ML20195J485

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NRC Operator Licensing Exam Rept 50-128/OL-99-01 (Including Completed & Graded Tests) for Tests Administered on 990405- 06.Exam Results:Both Candidates Failed Written Portion of Exams
ML20195J485
Person / Time
Site: 05000128
Issue date: 06/03/1999
From: Isaac P
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20195J444 List:
References
50-128-OL-99-01, 50-128-OL-99-1, NUDOCS 9906210033
Download: ML20195J485 (41)
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Text

s U. S. NUCLEAR REGULATORY COMMISSION  !

OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-128/OL-99-01 FACILITY DOCKET NO.: 50-128 FACILITY LICENSE NO.: R--8 3 FACILITY: Texas A&M University EXAMINATION DATES: April 5 - 6,1999 1

EXAMINER: Patric, aac Chief Ex miner {

7 SUBMITTED BY: e oo- 63 9 Patrick Isaac, ChihIExaminer Dat'e '

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SUMMARY

I During the week of April 5,1999, NRC administered Operator Licensing Examinations to two Reactor Operator (RO) candidates. Both candidates failed the written portion of the examinations.

l 9906210033 990610 PDR ADOCK 05000128 i V PDR c j

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2-REPORT DETAILS

1. Examiners:

Patrick Isaac, Chief Examiner

2. Results:

RO PASS / Fall ' SRO PASS / Fall TOTAL PASS / Fall Written 0/2 n/a 0/2 Operating Tests 2/0 n/a 2/0 i Overall 0/2 n/a 0/2 l

3. Exit Meeting: l l

Personnel attending: l Mr. William Asher, TAMU Manager of Operations Mr. Patrick Isaac, Chief Examiner The facility examination comments were discussed as noted in Enclosure 2. l 1

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NRC RESOLUTIONS -WRITTEN EXAMINATION QUESTION (C.11)

On a decreasing poollevel, the University communications room will receive an alarm. What other automatic action will occur?

a. Recirculation pump trip.
b. Skimmer pump trip.

- c. Core diffuser pump trip

d. Purification pump trip.

ANSWER: a Facility Comment:

In the answer choices, reference is made to the " Recirculation Pump Trip" and the " Purification Pump Trip." At the NSC the recirculation pump and the purification pump are one in the same.

Consequently, I feel that either answer should be accepted as a correct answer.

NRC Resolution: i Comment Accepted. Question C.11 will be modified to accept answers "a" and "d" as correct.

ENCLOSURE 2

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U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: Texas A&M REACTOR TYPE: TRIGA DATE ADMINISTERED: 04/05/99 CANDIDATE: .

i INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach all answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each 3 category 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 l j

20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING >

CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY 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.

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l Candidate's Signature ENCLOSURE 3

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o-A RX THEORY. THERMO & FAC OP CHARS ANSWER SH EET Multiple Choice (Circle or X your choice) ,

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

MULTIPLE CHOICE 001 a b cd 002 a bcd 003 a b c d 004 a b cd e

005 a bcd 006 a b cd 007 a bcd 008 a bcd 009 a b cd 010 a b c d 011 abcd 012 a b c d 013 a b c d 014 abcd 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 ""*)

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,g B $ORMAL/EMERG PROCEDURES & RAD CON q

t A N SWE R 'S H E ET Multiple Choice L (C'ircle or X your choice)

If you change your answer, wnte your selection in the blank. j i

- MULTIPLE CHOICE.

001 - a b ' c ,d 002: a b~c d

' 003 a ~ b c ~ d -

i 004 a b c d'

  • 005' a b . c . d i j

i 006 a ' b ' c . d .

007 ~2 3

'OC abcd 009 -L a - b e c 'd' I 010 a . b . c d 1

011o a b . c ' d .

012 a ' b c ' d'

013 -' a b'- c 014 a b-c'd 015 a b - c 'd j I

016 a b c ~ d 1

017 ' a b c od I

~

I 018 ' a ' b c .. d '

4 019 a b c d

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

C f)LANT AND RAD MONITORING SYSTEMS A NSWER SHEET Multiple Choice Circle or If you change you(r answer,X your choice) write your selection in the blank.

MULTIPLE CHOlCE 001 a b c d ,__

002 a b c d __

003 a b c d __

004 abcd _,_

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 abcd__

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 ,__

D18 a b c d ___

)19 a b c d __,,

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

END OF EXAMINATION """"")

. 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 neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4. Use black ink or dark pencil only to facilitate legible reproductions.
5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7. The point value for each question is indicated in (brackets) after the question.
8. If the intent of a question is unclear, ask questions of the examiner only.
9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.
10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.

