ML20058K087

Exam Rept 50-284/OL-93-01 on 931025-27.Exam Results:Reactor Operator Operating Test Retake Applicant Failed Exam.All Other Applicants Passed Exams

ML20058K087
Person / Time
Site:	Idaho State University
Issue date:	11/30/1993
From:	Caldwell J, Eresian W Office of Nuclear Reactor Regulation
To:
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ML20058J933	List: ML20058J930 ML20058K087
References
50-284-OL-93-01, 50-284-OL-93-1, NUDOCS 9312140394
Download: ML20058K087 (45)

Text

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. ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT

, REPORT NO.: 50-284/0L-93-01 FACILITY DOCKET NO.: 50-284 ,

FACILITY LICENSE NO.: R-II0 .i FACILITY: Idaho State University EXAMINATION DATES: October 25-27, 1993 ,

EXAMINER: Warren Eresian, hi Examiner SUBMITTED BY: les44 //j/o/h3 >

Warren Eresiyh, Chief Examiner Date APPROVED BY: " ^ b M < -~ , w/>,/ Pd i James L. Caldwell, Chief j/*7 Date Non-Power Reactor Section Operator Licensing Branch i Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation

SUMMARY

The NRC administered an initial license examination to one Senior Reactor Operator (Instant) applicant, an operating test retake examination to one Reactor Operator applicant, an operating test retake examination to a second Senior Reactor Operator (Instant) applicant, and a written retake examination to a second Reactor Operator applicant. The Reactor Operator operating test retake applicant failed the examination. All other applicants passed their examinations. '

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i REPORT DETAILS i

I. Examiners: ,

Warren Eresian, Chief Examiner  !

2. Results:

R0 SR0 Total j (Pass / Fail) (Pass / Fail) (Pass / Fail)  ;

NRC Grading: 1/1 2/0 3/1  !

3. Written Examination:

The SR0 Instant applicant passed the written examination. The R0 applicant passed the written retake examination, Category B.

4. Operating Tests:

SR0 Instant applicant initial examination - passed the operating test. l SRO Instant applicant retake exaniination - passed the operating test. i R0 applicant retake examination - failed the operating test.

5. Exit Meeting: l An exit meeting was held on October 27, 1993. Present were:

Warren Eresian, NRC Chief Examiner James Caldwell, Section Chief, Non-Power Reactor Section -

R. David Clovis, Reactor Supervisor, Idaho State University Hary Charyulu, Idaho State University The NRC thanked the Idaho State University staff for their assistance t and cooperation during the examinations. The examinations were discussed and the facility advised the NRC that written examination comments would be forthcoming.  !

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ENCLOSURE 2  !

Idaho State University l Comments of SRO/RO Exam l Administered October 25, 1993 j t

,t Section A Question 6: This question is somewhat ambiguous and should be  :

thrown out. For two identical reactors with each I having a different source strength, the reactors [

will go critical at the same rod height. After ,

I criticality is reached, the reactor power will continue to rise in a linear fashion due to the The

[

source, providing it is still present.

stronger source will provide a steeper linear rise.

But please note that the source does not determine  ;

the critical power level anymore'than rod height. j Question 15: The answer provided for this question is "D" and should be, of course, "C." Most of the energy ,

released from fission is from the kinetic energy of  !

the fission fragments. I don't believe anymore  ;

explanation is necessary.

Question 16: This question really does a fine job of testing an i operators knowledge of approaching criticality and  ;

the subcritical operations. However, this question j has two (2) possible answers, "A" or "B." The most  ;

correct answer is probably "a" with "b" being a  !

close second. If 1/M is plotted, on non-linear j function, 1/M will have a value of zero around 18 cm. But if'an examinee assumes that he/she needs to perform linear extrapolation from the data ,

provided from at ten (10) and fifteen (15) cm,.then a value of about twenty (20) cm. is answer. I consulted with Dr. A.E. Wilson on this question and  ;

he provided his results of a 1/M plot for both j mentioned cases. I have enclosed his 1/M plot as j an attachment.

Section B ,

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Question 2: "A" is the answer provided, which is correct. I However, "B" did not specify if the non-licensed '

operator was certified or not. If the non-licensed g

operator is certified, by the Reactor Supervisor, then "B" would also be a correct answer, because  ;

the SRO would perform the duties of'an RO and there would be no need for an SRO on call. Therefore, ,

"A" or "B" would be a correct answer. ]

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. .\ . 5 Section B'(Cont.) i i

Question 6: "D" is listed as the correct answer, but "C" is  ;

also a correct answer. In .accordance with -l Operating Procedure (0.P.) #1 (or #2) Section i I.B.2, the procedure states: " Carry the portable j detector for the area survey and note any. abnormal l readings as the tour is completed." Also note the high radiation alarm test is performed in Section II.F of 0.P. I, after the pre-startup radiation survey.

To re-iterate, both "C" or "D" are correct answers.

Question 8: The listed answer is "B." "A" is also an answer if the examinee interprets the 27 mr/hr in the reactor lab is at the reactor lab door or at the window to the Observation Classroom. This radiation level would then certainly exceed the 10 mr/hr level at the operations boundary, which would require evacuation of the building. The question would have been more appropriately addressed if the radiation levels provided for answers were more descriptive in location.

Again, "B" or "C" are correct answers.

I Se_gtion C Question 3: "B" is the listed answer. However, "A" is also answer. The Channel #1 ratemeter provides a full-scale input to its associated sensitrol. Although there is no requirement to have a high level trip with tilis particular sensitrol, this one is active tripping at approximately ninety -(90) percent'of full-scale. Ninety percent' of full-scale corresponds to about 9000 counts per minute (cpm)

. on the 410K scale (the scale that corresponds to the 5'

3 X 10 amp scale of Channel #3). Operators and i

candidates are familiar with this more stringent setting. Therefore, an operator could possibly answer "A" as well as "B."

Again, "A" or "B" are possible answers.

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. Section C (cont.)

Question 4: The listed answer is "C." However, there appears to be some confusion, I feel on behalf of the test '

author, of how our rod position indication lights operate. The green light is the "down" light, the yellow light is the " engaged" light, and the red light is the "up" light. On loss of electrical power, the CCR, SR1 and SR2 rods will drop. All the rod magnets will drive down after power is restored. The only way the red light could be on for the FCR is if power was just restored and for a split second the rod was still at the top of the core. If this is the case, the green lights for.  ;

the CCR, SR1, and SR2 will not be on yet. Travel time for the CCR, SR1, and SR2 magnets is approximately tnirty-two (32) seconds. The FCR magnet takes nearly one minute and forty-five seconds for full travel.

