ML20045E675

Exam Rept 50-134/OL-93-01 on 930419-21.Exam Results:Sro Passed Exams

ML20045E675
Person / Time
Site:	05000134
Issue date:	05/11/1993
From:	Caldwell J, Doyle P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20044G934	List: ML20044G933 ML20045E675
References
50-134-OL-93-01, 50-134-OL-93-1, NUDOCS 9307020302
Download: ML20045E675 (47)

Text

.

ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING RE00ALIFICATION EXAMINATION REPORT REPORT NO.:

50-134/0L-93-01 FACILITY DOCKET NO.:

50-134 FACILITY LICENSE NO.:

R-61 FACILITY:

Worcester Polytechnic Institute EXAMINATION DATES:

April 19 - 21, 1993 EXAMINER:

Paul Doyle, Chief.xaminer h,

,D.

5 ll i t SUBMITTED BY:

P 1 Doyle,' Ch' f Ex rdiner Date.

APPROVED BY:

'h f/q h3 a

Jamds L. Ca well, Chief Date h Non-Power eactor Section

%erator Licensing Branch.

i Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation

SUMMARY

Written and operating requalification examinations were administered to one Senior Reactor Operator (SRO).

The SR0 passed the' examinations.

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9307020302 930525 PDR ADDCK 05000134 V

PDR

REPORT'DETAllS-1.

Examiners:

1 Paul Doyle,-Chief Examiner.

2.

Results:

R0 SRO

' Total-(Pass / Fail)

(Pass / Fail (Pass / Fail)-

I NRC Grading:

0/0 1/0-1/0 Facility Grading:

N/A N/A N/A 3.

Written Examination:

The written examination was administered on April 19,.1993'to one Senior Reactor Operator. The SR0 passed the written examination.

The facility's written examination comments and the NRC's resolution to those comments 'are found.in Enclosure 2.

4.

' Operating Tests:

9 An Operating Test was administered on April 21, 1993. The SR0 passed the operating' test.

5.

Exit Meeting:

Personnel attending:

Paul Doyle, Chief Examiner, Nuclear Regulatory Commission Leo Bobek, Reactor Facility Director, Worcester Polytechnic.

Institute The exit meeting was conducted on April 21, 1993.

The facility examination comments were discussed as noted in Enclosure ~2.

4 0

Facility Comments and NRC Resolution

. Enclosure 2 Section A

' Question! 13

- WHICH'ONE (1)~ of the following atoms in the reactor core is most efficient-in thermalizing neutrons?

a.

Hydrogen atoms in the water molecules, b.

Oxygen atoms in the water molecules.

c.

Aluminum atoms in the fuel cladding.

d.

Carbon atoms in the reflector.

f_acility Comment The term " efficient" in the question is misleading.

Since the absorption cross-section for hydrogen is 100 times greater than that for carbon, versus the average energy loss per collision for hydrogen being only ~4-times greater than that for carbon, carbon would be the better element for generating thermal neutrons.

If the question is interpreted as asking which element will produce a larger number of thermal neutrons from a given number of-fast neutrons, then carbon is more " efficient" and D is the correct answer.

NRC Resolution Comment noted.

The candidates asked the examiner to clarify this question-during administration.

The examiner told all of the candidates that the-intent of the question was to identify the. atom which would result-in the greatest energy loss per collision.

Therefore this question does not warrant a grading change.

However the question will be rewritten for clarification prior to upload into the examination question bank.

Section B

• Question 04 An individual receives 100 mrem of Beta, 25 mrem of Gamma, and 5 mrem of neutrons. What is his total dose?

a.

275 mrem b.

205 mrem c.

175 mrem d.

130 mrem facility Comment Although the reference answer key gives the correct answer D, the answer key lists an incorrect answer C.

NRC Resolution Comment noted.

The examination was graded using the correct' answer D.

Section B

• Question.08 WHICH ONE-(1).of the following is a reportable occurrence ~as. defined by Technical Specifications?

a.

Movement of an unsecured experiment results in an. unanticipated decrease in reactivity of 0.06% delta k/k.

b.

A reactor shutdown is immediately initiated due to a loss of nuclear instrumentation which rendereo the regulating rod immobile.

During a surveillance with the reactor shutdown, the el'ectronic.

c.

scram setpoint for Reactor period is found to be 3 seconds and is readjusted to 5 seconds.

d.

A leaking fuel element releases fission products to the' Reactor pool but within the limits specified in 10CFR20.

Facility Comment In addition to answer D, answer C may also be considered correct.

Although included in the ANSI /ANS-IS.1 definitions of Reportable Occurrences, Reportable Occurrence (1) of the WP1 Technical Specifications (TS) does not include the phrase "... operation with..." a safety system setting less conservative than those in the TS.

The definition could be interpreted as requiring a report ur. der the conditions outlined in answer C.

NRC Resolution Comment accepted.

The answer key has been modified to accept both'C and D as correct.

• Question 09 WHICH ONE (1) of the following states the reactor operator's required actions prior to evacuating the building due to a radioactive spill?

a.

Position the Master Switch to 0FF, turn room ventilation on.

b.

Position the Master Switch to 0FF, turn room ventilat' ion off, c.

Scram the reactor, turn room ventilation on.

d.

Scram the reactor, turn room ventilation off.

Facility Comment In addition to answer C, answer A may also be considered correct.

By positioning the master switch to off, the operator will initiate a' scram by de-energizing the power supplies for the safety blade magnets.

The operators are trained to utilize this option or opening the circuit breakers for the control panel in the event the manual pushbutton scram fails.

In any case, the operator must eventually turn the swi.tch to off before leaving the panel.

ILRC Resolution Comment not accepted.

The Technical Specifications specify that "The Reactor Operator or the Facility Director will:

1)

Open the master switch to the reactor.

l This is not the same as scramming the reactor as listed in C above.