Scrap paper will be disposed of immediately following the examination.

11. To pass the examination you must achieve a grade of 70 percent or greater in each category.
12. There is a time limit of three (3) hours for completion of the examination. j
13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

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- EQUATION SHEET b = sc, 6 T z 6 an = ";, S T :p-g:;

p~ "

2cx ( k) (

l' = 5 x 10

  • seconds -

SCR - ~

-o 1-Kg,

~

h gf = 0.1 seconds -

CR. ( 1 -K,,, .

) =

CR, ( 1 -K,,7 )

5 = 0. 007 .

CA: l ~P: ) CR: I -C' )

1-Kerr h*!:p )

M=

S UR = 2 6 . 0 E 1 ~ ^,,e r f.

3-9 1 CR. p_p 39s;:p,:,

'y , . _,

1~K,,, CR SDM = :1-K'")

p-p g i e

- err T=

f p- oil ~P) p o-0 S-p K, ~, , - Kg,

~- C, p Sp = T _ +

ke!!." Ke!!. O h, gyp  ;

-H*_ 0.693 A _

(Kett -1) eff DR = DR o e'^* DR, d,* = DR,d 6CiE(n) (P,-0)#

(p3 -B)2

=

DR =

R: Peak 2 Peak 1 l I=I,e* l l

1 Curie = 3.7 x 10"' dis /sec 1 kg = 2.21 lbm l

1 BTU = 778 ft-thf F = 9/5 C + 32

- I gil (H 2O) = 8 lbm C = 5/9 (*F - 32) cp = 1.0 BTU /lbm/"F cp= 1 callsec/gm/'C l

4 Section A R Theory. Thermo & Fac. ODeratina Characteri tic t _s Page 1 Question (A.1) [1.0]

A reactor scram h'as'resulted in the instantaneous insertion of .006AK/K of negative reactivity.

Which one of the following is the stable negative reactor period resulting from the scram?

a. 45 seconds
b. 56 seconds
c. 80 seconds
d. 112 seconds Question (A.2)- [1.0)

. The count rate is 50 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 25 cps. Given the initial K., of the reactor was 0.8, what is the worth of the experiment?

a; Ap = - 0 42

b. Ap = + 0.42
c. op = - 0.21

- d. Ap = + 0.21 i

Question (A.3) [1.0]

Given the lowest of the high power scrams is 110%, and the scram delay time is 0.5 sec. If the l reactor is operating at 100% power prior to the scram, approximately how high will reactor power get with a positive 20 second period?

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a. - 113%' i i

b, 116 %

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- c. 124 % i

d. 225 %

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Page 2 Section A: R Theory. Thermo & Fac Ooeratino Characteristics Question (A.4) [1.0)

Which one of the following is the dominant factor in determining differential rod worth?

a. Axial and Radial Flux

- b. Total Reactor Power

c. Rod speed
d. Delayed neutron fraction 1

Question (A.5) [1.0)

Which one of the following is the MAJOR source of energy recovered from the fission process?

a. Kinetic energy of the fission neutrons
b. Kinetic energy of the fission fragments
c. Decay of the fission fragments
d. Prompt gamma rays Question (A.6) [1.0)

Which statement illustrates a characteristic of Subcritical Multiplication?

a. As Keff approaches unity (1), for the same increase in Keff, a greater increase in neutron population occurs.
b. The number of neutrons gained per generation gets larger for each succeeding generation.
c. The number of fission neutrons remain constant for each generation.
d. The number of source neutrons decreases for each generation.

r Section A: R Theory. Thermo & Fac. Ooeratino Characteristics Page 3 t

Question (A.7) . [1.0]

Which one of the following could result from an attempt to start up the reactor with NO installed 3 neutron source?

a.' The reactor could not be started up because there would be no source of neutrons to start the chain reaction.

b. - .It is possible th'at reactor power would not be indicated on the nuclear instrumentation until an incident fission reaction resulted in a very short period.
c. . Subcritical multiplication would result in a stable count rate on the nuclear instrumentation even though power was increasing.

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d. Startup of the reactor would require increasing the voltage on the source range detectors to establish a count rate from photoneutrons.

' Question (A.8) [1.0]

Which one of the following statements describes Count Rate characteristics after a control rod withdrawal with the reactor subcritical? (Assume the Rx remains suberitical.)

a. Count Rate will rapidly increase (prompt jump) then gradually increase to a stable value.
b. Count Rate will rapidly increase (prompt jump) then gradually decrease to the previous value, c.- Count Rate will rapidly increase (prompt jump) to a stable value,
d. There will be no change in Count Rate until criticality is achieved.