If a momentary loss of power (say only a second) caused a scram, the rod position indication lights after sixty seconds would be as follow: CCR, SR1, and SR2 green and yellow lights on, and the green light for the FCR might be on depending upon its rod position prior to the scram. The yellow light for the FCR is wired in parallel with the CCR yellow light and will be on whenever the yellow light for the CCR is on.

The only possible way'to obtain the indications that the question states is if the magnets for the CCR, SR1, and SR2 are all the way drive down, all the yellow li hts burn out, and the FCR is stalled (stuck) out the top of the core.

I HIGHLY recommend that this question be thrown out.

Question 15: "A" is the listed answer. "B" is also an answer.

The Radium-Beryllium source used for startup of the AGN-201 reactor is placed in either in the glory hole or thermal column. OP #1 Section III.D instructs the operator to record the source location. This is because it is sometimes placed in the glory hole as previously mentioned.

Again, "A" or "B" are correct answers.

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

QUESTION 016 (1.00)

A~ reactor startup is being performed with an experiment installed in the glory hole. 1/M plots are being used to predict critical rod position.

Tha follow.ing data has been obtained: t,o f

ROD POSITION COUNT RATE

/s.suve @o = 44 &*~O K Tke w All rods removed 10 CPS 1 SR inserted 15 CPS

Ny ;A 2 SR's inserted 31 CPS O 44 /. O O FR fully inserted 44 CPS ff )gg CR e 5 cm inserted 51 CPS 7 CR e 10 cm inserted 60 CPS /0 60 0,73 CR e 15 era inserted 125 CPS fy g)y g ,yr l '  !

Based on the information provided, WHICH ONE (1) of the following coarse rod positions corresponds most closely with the expected critical rod position?

a. 18 cm inserted

b. 20 cm inserted i

c. 24 cm inserted -

d. Criticality cannot occur with all rods inserted due to the  !

experiment that is installed '

1/M PLOT t

[0715erv//,

(b \ USb ht 77e.

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n- 6'{t2 //

%A nne e&ght 1/M \

R M.

\N NN

• o g to Rod Position is ao

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

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NRC RESOLUTION OF IDAHO STATE UNIVERSITY COMMENTS i QUESTION A006  !

t Comment not accepted. During the approach to criticality, equilibrium l subcritical count rates depend directly on the source strength. It is l certainly true that the source strength does not determine the critical rod  ;

height (nor does it affect count rate ratios). However, the absolute value of ;

count rate, and hence power level as criticality is approached, is directly  ;

proportional to source strength (Count Rate - S/(I-k). l QUESTION AOIS i Comment noted. Typographical error in answer key. -

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QUESTION A0I6 Comment accepted. Either "a" or "b" will be considered correct.  !

i QUESTION B002 I Comment not accepted. Answer "a" states that the certified person is non- [

licensed. Unless explicitly stated, there is no reason to assume that the non-licensed person in answer "b" is certified. l QUESTION B006 i Comment accepted. Either "c" or "d" will be considered correct.

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QUESTION B008 I Comment not accepted. The Emergency Evacuation Plan (Appendix 3) requires an evacuation if the radiation levels are above 10 mR/hr outside the operations area of the Nuclear Reactor Laboratory.  !

' QUESTION C003:

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. Comment not accepted. With reference to the Study Guide, Neutron Monitoring ,

System, it is stated that the expected output of Channel #1 when the reactor +

is at 5 watts is about 9000 cps. With reference to the Test Bank questions,  ;

it is stated that a Channel #1 high scram occurs at 95% of full scale (9500 )

cps).

l QUESTION C004 Comment accepted. Question will be deleted.

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l QUESTION C015:  !

Comment not accepted. In "The AGN-201 Reactor," the section on " Source" '

states that'"the source may be removed [from its normal location in the top of the graphite reflector] and placed in any access port or in the thermal column :

for reactor startup...." OP#1,Section III.D does indeed instruct the r operator to note the source location, but that does not mean that the source '

may be located in the glory hole (which is different from an access port). If i the descriptive materials are deficient with regard to this point, they should i be corrected. l I

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ENCLOSURE 3 'i i

., U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION j FACILITY: Idaho State University REACTOR TYPE: AGN-201 [

DATE ADMINISTERED: 10/25/93 '

REGION: 4 l l

CANDIDATE: .

INSTRUCTIONS TO CANDIDATE: l

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Answers are to be written on the answer sheets provided. Attach [

all. answer sheets to the examination. Points for each question are  ;

indicated in parentheses for each question. A 70 percent overall

-is required to pass the examination. l Examinations will be picked up 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the examination l starts.  ;

% OF l CATEGORY  % OF CANDIDATE'S CATEGORY (

VALUE TOTAL SCORE VALUE CATEGORY  !

i 20.00 33.33 l A. REACTOR THEORY,  !

THERMODYNAMICS,  !

AND FACILITY  !

OPERATING  !

CHARACTERISTICS l 20.00 33.33  :

B. NORMAL AND l EMERGENCY  ;

PROCEDURES AND l RADIOLOGICAL CONTROLS  :

20.00 33.33 i C. PLANT AND '

RADIATION MONITORING

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SYSTEMS  :

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60.00 100.00 TOTALS FINAL GRADE -]

All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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

1. Cheating on the examination means an automatic denial of your i 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. t

4. Use black ink or dark pencil only to facilitate legible reproductions. l S. Print your name in the blank provided in the upper right-hand corner-of the examination cover sheet. .

6. Print your name in the upper right-hand corner of the answer sheets. i

7. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions. ,

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

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9. When turning in your examination, assemble the completed l examination with exarination questions, examination aids and '

answer sheets. In ac'dition, turn in all scrap paper.

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10. 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. <

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.A. RX THEORY, THERMO & FAC OP CHARS Page 4

. QUESTION 001 (1.00) f The following conditions exist: >

A thermal beam of neutrons is aimed at a thin foil target made of ,

10% copper and 90% aluminum.

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The absorption cross sections for copper and aluminum are 3.79 barns and 0.23 barns respectively.

The scattering cross sections for copper and aluminum are 7.9 barns I and 1.49 barns respectively.  !