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fQuestion 12 Shutdown Margin' is determiner' h; Je, ifying' the reactor is suLeritical under a.

specific plant configuration. ' WHICH ONE.(1)- of the following Mentifies' the'

~

required configuration for determining Shutdown Margin?

a.

the highest worth blade, one other safety blade, Land the.

regulating blade withdrawn with the source installed..

b.

the highest worth blade, one other safety blade, and the

~

regulating blade withdrawn with the source removed.

c.

the highest worth blade and the regulating blade withdrawn with-the source installed d.

the highest worth blade and the regulating blade withdrawn with the source removed Facility Comment i

Either answer A or B may be considered correct. With the reactor in-the configuration stated in the procedure, the source is remnved to verify:the reactor is indeed subtritical by observing a decreasing'countrate. Therefore, to make the ~ determination, the operator must first establish _ the configuration outlined in answer A and then proceed to verify this configuration.is subcrit-ical by establishing the configuration in answer B.

NRC Resolution Comment accepted.

• Question 20 According to Technical Specifications, WHICH ONE (1) of the following identifies the limits and the plant conditions when immediate corrective action is required for pool water qualit., /

at all-times when resistivity is LESS than 5 x 10'5-ohm-cm a.

b.

at all times when resistivity is GREATER than 5 x 10^5 ohm-cm L

c.

only during critical operation when resistivity:is LESS than -

5 x 10'5 ohm-cm d.

only during critical operation when resistivity is GREATER than 5 x 10~5 ohm-cm La_cllity Comment in reference to WPI TS 2.1 the correct _ answer-is B not-A.

NRC Resolution Comment noted.

During.the administration of the examination one of the candidates po1nted out that-for resistivity _the answer should have-a value'of lot vice 10'3 The' examiner agreed and asked all candidates to change' the-10'5 to a 10+5 for all choices.

Based on this~there is no correct answer and 1

this question has-been deleted.

The facility should correct their Technical Specifications _ as to whether,the value-in 2.1 (Water Purity) (2) is conductivity or the value should_be 5 x 10*5.

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~Section C

.* Question. 06 3-WHICH ONE (1) aof the following is located adjacent to the Log N detector?

a.

regulating blade i

b.

safety blade #1 c.

safety blade #2 d.

safety blade #3 Facility Comment-Although not updated'in the FSAR, positioning of the power level detectors had several months ago been rearranged to match the control blade designations,

~i.e. CIC 1 next to blade 1, CIC 2 next blade 2, and CIC 3 next to Log-N.

NRC Resolution Comment accepted. The answer key has been modified'to show 0 as the correct; answer.

t

• Question 15 An experiment fails,' adding 0.5% positive reactivity to the reactor' core instantaneously. According to the facility Safety Analysis Report, WHICH ONE.

(1) of the following will be the method of scram initiation, terminating.the transient?

a.

Auto scram due to Reactor Bridge High Radiation trip

.b.

Autc scram due to Log-N Reactor PeriodLtrip c.

Auto scram due to CIC High Reactor Power trip d.

Manual scram inserted by the operator i

Facility Comment 1

'Either answer B or C would-be correct.

The method of scram for the stated parameters of the problem would be strongly dependent Hon power level'.

If power level was at 100%, a step insertion.of 0.5% reactivity would indeed-cause a high power trip on the linear channels.

However,~for reactor power j

level much less, say 10-20%, the method of-scram would be from the period channel as a 0.5% step increase would generate a stable period of about seconds.

The portion of the safety analysis.for the problem-dues not actually indicate the mode of scram.

i NRC Resolution Comment accepted. The answer' key has been modified to accept either 8 or.C as:

correct.

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'oQuestion.117.

WHICH.0NE (1) of theifollowing describes how the signal"for Control Blade position on the console is generated?-

c-o~~

a.

As.the lead screw moves: out, the impedance of;a pick-up coil-changes generating-a ~ changing voltage.'

b.

A. mechanical position indicator connected via a chain.to the drive motor' generates the signal.

c.

A: series of limit 1 switches open and'close as the lead screw moves:

past.

d.

A circuit with input ~from switch 7S3 generates a signal,

~

proportional to rod travel for the time the' switch _ is in either.

the RAISE or. LOWER position.

Facility Comment

~

In-addition to answer B, answer C would also.be considered correct. WPI FSARL Pg-18, 4.1.4, second paragraphistates limit' switches at the end of st'roke provide control blade position indications on the control panel.

These indicators tell the operator if the control blade is in the IN' position of OUT position.

NRC Resolution Comment accepted.

Because this facility has a very value of excess reactivity, and;when operating the control blades are maintained. fully out,'C; could be considered correct.- Therefore the answer key has been modified to accept either B or-C as correct.

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3:

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REQUALIFICATION REACTOR LICENSE EXAMINATION FACILITY:

WorcesterPolv.Ihst.

REACTOR TYPE:

TEST DATE ADMINISTERED: 93/04/19 REGION:

I' CANDIDATE:

LICENSE APPLIED FOR:

REACTOR OPERATOR 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% overall-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 33.33 A.

REACTOR THEORY, THERMODYNAMICS.

AND FACILITY OPERATING CHARACTERISTICS 20.00 33.33 B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS

_20.00 33.33 C.

PLANT.AND RADIATION MONITORING-SYSTEMS 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

u

EQUATION SHEET Q=rhe,AT p"", (p - 0)2 2a(k)f Q = 5 bh SCR =

1-K4 CR (1-K,) = CR (I-f,)

d = UA AT 3

g 2

e SUR = 26.06[ 0-PA,p]

1-K#*

y.

1-K,g_

I I

0 M=

=

1-K CR, g

SDM = (1-Ky 8

p,Pe'*

o 4

Pwr = W, m p, O(1-P) p P-P

(* = 1x10-5 seconds

(*

p-p)

P A,sP

(*

(K -l) d T =

p=

P-p Kg A4 = 0.1 seconds

AKg K,,

0.693 p = 0.0077 T

=

w A

K DR,d,2 = DR d

• DR = DR e*"

22 o

DR -- mrem, Ci - curies, DR = 6CiE(n)

E - Mev, R - feet 2

R 1 Curie = 3.7 x 10' dis /sec 1 kg = 2.21 lbm 1 H,orsepower = 2.54 x 108 BTU /hr 1 Mw = 3.41 x 106 BTU /hr 1 BTU = 778 ft-lbf

• F = 9/5 C + 32 1 gal (H O) = 8 lbm

• C = 5/9 (*F - 32) 2 4

Page 3 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 exam-ination.