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Section A: R Theory Thermo & Fac. Operatino Characteristics Page 4

-- Question - (A.9) [ 1.0]

Most nuclear text books list U-235 delayed neutron fraction (p,) as being 0.0065Ap. Most research reactors however have an effective delayed neutron fraction (p.n .) of 0.0070 ap.

' Which one of the following is the reason for this difference?

a. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons.
b. Delayed neutrons are born at lower energies than prompt neutrons resulting in a greater worth for the neutrons.
c. The fuel includes U23a which has a relatively large p for fast fission.

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d. 2 The fuel includes U23a which via neutron absorption becomes Pu
  • which has a larger p for fission.

l Question (A.10) [1.0]

, Select the condition NOT assumed when calculating shutdown margin. j 1

a. The highest worth, unsecured experiment is in !:s most reactive state.
b. The regulating rod fully withdrawn.
c. The reactor i. in the cold condition without Xe.
d. The reactor has been shutdown for greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Question (A.11) [1.0]

A reactor with an initial population of 24000 neutrons is operating with K., = 1.01. Of the

- CHANGE in population from the current generation to the next generation, how many are prompt neutrons?

a. -24 '
b. 238  !

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c. 240
d. 24240

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Section A R Theory. Thermo & Fac. Operatina Characteristics Page 6  ;

l' Question (A.12) [1.0)-

An element decays at a rate of 20% per day. Determine its half-life. l l

a. 3 hr. ,

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b. 75 br.  !
c. 108 hr.

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d. 158 hr. I i

Question (A.13) [1.0] '

l The TRIGA reactor is required to pulse from low power levels. Which one of the following is the reason for this limitation on power level prior to the pulse?

a. To prevent exceeding the maximum power level limit
b. To prevent exceeding the fuel element temperature limit
c. To prevent exceeding the pool temperature limit
d. To prevent exceeding the reactivity insenion limits Question (A.14) [1.0]

Which statement best aescribes Xe-135 behavior following a Rx Scram?

a. Xenon concentration decreases due to production rate from fission stops.
b. Xenon concentration decreases due to production rate from I-135 decay increasing.
c. Xenon concentration increases due to production rate from Pm-149 increasing.
d. Xenon concentration increases due to 1-135 decay exceeding Xe-135 decay.

Section A: 9 Theory. Thermo & Fac. Operatina Characteristics Page 6 Question (A.15) [1.0)

As power level increases, the fuel temperature coefficient causes:

a. 238U to absorb neutrons over a wider range, thus decreasing the number of neutrons available for fission with 235U,
b. Doppler resonance effects to decrease.
c. The moderator density to decrease causing a significant increase in the number of neutrons absorbed by the fuel.
d. More thermal neutron absorption by the moden.+or.

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O Section A: R Theory. Thermo & Fac. Operatina Characteristics Page 7 Question (A.16) [1.0]

Experimenters are attempting to determine the critical mass of a new fuel material. As more fuel was added the following fuel to count rate data was taken-e.

Fuel Counts /Sec 1.00 kg 500 1.50 kg 800 2.00 kg 1142 2.25 kg 1330 2.50 kg 4000 2.75 kg 15875 Which one of the following is the amount of fuel needed for a critical mass?

a. 2.60 kg
b. 2.75 kg
c. 2.80 kg
d. 2.96 kg

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Section A: R Theory. Thermo & Fac. Operatina Characteristics Page 8 OuestioP 6 .17) [1.0]

Assuming the Samarium worth is 0.006 AK/K atf f power, which one of the following is the Samarium worth 10 days after shutdown from 'td;i power?

a. Essentially zero. e '

b.

Approximately twice the full power equihbrium value.

c.

Less than 0.006 AK/K but greater than zero.

d.

Greater than 0.006 AK/K.

Question (A.18) [1.0]

Which profile? one of the following is n_o_t a reason for or benefit of operating with a flat neutron flux a.

A higher average power density is possible.

b. More even burnup of fuel results.

c.

Moderator temperature is equahzed throughout the core.

d.

Control rod worth is made more uniform.

Question (A.19) [1.0]

The fundamental design parameter which permits a TRIGA reactor system to operate s during either steady-state or pulsing conditions is the large prompt negative temperature coefficient of reactivity. The largest contributor to this design parameter is:

a. doppler effects
b. core leakage c.

core neutron spectrum-hardening d.

formation of core voids

t Section A: R Theory. Thermo & Fac. Operatina Characteristics Page 9 Question (A.20) [1.0]

The term " reactivity" is described as:

a. a measure of the core's fuel depletion.
b. negative when Keff is greater than 1.0.
c. a measure of the core's deviation from criticality.
d. being equal to 50.66 when the reactor is prompt critical.