WHICH ONE (1) of the following has the HIGHEST probability of l occurrence? j

a. A neutron absorption in copper.  ;

b. A neutron absorption in aluminum. >

c. A neutron scattering reaction with copper.

d. A neutron scattering reaction with aluminum.  !

QUESTION 002 (1.00) l WHICH ONE (1) of the following is an example of the beta decay of Uranium?

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a. Uranium 238 becomes Thorium 234. l f

b. Uranium 239 becomes Neptunium 239. l

c. Uranium 238 becomes Uranium 239 i

d. Uranium 238 becomes Plutonium 239 l l

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. A. - RX THEORY, THERMO & FAC OP CHARS Page 5 -[

q QUESTION 003 (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 i neutrons and require more collisions to reach thermal energy. [

'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 than prompt neutrons. 1 QUESTION 004 (1.00)

WHICH ONE (1) of the following factors is affected MOST by an increase in fission product poisoning?

a. Resonance Escape Probability

b. Fast Fission Factor

c. Thermal Utilization Factor l

d. Reproduction Factor QUESTION 005 (1.00) -f A step insertion of positive reactivity to a critical reactor causes a  :

rapid increase in the neutron population known as a prompt jump. WHICH ONE (1) of the following explains the cause of this occurrence?-

a. rapid positive reactivity insertion due to the fuel temperature coefficient (Doppler) feedback

b. shift in the prompt neutron lifetime on up-power maneuvers

c. magnitude of the reactivity insertion exceeding the value of the average effective delayed neutron fraction

d. immediate increase in the prompt neutron population

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

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,-A. RX THEORY, THERMO & FAC OP CHARS Page 6 QUESTION 006 (1.00) ,

Two different neutron sources were used during two reactor startups.

Ons neutron source, which emits ten times as many neutrons as the second, was used in the first startup. Assume all other factors are the some for the second startup. WHICH ONE (1) 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 QUESTION 007 (1.00) i The following conditions exist: '

Two experiments are to be conducted, both starting with reactor power stabilized at 1 watt.

In experiment #1, the coarse rod is inserted 2 cm and the resulting stable reactor period is measured.

W In experiment #2, the coarse rod is withdrawn 2 cm and the resulting stable reactor period is measured.

WHICH ONE (1) of the two experiments will result in the' SLOWER rate of '

power change, including the reason for this response?

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a. Both experiments will result in the same rate of power change assuming that the rod worth for the 2 experiments are equal.

b. Experiment 1, because rod insertion results in a more dramatic prompt jump but the stable rate of power change is slower.

c. Experiment 2, because delayed neutrons average lifetime shifts towards the longer lived delayed neutron precursors.

d. Experiment 2, because of positive feedback from the moderator temperature coefficient and fuel temperature reduction. .

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

,A. RX THEORY, THERMO & FAC OP CHARS Page 7 !

QUESTION 008 (1.00)

The reactor is critical at one (1) Watt. An experiment requires reactor i power be raised to 5 Watts in one (1) minute. WHICH ONE (1) of the following is the approximate reactor period that must be established? l t

a. 15 seconds {

b. 28 seconds

c. 37 seconds [

d. 46 seconds l QUESTION 009 (1.00) i WHICH ONE (1) of the following is MOST efficient in thermalizing neutrons important to sustaining the chain reaction?

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a. Hydrogen atoms in the water shield tank molecules.

b. Hydrogen atoms in the polyethylene.

c. Aluminum atoms in the fuel cladding.

d. Carbon atoms in the reflector.  ;

QUESTION 010 (1.00)

The following conditions exist:

Rod reactivity worth testing is in progress.

Reactor power has been stabilized at I watt.

The coarse rod is inserted 2 cm. 3 The stable power rise from 2 to 4 watts takes 2 minutes.  !

WHICH ONE (1) of the following is the differential rod worth of the coarse rod?

a. 4 X 10" delta k/k per cm ,

b. 2.5 X 10" delta k/k per cm ,

c. 5.5 X 10-' delta k/k per em

d. 2 x 10-' delta k/k per cm

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

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

Although Xenon considerations within the AGN-201 are minor, Xenon is a major factor of reactor operation. WHICH ONE (1) of the following states the criterion that establishes Xenon as a significant fission product poison? ,

a. Xenon's large microscopic cross-section for absorption, but it '

only comprises a small percentage of the' fission product yield.

b. Xenon's large macroscopic cross-section for absorption and its relative abundance as a fission product.

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c. Xenon's large macroscopic cross-section for scattering and its ,

relative abundance as a fission product.

d. Xenon's physical existence in gaseous state allows greater diffusion resulting in higher atomic densities in high flux regions.

QUESTION 012 (1.00)

Which ONE of the following statements describes the difference between Differential and Integral (IRW) rod worth curves?

a. DRW relates the worth of the rod per increment of movement to rod position. IRW relates the total reactivity added by the rod to the rod position.

b. DRW relates *he time rate of reactivity change to rod position.

IRW relates the total reactivity in the core to the time rate of.

reactivity change.

c. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.

d. IRW is the slope of the DRW at a given rod position P

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

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

The reactor is initially subcritical with a Keff of 0.94. Two (2)_ f saist r rods worth a total of 2.4% delta k/k are inserted into the core. l WHICH ONE (1) of the following is the new Keff? i

a. 0.950

b. 0.954  ;

c. 0.962

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d. 0.971 QUESTION 014 (1.00) .

The following conditions exist:

i Two reactors are identical except that Reactor 1 has a beta l fraction of .0072 and Reactor 2 has a beta fraction of-0.0060. l An equal amount of positive reactivity is inserted into both  ;

reactors.  !

WHICH ONE (1) of the following will be the response of Reactor 2?  ;

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a. The resulting power level will be lower. '

b. The resulting power level will be higher. ,

c. The resulting period will be shorter. i

d. The resulting period will be longer.

QUESTION 015 (1.00) of the approximately 200 Fev of energy released per fission event, the largest amount appears in the form of:

a. Beta and gamma radiation

b. Prompt and delayed neutrons

c. Kinetic energy of the fission fragments

d. Alpha radiation )

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

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.A. -RK THEORY, THERMO & FAC OP CHARS Page 10 l QUESTION 016 (1.00)

A reactor startup is being performed with an experiment installed in the glory hole. 1/M plots are being used to predict critical rod position.