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 repro-ductions.

Print your name in the blank provided in the upper right-hand

5. ~

corner of the examination cover sheet.

6.

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

7.

Print your name in the upper right-hand corner of the first page of each section of your answer sheets, g

8.

Before you turn in your examination, consecutively number each answer sheet, includ nc any additional pages inserted when writing your answrrs oi the examination question page.

9.

The point value for each question is indicated in parentheses after the question.

10.

Partial credit will NOT be given.

11.

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

12.

When you are done and have turned in your examination, leave the -

examination area as defined by the examiner.

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

l

.?

A.

RX THEORY. THERM 0' & FAC OP CHARS Page 14 QUESTION: 001 (1.00)

The reactor is critical at one (1) Watt. An experiment requires reactor power.

be raised to 50 Watts in two minutes. WHICH ONE (1)'of_the following is the approximate reactor' period that must be established?

a.

15 seconds b.

20 seconds-c.

25 seconds d.

30 seconds QUESTION: 002. (1.00)

WHICH ONE (1) of the following describes the expected change in core reactivity caused by'an increase in reactor pool water temperature while critical? The core reactivity change will be:

a.

positive, due to reduced buckling.

b.

positive, due to a decrease in thermal neutron absorption in.the moderator.

c.

negative due to increased neutron leakage from the core.

d.

negative due to increased reflection from the core..

QUESTION: 003 (1.00)

Two different neutron sources were used during two reactor startups. : One neutron source, which emits ten times as many neutrons as the second, was used in the first startup. Assume all other factors are the same for the second startup. WHICH ONE (I) of the following states the expected result _ at criticality?

a.

power level will be higher for the first startup b.

power level will be higher for the'second startup c.

the first startup will result in.a higher rod position d.

the second startup will result in a higher rod position

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

3 _

A.

RX THEORY. THERMO & FAC OP CHARS Page 5-QUESTION: 004 (1.00)

WHICH ONE (1) of the following statements describes the effects of an increase in. fuel temperature?

a.

positive reactivity is added slowly due to the increased elastis scattering cross-section b.

positive reactivity is added rapidly due to' increased fuel to moderator ratio c.

negative reactivity is added rapidly due to increased resonance absorption d.

negative reactivity is added slowly due to the time required for-moderator temperature response QUESTION: 005 (1.00)

The reactor is operating at 10 KW when one safety blade having a total worth of 4% inadvertently scrams into the reactor. WHICH ONE (1) of the following is the approximate power level before assuming a stable period? ~

a.

0.155 KW b.

0.168 KW c.

1.549 KW d.

1.679 KW QUESTION: 006 (1.00)

WHICH ONE (1) of the following sources is the largest contributor to the total-energy release in the reactor one hour after shutdown?

a.

kinetic energy of the fission fragments b.

decay of fission fragment isotopes c.

kinetic energy of delayed neutrons d.

gamma radiation from structural components

~

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

j

lA.

RX THEORY. THERM 0 & FAC OP CHARS

'Page 6'

y QUESTION: 007 (1.00) i The reactor is ~subcritical with a Keff of 0.91.

Two safety rods ~ with 'a total worth of 6.8% are withdrawn from the core. WHICH ONE (1) of the following is the new Keff?

a.

.97 b.

.98 c.

.99 d.

1.00 QUESTION: 008 (1.00)

Beta and Beta

,,, both describe the total fraction of delayed neutrons.

Thedifferenc,,,f*e*tweenthetwois:

e a.

Beta,,,,,,,,, is smaller than Beta since delayed neutrons are born at a.

lower energy level than prompt neutrons.

b.

Beta,,,,,,,,, is-larger than Beta since delayed neutrons are born at a lower energy level than prompt neutrons.

c.

Beta is smaller.than Beta since delayed neutrons are born at a high,e,r,,,e,n,,,rgy level thanl prompt neutrons.

e d.

B e t a,,,,,,, y, is larger than Beta since delayed neutrons are born at a higher energy level than prompt neutrons.

QUESTION: 009 (1.00)

WHICH ONE (1) of the following statements explains why_ delayed neutrons allow control of the reactor?

a.

Delayed neutrons are born at higher energies than.' prompt. neutrons and require more collisions to thermalize.

b.

Delayed neutrons shorten the average time for core response.to a reactivity addition.

c.

Delayed neutrons increase the average' generation time of the neutron population, d.

Delayed neutrons make up a higher percentage of the core's total neutron population.

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

A.

RX THEORY. THERM 0 & FAC OP CHARS Page 7 QUESTION: 010 (1.00) in that K,,,,,,,,, takes into account:

K,,,,c,,,, differs from Kinfinit, a.

leakage from the core b.

neutrons from fast fission c.

the effect of poisons d.

delayed neutrons.

QUESTION: 011 (1.00)

WHICH ONE (1) of the following statements describes a thermal neutron?-

a.

A neutron that experiences a linear decrease in energy _as the temperature of the moderator increases.

b.

A neutron at resonant epithermal energy levels that causes fission to occur in Pu-240 and U-238.

c.

A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator.

d.

A neutron that experiences no net change in energy after several i

collisions with atoms of the moderator.

QUESTION: 012' (1.00)

WHICH ONE (1) of the following describes the beta decay of a nuclide?

a.

Atomic mass decreases by one and number of protons remains constant.

b.

Atomic mass remains the same and number of protons increases by_one.

c.

Atomic mass remains the same and neaber of protons remains constant.

d.

Atomic mass decreases by one and number of protons increases by one.

(***** CATEGORV A CONTINUED ON NEXT PAGE *****)~

4

I A;

RX THEORY. THERM 0 & FAC OP CHARS-Page

'8-QUESTION: 013 (1.00)

WHICH ONE (1)-of the following atoms in the reactor _ core is most efficient in thermalizing neutrons?

a. -Hydrogen atoms in the water molecules.

b.