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Section 8: Normal /Emera Procedures & Rad Con Page 10 Question - (8.1) [1.0]

A small radioactive source is to be stored in the reactor building. The source is a 0.5 curie and emits a 1.33 Mev gamma.

' Assuming no shielding is used, a Radiation Area barrier will have to be erected from the source at a distance of approximately:

a. 28 feet
b. 22 feet
c. 17 feet
d. 2 feet QUESTION (B.2) [1.0)

A room contains a source which, when exposed, results in a general area dose rate of 175 millirem per hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room.

a. Post the area v,-th the words " Danger-Radiation Area"
b. Equip the room with a device tc visually display the current dose rate within the room.
c. Equip the room with a motion detector that will alarm in the control room.
d. Lock the room to prevent inadvertent entry into the room.

Question (B.3) [1.0]

Identify the condition which is a reportable occurrence.

a. The reactor scrams on Hi Power Level at 115%.
b. The Transient Rod scrammed 12 seconds after a pulse.
c. An unexpected change in reactivity of 1.2% AK/K.
d. Discovering, while performing the pre-startup check, that the Fuel Element Temperature scram is set at 545 C.

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7 Section B: Normal /Emero Procedures & Rad Con Page 11

- Question (B.4) [1.0)

Consider two point sources, each having the same curie strength. Source A's gammas have an energy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading from the same Geiger counter 10 feet from each source. Concerning the two readings, which one of the following statements is correct?

a. The reading from Source B is four times that of Source A.
b. The reading from Source B is twice that of Source A.
c. Both readings are the same. ,
d. The reading from Source B is half that of Source A.

QUESTION (B.5) [1.0)

Which one of the following is the definition of Committed Dose Equivalent?

a. The sum of the deep dose equivalent and the committed effective dose equivalent.
b. The dose equivalent that the whole body receives from sources outside the body.
c. The sum of the external deep dose equivalent and the organ dose equivalent.  !
d. The 50 year dose equivalent to an organ or tissue resulting from an intake of radioactive l material.

QUESTION (B.6) [1.0) l In order to ensure the health and safety of the public,10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate from Tech. Specs?

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!- a. USNRC

b. Reactor Supervisor
c. Licensed Senior Reactor Operator,
d. Licensed Reactor Operator.

n Section Bi Normal /Emera.' Procedures & Rad Con Page 12 Question '(B.7) [1.5].

Match the requirements (10CFR55) for maintaining an active operator license in column A with

- the correct time period from column B.

Column A' Column B  !

=1, Renewal of license a.' 4 months .

'l 2.- Medical Examination b. - 1 year

3. C'onsole Manipulation Evaluation c. 2 years
d. 6 years ,

l Question (B.8) [1.0) l

- A point source of gamma radiation measures 50 mr/hr at a distance of 5 ft. What is the exposure rate (mr/hr) at a distance of 10 ft.

a. 25 mr/hr
b. 12.5 mr/hr
c. 6.25 mr/hr
d. 17,5 mr/hr Question - (B.9) [1.0]

Which ONE of the following does not require the direct supervision (i.e., presence) of an SRO7

a. Movement of the reactor bridge.
b. - Initiation of a pulse. I
c. . Removal of a control rod.

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d. - Performance of a' power calibration of the Linear Power Channel..

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t Section B: Normal /Emero. Procedures & Rad Con Page 13

- Question (B.10) - [1.0)

Which ONE of the following conditions is permissible when the reactor is operating, or about to be operated?

a. "A fuel element is known to be damaged, but has been moved to the periphery of the core assembly.-.
b. A non-secured experiment worth 51.50.
c. An experiment is inserted in a vacant core lattice position on the periphery of the core assembly.
d. The Continuous Air Radiation Monitor and the Exhaust Gas Radiation Monitor are inoperable due to maintenance and have been replaced with gamma sensitive instruments with alarms.

, Question (B.11) [1.0)

"The reactor power level shall not exceed 1.3 megawatts under any condition of operation "

This is an example of a:

a. safety limit.
b. limiting safety system setting.

- c. - limiting condition for operation.

d. surveillance reqmrement.

Quwtion (8.12) [1.0]

An experiment with a reactivity worth of 50.20 is to be removed from the core. Prior to

. performing this operation:

a. reactor pcwer must be less than 600 kW.
b. the reactor must be secured.
c. the reactor must be subcritical by at least 50.40.
d. the reactor must be shutdown.

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t Section B Normal /Emera. Procedures & Rad Con Page 14 l Question (B.13). (1.5)

Select the MODE from Column ll when the Safety Circuits from Column I are required to be operable. Modes may be used once, more than once, or not at all.