The following data has been obtained:

ROD POSITION COUNT RATE All rods removed 10 CPS 1 SR inserted 15 CPS 2 SR's inserted 31 CPS FR fully inserted 44 CPS CR 0 5 cm inserted 51 CPS CR 0 10 cm inserted 60 CPS CR 0 15 cm inserted 125 CPS 6 Based on the information provided, WHICH ONE (1) of the following coarse '

rod positions corresponds most closely with the expected critical rod position?

a. 18 cm inserted  ;

b. 20 cm inserted

c. 24 cm inserted

d. Criticality cannot occur with all rods inserted due to the  ;

experiment that is installed 1/M PLOT 1lM Rod Position

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

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QUESTION 017 (1.00)  !

The reactor is operating with an experiment installed. It was  !

datermined that the excess delta k/k for this startup was 0.53%. A  ;

reactor shutdown is-being performed. When the manual scram was ,

inserted, reactor console indications were that SR #1 failed to drop  ;

with all other rods dropping (SR #2 and CR) or driving (FR) out of the  ;

core. -

The Reactor Supervisor has asked you to perform a rough calculation of

' Shutdown Margin to ensure Technical Specification requirements are not violated. The most recent rod worth surveillance data is: t i

CONTROL ROD DELTA _K/K WORTH SR #1 1.23%

SR #2 1.19%  !

CR 1.24%  :

FR 0.31% l E

Shield tank temperature is 20 Degrees C.

Based on the provided information, WHICH ONE (1) of the following is the present shutdown margin?

a. 4%

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b. 2.7%

c. 2.2% ,

d. 1.2%

I QUESTION 018 (1.00) l Insertion of a control rod into the core adds positive reactivity.

WHICH ONE (1) of the following does NOT describe one of the effects i which contributes to the positive reactivity insertion?

a. On control rod insertion, moderator is being added.

b. On control rod insertion, decreased neutron leakage is occurring due to reduction of air gap.

c. On control rod insertion, fuel is being added.

d. On control rod insertion, poison is being removed due to reduction of air gap.

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

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.A. RX THEORY, THERMO &.FAC OP CHARS Page 12 ,

QUESTION 019 (1.00) i A-reactor startup is being performed, conditions are as follows:  !

Both SR's and FR inserted, CR at 10 cm inserted.  ;

Source is installed.

Count rate has increased and stabilized at 120 CPS for the last 5 ninutes. i The reactor operator states that the reactor is critical. WHICH ONE (1) f of the following states the reason why this was an incorrect statement?  !

a. For a reactor to be critical (Keff=1.0), there has to be an ,

increasing count rate with no rod motion.  !

b. Present neutron population is being held constant due to subcritical multiplication. Removal of the source will result  !

in count rate decaying away.

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c. Criticality cannot be achieved below a count rate of 200 CPS based on insufficient sub-critical multiplication.  !

d. For a reactor startup with the FR being fully inserted prior to j the CR, criticality cannot occur prior to the CR being inserted ,

15 cm to ensure the Technical Specification for excess '

reactivity will not be violated.

QUESTION 020 (1.00)

The AGN-201 design is to produce a fission rate within the thermal fuse that is approximately twice the average of the core. WHICH ONE (1) of the following describes how this higher reaction rate is accomplished? ,

a. The polystyrene media used in the thermal fuse is a better i moderator raising the thermal flux in the fuse area.

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b. The non-uniform fuel loading in the upper #uel disc is to l increase the thermal flux in fuse area. -

c. The fuel enrichment used in the thermal fuse is twice that of  ;

the balance of the core resulting in a higher fission rate in the fuse area.

d. The fuel density used in the thermal fuse is twice that of the balance of the core resulting in a higher fission rate in the -

fuse area. l i

(***** END OF CATEGORY A *****, '

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, B. NORMAL /EMERG PROCEDURES & RAD CON Page 13 QUESTION 001 (1.00)

WHICH ONE (1) of the following MUST supervise all reactor maintenance or modification which could affect the activity of the reactor?

a. Anyone certified by the Reactor Supervisor as qualified to initiate emergency procedures.

b. Licensed Reactor Operator

c. Licensed Senior Reactor Operator

d. A member of the Reactor Safety Committee QUESTION 002 (1.00) f i

The reactor is being prepared for inserting and withdrawing control rods [

one at a time for testing. In accordance with the Technical i Specifications, WHICH ONE (1) of the following composes a. proper i minimum operating staff?

a. A certified person (non-licensed) on the console, a licensed RO

directing the actions of the operator at the console, and an SRO in his third level office,

b. A licensed SRO at the controls, a non-licensed operator in the  !

Reactor Lab, and a Licensed RO in the machine shop. l

c. A licensed SRO on the console and a licensed SRO in the Isotope Laboratory.  ;

d. A non-licensed person on the console, a licensed RO in the  !

Isotope Laboratory, and an SRO in his third level office.

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QUESTION 003 (1.00)

WHICH ONE (1) of the following calculations describes the use of QUALITY FACTOR?

a. RAD x QF = Dose Rate '

b. RAD x QF = Dose ,

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c. RAD + QF = Dose  ;

d. RAD + QF = Dose Rate

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

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B.-NORMAL /EMERG PROCEDURES & RAD CON Page 14 l l

i QUESTION 004 (1.00)  ;

What are Limiting Safety System Settings, as defined by Technical Specifications?

a. Settings for automatic protective devices related to those variables having significant safety functions ,

b. Administrative 1y established constraints on equipment and operational characteristics which shall be adhered to during operation of the facility

c. Limits on important process variables which are found to be .

necessary to reasonably protect the integrity of certain  :

physical barriers which guard against the uncontrolled t release of radioactivity j

d. Systems which are designed to initiate automatic reactor protection or to provide information for initiation of manual ,

protective action.  ;

QUESTION 005 (1.00) l The Automatic Reactivity Control System will be used during the next f reactor operation. While the procedure OP-3, Automatic Reactivity i

control System, was being performed, the override switch failed to stop the drive motor. WHICH ONE (1) of the following must be done to  !

continue the startup?

a. Put auto-rod in the MOST reactive position, place the override switch in the OPERATE position, de-energize the drive motor power supply.

b. Put auto-rod in the MOST reactive position, disconnect motor power supply and control wires.

c. Put auto-rod in the LEAST reactive position, place the override switch in the OPERATE position, de-energize the drive motor r power supply. '

d. Put auto-rod in the LRAST reactive position, diccannect motor power supply and control wires.

