REFERENCE:

5 (2 4 -18 ) =3 0 - Rem life time limit = 30-28= 2 Rem . With NRC form 4 on file' up to 3 REM /qtr is permitted not to exceed 5(n-18)

Life time limit is most restrictive -

. Rem = Rem no quality factor.is required 0.4 Rem /hr + 2.0 Rem /hr =2.4 Rem /hr ,;

2.0 Rem /(2.4 Rem /hr) =0.83 hrs = 50 min 10 CFR 20.101, .102 ANSWER: 015 (1.00) a.

REFERENCE:

SOP VII-B7, page 7.

1 p

(***** -

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

T

B '. . -NORMAL /EMERG PROCEDURES--& RAD CON .Page 44.

i ANSWER: 016 (1.00) '

l a

REFERENCE:

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

l ANSWER: 017 (1.00)

C.

REFERENCE:

NSC SOP IX-A, page 4. >

ANSWER: 018 (1.00) d.

REFERENCE:

NSC Tech Specs 3.6.1, page 23.

l

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

1 j

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'B..

- NORMNL/EMERG PROCEDURES & RAD CON. Page-45 i

i p

ANSWER: 019 (1.00).

i

a. .

+

REFERENCE:

NSC Tech Specs 3.1.3, page 13.

ANSWER: 020' (1.00) b.

i

REFERENCE:

10 CFR 55.53 l

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(*****

END-OF CATEGORY B'*****)

I i

'I '

C. ' PLANT AliD RAD M0111TORING SYSTEMS Page 46 ANSWER: 001 (1.00) c.

REFERENCE:

SAR, page 18, 96, & 97.

ANSWER: 002 (1.00) c.

REFERENCE:

SAR,'page 68.

'1 ANSWER: 003 (1.00) d.

REFERENCE:

SAR page 79.

~ ANSWER: 004 (1.00) b.

REFERENCE:

SAR page 82.'

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

--C. PLANT'AND' RAD--MONITORING SYSTEMS _Page 47 ,

ANSWER: 005~ (l'. 0 0)-

b.

REFERENCE:

SAR page 87.

b T

ANSWER: 006 (1.00) a.

REFERENCE:

SAR page 93.

ANSWER: 007 (1.00) c.

REFERENCE:

SAR page 38.

ANSWER: 008 (1.00)

'd.

1

REFERENCE:

1 SAR page 119 -

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

l'

C. PLANT AND. RAD MONITORING SYSTEMS- Page 48

. ANSWER: 009 (1.00) d.

REFERENCE:

SAR page 73.

ANSWER: 010 (1.00). '(/

, e p' r

< .i.

c.

- 6 Q. bk '

REFERENCE:

\'

SAR page 93.

y if ANSWER: 011 (1.00) c.

REFERENCE:

~SAR page 18.

ANSWER: 012 (1.00) d.

REFERENCE:

SAR page 65

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

E C. -PLANT AND RAD MONITORING SYSTEMS Page 49.

ANSWER: 013 (1.00)

, j, j' CK= ,

REFERENCE:

L TAMU NSC SAR p. 89, and TAMU NSC SOP IV F p.2 1

ANSWER: 014 (1.00)

C.

REFERENCE:

SAR page 107

-l

')

ANSWER: 015 (1.00) l C.

REFERENCE:

i SAR page 93 ANSWER: 016 (1.00) b.

1

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

-; . . l C.- PLANTLANDJRAD MONITORING SYSTEMS- Page 50 1

REFERENCE:

.SAR page 79

~

l ANSWER: 017 (1.00) d.

REFERENCE:

SAR page 112.

ANSWER: 018 (1.00) '

a.

REFERENCE:

-SAR page 68 and Figure 4-8.

' ANSWER: 019 (1.00) b.

~

REFERENCE:

Technical Specifications page 44.

ANSWER: 020 ( 1. 0 0 ) .

a.

.(*****

CATEGORY C CONTINUED ON NEXTsPAGE *****) ,

.. l l

.... -.-- 'j C. PLANT AND' RAD MONITORING-SYSTEMS Page 51: '

I h,

REFERENCE:

SAR page 14. .

I r

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

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

A. 'RX THEORY,: THERMO & FAC OP CHARS Page 1 ANSWER K E' Y-MULTIPLE CHOICE

-001 d

-002 d 003 -a 004 c 005 b 006 d 007 c 008- a 009 a 010 c 011 c 012 c 013- b 014 a 015 d 016 d 017 b 018- c

.019- c 020. 'c

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

;g .

\

1B; -NORMAL /EMERG PROCEDURES-& RAD CON Page- 2 .;

ANSWER KEY y ..

MULTIPLE CHOICE 001. d t

002 b 003 d 004 a 005- d 006 c

-007 a 008. c 009 d 010 c 011 c 012; d 013 b t

-014 b 015 a ,

016 a 017- c 018' d 019- a 020' b

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

, q.. ,

C. PLANT AND RAD MONITORING SYSTEMS Page .3~

ANSWER K'E Y

. MULTIPLE CHOICE 001 c ,

002 c 003 d 004 b 005 b 006 a 007 c 008 d -

009 d ,

010 v ;c / J 011 c

-012 d 013 a-o-3 [3 014 c 015 c 016 b 017' d-

'018 a ,

1 019. b 020 -a l

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

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

I

ML20056C457

Text

SUMMARY

Dear Mr. Collins:

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