Oxygen atoms in the water molecules, c.

Aluminum atoms in the fuel cladding.

d.

Carbon atoms in the reflector.

QUESTION: 014 (1.00)

WHICH ONE (1) of the following conditions describes a reactor that is exactly critical?

a.

Keff equals 0; delta K/K equals 0 b.

Keff equals 0; delta K/K equals I c.

Keff equals 1; delta K/K equals 0 d.

Keff equals 1; delta K/K equals.

QUESTION: 015 (1.00)

. HICH While withdrawing control rods during startup, the count rate doubles.

W ONE (1) of the following describes the result of again adding the same_ amount of reactivity that caused the first doubling?

a.

Count rate will double and the reactor will remain subtritical.

b.

Count rate will more than double and the reactor will remain subcritical.

c.

Count rate will double and the reactor will be critical.

d.

Count rate will more than double' and the reactor will be critical.

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

.Page-. 9-

~A.

'RX THEORY! THERMO~& FAC OP CHARSf (QUESTION:016-(1.00)1

.J vt

<WHICH ONE (1) of the ~following is ti:e approximate ' energy released. by a single fission?

i a.-

2 mrv -

t b. ^100 MeV-c.

200 MeV:

d.

1000 MeV Q'UESTION: 017 (1.00)

The reactor begins withf a shutdown margin of 10.8% and.the suberitical count-rate. increases by a factor of 20. WHICH ONE (1) of theLfo110 wing;isithefnew!

Keff?

a.

.975 b.

.985

ci

.995

d.

.999 QUESTION: 018_ (1.00)

' ~

The reactor is operating at 9 Kwatts (90%) Land the scram setpointgisiset-at 1

125%. What will be the resulting peak power if an. experiment inserted into...

the. reactor causes a 100 millisecond period:and the scram;delayLis~0.11second??

a.

14 Kwatts b.

'28:Kwatts cc 34 Kwatts d.-

-50 Kwatts h

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

9 s

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p gw

A. "RX THEORY.:THERMO & FAC OP CHARS Page 10 QUESTION:;019 '(1.00)

WHICH ONE (1) of the following is defined by the number of neutrons in one-ganeration to the number of neutrons in'the previous generation?

a.

effective multiplication factor b.

fast fission factor-c.

neutron non-leakage factor d.

neutron reproduction factor QUESTION: 020 (1.00)

Integral Rod Worth is defined as the reactivity:

a.

change per unit'of rod motion.

b.

due to control rod position.

c.

required for shutdown with the most reactive rod withdrawn.

d.

available for shutdown after control rod withdrawal.

7

(***** END.0F CATEGORY A *****)

1 B.

NORMAL /EMERG PROCEDURES & RAD CON Page 11 QUESTION: 001 (1.00) l

- Personnel 'using powdered or liquid radioactive isotopes must monitor regularly.

using appropriate instruments. According to WPI radiation procedures, WHICH

'ONE (1) of the following states the MINIMUM skin contamination level requiring notification of the Radiological Safety officer?

a.

twice background radiation level b.

five times background radiation level c.

ten times background radiation level d.

any increase in instrument response QUESTION: 002 (1.00)

~

An experiment is removed from the facility after irradiation.

It is stopped four feet below the surface aof the pool water and measured at 5 mr/hr'using a portable instrument. Assuming 24 inches of water equals one." tenth thickness", WHICH ONE (1) of the-following is.the expected dose rate at one

~

foot when the experiment is removed from the pool?

a.

400 mr/hr b.

1600 mr/hr c.

2 R/hr r

d.

8 R/hr QUESTION: 003 (1.00)

In accordance with Technical-Specifications, under normal circumstances a.

senior reactor operator may be 'on call.' To meet. the requirements this person

-must be:

a.

within the reactor room b.

within the reactor building c.

within the confines of the campus d.

within a reasonable (% hour) drive from the reactor building s

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

w

B.

NORMAL /EMERG PROCEDURES & RAD CON Page 12 QUESTION: 004 (1.00)

An individual receives 100 mrem of Beta, 25 mrem of. Gamma, and 5 mrem of neutrons. What is his~ total dose 7 a.

275 mrem b.

205 mrem c.

175 mrem

'd.

130 mrem QUESTION: 005 (1.00)

WHICH ONE (1) of-the following states the reason for plotting 'a. reciprocal multiplication curve during fuel loading?

a.

verify minimum shutdown margin b.

measure reactivity worth of the regulating blade estimate a new val,ue of critical mass c.

d.

calibrate in-core instrumentation QUESTION: 006 (1.00)

WHICH ONE (1) of the following conditions constitutes a. violation of the reactor pool water temperature limit?

a.

12 fuel elements are loaded in the core and one control blade is withdrawn 10 inches. Reactor pool water temperature is 102*F.-

b.

16 fuel elements are loaded in the core and two control blades are withdrawn 5 inches.

Pool water temperature is~-107*F.

c.

16 fuel elements are loaded in the core and the reactor key is inserted to position the Master Switch to ON.

Reactor pool water temperature is 57'F.

d.

28 fuel elements are loaded in the core and the reactor key is inserted to position the Master Switch to Test. Reactor pool water temperature is 42*F.

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

B.

NORMAL /EMERG PROCEDURES & RAD CON Page 13 QUESTION: 007 (1.00)

WHICH ONE (1) of the following experiments requires the samples to be doubly encapsulated and leak tight?

An experiment with maximum allowable positive reactivity, failure of a.

which could release excessive airborne contamination.

b.

An experiment with maximum allowable negative reactivity, failure of which could increase reactor period to the scram setpoint.

An experiment containing corrosive materials, failure of which could c.

result in damage to reactor components.

d.

Experiments containing unstable materials, failure of which could combine violently resulting in expiosion.

4 QUESTION: 008 (1.00)

WHICH ONE (1) of the following is a reportable occurrence as defined by Technical Specifications?

a.