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

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

QUESTION 006 (1.00)

Given the following conditions:

Portable radiation survey instruments were calibrated during June, )

1993.

Fixed radiation survey instruments were calibrated during August, 1993.

Radiation surveys of the reactor room and the reactor control room '

were completed during August, 1993.

l Radiation alarms were tested prior to yesterday's only reactor  !

operation.

The same experiment from yesterday will be repeated. The reactor will  ;

be started up today at 10:00 am and operated until 2:00 am tomorrow.  ;

WHICH ONE (1) of the following must be completed before the reactor startup?

a. Calibrate the portable radiation survey instruments prior to the i reactor start up.

b. Calibrate the fixed radiation survey instruments prior to reactor start up.  !

c. Perform a survey of the reactor room and reactor control room during start up.

d. Verify that the high radiation alarms are operable prior to -

reactor start up.

QUESTION 007 (1.00)

• While walking through the Reactor Laboratory with a portable survey  ;

instrument, the reading increases abnormally. WHICH ONE (1) of the  :

following actions is INITIALLY required of the individual?

a. Leave the area and turn the instrument off.

b. Shift to the next higher range.

c. Contact the HP and check the latest survey results. I I

d. Back away and see if the reading decreases.

-i

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

i r

'B. NORMAL /EMERG PROCEDURES & RAD CON Page 16 QUESTION 008 (1.00)

MHICH ONE (1) of the following conditions requires evacuation of the building?

a. Reactor Laboratory is 27 mr/hr

b. Observation Classroom 13 nr/hr

c. Graduate Student Office 6 mr/hr

d. Electronic Laboratory 4 nr/hr QUESTION 009 (1.00)

WHICH ONE (1) of the following is the basis for the maximum core temperature safety limit?

a. Prevent separation of the core.

b. Prevent nelting of the polyethylene core material.

c. Prevent operating personnel from being exposed to high temperature.

d. Prevent spontaneous ignition of the graphite reflector.

QUESTION 010 (1.00)

WHICH ONE (1) of the following is the MAXIMUM allowable excess reactivity with all control and safety rods fully inserted and including i the reactivity worth of all experiments at 20 degrees C? l

a. 0.65% delta k/k

b. 0.73% delta k/k l

c. 0.86% delta k/k

d. 1.0% delta k/k i

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

4

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, B. NORMAL /EMERG PROCEDURES & RAD CON Page 17 f QUESTION 011 (1.00)

WHICH ONE (1) of the following defines a CHANNEL CHECK 7

a. Connection of output devices for the purpose of measuring the [

response to a process variable. j

b. Adjustment such that the output responds within standards of f accuracy and range to known inputs. j l

c. Introduction of a signal into a channel to verify it is operable. {

i

d. A ._aalitative verification of acceptable performance by [

observation of behavior, i

QUESTION 012 (1.00)  !

WHICH ONE (1) of the following is NOT-required to be notified when a {*

safety limit has been violated?

t

a. Reactor Safety Committee [

b. State Radiation Control Section  !

)

c. NRC Regional Office of Inspection and Enforcement fi

d. Director of NRR $

QUESTION 013 (1.00) f The reactor laboratory has been evacuated during a bomb threat. WHICH f ONE (1) of the following may enter a suspected radiation area without  ;

being under the direction of the Radiation Safety Officer? I l

a. Any licensed SRO  !

i

b. Reactor Supervisor j

c. Police or firemen }

i

d. Reactor Administrator i

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

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.B. NORMAL /EMERG PROCEDURES & RAD CON Page 18 QUESTION 014 (1.00)

During reactor maintenance an accessible area has a whole body dose rate of 3 mrem /hr. A worker is expected to receive 120 mrem over a 5 day

.pariod to complete the required maintenance. WHICH ONE (1) of the following is the required designation for that area?

a. Unrestricted Area

b. Radiation Area

c. High Radiation Area

d. Contaminated Area QUESTION 015 (1.00)

WHICH ONE (1) of the following precautions must be taken to prevent corrosion of reactor components during an experimental failure?

a. The corrosive elements of the experiment shall be chemically neutralized.

b. The experiment shall be doubly encapsulated.

c. The experiment shall not be inserted into the reactor.

d. The mass of the corrosive material in the experiment shall be leass than 2 grams.

QUESTION 016 (1.00)

How would an accessible area be posted if the radiation level in the area is 110 mR/hr?

a. CAUTION- RADIATION AREA

b. CAUTION- HIGH RADIATION AREA

c. CAUTION- AIRBORNE RADIOACTIVITY AREA

d. CAUTION- RESTRICTED AREA

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

,B. NORMAL /EMERG PROCEDURES & RAD CON Page 19 [

QUESTION 017 (1.00)

WHICH ONE (1) of the following is the dose rate from a 20 curie cobalt source at 5 feet? (Assume Co-60 emits 2.5 Mev) ,

a. 0.6 rem /hr

b. 1.2 rem /hr

c. 6 rem /hr

d. 12 rem /hr l

QUESTION 018 (1.00)

During reactor operation electrical power is temporarily interrupted. '

WHICH ONE of the following is the action that must be taken'to satisfy tfe(1)Technical Specification requirements for reactor shutdown once power is restored?

a. The control and safety rods must fully withdrawn and the reactor switch must be in OFF position. >

b. The cadmium plug must be inserted in the glory hole and all experiments must be removed.

c. The Interlock bus reset buttons must be pressed and the Channel 1 and Channel 2 control switches must be taken out of OPERATE.

d. The fixed radiation monitors must be re-energized and the i

~

readings verified to be at normal shutdown values.

QUESTION 019 (1.00)

WHICH ONE (1) of the following must be present when the AGN-201 Core Tank is open?

a. A Licensed SRO ,

b. Reactor Safety Officer

c. Reactor Supervisor

d. Reactor Administrator

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

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

QUESTION 020 (1.00)  !

WHICH ONE (1) of the following is the MAXIMUM allowable scram times for the coarse control rod and the safety rods?

l

a. 200 milliseconds

b. 300 milliseconds

c. 400 milliseconds

d. 500 milliseconds  !

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

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~C. PLANT AND RAD MONITORING SYSTEMS Page 21 i I

QUESTION 001 (1.00)

WHICH ONE (1) of the following methods is used to ensure the-Channel 3 I nsutron monitoring system high level scram trip remains active and within Technical Specification limits at all times? j

a. The detector is partially covered by a cadmium jacket.  !

b. Two Coax cables are used to provide redundant power supplies. ,

c. The position of the detector is moved during power ascension.

d. A mechanical stop restricts movement of the range switch.