Column I Column 11 l (Safety Channel) (Mode) a.- Fuel Element Temperature - 1. Steady State only

- b. Transient Rod Position 2. Both modes

c. Shim-safeties & 3. Pulse only Regulating Rod Position

-Question (B.14) [1.0)

A system or component is defined as " operable" by Technical Specifications if: ,

a. a channel check has been performed.
b. it is capable of performing its intended function.
c. it has no outstanding testing requirements.
d. a functional test has been performed.

Question (B.15) [1.0)

"The area within the operations boundary for the NSCR (defined as the reactor confinement .

building)."

Which one of the following terms matches the above definition?

a. Emergency Support Center (ESC).
b. Emergency Planning Zone (EPZ)
c. Site Boundary..
d. Controlled Access Area (CAA) i

Section B: Normal /Emera Procedures & Rad Con Page 15 Question (B.16) [1.0)

Based on the Requalification Plan for operators at NSC, each licensed operator must complete a minimum of reactivity control manipulations during each 2 year cycle.

a. 2' I
b. 6
c. 12 ,

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d. 16

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Question (B.17) [1.0]

Which one of the following incidents should be classified as a " Notification of Unusual Event"?

a. Reactor pool level decreasing at a rate exceeding makeup capacity.
b. Stack gas monitor (Channel 3) is alarming.
c. Report of a tornado which could strike the facility.
d. Personnel injury with radiological complications.

l Question (B.18) [1.0)

Which one of the following actions listed below qualifies as a Channel Test? l I

a Verifying overlap between Nuclear instrumentation meters.

b. Replacing an RTD with a precision resistance decade box, to verify proper channel output for a given resistance.
c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear Ir;strumentation to agree.
d. During shutdown you verify that the period meter reads -80 seconds.

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. Section 8:_ Normal /Emero Procedures & Rad Con Page.16 Question' (B.19) [1.0]

Which ONE of the following is a duty of the Reactor Operator (RO) during an emergency which requirds a facility evacuation?

.. a . . ; Verify that rope barriers are in place in the reception room.

b, ' Verif'y all persons are accounted for.

c. . Verify all doors'to the reactor building are closed
d. Shutdown building air handling and exhaust systems.

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e Section C: Plant and Rad Monitorina Systems

' Question (C.1) [1.0)'

Mechanical stops prevent inadvertent movement of the NSCR closer than from the irradiation cell window.

a. 12 ft
b. 8 ft
c. 18 inches
d. 3 inches Question (C.2) [1.0)

According to SOP ll-C, " Reactor Startup," which one of the following anticipated power levels would require placing the diffuser system in operation?

a. 5 Kw
b. '10 Kw c.100 Kw
d. 500 Kw Question (C.3)': [1.0)

The reactor is operating at max allowed power (per SOP IV-F, Neutron Radiography Beam Port

  1. 4) while located in the stall and positioned against the radiography reflector. Select the statement that describes the indication [s] the operator would see in the control room if the shield door to enter the cave were to be opened.
a. The C-2 device would cause the reactor to trip and an alarm would sound.
b. .The C-2 device would sound an alarm in the control room.
c. The beamport No. 4 area radiation monitor would alarm.
d. No indication in the control room.

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Section C: Plant and Rad Monitorino Systems Question. (C.4)' [1.0)

Which one of the following choices correctly describes the capability of the emergency pool fill system,in case of a loss of beam port integrity?.

a. Approximately 1200 GPM
b. Approximately 800 GPM.
c. Approximately 400 GPM.
d. Approximately 200 GPM.

Question (C.5) [1.0]

The emergency exhaust air filter system, installed between the exhaust fan and the exhaust stack, consists of;

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

d, ONE activated carbon filter bank, and ONE particulate filter bank.

Question - (C.6) [1.0]

The reactor is being operated at 100 kw in the " Servo" mode of control. The compensating voltage to the Linear Pcwer measuring channel suddenly begins to trend down due to a malfunction. Select the statement that describes reactor response with no operator action.

a. The regulating rod would move in, causing power to decrease
b. The regulating rod would move out, causing power to increase
c. All scram capable rods would insert
d. The regulating rod would shift back to manual due to a lower indicated reactor power, i

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II Section C: Plant and Rad Monitorina Systems Question (C.7) [1.0)

Select the statement that describes the method of selecting the amount of reactivity inserted for a pulse.

a. Placement of the mechanical pulse stop on the transient rod mounting plate.

/- b. . Adjustment of the air supply pressure to the pneumatic cylinder.

c. Placement of the mechanical pulse stop on the air supply solenoid valve.
d. Adjustment of the position of the pneumatic cylinder.