Movement of an unsecured experiment results in an unanticipated decrease in reactivity of 0.06% delta k/k.

b.

A reactor shutdown is immediately initiated due to a loss of nuclear instrumentation which rendered the regulating rod immobile, During a surveillance with the reactor shutdown, the electronic c.

scram setpoint for Reactor period is found to be 3 seconds and is readjusted to 5 seconds.

d.

A leaking fuel element releases fission products to the Reactor pool but within the limits specified in 10CFR20.

L QUESTION: 009 (1.00)

WHICH ONE (1) of the following states the reactor operator's required actions prior to evacuating the building due to a radioactive spill?

a.

Position the Master Switch to 0FF, turn room ventilation on.

b.

Position the Master Switch to 0FF, turn room ventilation off.

f c.

Scram the reactor, turn room ventilation on.

d.

Scram the reactor, turn room ventilation off.

L

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

B.

NORMAL /EMERG PROCEDURES & RAD CON Page 14'

QUESTION

010 (1.00)-

WHICH ONE (1) of the following outside agencies shall be contacted first in -

the event of-an Emergency Alert?

F a.

Worcester Police Department

b. -Worcester Fire Department c.

Nuclear Incident Advisory Team d.

Nuclear Regulatory Commission QUESTION: 011 (1.00)

WHICH ONE (1) of the following states the maximum dose an. emergency worker may accept in order to reenter the building and secure equipment to-terminate a radiological accident? Assume the worker has no previous exposure history.

a.

300 mrem (one time only) b.

1.25 Rem (per calendar quarter) c.

3 Rem (per calendar quarter) d.

25 Rem (one-time only)

QUESTION: 012 (1.00)

Shutdown Margin is determined by verifying'the reactor is subcritical under a specific plant configuration. WHICH ONE (1) of the following identifies the required configuration for determining Shutdown Margin?

a.

the highest worth blade, one other safety blade, and the regulating blade withdrawn 'with the source installed b.

the highest worth blade, one other safety blade, and-the regulating blade withdrawn with the source removed c.

the highest worth blade and the regulating blade withdrawn with the-source installed d.-

the highest worth blade and the regulating blade withdrawn with' the.

source removed

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

B.

NORMAL /EMERG' PROCEDURES & RAD CON Page 15' QUESTION: 013 (1.00)

WHICH ONE (1) of the following identifies the approval required to make temporary changes to an initially approved procedure? Assume there is no change in intent.

a.

Two faculty staff members, at least one of which tiU11 be -the facility director.

b.

Two faculty staff members, at least one of whom MUST be a licensed senior reactor operator.

c.

Two faculty staff members, at least one of whom MUST be a licensed reactor operator, d.

Two licensed faculty staff members, both of whom MUST be. licensed senior reactor operators.

QUESTION: 014 (1.00)

WHICH ONE (1) of the following states the minimum requirements for fully withdrawing the B10 detector?

a.

the Log N reading is on scale b.

both Compensated Ion Chamber readings are on scale one Compensated Ion Chamber and the Log N readings are on scale c.

d.

both Compensated Ion Chambers and Log N readings are on scale QUESTION: 015. (1.00)

The total worth of the regulating blade is determined by measuring the subcritical worth of the rod and correcting for WHICH ONE (1) of the following?

a.

power defect and excess reactivity b.

power defect and worth of experiments c.

source worth and excess reactivity d.

source worth and worth of experiments i

i

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

1 L

B.

NORMAL /EMERG PROCEDURES & RAD CON

.Page'16.

=*

QUESTION: 016 (1.00)_

A Wipe sample is taken of a potentially contaminated area. WHICH ONE (1) of the following identifies the MINIMUM levels above background that require further investigation?

a.

3 cpm alpha or 10 cpm beta / gamma b.

10 cpm alpha or 20 cpm beta / gamma c.

30 cpm alpha or 100 cpm beta / gamma d.

100 cpm alpha or 200 cpm beta / gamma l:

L QUESTION: 017 (1.00) l-WHICH ONE (1) of the following activities may be performed by a licensed operator without the supervision of a senior licensed operator?

examining ventilation exhaust air samples for evidence of a.

non-background radiation b.

placing the pool water level safety switch in the BYPASS position.

c.

directing maintenance of the control drive for the regulating control rod d.

checking individuals who have reported possible personal contamination QUESTION: 018 (1.00)

WHICH ONE (1) of the following has the authority to review and approve experimental procedures?

a.

Facility Director l

b.

Radiological Safety Officer c.

Radiation, Health and Safeguards Committee d.

University President

)

{

3

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

l l

1

B NORMAL'/EMERG PROCEDURES & RAD CON'

. Page'17f QUESTION: 019 (1.00)

WHICH ONE (1) of the~following identifies. the required number of-control.

. blades and. distance. they must be withdrawn to provide fast scram ' capability

- during core' alteration?

a.

two blades withdrawn 15 inches b.

two blades withdrawn fully c.

three. blades withdrawn'15 inches-3 d..

three blades withdrawn fully QUESTION: 020 (1.00)

I According to Technical Specifications,'WHICH ONE -(1) of the following; identifies the. limits and the plant conditions when immediate corrective :

actionLis required for pool water quality?'

1 5

.a.

at all times when resistivity is LESS than'5 x:10 ohm-cm b'.

at. all -times' when resistivity' is GREATER.than 5 x;10'5 ohm-cm.

only-du[ingcritical. operation lwhenresistivity~isLESSthan c.

5 x:10' -ohm-cm

. d.

onlydu[ingcritical'operationwhenresistivityisLGREATERthan, 5 x 10' chm-cm 1

1 b

6 1

g

(***** END 0F CATEGORY 'B *****)

7

)

[f

'Q

(

-P gi-Y Y

W

• ?

g-

e M

t w'

'--'O v

~'

C.

PLANT AND RAD MONITORING SYSTEMS Page 18

. QUESTION: 001 (1.00)

WHICH ONE (1) of the following will cause an electronic (fast) scram?

a.

Manual scram.

b.