QUESTION 002 (1 00)

Given the following control rod positions:

FCR is at p.sition 0.00 cm +

CCR is at position 0.00 cm .

SR1 red light is illuminated SR2 red light is illuminated i WHICH ONE (1) of the following states the rod manipulations that can be performed? j

a. Either FCR or CCR can be inserted. Neither SR can be withdrawn. ,

b. Only CCR can be inserted. Neither SR can be withdrawn. -

c. Either FCR or CCR can be inserted. SR1 can be withdrawn.

f

d. Only CCR can be inserted. SR1 can be withdrawn. <

QUESTION 003 (1.00)

WHICH ONE (1) of the following will result in a neutron monitoring j system reactor scram? .

t

a. Channel 1 reads 9000 cpm. I

b. Channel 2 reads 9E-07. [

i

c. Channel 3 reads 8%.  !

d. Reactor period reads 9 seconds.

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

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.C. PLANT AND RAD MONITORING SYSTEMS Page 22 QUESTION 004 (1.00) i Given the following control rod light indications 60 seconds after a reactor scram. -

FCR Green extinguished, Red illuminated CCR, SR1, SR2 Green illuminated, Red and Yellow extinguished ,

i WHICH ONE (1) of the following could have caused the reactor scram?  ;

a. Neutron monitoring system high power level  !

b. Water level low sensor e

c. Loss of electrical power ,

d. Manual scram QUESTION 005 (1.00)

WHICH ONE (1) of the following identifies the type of detector used in t the Channel 2 Neutron Monitoring system?

a. GM tube .j

b. BF-3 Ion Chamber

c. BF-3 Proportional Counter .

d. Scintillation detector j

[

QUESTION 006 (1.00) l WHICH ONE (1) of the following identifies the location of the Channel 1  :

neutron monitoring detector?

a. In the water shield E i

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b. In the thermal column

c. Directly under the core

d. In Reflector port No. 2

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

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.C. PLANT AND RAD MONITORING SYSTEMS Page 23 QUESTION 007 (1.00)

WHICH ONE (1) of the following is designed to contain fission product gases that-might leak from the core? l

a. Lead shield

b. Water shield

c. Steel Support Tank ,

d. Aluminum Core Tank Assembly QUESTION 008 (1.00)

WHICH ONE (1) of the following states the design purpose of the air  !

space between the reactor core and the graphite reflector?

a. Ensures free fall of the bottom half of the core during severe accidents.

b. Increases the fast neutron population in the vicinity of experiments placed in the Access Ports.

c. Allows for accumulation and venting of fission product gases created during reactor operation.

d. Prevents core damage during the design basis earthquake of 0.6g accelerations and 6 cm displacements.

QUESTION 009 (1.00)

WHICH ONE (1) of the following conditions will open the interlock bus?

a. Neutron monitoring system Channel 1 test switch in " calibrate".

b. Neutron monitoring system Channel 3 reads 4%.

c. Reactor period of 4 seconds.

d. Water temperature sensor reads 19 degrees c.

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

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,C. PLANT AND RAD MONITORING SYSTEMS Page 24  ;

QUESTION 010 (1.00) '

WHICH ONE (1) of the following features is designed to break the rod -

support plate loose from the electromagnet ensuring quick rod release?

a. Reset relay

b. Overcurrent relay i  !

c. Current Reversal relay

d. Interlock bus QUESTION 011 (1.00)

During annual control rod maintenance, only one control rod may be

. removed and disassembled at a time. WHICH ONE (1) of the following is ,

the basis for this precaution?

a. To ensure that parts are not interchanged.

b. To prevent inadvertent criticality.

c. To maintain QA per the QA manual chapter 7.

i

d. To ensure radiation exposure is ALARA. ,

L QUESTION 012 (1.00)

The reactor is being started and power is 0.1 watt. WHICH ONE (1) of the following states the consequences of failing to rotate the range  !

. switch when the movable Nuclear Monitoring system detector is raised? I i

a. The reactor will scram on fast period. l

b. The reactor will scram on low power level. I

c. The reactor will scram on high power level. l

d. The reactor will operate with invalid scram setpoints. i i

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

C. PLANT AND RAD MONITORING SYSTEMS Page 25 QUESTION 013 (1.00)

WHICH ONE (1) of-the following describes the operation of the movable Nuclear Monitoring detector?

a. The weight of the detector holds it in the lower position; ENERGIZING the solenoid arm lifts the detector to the upper position.

b. The weight of the detector holds it in the lower position; DEENERGIZING the solenoid arm lifts the detector to the upper position.

c. The solenoid arm holds the detector in the lower position; ENERGIZING the solenoid allows the detector to float to the upper position.

d. The solenoid arm holds the detector in.the lower position; DEENERGIZING the solenoid allows the detector to float to the upper position.

QUESTION 014 (1.00)

To complete reactor shutdown, Console power is turned off by depressing the "OFF" pushbutton. WHICH ONE (1) of the following identifies the Console components that will remain operable?

l

a. Nuclear Monitoring Channel 1 and Control Rod Position indication

b. Nuclear Monitoring Channel 3 and the Fixed Radiation Monitor

c. The 6L6 electronic switch and Control Rod Position indication

d. The 6L6 electronic switch and the Fixed Radiation Monitor 1

I QUESTION O'S (1.00)

! The glory hole is primarily used to conduct experiments. WHICH ONE (1) of the following states two additional functions of the glory hole?

a. Holds a cadmium plug during shutdown and supports the upper half of the core during severe accidents.

b. Holds a cadmium plug during shutdown and holds the Radium-Beryllium source during startup.

! c. Holds graphite, lead and wood when not in use and supports the upper half of the core during severe accidents,

d. Holds graphite, lead and wood when not in use and holds the Radium-Beryllium source during startup.

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

1

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,C. PLANT AND RAD MONITORING SYSTEMS Page_26

-QUESTION 016 (1.00)

WHICH ONE (1) of the following describes the reset capabilities of reactor scram system trips and Interlock bus trips?- <

a. Both sensitrol trips and Interlock bus trips must be manually reset.

b. Sensitrol trips must be manually reset, but Interlock bus trips will automatically reset. .

c. Sensitrol trips will automatically reset, but Interlock bus trips must be manually reset.

d. Both sensitrol trips and Interlock bus trips will automatically reset.