Question (C.8) [1.0]

A power calibration (calorimetric) of the linear power channel has been performed. In order to make the front panel meter indication agree with the calculated power:

a. the compensating voltage of the linear channel CIC is adjusted.
b. the high voltage of the linear channel CIC is adjusted.
c. the position of the linear channel CIC is adjusted.
d. the full power gain adjust potentiometer is adjusted.

l Question (C.9) [1.0]  !

The primary purpose of the safety plate assembly is to:

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a. Provide additional support to the reactor grid plate for the use of highly enriched FLIP fuel elements. l 1
b. Insure that the maximum reactivity insertion for a pulse cannot be exceeded..
c. Retain a shim-safety rod fuel follower if it becomes detacht.' from its mounting.
d. Retain any debris resulting from an accident which has directly involved the fuel elements.

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. 'l Section C: Plant and Rad Monitorino Systems Question (C.10) - [1.0) -

Assume the reactor is initially operating in the Steady State mode at a power level of 500 Kw.

Which one of the following describes the response of the control rods on the receipt of a scram signal generated by ONLY Safety Amplifier Channel #1? Assume no operator action.

a.-  : Shim-safety rods #1 and #2 will scram, all other rods will remain at their pre-scram positions.

b.- ' Shim safety rods #1 and #3 will scram, all other rods will remain at their pre-scram positions.

c. All Shim-safety rods and the transient rod will scram regulating rod will remain at its .

pre-scram position. ..

-d All six control rods will scram.

- Question (C.11)- [1.0)

On a decreasing pool. level, the University communications room will receive an alarm. What

. other automatic action will occur?

l

a. Recirculation pump tnp. i l
b. Skimmer pump trip.  !
c. . Core diffuser pump trip
d. Purification pump trip.

{

e

n l'

Section C' Plant and Rad Monitorina Systems-Question '(C.12)

. _[1.0)

De-energizing the solenoid valve which controls the supply of air to the pneumatic transient rod drive unit will cause .

a. the piston and the transient rod to drive upward until the piston reaches its upper limit stop.
b. the pneumatic piston to drop to its lower lirnit and the transient rod to remain in the full down position. .l

' c. the air pressure to remain at an operating level for several hours maintaining the j transient rod in its original position.

d; the transient rod to remain at its original position and a low pressure alarm to initiate in l the control room. )

Question (C.13) [1.0]

A reactor scram has occurred from an initial shim-safety rod position of 50.0%. Which one of the following correctly describes the indications for shim safety rod #3 immediately following the scram? Assume no operator action.

a. ENGAGED light off ROD DOWN light energized, CARR DOWN light off, digital indication 0.0%.
b. ENGAGED light off, ROD DOWN light energized, CARR DOWN light energized, digital indication 50.0%.
c. ENGAGED light off, ROD DOWN light energized, CARR DOWN light off, digital indication 50.0%.
d. ' ENGAGED light energized, ROD DOWN light off, CARR DOWN light off, digital indication 0.0%.

f 4

L .

Section C: Plant and Rad Monitorina Systems Question (C.14) [2.0)

Match the nuclear instrumentation channel in column 8 that satisfies the control function in column A. (the items in column B may be used once. mare than once or not at all; and only a single answer may occupy one answer space in column A)

Col'umn A'- Column B (control function) (nuclear instrument) .

a. Energizes interlock that prevents 1. Log power channel )

start-ups when less than 2 cps J

b. _ Energizes interlock that prevents 2. Linear power channel pulsing operations when greater ,

than 1 kw

3. Safety channel (s)
c. Inputs reactor scram signal when power is greater than 125%
d. Inputs reactor scram signalin the event of a reactor period of 3 seconds or less Question (C.15) [1.0)-

The minimum allowable number of FLIP fuel elements in a mixed core is:

a.- _20

b. 25
c. 30 1
d. 35 I

[^

e-i

. Section C: Plant and Rad Monitorina Systems

' Question ' (C,16) [1.0)'

Which one of the following choices is correct regarding the minimum equipment required to achieve confinement of the reactor building? Assume no maintenance is in progress.

. a. . Central exhaust fan available,

b. Central exhaust fan in operation and the. ventilation system controls in the reception -

room available.

1 The ventilation system and the Radiation Monitoring Channels in operation.

- c.

i

d. Central exhaust fan and the Radiation Monitoring Channels in operation.