High voltage failure in the control center cubicle.

c.

4 second reactor period d.

120% power spike QUESTION: 002 (1.00)

WHICH ONE (1) of the following is allowed when the Master Switch is in the TEST position?

a.

Insertion of a scram signal without control blade movement.

b.

Control power and~1 amp indication operability testing.

c.

Bypass of the safety blade withdrawal interlocks.

d.

Coatrol drive motion without energizing the scram magnets.

QUESTION: 003 (1.00)

WHICH ONE (1) of.the following is equipped with a high flux scram contact?

a.

Log CR meter b.

Boron 10 proportional counter c.

Micromicroammeter. range switch d.

Log N recorder 4

I i

i

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

C.

PLANT AND RAD MONITORING SYSTEMS-Page 19.

QUESTION: 004' (1.00)

WHICH ONE (1) of the following is the rate at which the reactor compartment ventilation system changes out the reactor compartment air?

a.

I change /hr b.

2 changes /hr c.

3 changes /hr d.

4 changes /hr QUESTION: 005 (1.00)

WHICH ONE (1) of the following is the approximate reactor power at which the Log N and Safety Channel indications overlap with the Startup Channel indications?

a.

0.2 Watts b.

2.0 Watts t.

c.

20.0 Watts d.

200.0 Watts 1

QUESTION: 006 (1.00) l l

I WHICH ONE (1) of the following is located adjacent to the Log N detector?

a.

regulating blade b.

safety blade 71

-l c.

safety blade t d.

safety blade #3 1,

I l

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

C.

PLANT AND RAD MONITORING SYSTEMS Page 20 QUESTION: 007 (1.00)

WHICH ONE (1) of the following provides personnel protection from excessive radiation exposure through the beam port?

a.

rolling, high density concrete door b.

instrument leads pass through spiral conduit c.

biological shield d.

boron filled shield plugs QUESTION: 008 (1.00)

WHICH ONE (1) of the following provides the best indication of neutron flux during reactor startup?

a.

Boron 10 proportional counter b.

Compensated ion chamber c.

Geiger Mueller detector-j d.

Scintillation detector QUESTION: 009 (1.00)

WHICH ONE (1) of the following control blade withdrawal interlocks gives a measure of protection against erroneous loading causing an abnormally high

i excess reactivity?

a.

Log CRM count below 3000 cpm.

b.

7 second delay subsequent to reactor startup.

c. - Regulating blade is withdrawn from its lowest position.

d.

Flux rises above a preset level before.the safety blades are completely withdrawn.

r

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

~

~

C.

PLANT AND RAD MONITORING SYSTEMS

'Page 21 QUESTION: 010-(1.00)

WHICH ONE (1)f of the following types of detectors is located near the Beam Port and Thermal Column?

a.

Geiger Mueller tube b.

Ionization chamber.

c.

Proportional counter d.

Scintillation detector QUESTION: 011 (1.00)

WHICH ONE (1) of the following will. cause a building evacuation alarm?.

a.

Loss of electrical power.

b.

High pool temperature.

c.

Electronic (fast) scram.

d.

Low pool water level.

QUESTION: 012 (1.00)

WHICH ONE (1) of the following demineralizer regeneration processes will

-remove sediment from the resin bed?

a.

Resin mixing b.

Caustic soda treatment c.

Acid solution treatment d.

Backwash t

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

C. ' PLANT AND RAD-MONITORING SYSTEMS Page 22-

. QUESTION: 013 (1.00)

WHICH ONE- (1) of the following does NOT use a neutron source check to verify operability?

a.

Scram circuits b.

Console amplifiers c.

Area radiation monitors d.

Rod permissive interlocks QUESTION: 014 (1.00) n l

WHICH ONE (1) of the following is the maximum speed that the control blades are withdrawn from the core?

a.

4 in/ min b.

7.5 in/ min c.

15 in/ min d.

24 in/ min

. QUESTION: 015 (1.00)

An experiment fails, adding.5% positive reactivity-to the reactor core.

instantaneously. According to the facility Safety Analysis Report, WHICH ONE -

(1) of the following will be the method of scram initiation, terminating the transient?

a.

Auto scram due to Reactor Bridge High Radiation trip b.

Auto scram due to Log-N Reactor Period trip.

c.

Auto scram due to CIC High Reactor Power trip d.

Manual scram inserted by the operator

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

_ _ _ _ _ = _ _ _ _ _ _ _ _ _ _

N C.

PLANT AND' RAD MONITORING-SYSTEMS-

Page 23

.4.

QUESTION:?016 -(1.00)-

'WHICH ONE (1) of the following represents the amount of plutonium-beryllit:m -

t used as a neutron source.at WPI?

a.

I curie b.

2 curies-

+

l c.

3 curies-

'd.

4 curies

-l x

QUESTION: 017 (1.00)

WHICH ONE (1) of the following describes how,the signal ~ for Control: Blade a

position on the console is generated?

a.

As the lead-screw moves out, the impedance of a pick-up coil change's.

q generating a changing voltage, j

b.

A mechanical: position indicator connected via a chain-to the' drive motor generates the signal..

-i c.

A series of-limit' switches open and close as the lead screw moves-

~

past.

j d.

A circuit with. input from switch 7S3 generates 'a signal. proportional.

to rod travel for the time the switch'is in either'the' RAISE orf 1

LOWER position.

1

'b QUESTION: 018 (1.00) q One of four fuses downstream ~ of circuit breaker CB3 fails, cuttingoff.'the' 115V electrical supply to the Scram relays. WHICH ONE (1)'of.the-following.

components:on the same branch circuit-will-also become deenergized?

3

' a.

alarm horn

~

'b.

Log N Recorder:

c.

regulating rod drive motor-d.. safety rod position indic'ation

^'

L q

q

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

u

is C.

PLANT AND RAD MONITORING' SYSTEMS Page 24 QUESTION: 019 (1.00)

WHICH ONE (1) of the following is (are) the material (s) used to construct the regulating blade?

a.

Stainless steel b.

Aluminum c.