QUESTION 017 (1.00)

WHICH ONE (1) of the following scram trips is designed to prevent excessive radiation levels?

a. reactor period

b. high reactor power

c. low water level

d. low water temperature QUESTION 018 (1.00)

WHICH ONE (1) of the following identifies the preferred locations for Automatic Reactivity Control system components?

a. The auto-rod will be placed in reflector port No. 2 and the ion chamber will be placed in reflector port No. 4.

b. The auto-rod will be placed in reflector port No. 2 and the ion chamber will be placed in the thermal column.

c. The auto-rod will be placed in reflector port No. 4 and the ion chamber will be placed in reflector port No.-2.

d. The auto-rod will be placed in reflector port No. 4 and the ion chamber will be placed in the thermal column.

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

I i

.C. PLANT AND RAD MONITORING SYSTEMS Page 27

. QUESTION 019 (1.00)

A nuclear emergency requires evacuation of the entire building. WHICH  :

ONE (1) of the following identifies where the alarm can be actuated?

a. at the reactor console ,

b. in the Subcritical Assembly Laboratory t

t

c. south wall across from the health physics office  ;

d. at the bottom of the stairs on the south side of the' building ,

QUESTION 020 (1.00)

WHICH ONE (1) of the following conditions could put a negative signal on the 6L6 grid?

a. Magnetic Overcurrent trip '

b. Failure of the 250V power supply

c. Failure of the Period Trip relay

d. Failure of the 6L6 electronic switch [

t 4

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k

[

( * * * *

• END OF CATEGORY C * * * * *)

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

I

?

am - -

t A. RX THEORY, THERMO & FAC OP CHARS i

ANSWER 001 (1.00) '

D.

REFERENCE l

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 47.

Reaction Rate proportional to microscopic cross-section x u.nsity ANSWER 002 (1.00)

B.- '

REFERENCE Lamarsh, Second Edition, Section 2.8, page 19 ANSWER 003 (1.00)

C.

-REFERENCE Glasstone & Sesonske, Sec. 5.28  !

ANSWER 004 (1.00)

C.

REFERENCE _

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 316. l ANSWER 005 (1.00) ,

D.

REFERENCE Glasstone & Sesonske, Sec. 5.32 l ANSWER 006 (1.00)

A.

REFERENCE Glasstone & Sesonske, Sec. 5.175 e

ANSWER 007 (1.00)

C.  !

REFERENCE ,

Glasstone & Sesonske, Sec. 5.42 ^

. ANSWER 008 (1.00)

C.

REFERENCE Glasstone & Sesonske, Sec. 5.36  !

Period = Time /In (P/Po)

Period = 60 seconds /In (5 watts /1 watt) = 37.3 seconds ANSWER 009 (1.00)

B. i REFERENCE AGN-201 Reactor System Description j;

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A

'A. RX THEORY, THERMO & FAC OP CHARS ANSWER 010 (1.00)

D.

REFERENCE I

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 290.

Pariod= Time /In (P/Po)  !

Pcriod= 120 seconds /In (4 watts /2 watts)

Period = 173 seconds ; roe = betabu/ ((lamda.rr

• Period) + 1) rom = 0.0065/((0.08

• 173) + 1) ; roe = 0.0065/(13.84 + 1) ron = 0.0065/14.84 ; roe = 4 X 10" ron/cm = 4 X 10"/ 2 = 2 X 104/cm ANSWER 011 (1.00)

B.

REFERENCE Glasstone & Sesonske, " Nuclear Reactor Engineering" Section 5.87 ANSWER 012 (1.00) ,

A. .

REFERENCE

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 303.

ANSWER 013 (1.00) ,

C.

REFERENCE i

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 282.

roe =Keff - 1/Keff, 0.94 - 1/0.94= .0638 (initial -reactivity)

+ .024 delta k/k added by safety rods net negative reactivity = .0638 + .024= .0398 New Keff is: Keff= 1/(1 - roe)

Keff= 1/(1 - [ .0398])= .9617 ANSWER 014 (1.00)

C.

REFERENCE

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 290.

ANSWER 015 (1.00)

C.

REFERENCE Equation sheet  ;

ANSWER 016 (1.00)

B. ,

REFERENCE

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 102.

Appropriate solution can be arrived at using a number of methods. The i most accurate and easiest to use is to have the count rate following ,

fine rod insertion as initial counts (Co) and plot 1/M from that point  ;

using the equation 1/M= Co/C, where "x" is the stable count rate following each coarse rod insertion.

e i

i

i

,A.- RX THEORY, THERMO & FAC OP CHARS ANSWER 017 (1.00)

C.

REFERENCE

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 282.

SDM measures the extent to which the reactor is shutdown. '

Withdrawn Control rod worth = 1.19% + 1.24% + .31%= 2.74% (-

reactivity)

Excess + reactivity given reactor conditions = +0.53% (Given) ,

SDM= - reactivity inserted by rods minus excess reactivity of the core SDM= 2.74% - 0.53%= 2.21% Shutdown Note: Shield tank was given at reference temperature (20 degrees C) so that no temperature correction would be required.

ANSWER 018 (1.00) '

D.

REFERENCE ISU Test Bank Ques: Modified ANSWER 019 (1.00)

B.

REFERENCE

" Introduction To Nuclear Engineering", Lamarsh, 2nd Edition, page 102. r ANSWER 020 (1.00)

D.

REFERENCE -

AGN 201 Reactor Handout t

t l

i-(***** END OF CATEGORY A *****)

i

,B. NORMAL /EMERG PROCEDURES & RAD CON ANSWER 001 (1.00) [

C .'

REFERENCE

1. ISU: Technical Specification 6.1.9.b.

ANSWER 002 (1.00)

A.

REFERENCE

1. ISU: Technical Specifications 6.1.9.a ANSWER 003 (1.00) ,

B.

REFERENCE '

1.. ISU: Radiation Protection Fundamentals

2. ISU: Study-Guide ANSWER 004 (1.00)

A. ,

REFERENCE

1. ISU: Technical Specification 1.0 ANSWER 005 (1.00)

. :B . t REFERENCE

1. ISU: OP-3, step 7.

3 i

ANSWER 006 (1.00) ,

D.