1 Question (C.17) (1.0)

Which ONE of the following alarms requires the air handlers to be shut down as part of immediate action? -

a.- stack particulate monitor I

b. stack gas monitor ,
c. ~ building particulate monitor
d. building gas monitor Question (C.18) -[1.0]

Assuming the reactor is shutdown and all systems in a normal line-up, which one of the following pressures at the primary pump would indicate a full reactor pool?

a. ~ 47 psig i b .- ~42 psig.
c. 33 psig d.- 15 psig i

9 A

l Section C: Plant and Rad Monitorino Systems Question (C.19) [1.0)

Thermocouples in the instrumented fuel element measure temperature at the:

a, intenor surface of the cladding.

b. center of the zirconium rod.
c. ' outer surface of the fuel.
d. interior of the fuel.

l l

l

k u

[1

. Section A' R Theory.Therrno & Fac. Operatina Characteristics Page 1

  • ANSWER ; 1(A.1)

' c'

. REFERENCE ~

l' Burn, R.', Introduction to Nuclear Reactor Operations. @ 1982, 4.6, p, 4-16.

l:

l ' *ANSWE' R ' -(A.2)

-a i

  • REFERENCE l CR, , . I( ~ K ,f,) 50 _ fI -#<#,}

i CR ~ (I~#,p,) .

2 5 ~ (1 -0.8)

Therefore K,, = 0.6

' K,,' - K,,, -_ 9.5 , 9_ g 9.3 _

ap = =- = -0.41667

K, K,, . -0.80.6- 0.48 l
  • ANSWER (A.3) a.
j. ~
  • REFERENCE -

5'2 i -. P = Po e" P, = 1.10% T = 20 sec. t = 0.5 P = 110 e = 112.78%

l

" ANSWER '(A.4) a l

  • REFERENCE l Standard NRC Theory Question 1 l~
  • ANSWER -(A.5) b-
  • REFERENCE p Standard NRC Reactor Theory Question -
  • ANSWER (A.6) .,

a

  • REFERENCE.-

[

Standard NRC Reactor Theory Question l

i

i. l l
l. :

[4

p ]

E i

[:

L .; ;

lSection A: R Theorv.'Thermo & Fac. Ooeratina Characteristics Page 2 L

  • ANSWER .(A.7) j "b l
  • REFERENCE.

Glasstone, S.' and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, _1991, @$ 2.70 - 2.74, pp. 65 -- 66.

Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, @ 5.2, p. 5-2.-

  • ANSWER .(A.8).

a

  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, 5.7, pp. 5 5-38

.* ANSWER (A.9) b

  • REFERENCE Standard NRC Reactor Theory Question
  • ANSWER (A.10) d
  • REFERENCE

, NSC Tech Spec 3.1.3

  • ANSWER (A.1'1)

.b

  • REFERENCE 24000 neutrons in current generationf.1.01'= 24240 neutrons in next generation 240 neutrons added - 0.7% delayed neutron fraction = 238 prompt neutrons added

' *ANSWER (A.12) b REFERENCE A = A, e '" - - A = .693/T2 -

In(A/A ) = .693t/T2 T2 = .693 24hr/In 0.8 = 75 hr

F Section A: R Theory. Thermo & Fac. Operatina Characteristics Page 3

  • ANSWER (A.14) d
  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1988, %% 8.2 - 8.4, pp. 8 8-14.
  • ANSWER (A.15) a

" REFERENCE Reactor Physics Notes - Reactivity Feedback: Sect. 5 (b).

  • ANSWER (A.16) c
  • REFERENCE Glasstone, S. and Sesonske, A. Nuclear Reactor Engineering, Kreiger Publishing, Malabar. 4 Florida,1991, @ 3.161 - 3.163, pp.190 & 191. l Lamarsh J.R.. Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983 9, p.102.

Burn, R., Introduction to Nuclear Reactor Operations. @ 1982, S 5.5, pp. 5 5-25.

  • ANSWER (A.17) d
  • REFERENCE Glasstone, S. and Sesonske, A Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, S 5.81 - 5,83, p. 260.
  • ANSWER (A.18) c l
  • REFERENCE i MIT Reactor Physics Notes; Reactivity Feedback l l
  • ANSWER (A.19) l c  !
  • REFERENCE NSC SAR p. 47-53 j 1

1 i

  • ANSWER (A.20)

I c 1 l

  • REFERENCE .,

Lamarsh, J.R., lntroduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983. @ , p. 282.

I

a Section 8: Normal /Emero Procedures & Rad Con Page 4

  • ANSWER (B.1) a REFERENCE DR= 6CE/x2 = 0.005 = 6(%)(1.33)/x2, 2x = 798, x = 28.25 feet
  • ANSWER (B.3) c
  • REFERENCE i T.S. Definition 1.29; T.S. 3.2.2 Table 1 l ANSWER (B.4) c REFERENCE GM is not sensitive to energy.