Stainless steel and boron carbide d.

Aluminum and boron carbide QUESTION: 020 :(1.00)

WHICH ONE (1) of the following is the capacity of the pump used for circulating pool water to the cleanup demineralizer?

a.

5 gpm b.

10 gpm c.

15 gpm d.

20 gpm P

l

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

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

L Page 25 f.

A.

RX THEORY. THERM 0 & FAC OP CHARS

" ANSWER:

001 -(1.00) d.

REFEREhCE:

Lamarsh, Second Edition, Section 7.1, page 289 Pe' V

P

=

o in (P/P ) - t/T ot/[1n (P/Po)]

T T - 120/[1n (50/1)] - 30.67 i

ANSWER:

002 (1.00) t c.

l l

REFERENCE:

l Lamarsh, Second Edition, Section 7.3, page 307 I

WPI: Reactor Facility Data, Figure 8 ANSWER:

003 (1.00) a.

4

REFERENCE:

Lamarsh, Second Edition, Section 4.1., pages 102-104 i

ANSWER:

004 (1.00)

C.

REFERENCE:

Lamarsh, Second Edition, Section 7.3, page 308.

ANSWER:

005 (1.00) d.

REFERENCE:

-Lamarsh, Second Edition, Section 7.1, page 289 P= 8(1-0)P3 B-p

- 0.0077(1+0.04110 KW 0.0077+0.04.

-1.679 KW

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

hi A.

RX THEORY.-THERM 0 & FAC OP CHARS Page 26

i..

ANSWER:

006 (1.00)-

b.

REFERENCE:

Lamarsh, Second Edition, Section'8.2, page 350 ANSWER:

007 -(1.00).

a.

REFERENCE:

Lamarsh, Second Edition, Page 282 ANSWER:

008 (1.00) b.

REFERENCE:

Lamarsh, Second Edition, Section 7.4, pages 317-322 ANSWER:

009 (1.00) c.

REFEkFNCE:

marsh, Second Edition, Section-3.7, page 73 ANSWER:

010 -(1.00) a

REFERENCE:

' Lamarsh, Second Edition, S 6.5, pp. 238 -- 239.

ANSWER:

011 (1.00) d.

REFERENCE:

Lamarsh, Second Edition, Section 5.9, page 208 ANSWER:

012 (1.00) b.

REFERENCE:

Lamarsh, Second Edition, Section 2.8, page 19

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

~

1 lRXiTHEORY. THERM 0 & FAC OP CHARS-

Page.27; c

TANSWER:

013i(1.00)l zi

. a.1

~

l

REFERENCE:

1

.Lamarsh, Second: Edition, Section 3.5,;page 60:-

u..

i

.l

ANSWER:

014 (1.00)?

c.

REFERENCE:

l

Lamarsh, Second-Edition, Section 4.1, page 102.

M ANSWER:

015 :(1.00) d.

c t

REFERENCE:

y _ g*"*, G1 g y _g'"1).

g 1-Kn, CR -

o 1

. CR l

1 -K,u, CR, 2

Given that 1 - Keff is-the' distance by which-the. reactor.is removed from-

~

criticality, and by doubling the counts you have effectively ANSWER:

016~f(1.00)

-j c.

REFERENCE:

hi

.Lamarsh, Second Edition, Section 3.7, page 77 I

i ANSWER:

017 (1.00) c.

REFERENCEi (1 - K;,,).

K,,, (SDM) = 1 - K,,,_

li SDM

=

eff

- K,,, (SDM + 1);- 1 K,,, (.108 + 1) = 1

}

K,,,3 -.9025 CR, (1 - K,,5)

- CR2 (l!- Keffz) 20 (I - Kef fz) -

Keffz. -. 20

.0975

.I'(.0975)

=

20 Keff2' =

.995-a y

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

4

~i 8

s a

A.

RX-THEORY. THERM 0-& FAC OP CHARS' Page 28

-ANSWER

.C

REFERENCE:

Standard Power Equation P=Pe P = 12.5 Kwat'ts e* *"

UT-P=1k.5Kwatts(2.72)

P - 33.98 Kwatts ~ 34 Kwatts ANSWER:

019 (1.00) a.

REFERENCE:

NRC Fundamentals Exam bank ANSWER:

020 (1.00) b

REFERENCE:

NRC Fundamentals Exam bank

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

B.

' NORMAL /EMERG PROCEDURES & RAD CON' Page 29-ANSWER:

001 (1.00) a.

REFERENCE:

WPI: RHSC Radiation _ Regulations,Section II.F, paragraph 4.

ANSWER:

002 (1.00) d.

DoseRate, Distance 2 1

DoseRate Distance 3~

s 1

, 100 DoseRate, (distance )2 1

distance' 2

1 0 Smd eet) 2 DoseRate =

2 Ifoot*

500mr/hr 16 = 8000mr/hr = Br/hr DoseRate g

REFERENCE:

Lamarsh, Second Edition, Section 9.11, page 461 ANSWER:

003 (1.00) d

REFERENCE:

i WPI: Technical Specifications, S 1.0 Definitions ANSWER:

004 (1.00) d

REFERENCE:

~10CFR20 rem - rem ANSWER:

005 (1.00)

-l c.

REFERENCE:

WPI: Technical Specifications Section 5.10(3)

ANSWER:

006 (1.00) a.

REFERENCE:

WPI: Technical. Specifications 1.0 and 2.1

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

D+.

B.

NORMAL /EMERG PROCEDURES &' RAD CON Paga 30 ANSWER:

007- (1.00)-

c.

REFERENCE:

WPI: Technical Specification 2.3(5)

ANSWER:

008 (1.00 pce f 36 M ) o s, m d.

d. or c.

7

REFERENCE:

WPI: Technical Specification 1.0 ANSWER:

009 (1.00) c.

REFERENCE:

WPI: SAR 6.5.4.II, pg 38a ANSWER:

010 (1.00) a.

REFERENCE:

WPI: SAR 6.5.6, pg 38c ANSWER:

011' (1.00) b.