REFERENCE

1. ISU: Technical Specification 4.4 [

ANSWER 007 (1.00)

D.  ;

REFERENCE t

1. ISU: Radiation Protection Fundamentals ANSWER 008 (1.00) ,

B. j REFERENCE -

1. ISU: Emergency Plan, Appendix 3, figure 1.

ANSWER 009 (1.00)

B.

REFERENCE

1. .ISU: Technical Specification 2.1 ANSWER 010 (1.00) i A. l REFERENCE

1. ISU: Technical Specification, 3.1, p. 7

r

,B. NORMAL /EMERG PROCEDURES & RAD CON  !

ANSWER 011 (1.00)

D. i REFERENCE l

1. ISU: Technical Specification 1.2 i ANSWER 012 (1.00)

B.  ;

REFERENCE -

1. ISU: Technical Specification, 6.8, p. 26 ANSWER 013 (1.00)

• C.  ;

REFERENCE '

1. ISU: Emergency Plan, p. 10. l ANSWER 014 (1.00)  ;

B.

REFERENCE

1. ISU: Radiation Protection Definitions  !

ANSWER 015 (1.00) '

B.

REFERENCE ,

1. ISU: Technical Specification 3.3

-1 ANSWER 016 (1.00)

B.  !

REFERENCE

1. ISU: Rules and Procedures for Use of Ionizing Radiation at Idaho  ;

State University, Page 21  !

ANSWER 017 (1.00)

D.

REFERENCE I

1. ISU

D= 6CE/d**2 ; D= 6 (20) (2.5) /25 ; D= 12 rem /hr ANSWER 018 (1.00)  ;

A. i REFERENCE

1. ISU: Technical Specification, 1.14 ANSWER 019 (1.00) ,

C. '

REFERENCE

1. -ISU: MP-2, Prerequisites and Safety

. ANSWER 020 (1.00)

A. ,

-REFERENCE

1. ISU: Technical Specifications 3.2.a

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

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'C. PLANT AND RAD MONITORING SYSTEMS '

r ANSWER 001 (1.00) ,

D.

REFERENCE

1. Study Guide, Neutron Monitoring

~

ANSWER 002 (1.00) ,

A.

REFEPENCE

1. "The AGN-201 Reactor," Control Rods i ANSWER 003 (1.00)

B.

• REFERENCE *

1. Technical Specification table 3.1 ANSWER 004 (1.00) '

C.

REFERENCE I

1. "The AGN-201 Reactor," Control Rods (If electrical power available, all drives will retract and magnets'will engage.) ,

ANSWER 005 (1.00)

B.

REFERENCE

1. Study Guide, Neutron Monitoring ANSWER 006 (1.00)

A.

REFERENCE

1. Study Guide, Neutron Monitoring ANSWER 007 (1.00)

D.

REFERENCE

1. Technical Specification 5.1.b ANSWER 008 (1.00)

A. '

REFERENCE

1. Technical Specification 5.1.a ANSWER 009 (1.00)

A.

REFERENCE

1. -Study Guide, Safety Chassis ANSWER 010 (1.00)

C.

REFERENCE

1. Study Guide, Safety Chassis

i

.C. PLANT AND RAD MONITORING SYSTEMS [

ANSWER 011 (1.00)

A. j REFERENCE '

1. ISU: MP-1  ;

P ANSWER 012 (1.00) -

B. i REFERENCE

1. Operating Procedure 1, page 10 ANSWER 013 (1.00) .;

C. I REFERENCE l

1. Operating Procedure 1, page 2 ANSWER 014 (1.00) f B.

REFERENCE

1. Operating Procedure 2, page 10  ;

ANSWER 015 (1.00)

A.

REFERENCE 1

1. "The AGN-201 Reactor," Access Holes and glory hole

2. Operating Procedure 2, page 5 l ANSWER 016 (1. 00) ,

B.

REFERENCE ,

1. Surveillance Procedure 1, page 3; III.E i

2. Surveillance Procedure 6, page 2; II.A,B,C ANSWER 017 (1.00)  ;

i C.

REFERENCE 1.- Technical Specification 3.1 Bases, page 10  ;

i ANSWER 018 (1.00) j D.

REFERENCE 1.. Experiment Procedure No. 21  ;

ANSWER 019 (1.00) t D. i REFERENCE

1. Emergency Plan, page 13 ANSWER O20 (1.00)

C.  ;

REFERENCE l

1. Study Guide, Safety Chassis  ;

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,A. RX THEORY, THERMO & FAC OP CHARS Page 1 ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)

If you change your answer, write your selection in the blank. j 001 a b c d  ;

.002 a b c d  :

003 a b c d 004 a b c d i 005 a b c d 006 a b c a '

t 007 a b c d  !

008 a b c d 009 a b c d 010 a b c d l

011 a b c d i

012 a b c d  ;

013 a b c d 014 a b c d i'

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 1

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

B. NORMAL /EMERG PROCEDURES & RAD CON Page 2 ANSWER SHEET r

-MULTIPLE CHOICE (Circle or X your choice)

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

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 1

011 a b c d 012 a b c d v

013 a b c d i 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  !

l 020 a b c d  ;

i

(***** END OF CATEGORY B *****)  !

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,C. PLANT AND RAD MONITORING SYSTEMS Page 3 l 1

ANSWER SHEET l

MULTIPLE CHOICE (Circle or X your choice) l t

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

001 a b c d l i

002 a b c d  !

.003 a b c d  ;

004 a b c d I 005 a h c d l

006 a b c d 007 a b c d 008 -a b c d i

009 a b c d '

i 010 a b c d l

011 a b c d 012 a b c d 013 a b c d ,

014 a b c d  ;

i' 015 a b c d 016 a b c d

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017 a b c d ,

018 .a b c d l 019 a b c d i

020 a b c d i i

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

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. 1 EQUATION SHEET l r

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.i SUR = 26.06/r 8 **)

P = Pa 10 '

l Ir P=Po e it/' 3 7 = (t*/p) + [ ($-p) /hertP 3 -

A,gg = 0.08 seconds ~1 DR3D22 = DR 2D2*  !

l DR = 6CiE/D 2 DR = DR o e~^'

a p= (Keff-1)/Keff R = No l i

i 1 Curie = 3.7x1010 dps 1 gallon water = 8.34 pounds f 1 Btu = 778 ft-lbf *F = 9/5*C + 32 j 1 Mw = 3.41x10' BTU /hr *C = 5/9 (*F - 32) -

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