ANSWER (8.5) d REFERENCE 10CFR20.1003 ANSWER (8.6) c REFERENCE-10CFR50.54(y)

ANSWER (B.7) 1 d 2e 3b REFERENCE 10CFR55-i

  • ANSWER (B.8) b
  • REFERENCE DRi D,2 = DR 2 D,2 - DR tDu2 = DR2 - DR
  • 250 mr/hr x 5 ft2 = 12.5 mr/hr D2 2 10 fta

l f

c -

Section B: Normal /Emera.' Procedures & Ra'd con Page 5

  • ANSWER (B.9) d.
REFERENCE '

SOP ll-G Step 1 - SOP ll-l Step 1,a - SOP ll-E Step g - SOP ll-J l

  • ANSWER' (B.10)

.c REFERENCE T.S. Sections 3.1.4; 3.5.1; 3.6.1

  • ANSWER (B.11) I c-REFERENCE-T.S. 3.1.1 I
  • ANSWER (B.12) l

'a REFERENCE-SOP ll-D Step 6

  • ANSWER ~ ('B.'13) a .2_. b .j_ c _3_ -

REFERENCE-T.S. 3.2.2 Table 1

  • ANSWER - (B.14) ~

~-

b

  • REFERENCE-T.S. Definition 1.18-

'* ANSWER (6.15) b REFERENCE Emergency Preparedness Plan Section 6.0

  • ANSWER ' (B.16) l

-c l

  • REFERENCE.

NSC Requalification Plan -

t

s Section B:. Normal /Emero. Procedures & Rad . Con Page 6

  • ANSWER (B.17) c REFERENCE Emergency Classification Guide
  • ANSWER (8.18) b ,

REFERENCE Tech. Specs, Definitions.1.3.1

  • ANSWER (B.19) d REFERENCE SOP IX @ B Step f i

=

r s

Section C: Plant and Rad Monitorina Systems. Page 7 l

  • ANSWER (C.1) I b' ~1
  • REFERENCE .

SOP IV-E; SAR pg. 87

  • ANSWER -(C.2) d
  • REFERENC'E l SOP ll-C, p. 2.
  • ANSWER .(C.3) a

.* REFERENCE-SAR p. 89, and SOP IV F p.2 I

l

  • ANSWER (C.4) c
  • REFERENCE SAR, p.' 112.

i

'

  • ANSWER (C.5)  !

c

  • REFERENCE SAR, p. 79.

'

  • ANSWER (C.6) a
  • REFERENCE SOP lil-C
  • ANSWER .(C.7) d
  • REFERENCE SAR p.38, ~ SOP ll-E step 4
  • ANSWER (C.8) d
  • REFERENCE

. SOP ll-J; Step 4.c '

1

~

Section C: Plant and Rad Monitorina Systems Page 7

  • ANSWER .

.(C.1)-

b REFERENCE

. SOP. IV-E; SAR pg. 87 -

~

? ANSWER .' . (C.2) ' '

d --'

c, .

  • REFERENCE

'. SOP ll-C p._2.

  • ANSWER .(C.3) a
  • REFERENCE SAR p. 89, and SOP IV F p.2
  • ANSWER . (C.4) c
  • REFERENCE SAR, p '112.
  • ANSWER (C.5)

.c

  • REFERENCE SAR, p 79. .
  • ANSWER (C.6) a

'* REFERENCE ~

SOP lil-C -

'

  • ANSWER .(C.7) d

' ' REFERENCE '.

SAR p.38; SOP ll-E step 4

. ANSWER .(C.8) d-

  • REFERENCE SOP ll Jl Step 4.c e

L L. -

s Section C: Plant and Rad Monitorina Systems Page 32 l

  • ANSWER (C.9).

c

  • REFERENCE-SAR, p.- 14.

i

  • ANSWER (C.10) c
  • REFERENCE SAR, Figure 7-3.
  • ANSWER (C.11) a, d -

REFERENCE SAR, @ Vill, G.1, p.112 )

  • ANSWER (C.12) b I
  • REFERENCE SAR p.38
  • ANSWER (C.13) c;
  • REFERENCE SAR, pp. 26-29.
  • ANSWER (C.14)
a. 1 b. 1 - c. 3 d. 1
  • REFERENCE SAR pp 91-93
  • ANSWER (C.15)
d
  • REFERENCE-TS 3.1.4(a).
  • ANSWER (C.16) b

' REFERENCE TS 3.3.2.

,,r a'

Section C Plant and Rad Monitorina Systems Page 9

  • ANSWER (C.17) a
  • REFERENCE SOP Vll-A4.c 2
  • ANSWER (C.18) d
  • REFERENCE SOP IX-E-1 p. 2
  • ANSWER (C.19) d REFERENCE SAR, p 18.

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