REFERENCE:

WPI: SAR 6.5.10, page 38 ANSWER:

012 (1.00) pe r kiid, <,m me d

b. av a

REFERENCE:

WPI: Operating Procedures, page 48 ANSWER:

013 (1.00) b.

REFERENCE:

WPI: Technical Specification 5.5 ANSWER:

014 (1.00) d.

REFERENCE:

WPI: Operating Procedur_es II.5-(***** CATEGORY B. CONTINUED ON NEXT PAGE *****)

~

6 B.~ NORMAL /EMERG PROCEDURES'& RAD CON

.Page 31-

-ANSWER:

015 (1.00).

C.

REFERENCE:

WPI: Operating Procedures, page 14, paragraph 1

. ANSWER:

016 (1.00) a.

REFERENCE:

WPI: Operating Procedures, page 20 ANSWER:

017 (1.00) d.

REFERENCE:

.WPI: SAR 6.5.4.I.3)c), page 38 ANSWER:

018 (1.00) c.

REFERENCE:

WPI: SAR 6.3.4, page 35 ANSWER:

019 (1.00) a.

• REFERENCE WPI: SAR 6.3.2.2, page 34 ANSWER:

020 (1.00)

+

Oet-l.

REFERENCE:

WPI: Technical Specification 2.1 t'

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

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

-C--

-PLANT AND RAD MONITORING SYSTEMS Page 32 ANSWER:

001 (1.00)'

C.

REFERENCE:

WPI: Safety Analysis Report, 4.3.12.

ANSWER:

002 (1.00) d.

REFERENCE:

WPI: Safety Analysis Report, 4.3.3.

ANSWER:

003 (1.00).

d.

REFERENCE:

WPI: Safety Analysis Report,' 4.3.7.

ANSWER:

004 (1.00) y; Per Facility Coiment sr

REFERENCE:

WPI: Safety Analysis Report, 3.2.2.

ANSWER:

005 (1.00) a.

REFERENCE:

WPI: Technical Specifications, 4.5.1.

ANSWER:

006 (1.00) br

.Bs

REFERENCE:

WPI: Safety Analysis Report, Appendix B,-Core layout, Figure 13.

Per facility comment the SAR picture is incorrect.

ANSWER:

007 (1.00) b.

REFERENCE:

WPI: Safety Analysis Report, 4.2.2 ANSWER:

008 (1.00) a.

REFERENCE:

WPI: Safety Analysis Report, 4.3.8

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

i-C.

PLANT AND RAD MONITORING SYSTEMS-

-Page 33 ANSWER:

009 '(1.00) d.

REFERENCE:

WPI: Safety Analysis Report, 4.3.10

' ANSWER:

010 (1.00) a.

REFERENCE:

WPI: SAR, Section 4.3.9 ANSWER:

011 (1.00) d.

REFERENCE:

WPI: Technical Specifications, table 4.1, p.10.

ANSWER:

012 (1.00) d.

REFERENCE:

WPI:-Operating and Test Procedures, p. 31 ANSWER:

013 (1.00) c.

REFERENCE:

WPI: Operating and Test Procedures, p. 3 ANSWER:

014 (1.00) b.

REFERENCE:

WPI: Safety Analysis Report, 2.3, p.11 ANSWER: pe, fac, Id)y comr"ral:

015 J1.00

c. e h,

REFERENCE:

J WPI: SAR 7.4.3, page 45 ANSWER:

016 (1.00)'

)

a.

REFERENCE:

WPI: Safety Analysis Report, 4.4, p. 26

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

-l

?,u C.

PLANT'AND RAD MONITORING SYSTEMS' Page 34

'017 (1.00)\\ commed.

ANSWER:-

per [ge,lj.

. b. e< g.

REFERENCE:

WPI: Safety Analysis Report, 4.3.10, p. 25 WPI: Figure 19 ANSWER:

018 (1.00) a.

REFERENCE:

WPI: Safety Analysis Report, 4.3.5, p. 23.

ANSWER:

019 (1.00) a.

REFERENCE:

WPI: Safety Analysis Report, 4.1.3, p.18 ANSWER:

020 (1.00) b..

REFERENCE:

WPI: Safety Analysis report, 4.1.10, p. 20.

s

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

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

A.

RX THEORY. THERM 0 & FAC OP CHARS-Page 1-ANSWER KEY MULTIPLE-CH0 ICE 001-d 002 c

003 a

004 c

005 d

006 b

007 a

008 b

009 c

010 a

011 d

012 b

013 a

014 c

015 d

016 c

017 c

018 c

019 a

020 b

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

4 m

c.,

B.

NORMAL /EMERG PROCEDURES &' RAD CON Page 2 ANSWER KEY MULTIPLE CHOICE 001 a

002 d

003 d

004 c

005 c

006 a

- 007 c

008 d

009 c

010 a

011 b

012 b

013 b

014

'd 015 c

016 a

017 d

018 c

- 019 a

020 b

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

C.

' PLANT'AND' RAD MONITORING SYSTEMS-Page~ 3 y,

ANSWER KEY MULTIPLE CHOICE 001 c

002 d

003 d

004 a 6 005 a

006 b @

007 b

008 a

009 d

010 a

011 d

012 d

013 c

014 b

015 c

016 a

017 b

018 a

019 a

020 b

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

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

l

g, A.

RX THEORY; THERM 0 &JFAC OP CHARS ANSWER SHEET

. MULTIPLE CH0 ICE ~

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 019 a b c d 020 a b c d

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

^

L

J.-

~-

^

-J'

.B.

NORMAL /EMERG PROCEDURES & RAD CON ANSWER

~ SHEET

-; MULTIPLE CH0 ICE 001 a bl c d 002 a b c d 003 a'b c d 004 a b c d 005 a b c.d 006 a bc d 007 a b c d 008 a b c d I

009 a b c d 010 a b c d 011 a bc 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 019 a b c d 020 a b c d

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

C.

PLANT AND RAD MONITORING SYSTEMS o

ANSWER SHEET 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 019 a b c d 020 a b c d

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

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

l